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人間環境デザインスタジオ
Human Environmental Design Studio

              1:00-4:15 pm
June 24, July 1, July 8, and July 15, 2008
                    at
  Graduate School of Frontier Sciences
        The University of Tokyo
                  Joonhong Ahn
        Department of Nuclear Engineering
         University of California, Berkeley
Who am I?
• Professor, Dept. of Nuclear Engineering, UC Berkeley

•   BS, NE, Todai, 1981 (Prof. Iwata)
•   MS, NE, Todai, 1983 (Prof. Kiyose/Suzuki)
•   PhD, NE UCB, 1988 (Prof. Pigford)
•   D. Eng, NE, Todai, 1989 (Prof. Suzuki)
•   JSPS Junior fellow, 1988-1990
•   Lecturer, Todai, 1990-1993
•   Assoc. Prof., Tokai U., 1993-1995
•   UCB since 1995

• third generation Japan-born Korean
Objective of the class
• This series of lectures introduces
  – fundamental technical facts about
    environmental issues with nuclear power
    utilization.
  – discussions on long-term environmental
    safety of geologic disposal, including
     • How engineers have established technologies for
       securing and assessing long-term safety, and
     • How societal agreement has (not?) been
       developed, particularly in US.
Syllabus
• June 24 – Technical basis for nuclear environmental
  issues
   – Nuclear fuel cycle and the environment
   – Geologic disposal
• July 1 – Performance assessment of geologic disposal
   – Performance assessment
   – Can the environmental impact be reduced by recycling?
• July 8 – Societal and ethical issues of geologic disposal
   – Development of societal agreement for geologic disposal
   – Ethics in/of geologic disposal
• July 15 – International aspects of nuclear power
  utilization
   – (Introductory summary for nuclear activities in India)
   – (Comparative discussions among Japan, US, and India)
Format of class
• Prerequisites
  – Fundamental knowledge about nuclear fission
  – Fundamental knowledge about chemical reactions
• Each topic consists of:
  – ~ 1 hour lecture for summarizing basic facts
  – discussion
• Reading materials/text books:
  – Relevant reading materials will be given to
    supplement class discussions upon request.
• Grading:
  – ?? (Ask Prof. Iwata!)
Do you know these?
•   Isotope                     •   McCabe Thiele diagram
•   Half life, decay constant   •   PUREX
•   Radioactivity               •   TBP
•   Uranium, plutonium          •   Retardation factor
•   E=mc2                       •   Darcy’s law
•   Fission                     •   Aquifer
•   Fission products            •   Biosphere
•   Thermal neutrons
•   Fast neutrons
•   Cross sections
•   Light-water reactors
Week 1 (6/24):
Technical basis for nuclear
  environmental issues

 Nuclear fuel cycle and the environment
           Geologic disposal
Nuclear fuel cycle
      and
the environment
Fuel consumption and waste generation from various
     electricity generation sources for 1GWe.year

            Fuel consumption [ton]   Waste generation [ton]
                                     CO2                      5,000,000
Crude oil                 1,400,000 SO2                         40,000
                                     NOx                        25,000
                                     dust, particles, ashes     25,000
                                     CO2                      6,000,000
Coal                     2,200,000 SO2                         120,000
                                     NOx                        25,000
                                     dust, particles, ashes    300,000
                                     (Uranium)                   (28.8)
Nuclear                          30 (Plutonium)                   (0.3)
                                     Fission products               0.9
Comparison with Fossil Fuels
  Chemical reaction
                          12
                               C + O2 → CO2 + 4 eV
                                                 12




                                                y                          200MeV
   Nuclear Fission    0n
                           1                              x

                                              2.43
                                  92U
                                        235
                                                                            94Pu
                                                                                   239


                                                               92U
                                                                     238
                                                     0n
                                                          1



              per atom [eV]       per gram
                                   [W•hr]
                                                              92U
                                                                    235

 Carbon              ~4             ~ 10
 Uranium         ~ 2E8             ~ 2E7
Uranium
• Uranium is mined as U3O8.
• It is composed of;
    – 99.3% by weight 92U238
    – 0.7% by weight 92U235
•   92 U235 is fissionable with slow neutrons, i.e.,
    thermally fissile.
       Light-water reactors (Current fleet of commercial
      reactors)
•   92 U238 is fissionable with only fast neutrons.
    – However, 92U238 is a “fertile” isotope, generating
          239 (thermally fissile).
      94Pu
       Reprocessing and recycle of spent U fuel
Uranium Ores
Uranium mining technologies
                                         Underground
Open Cast Mining                         Mining




                                         Production per Method (%) as in 2003
                                                   (total 35 772 t U)
                                                                         Co-/By-
                                                                        product
                                       ISL m ining
                                                    20%        11%

                                              28%              41%




                                   Open pit                                  Deep
             In-Situ Leach (ISL)    m ining                              underground
                                                                            m ining
             Mining
Uranium Resources (million ton)
             Known Conventional &           Undiscovered Resources
             Identified Resources
Cost range   Reasonably        Inferred     Prognosticat Speculative
(US$/kgU)    Assumed                        ed
             Resources
             (RAR)
< 80             2.64             1.16            1.70
80 – 130         0.66             0.28            0.82
>130                                                             4.56
Unassigned                                                       2.98
Subtotal         3.30             1.44            2.52           7.54
Total                   4.74                             10.06
                                          14.80
                                   IAEA Red Book 2005
Global Uranium Resources & Production
                 Uranium Production
               (total 41.360 tU in 2005)
                      USA         Other
                      2%           9%
     Uzbekistan
        6%                                 Canada
                                            28%
  Namibia
    7%

   Russian
  Federation                                                 Identified (RAR+Inferred) Uranium Resources
                                                               below $130 /kgU (total=4 743 000 t in 2005)
     8%                                                                          Other
               Niger                                             Uzbekistan
                                                                    2%           20%
                                                                                                 A ustralia
                8%                    A ustralia                                                   24%
                                                     Russian
               Kazakhstan               22%         Federation
                  10%                                  4%


                                                    Niger
                                                     5%
Kazakhstan’s large resource is
                                                                                                    Kazakhstan
planned to be utilized by in-situ                                                                      17%
leaching.                                           Brazil
                                                     6%                Namibia
                                                                         6%      USA      Canada
                                                                                 7%         9%
Nuclear Fuel Cycle and Waste Generation
                                                       LLW 1,000 drums
              ~0.2 ton U
                                27.3 ton



                                                    26 ton U
                 27.5 ton
                                                    0.95 ton FP
                                                    0.27 ton Ac
                                                                   0.24 ton Pu
                                     26 ton
~ 0.5 ton U                                                                   TRU/LLW


                                                                       < 0.26 ton U
        165 ton                                                        0.95 ton FP
        (0.3%U-235)                  167 ton                           0.27 ton Ac
                           100,000
                           ton ore
                                                                              1 GWe, LWR, 1 year
                                                                              Reprocessing scheme
                  0.2% U3O8                                                   Thermal efficiency 0.325
                                                                  ~ 1 ton U
                  = 181 ton U                                                 Capacity factor 0.8
                                           Mill tailings U7%      Ra, Th
                          Airborne Rn      Th-230 100%, Ra 98%
Yellow cake
Mill tailings pile in Utah
Uranium enrichment
uranium mines, enrichment plants,
      and Yucca mountain repository




                                    Portsmouth, OH


                                 Oak Ridge, TN

                               Parducah, KY

Yucca Mountain Repository
Presently, 704,000 tons of DU stored in
          UF6 form in the US.
Nuclear Fuel Cycle and Waste Generation
                                                              LLW 1,000 drums
              ~0.2 ton U
                                27.3 ton



                                                    26 ton U
                 27.5 ton
                                                    0.95 ton FP
                                                    0.27 ton Ac
                                                                   0.24 ton Pu
                                     26 ton
~ 0.5 ton U                                                                   TRU/LLW


                                                                       < 0.26 ton U
        165 ton                                                        0.95 ton FP
        (0.3%U-235)                  167 ton                           0.27 ton Ac
                           100,000
                           ton ore
                                                                              1 GWe, LWR, 1 year
                                                                              Reprocessing scheme
                  0.2% U3O8                                                   Thermal efficiency 0.325
                                                                  ~ 1 ton U
                  = 181 ton U                                                 Capacity factor 0.8
                                           Mill tailings U7%      Ra, Th
                          Airborne Rn      Th-230 100%, Ra 98%
Interim Storage of Spent Fuel
Spent Fuel Accumulation in US



YMR
capacity      September 2007
Repository Availability in US
• Repository capacity, 63,000 ton SF.
• Assume that:
   – The present annual electricity generation (G = 70 GWy/year) is
     maintained (no growth).
   – The spent fuel generation per GWy is calculated by
       W = 38,000 ton SF/1420 GWy = 27 ton/ GWy.
   – The electricity generation C supported by this capacity:
       C = 63000/27=2330 GWy
• The YM repository availability is obtained as
   – C/G = 2330/70 = 33 years.
• 3 YM repositories will be necessary for one century.
Reprocessing of Spent Nuclear Fuel

Step 1: Decladding and          Step 3: Extraction of U and Pu
        Chopping                        by Tri Butyl Phosphate
Step 2: Dissolution into HNO3           (TBP)
                                Step 4: Pu Recovery from TBP
                                        to Aqueous phase
Treatment of spent fuel with
      reprocessing

                               High
                               Level
                               Waste
COMMERCIAL SPENT URANIUM OXIDE FUEL REPROCESSING PLANTS
         IN OPERATION AND UNDER CONSTRUCTION IN THE WORLD

                                                                      Capacity
Country / Company               Facility / Location     Fuel Type   (tHM/year)

                                                                      1700
France, COGEMA                UP2 and UP3, La Hague      LWR
                                                                      1200
UK, BNFL                         Thorp, Sellafield     LWR, AGR
                                                                      1500
UK, BNFL                          B205 Magnox          Magnox GCR
                              RT-1 / Tcheliabinsk-65
Russian Federation, Minatom        Mayak 400             VVER          400

                                                                       90
Japan, JNC                         Tokai-Mura          LWR, ATR
                                 Rokkasho-Mura
Japan, JNFL                    (under construction)      LWR           800

                               PREFRE-1, Tarapur
                                                         PHWR          100
India, BARC                   PREFRE-2, Kalpakkam
                                                         PHWR          100
China, CNNC                     Diowopu (Ganzu)          LWR          25-50
Storage of High-Level Waste solidified with
            Borosilicate Glass




               Storage pit at R7 COGEMA (France)
Radioactivity of HLW

• Fission Products
   – Sr-90, Cs-137, Cs-135, I-
     129, Tc-99, ...
• Trans-uranic + U, and
  their decay daughters
   – Am-243, Am-241, Np-237,
     Pu-239, Pu-240, Pu-242,
     Cm-245, Cm-244, ...
• Activated materials
   – H-3, C-14, Zr-95, Ni-63,
     Fe-55, Co-60, ...
Geologic disposal
Yucca Mountain
                                                 HUMBOLDT                         ELKO
                                                  COUNTY                         COUNTY

• Location: 100




                                     WASHOE
                                     COUNTY
  miles NW of Las                                PERSHING
                                                  COUNTY




                                                               COUNTY
                                                               LANDER


                                                                        EUREKA
                                                                        COUNTY
  Vegas in Nye                                   CHURCHILL
                                                  COUNTY
  County                            CARSON
                                     CITY
                                          LYON
                                                 STOREY
                                                                                 WHITE PINE
                                                                                  COUNTY

• Withdrawal Area:
                                    DOUGLAS


                                                                    NYE
                                                 MINERAL
  230 sq. miles                                  COUNTY
                                                                   COUNTY


  (150,000 acres)                                     ESMERALDA
                                                        COUNTY      NELLIS         LINCOLN

• Distance: 14 miles
                                                                  AIR FORCE        COUNTY
                                                                    RANGE

                                                                          NV

  from nearest year-                                                     TEST
                                                                         SITE
                                                                                   CLARK
  round population                  YUCCA                                          COUNTY

                                   MOUNTAIN                INYO COUNTY
                                                            CALIFORNIA             LAS
                                                                                  VEGAS



   1 acre = 4,046.86 m2 = 1,224坪
Yucca Mountain
• Geology:
  Composed of
  ash tuff
  deposited 10
  million years ago
• Elevation: 4950
  ft. at crest
• Climate:
  receives less
  than 7.5 inches
  rain annually
• Resources:
  none of
  commercial
  value
Yucca Mountain Repository




63,000 ton HM for CSNF
7,000 ton HM for Defense wastes
         4,500 ton HM equivalent HLW
         2,500 ton HM SNF (15 categories)
Yucca Mountain Repository Design
Three Types of Waste Packages




                 Number of packages
CSNF                            7886
       Co-disp                  3564
DW
       Naval                     300
Program Key Milestones
•   Design for License Application
    – Completed December 1, 2007
•   License Support Network Certification
    – October 19, 2007 (two months earlier than schedule)
    – Recertification: June 3, 2008
•   Supplemental EIS
    – Draft issued October 2007/hearings completed
•   License Application
    – Submitted to NRC on June 3, 2008
    – Submittal included 208 references
    – Will be “docketed” within 90 days (8/31) from the submittal
      date
    – Review by NRC will be completed within 3 years (2011).
Program Key Milestones (cont’d)
•   Start Nevada Rail Construction - October 2009
    – Delayed - Inadequate funding to proceed with design
•   YM Construction Authorization - September 2011
    – Depends on NRC decision
•   Operating License Submittal - March 2013
    – Predicated on funding and construction schedule
•   Rail Line Operational - June 2014
    – 2016 is achievable only if adequate funding is provided
•   Begin Receipt - March 2017 (Best Achievable Date)
    – Currently under evaluation due to FY 07 and 08 actual funding
      shortfalls and expected near term funding limitations
    – Firm date cannot be set until funding issue resolved
Waste Isolation Pilot Plant (WIPP),
              Carlsbad, NM
•    The world's first underground
     repository licensed to permanently
     dispose of transuranic (TRU) waste
     left from the research and
     production of nuclear weapons.
•    After more than 20 years of
     scientific study, public input, and
     regulatory struggles, WIPP began
     operations on March 26, 1999.
•    Located in the remote Chihuahuan
     Desert of Southeastern New Mexico     • undertaken by DOE
•    disposal rooms mined 2,150 feet       • Waste from defense activities
     underground in a 2,000-foot thick
     salt formation that has been stable   • Exempted from NRC regulation
     for more than 200 million years.      (EPA Certificate)
•    Transuranic waste is currently        • Bedded salt
     stored at 23 locations nationwide.    • 176,000 m3 Contact-Handled
•    Over a 35 year period, WIPP is        (CH)TRU,
     expected to receive about 19,000      • 71,000 m3 Remote-Handled
     shipments.
                                           (RH)TRU
$ 410,000 per TRUPACT-II
Waste package located in WIPP




                                Inside the package
Geologic Disposal Concept in
              Sweden/Finland

• water-saturated
  granite
• LWR spent fuel
• copper canister
  (lined with titanium)
• bentonite buffer
HLW Geologic Disposal Concept in Japan




    Tunnel type
    water-saturated granite
    Vitrified waste
    carbon-steel overpack
    bentonite buffer
Functional requirements for Geologic Disposal
                    (OECD, 1989)
•   The goal of final disposal is to protect human health and the
    environment and to limit the burdens on future generations.
•   The waste must not be released to the biosphere at concentrations
    deemed to present an unacceptable hazard.
     – Health risks and effects on the environment from waste disposal, at any
       time in the future, shall be low and not greater than would be acceptable
       today. The judgment of the acceptability of a disposal option shall be
       based on radiological impacts irrespective of any national boundaries.
•   The waste must be removed and isolated from the effects of human
    activity or catastrophic natural events,
•   the technology to implement disposal must be readily available as
    well as achievable at a reasonable cost,
•   The burden on future generations shall be limited by implementing
    “at an appropriate time” a final disposal option which does not rely
    for its safety on long-term institutional controls or remedial actions.
     – in some countries, the retrieval of some types of disposed nuclear
       wastes must be technologically and economically feasible, if so desired
       by future generations,
•   The processes which control safe performance of nuclear waste
    disposal must be well-characterized by modeling.
•   Sufficient, relevant data should be obtained and used in such
    models to demonstrate predicted performance reliably.
Week 2 (7/1):
Performance assessment of
     geologic disposal
      Performance assessment
   Can the environmental impact be
        reduced by recycling?
Performance assessment
Performance Assessment (PA) ,
 Total System Performance Assessment (TSPA),
               Safety Assessment




• PA: method for evaluation system, subsystem or
  component performance
• TSPA: a system-level PA; subsystems and components
  are linked into a single analysis
• Safety Assessment: if the result of TSPA is compared
  with a safety standard and judgment is made, TSPA is
  called safety assessment. (For YMR, TSPA = SA)
Annual Dose as the repository performance
                measure
                                                                            Biosphere

                                                                     Biosphere
                                    Annual dose,
                                                                dose conversion
                                    BiCi mrem/yr
                                                           factor, Bi (mrem/yr)/(Ci/m3)


  Repository




                                                                              well
                                        Geosphere



Plum                         Release,
                                                                Local nuclide
       e of r                Fi(t)
                adion                                           concentration, Ci(r,t)
                      u   clide
                               s

   Near field                                       Far field
Barriers Evaluated in the Analysis
• Surficial soils and topography
• Unsaturated rock layers overlying the
  repository
• Drip shield
• Waste package
• Spent fuel cladding
• Waste form / concentration limits
• Drift invert
• Unsaturated rock layers below repository
• Tuff and alluvial aquifers
Emplacement Drift




            Emplacement drifts
               5.5 m diameter
               50-90 drifts, each ~ 1 km
               long
The Emplacement Environment at
       Yucca Mountain
Thermal hydraulic conditions
 around emplacement drifts
Thermal Design Goals
    Requirement                     Description

Tclad < 350°C     Limit to prevent clad failure by increase in
                  creep rupture.


TDW < 200°C       Prevents alteration of rock crystalline structure.



Tcenter < 96°C    Pillar Drainage requirement, creates flow path
                  for water.
Natural System of Yucca Mountain
            Repository located:
             ~1,000 ft. Below
                 Surface
             ~1,000 ft. Above
               Water Table

                                  Desert Environment

                                    Unsaturated
                                    Overburden

                                    Unsaturated
                                    Host Rock

                                   Repository Horizon

                                   Underlying
                                   Unsaturated
                                   Rock


                                    Deep Water
                                    Table
Estimating Dose to Hypothetical
        Future Humans
Total System Performance
 Assessment Architecture
Total System Performance Assessment Results
     Total Mean and Median Annual Dose
      (Draft Supplemental EIS, Oct. 2007)
Total Expected Dose: 10,000 years
 (Draft Supplemental EIS, Oct. 2007)
Radionuclides Contributing to Total Mean Dose at
                 10,000 Years
      (Draft Supplemental EIS, Oct. 2007)
Summary of 10,000-year Results
       (Draft Supplemental EIS, Oct. 2007)
• Total mean dose determined by contribution
  from seismic scenario class
  – Probability of damage to co-disposed waste packages
    within 10,000 yr < 0.2
• Largest contribution to mean dose from 99Tc
• Magnitude of mean dose determined by
  – Probability of events (seismic, igneous)
  – Diffusion of radionuclides through cracks in waste
    package outer barrier
• Total estimated peak mean annual dose for
  10,000 years: 0.24 mrem/yr
  – Well below regulatory limit of 15 mrem/yr
Total Expected Dose: 1 million years
  (Draft Supplemental EIS, Oct. 2007)
Radionuclides Contributing to Total Mean Dose at
                1 million Years
      (Draft Supplemental EIS, Oct. 2007)
Summary of 1 million-year Results
         (Draft Supplemental EIS, Oct. 2007)
• Total mean dose determined by occurrence of igneous
  events, seismic damage and general corrosion
• Major contributors to dose are 99Tc, 129I, 239Pu, 242Pu,
  226Ra, and 237Np
• Waste package outer barrier has primary influence on
  releases of technetium and iodine
• Chemistry influences release of plutonium from waste
  package
• Total estimated peak median annual dose for 1 million
  years: 0.96 mrem/yr
   – Well below proposed regulatory limit of 350 mrem/yr
Steps for TSPA
            Detail models –– A
            calculation typically
            includes only a subset
            of the repository system.
            The calculation
            produces predictions
            that can be compared
            with laboratory or field
            data.
            System models ––A
            calculation produces
            assessment of
            regulatory performance
            measures and the
            uncertainty in the
            performance measures
            caused by the parameter
            and model uncertainties
            in the analysis.
Evolution of Previous TSPAs
Model Development for TSPA
                   Abstraction



                    Process
                     Model



                      Data
Two Major Issues with Geologic
             Disposal
• Repository Capacity for future nuclear-
  power utilization
• Uncertainty and Confidence building in
  long-term performance assessment
Types of uncertainty
• Aleatory:
   – arises from an inherent randomness
   – Stochastic, irreducible, Type A
• Epistemic:
   – Derives from a lack of knowledge about the appropriate value to
     use for a quantity that is assumed to have a fixed value.
   – Subjective, reducible, Type B
• Examples
   –   Regulatory uncertainty (Epistemic)
   –   Conceptual-model uncertainty (Epistemic)
   –   Model parameter uncertainty (Epistemic)
   –   Stochastic uncertainty (Aleatory)
Regulatory uncertainty
• How can “repository performance” be
  measured?
• How can a technical safety case be
  justified within the regulatory framework?
  – Safety criteria are themselves uncertain.
Congress, EPA, NRC, DOE
         1980-85 1985-90 1990-95                        1995-00 2000-05 2005-10
                                            EnPA
              NWPA           NWPAA          1992         VA                              Report for
Cong-          1982           1987                      1996
                                                                         Site Rec
                                                                                       2nd repository
                                                                      By Energy Sec.
ress                                       WIPPLWA                         2002           2008-10
                                             1992
                       40CFR                               40CFR194         40CFR197
                      Part 191                               WIPP            DENIAL
                        1985                40CFR191         1998
EPA                                         amended
                                                                              2004
                                                                                                        Mass of stored SF
(Standard)                40CFR191            1993                40CFR197        40CFR197
                                                                                                         Exceeds YMR
                                                                    YMR            proposal
                           DENIAL                                                                           capacity
                                                                    2001             2005
                            1987                                                                              2014
        10CFR60         10CFR60                      10CFR60
        Procedure       Un-satu’d                   Pre-closure       10CFR63
NRC        1981           1985                         1996             YMR
(Regulation)
           10CFR60               10CFR60                                2001
              Technical           NEPA
                1983               1989

                                      TSPA          TSPA          10CFR963
                                      1991          1995            2001
DOE             10CFR960
                                                           TSPA-VA                         License
(Guideline)       1984                       TSPA                                         Application
                                                             1998
                                             1993                  TSPA-SR                And review
                                                                     2001                 2008-2011
Nuclear Waste Policy Act
             (1982)
• Set the schedule for siting 2 repositories.
• EPA was charged with issuing generally
  applicable limits on radioactivity releases
  to the environment. (40CFR191)
• NRC was directed to develop regulations
  and criteria for construction, operation,
  and closure. (10CFR60)
• 1986: 9 sites ––> 5 sites ––> 3 sites
  – Deaf Smith, Hanford, Yucca Mountain
NWPA Amendment Act (1987)
• Only Yucca Mountain be characterized to
  evaluate its suitability as a repository.
• No site-specific work for a second
  repository.
• Nullified the DOE proposal for MRS at the
  Clinch River, TN.
• Site Characterization Plan for YM (1988)
10CFR60 (1983)
• Waste-package lifetime > ~1000 yr
• Radionuclide fractional release rate from
  EBS < 1/100,000 of its 1,000 yr inventory
• Groundwater travel time > 1,000 yr
• Overall performance: radionuclide release
  to the accessible environment
  (40CFR191).
40CFR191 (1985)
• Disposal systems shall be designed so that
  for 10,000 years the following limits will not
  be exceeded at the accessible environment
  with the likelihood of
   – < 1 chance in 10 of exceeding the limit, and
   – < 1 chance in 1000 of exceeding 10 times the
     limit.
• Release limits are set on the basis of 1,000
  MTHM.
   – I-129: 100 Ci, Sr-90: 1000 Ci,
   – Np-237: 100 Ci, Th-230: 10 Ci
Energy Policy Act (1992)
• Mandated a separate process for setting a
  standard specifically for YMR.
• Required EPA to arrange for an analysis
  by National Academy of Sciences (NAS).
  – Can scientifically justifiable analyses of
    repository behavior over many thousands of
    years in the future be made?
• EPA reissued revised 40CFR191 in 1993.
Recommendations by
              NAS Report (1995)
•   Denial of release limits, i.e., 1000 incremental fatalities over 10,000
    years
     – The use of a standard that sets a limit on the risk to individuals of
       adverse health effects from releases from the repository is
       recommended.
     – The critical-group approach should be used.
•   Extension of time frame from 10,000 yr to a million yr
     – The compliance with the standard measured at the time of peak risk,
       within the limits imposed by the long-term stability of the geologic
       environment, which is of the order of one million years.
•   Denial of risk-based calculation of the adverse effect of human
    intrusion into the repository
     – The consequence of an intrusion should be calculated to assess the
       resilience of the repository to intrusion.
10 CFR Part 63 was rejected by the
 federal appeals court due to a lawsuit
     by Nevada State, July 2004.
• Post Closure Performance Assessment
  – Computer simulation of repository performance over
    10,000 years to:
     • Consider geologic and engineered barriers
     • Determine capabilities and time period to prevent or retards
       movement of water and radionuclides
     • Calculate radiological dose at 18 km (using lab and field
       evidence for simulations)
  – DOE must demonstrate using performance
    assessment, that for 10,000 years the “reasonably,
    maximally exposed individual” receives no more than
    15 mrem per year from all pathways releases of
    undisturbed YM disposal system.
Nominal Performance case with
proposed standard (TSPA-VA)
                 350mrem/year


          15mrem/year
Total System Performance Assessment Results
     Total Mean and Median Annual Dose
      (Draft Supplemental EIS, Oct. 2007)
Some thoughts about geologic
             disposal
• Retrievability of wastes from a repository
   – Final disposal vs. interim storage
• Fairness/Equity to future generations
   – Who are “future generations”?
• Fairness/Equity to the local community around the
  repository site
   – Why Nevada, where no nuclear power plants exist?
• “Natural Barrier”
   – May we contaminate rocks?
• Relationship with recycle/reprocessing
   – Is recycle effective in improving repository performance?
Some thoughts about performance
       assessment (PA)
• Performance assessment is:
   – based on scientific facts and abstracted reality, and
   – used as a tool for objective and optimized societal decision.
   – a good way to communicate with the public?
• Annual dose as the performance measure for judgment
  of long-term “environmental” safety.
   – Should be understood as a “stylized” measure.
       • The biosphere part of PA model is based on hypothetical
         assumptions.
       • This is actually not a measure for environmental safety, but
         radiological safety.
   – What kind of (technical) information needs to be provided by PA
     for societal decision-making?
Can the environmental impact
  be reduced by recycling?
Nuclear Fuel Cycle

               System parameters
              d1, d2, p2, αf, γ1,γ2, … Solidification
                   Fuel cycle          Matrix
   M
                                                        System parameters
                    Reactor                              v, D, C*, ε, εp, d,
Uranium                            Process                 L, R, K, N, …
                                   Loss
                                                waste
            Fuel         Separation
          Fabrication    Process
                                                  Repository

                        Nuclear system
                                                                 “IMPACT”
                                           Environment
Generation of long-lived FPs in LWRs
   (3410 MWt, 33,000 MWD/MT, 150-day cooling)
Half-lives         fraction (%)   nuclides
< 1 yr             4.8
1 to 10 yr         1.3            Ru-106, Sb-125, Cs-134, Pm-147,
                                  Eu-154, Eu-155
10 to 30 yr        5.3            Kr-85 (11 yr), Sr-90 (29 yr), Cs-137 (30 yr)
30 to 100 yr       0.03           Sm-151
100 to 10,000 yr   0.0            N.A.
1E4 to 5E9 yr      6.6            Se-79, Zr-93, Tc-99 (2.1E5),
                                  Pd-107, Sn-126, I-129(1.6E7)
                                  Cs-135 (2.3E6)
> 5E9 yr           7.6            Rb-87, In-115, Ce-142, Nd-144,
                                  Sm-147, Sm-148, Sm-149
Stable             78.1
Total              100.0
Generation of minor actinides (MA) per year

      Nuclide                      3410 MWt PWR
                         3 yr cooling       10 yr cooling


      Np-237             57.9 %             41.3
      Am-241             27.4               48.8*
      Am-243             11.9               8.33
      Cm-243             0.03               0.02
      Cm-244             2.67               1.44
      Cm-245             0.15               0.10
      Total              100                100



    *Am-241 increases due to beta decay of Pu-241.
Partitioning and Transmutation of HLW
• By destruction of long-lived radionuclides in HLW,
   – Radioactivity and radiotoxicity of long-lived HLW are reduced
   – risk for future recovery of nuclear weapons materials from a final
     repository is reduced
   – additional nuclear energy is gained by fissioning minor actinides
• For P-T,
   – Reprocessing is a prerequisite
   – Total radiological hazard arising from nuclear energy production
     must be reduced.
   – Secondary wastes from P-T processes must be taken into
     account.
   – Net energy production is desirable.
   – System must be economical.
Processes for P-T
•   Partitioning
     – Conventional PUREX process + additional chemical partitioning process
         ex. for Np, TRUEX has been developed.
     – A process where separation of uranium and plutonium is combined with
       recovery of elements to be transmuted.
        ex. pyrochemical processing
•   Transmutation
     – Reactors
         • LWR, FBR for electricity generation + actinide burners
         • Th-U fuel cycle
     – Accelerator
         • high-energy proton spallation
                   (n, fission), (n, gamma), (n, 2n), (n, p) reactions
                   photo-nuclear reaction (gamma, n)
     – Fusion reactor
P&T benefits
Toxicity Index
                                   λ i Ni
          Toxicity index        =Σ                        [m3]
                                 i Ci,k
where
Ci,k : radioactivity concentration limit for nuclide i in medium k
          (k = water or air) [Bq/m3],
Ni: the number of atoms of nuclide I

If more than one radionuclide is involved, a summation is performed over all
the isotopes present in the mixture.

Toxicity index is the volume of air or water with which the mixture of
radionuclides must be diluted so that breathing the air or drinking the water
will result in accumulation of radiation dose at a rate no greater than 0.5
rem/year.
P-T flow sheet
Geologic disposal and P&T (1)
• 1970s
  – Several disposal concepts were investigated and compared from
    scientific viewpoints.
  – Geologic repository concept
      • 1977 Polvani Report (OECD/NEA)
      • 1977 Stripa Project in Sweden
  – Partitioning and Transmutation was proposed as an alternative
    to geologic disposal
• 1980s
  – Scientific studies to demonstrate the safety of geologic disposal
      • OECD International Symposium on Safety assessment of
        radioactive waste repositories, Paris 1989
  – Denial of P&T concepts as an alternative to geologic disposal
      • International Conference on Partitioning and Transmutation, Ispra,
        1980
      • UCBNE4176, Prof. T.H. Pigford, Paper presented at MIT
        conference
      • L. D. Ramspott, et al., “Impacts of New Developments in Partitioning
        and Transmutation on the Disposal of High-Level Nuclear Waste in
        a Mined Geologic Repository,” UCRL ID-109203, LLNL, March 1992.
UCBNE4176, 1990 by Pigford
  (In the framework of 40CFR191)
1. By recycling actinides, the length of time that
   needs to be considered for geologic disposal
   would not decrease from 100,000 yr to 1000yr,
   as claimed by P&T studies.
2. P&T is not necessary to satisfy 40CFR191
   requirement for cumulative release of
   radionuclides to the environment at 10,000yr.
3. To have significant reduction of actinide
   inventory in a cycle, it will require more than
   1000 yr of operation of P&T system to reach a
   steady state. Even in such a case, reduction
   better than 1/1000 is not possible.
Geologic disposal and P&T (2)
•   1990s
    – Demonstration of geologic disposal concepts (more site specific studies)
    – Shifting from natural barrier to engineered barriers
        • TSPA studies in US for Yucca Mountain Repository
        • SKB report, Sweden, 1991
        • H3 and H12 reports, Japan, 1991, 1999
    – P&T to improve repository performance
        •   EC/EU Framework
        •   France: SPIN project
        •   OECD/Japan OMEGA project
        •   US Liquid metal cooled actinide burner with pyroprocessing at ANL
•   2000s
    – Sites for repositories announced
        • YMR (US), Olkiluoto (Finland)
    – Repository capacity issue has emerged.
    – P&T and advanced fuel cycle
        • Generation IV
        • AFCI/GNEP
Results of Swedish
repository-performance study
                       Dose limit
                       (0.15mSv/y)




             I-129
Water-Saturated repository
   (Japanese repository concept, H12)
                                 4
                            10
                                 3
                            10   Engineered Barrier System
Calculated dose[μSv y -1]


                              2 Geosphere
                            10
                              1
                                Surface Environment
                            10 Lifestyle                                         Total
                                 0
                            10
 Dose [ Sv/y]




                             -1
                            10
                                                                     Np-237          U-234 U-238
     μ




                             -2
                            10
                             -3
                            10
                                                         Th-229
                             -4
                            10
                             -5
                            10
                             -6                         Se-79                                  Pb-210
                            10
                             -7
                            10                     Cs-135
                             -8
                            10
                                 100   101   102     103       104        105      106   107    108
                                              Time after disposal [y]
                                                       Time after disposal [y]
Effects of P&T in terms of
              exposure dose rate (H12)
              1.0E+00

              1.0E-01

              1.0E-02
                                                                    Reference case
総線量 [μSv/y]




              1.0E-03

              1.0E-04

              1.0E-05
                                                               99% actinide removed
              1.0E-06

              1.0E-07
                   1.0E+03   1.0E+04     1.0E+05     1.0E+06        1.0E+07           1.0E+08

                                   Time after emplacement in repository, year
                                            処分後の時間 [y]

                                                      Wakasugi, et al., Personal communications
Repository performance is
 insensitive to P/T application
-- L. D. Ramspott, et al., “Impacts of New Developments in
Partitioning and Transmutation on the Disposal of High-Level
Nuclear Waste in a Mined Geologic Repository,” UCRL ID-
109203, LLNL, March 1992.

 All other things being equal, less inventory means less
 risk. However, the risk reduction benefits that P-T might
 offer depend on the release scenario involved, and in
 many cases, may not be as great as a 99.9% reduction in
 actinide inventory might suggest.
So, can the environmental impact
      be reduced by recycle?
• Yes, it can.
• However, whether reduction is meaningful or not
  depends on
   – combination of (a) waste form, (b) separation efficiency, and (c)
     performance measures, suitable for geo-hydrological and
     geochemical conditions of the repository.
• Environmental impact reduction would not necessarily be
  the motivation for recycle;
   – U resource utilization and proliferation resistance of the
     repository could be more important.
• Environmental impacts from other parts of the fuel cycle
  would directly be imposed on the current people, not
  those in 10,000 years in future. Thus, comparison or
  combination with other EI should be done carefully.
Week 3 (7/8):
Societal and ethical issues of
     geologic disposal
   Development of societal agreement
         for geologic disposal
      Ethics of geologic disposal
Development of societal
agreement for geologic disposal
The Repository World

•   Disposal in a geologic repository remains the preferred ultimate
    solution, with or without reprocessing
•   Much of the technical community has confidence in determining site
    suitability
•   A number of geologic media are being pursued
•   Most programs have experienced substantial difficulties
•   Siting remains the biggest hurdle
•   Increasing recognition of multi-disciplinary nature
•   Select ideas have become prominent, e.g. volunteer/veto,
    retrievability, monitoring, phased management
•   We will have storage for decades
Some Highlights and Lowlights

• National programs have been abandoned or siting
  stopped
   – France, U.K., Canada, Germany, Spain, Switzerland, U.S.A.
• National (re)reviews have been undertaken
   – Canada, France, U.K.,…
• Schedules have been delayed
   – Almost everywhere
• Some countries have moved forward and others have
  restarted
   – Finland, Sweden, U.S.A., France, Canada, Japan, U.K….
An (Optimistic) Current Snapshot
• Countries with candidate sites
   – Finland, Sweden, U.S.A., France


• Countries with programs underway
   – Canada, Belgium, Japan, U.K., Switzerland,…


• Countries “thinking about it”
   – Spain, South Korea, China, India,…


• Countries starting out
   – Argentina, Slovakia, Slovenia, South Africa,…
The Seaborn Panel Conclusions (1998)
            --Canada--
• “From a technical perspective, safety of the AECL
  concept has been on balance adequately demonstrated
  for a conceptual stage of development. But from a social
  perspective, it has not.”

• “As it stands, the AECL concept for deep geological
  disposal has not been demonstrated to have broad
  public support. The concept in its current form does not
  have the required level of acceptability to be adopted as
  Canada’s approach for managing nuclear fuel wastes.”
NWMO Techniques for Broad Engagement
“Choosing a Way Forward”:
        The Foundation
• “…this generation of citizens which has enjoyed
  the benefits of nuclear energy has an obligation
  to begin provision for managing that waste.”

• “…our obligation is to give them (succeeding
  generations) a real choice and the opportunity
  to shape their own decisions while at the same
  time not imposing a burden which future
  generations may not be able to manage.”
“Choosing a Way Forward”:
 Some Key Recommendations
• Sequential decision-making and flexibility in the pace
  and manner of implementation through “Adaptive
  Phased Management”
• Ultimate centralized isolation in a deep geologic
  repository
• Option for interim step of shallow underground storage
  at the central site
• Program of continuous learning and R&D
• Long-term monitoring with potential for retrievability
• Seek an informed, willing community as host
What makes nuclear waste
        management special?
• The technical challenge
   – Performance over geological time
   – “Proof” not possible
   – Central role of “ologists”

• The institutional challenge
   –   The extraordinary time frame
   –   Siting
   –   Linkage to other agendas
   –   Values and ethics in conflict
   –   Political implications
   –   Nuclear stigma and fears

                » But there are unique advantages…
Virtues of a Repository
•   Passive
•   Occurrences will be slow
•   No inherent energy to release materials
•   Retrievable
•   Only a repository upon closure, when future
    generations are comfortable
Some Key Enduring Features
• Core, stable goal
• Roles and responsibilities clear
• Clear, open, and transparent decision making process
• Respect for fairness and societal consent apparent
• Sequential decision-making and contingency planning
• Possibility of altering or reversing course
• Appropriate compensation
Some Potential Lessons Learned
• Take the necessary time - go slow in order to go fast
• Assign importance to the societal considerations as well
  as the technical ones
• There are many ways to effectively engage the public
  and key stakeholders
• Listening, respecting, and then responding can build trust
  and even advocacy, particularly with local community
• Plan carefully and involve the right experts
• Be prepared to respond in real time to unexpected events
• Promise, then deliver, then do it again and again
Ethics of geologic disposal
three main virtues that have
    withstood the test of time

• Humility
• Charity
• Veracity
Humility
Humility means you should treat yourself fully as one,
  but not more than one.

• How does this apply when you have a group of
  people (a corporation/government) that want to install
  a nuclear plant/geologic repository?
• Is it considering that that group of people may have
  different priorities than the group of people that they
  are affecting by installing the plant?
• Is it the mentality that installing a power plant will
  affect each person in their own situation differently?
• How do we reconcile these differences?
Charity
Charity means that you should treat others as fully one,
  just the same as you treat yourself.

• Should the groups of people that run corporations
  consider the groups of people that are affected by their
  projects as equal to them?
• Should the people that are affected consider the
  corporations equal?
• Who’s right is it to decide whether a project should go
  forward? The people affected? Corporations?
  Government?
Veracity
Veracity simply means telling the truth.

• It has already proven successful for some countries
  to be completely open and honest with the people
  who will be affected by power plant projects.
• It has been shown that when the company or
  government that is planning the project takes the
  time to sit down and discuss the plans with the
  people, they are more receptive to the project.
• How important is it when it comes to these issues
  for corporations? The government?
Consequentialism (帰結主義)
G.E.M. Anscombe, quot;Modern Moral Philosophyquot; (1958)

• Actions are evaluated based on the results they
  achieve.
• A morally right action is one that produces a good
  outcome, or consequence.
• The ethical action is the one that maximizes overall
  good.
• Such theories are labeled teleological(目的論的).
• A consequentialist may argue that lying is wrong
  because of the negative consequences produced
  by lying — though a consequentialist may allow
  that certain foreseeable consequences might make
  lying acceptable.
Utilitarianism(功利主義)
John Stuart Mill's essay Utilitarianism (1861)
• “the greatest good for the greatest
  number”(最大多数の最大幸福)
• the moral worth of an action is solely
  determined by its contribution to overall
  utility, that is, its contribution to happiness
  or pleasure as summed among all persons.
Deontology(義務論)
• Actions are evaluated based on the
  motivation behind them.
• Deontology derives the rightness or
  wrongness of an act from the character
  of the act itself.
• A deontologist might argue that lying is
  always wrong, regardless of any
  potential quot;goodquot; that might come from
  lying.
Kant’s three significant formulations
   of the categorical imperative
           (deontological)
• Act only according to that maxim by which you
  can also will that it would become a universal
  law.
• Act in such a way that you always treat humanity,
  whether in your own person or in the person of
  any other, never simply as a means, but always
  at the same time as an end.
• Act as though you were, through your maxims, a
  law-making member of a kingdom of ends.
Conflicting motives
• Consequentialism seeks the best
  outcome, despite the action.
• Deontology seeks the best action,
  despite the consequences.
ANS Code of Ethics
            http://www.ans.org/about/coe/

1. We hold paramount the safety, health, and
   welfare of the public and fellow workers, work
   to protect the environment, and strive to
   comply with the principles of sustainable
   development in the performance of our
   professional duties.
2. We will formally advise our employers, clients,
   or any appropriate authority and, if warranted,
   consider further disclosure, if and when we
   perceive that pursuit of our professional duties
   might have adverse consequences for the
   present or future public and fellow worker
   health and safety or the environment.
   (veracity)
ANS Code of Ethics
             http://www.ans.org/about/coe/
3. We act in accordance with all applicable laws
   and these Practices, lend support to others
   who strive to do likewise, and report violations
   to appropriate authorities. (veracity, humility)
4. We perform only those services that we are
   qualified by training or experience to perform,
   and provide full disclosure of our qualifications.
   (humility)
5. We present all data and claims, with their
   bases, truthfully, and are honest and truthful in
   all aspects of our professional activities. We
   issue public statements and make
   presentations on professional matters in an
   objective and truthful manner. (veracity)
ANS Code of Ethics
             http://www.ans.org/about/coe/

6. We continue our professional development
   and maintain an ethical commitment
   throughout our careers, encourage similar
   actions by our colleagues, and provide
   opportunities for the professional and ethical
   training of those persons under our supervision.
7. We act in a professional and ethical manner
   towards each employer or client and act as
   faithful agents or trustees, disclosing nothing of
   a proprietary nature concerning the business
   affairs or technical processes of any present or
   former client or employer without specific
   consent, unless necessary to abide by other
   provisions of this Code or applicable laws.
ANS Code of Ethics
            http://www.ans.org/about/coe/

8. We disclose to affected parties, known or
    potential conflicts of interest or other
    circumstances, which might influence, or
    appear to influence, our judgment or impair the
    fairness or quality of our performance.
9. We treat all persons fairly. (Charity)
10. We build our professional reputation on the
    merit of our services, do not compete unfairly
    with others, and avoid injuring others, their
    property, reputation, or employment.
11. We reject bribery and coercion in all their
    forms.
ANS Code of Ethics
             http://www.ans.org/about/coe/

12. We accept responsibility for our actions; are
    open to and acknowledge criticism of our work;
    offer honest criticism of the work of others;
    properly credit the contributions of others; and
    do not accept credit for work not our own.
    (humility, veracity)
Ethics in Nuclear Engineering
• ANS Code of Ethics reflects a Deontological approach of
  obeying a set of rules or principles. 9th point specifically
  mirrors Kant’s Categorical Imperative.

• This contrasts, however, with the Consequentialism approach
  which is taken in the matter of waste disposal.

• The potential for greater good for the greater number of
  people is considered more important than the action, which
  puts people at risk.
Yucca Mountain
• Yucca Mountain seemingly contradicts two tenets
  of the ANS Code of Ethics:
   – 1) welfare of the public, and
   – 9) We treat all persons fairly
• is it fair that Nevada gets a site when they have no
  nuclear power, and have been lied to in the past?
• Utilitarianism is the basis for ethics (greatest good
  for the greatest #), but we still shouldn’t violate the
  code of ethics, (#9)?
• In utilitarianistic consideration, is future generation
  included?
Week 4 (7/15):
International aspects of nuclear
        power utilization
    (Introductory summary for nuclear
             activities in India)
    (Comparative discussions among
           Japan, US, and India)
(Introductory summary for
  nuclear activities in India
by Dr. R. K. Dayal, IGCAR)
Topics to be Discussed in This Week

• As Asian economy expands rapidly, so
  does energy demand in Asia.
  – Why is this so important to us (or the US)?
• Nuclear Energy is an indispensable choice
  for Asian countries.
  – Are they ready for nuclear energy?
  – How will it influence the world in the future?
  – What is needed most there? And how can the
    US respond to such needs?
http://www.peakoil.net/ (Association for the Study of Peak Oil & Gas)
Chinese Development Plan of Nuclear Power
              Units to 2020

                                    NPPs in operation and under construction
                        50000
 Power Capacity (MWe)



                        45000         under construction
                        40000         in operation
                        35000

                        30000

                        25000                9,068MW
                        20000
                                                                      7,860MW
                                            1981-2007
                        15000                                         2004- 2014
                        10000
                        5000

                           0
                                19     1     1     1     1     2     2     2     2     2
                                  8 2年 98 6年 99 0年 99 4年 99 8年 00 2年 00 6年 01 0年 01 4年 01 8年
                                                                               26,000MW
                                                                              2008- 2020

                            1.8%                                                               4.0%
Scenarios for Total Installed Power
        Capacity in India
(DAE-2004 and Planning Commission-2006 studies)
       1600
       1400
       1200
       1000
 GWe




        800
        600
        400
        200
          0
          1990   2000   2010   2020   2030    2040   2050   2060
                                  Year
                 DAE    PC_GDP-Growth 8%     PC_GDP-Growth 9%
Electricity growth rate – a scenario
                                                   Primary              Electricity
                                Period
                                            energy       % annual    % annual growth
 2002-2022                                         growth
                                                     4.6                     6.3
 2022-2032                                           4.5                     4.9
 2032-2042                                           4.5                     4.6
 2042-2052                                           3.9                     3.9
Per Capita Generation (kWh)




                              6000
                                                                                      5305
                              5000

                                                                      3699
                              4000

                              3000                           2454

                              2000                  1620
                                            1000
                              1000   613


                                 0
                                     2002    2012    2022     2032    2042         2052

                                                      Time period
GDP/capita vs. kWh/capita
                                                                                           US (2006)
                                                                                            ($44,000, 13,000 kWh)
             10000                                                            Singapore
                                                                         Brunei         Japan
                           From 1999 to 2006
                                                                                       Hong Kong

                                                                         South Korea
                                                       Malaysia
kWh/capita




                                      China                  Thailand
              1000

                                                      Philippines
                           India

                               Indonesia

                                   Sri Lanka


               100
                     100                       1000                     10000                  100000


                                               GDP/capita (US$)
By Increase in Energy
        Consumption in Asia ....
• Global Environment
  – CO2, SOx, NOx emissions
     • Greenhouse effect, Acid Rain, etc.
• Competition for Limited Resources
• Nuclear Safety and Security
• International System
  – If nuclear energy is developed on a large scale,
    restructuring of international organizations for
    safeguards will be necessary.
The Global Nuclear Energy Partnership Objectives are
      Stated in The National Security Strategy

• The United States “will build the Global Nuclear Energy
  Partnership to work with other nations to develop and
  deploy advanced nuclear recycling and reactor
  technologies.
• This initiative will help provide reliable, emission-free
  energy with less of the waste burden of older
  technologies and without making available separated
  plutonium that could be used by rogue states or terrorists
  for nuclear weapons.
• These new technologies will make possible a dramatic
  expansion of safe, clean nuclear energy to help meet the
  growing global energy demand.”
GNEP Process
Spent fuel accumulation in South
             Korea
                                 90
Spent Fuel Accumulation (ktHM)
Accumulated SF Arisings (ktHM)




                                 80

                                 70

                                 60

                                 50                             PWR
                                 40

                                 30

                                 20                                     CANDU

                                 10

                                 0
                                  2005 2015   2025 2035   2045 2055   2065 2075   2085 2095

                                                             Year
(Comparative discussions
among Japan, US, and India)
Discussion topics
• Developed vs. developing countries
  – Resources
  – Global environment
  – Proliferation resistance – Access to technologies
     • For whom? Why?
• Current vs. future generations
  – Resources
  – Global environment
• Nuclear vs. non-nuclear communities
  – Public perception and communication
  – Decision making processes

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Lectures On Nuclear technology and Environment(2008 07@The University of Tokyo)

  • 1. 人間環境デザインスタジオ Human Environmental Design Studio 1:00-4:15 pm June 24, July 1, July 8, and July 15, 2008 at Graduate School of Frontier Sciences The University of Tokyo Joonhong Ahn Department of Nuclear Engineering University of California, Berkeley
  • 2. Who am I? • Professor, Dept. of Nuclear Engineering, UC Berkeley • BS, NE, Todai, 1981 (Prof. Iwata) • MS, NE, Todai, 1983 (Prof. Kiyose/Suzuki) • PhD, NE UCB, 1988 (Prof. Pigford) • D. Eng, NE, Todai, 1989 (Prof. Suzuki) • JSPS Junior fellow, 1988-1990 • Lecturer, Todai, 1990-1993 • Assoc. Prof., Tokai U., 1993-1995 • UCB since 1995 • third generation Japan-born Korean
  • 3. Objective of the class • This series of lectures introduces – fundamental technical facts about environmental issues with nuclear power utilization. – discussions on long-term environmental safety of geologic disposal, including • How engineers have established technologies for securing and assessing long-term safety, and • How societal agreement has (not?) been developed, particularly in US.
  • 4. Syllabus • June 24 – Technical basis for nuclear environmental issues – Nuclear fuel cycle and the environment – Geologic disposal • July 1 – Performance assessment of geologic disposal – Performance assessment – Can the environmental impact be reduced by recycling? • July 8 – Societal and ethical issues of geologic disposal – Development of societal agreement for geologic disposal – Ethics in/of geologic disposal • July 15 – International aspects of nuclear power utilization – (Introductory summary for nuclear activities in India) – (Comparative discussions among Japan, US, and India)
  • 5. Format of class • Prerequisites – Fundamental knowledge about nuclear fission – Fundamental knowledge about chemical reactions • Each topic consists of: – ~ 1 hour lecture for summarizing basic facts – discussion • Reading materials/text books: – Relevant reading materials will be given to supplement class discussions upon request. • Grading: – ?? (Ask Prof. Iwata!)
  • 6. Do you know these? • Isotope • McCabe Thiele diagram • Half life, decay constant • PUREX • Radioactivity • TBP • Uranium, plutonium • Retardation factor • E=mc2 • Darcy’s law • Fission • Aquifer • Fission products • Biosphere • Thermal neutrons • Fast neutrons • Cross sections • Light-water reactors
  • 7. Week 1 (6/24): Technical basis for nuclear environmental issues Nuclear fuel cycle and the environment Geologic disposal
  • 8. Nuclear fuel cycle and the environment
  • 9. Fuel consumption and waste generation from various electricity generation sources for 1GWe.year Fuel consumption [ton] Waste generation [ton] CO2 5,000,000 Crude oil 1,400,000 SO2 40,000 NOx 25,000 dust, particles, ashes 25,000 CO2 6,000,000 Coal 2,200,000 SO2 120,000 NOx 25,000 dust, particles, ashes 300,000 (Uranium) (28.8) Nuclear 30 (Plutonium) (0.3) Fission products 0.9
  • 10. Comparison with Fossil Fuels Chemical reaction 12 C + O2 → CO2 + 4 eV 12 y 200MeV Nuclear Fission 0n 1 x 2.43 92U 235 94Pu 239 92U 238 0n 1 per atom [eV] per gram [W•hr] 92U 235 Carbon ~4 ~ 10 Uranium ~ 2E8 ~ 2E7
  • 11. Uranium • Uranium is mined as U3O8. • It is composed of; – 99.3% by weight 92U238 – 0.7% by weight 92U235 • 92 U235 is fissionable with slow neutrons, i.e., thermally fissile. Light-water reactors (Current fleet of commercial reactors) • 92 U238 is fissionable with only fast neutrons. – However, 92U238 is a “fertile” isotope, generating 239 (thermally fissile). 94Pu Reprocessing and recycle of spent U fuel
  • 13. Uranium mining technologies Underground Open Cast Mining Mining Production per Method (%) as in 2003 (total 35 772 t U) Co-/By- product ISL m ining 20% 11% 28% 41% Open pit Deep In-Situ Leach (ISL) m ining underground m ining Mining
  • 14. Uranium Resources (million ton) Known Conventional & Undiscovered Resources Identified Resources Cost range Reasonably Inferred Prognosticat Speculative (US$/kgU) Assumed ed Resources (RAR) < 80 2.64 1.16 1.70 80 – 130 0.66 0.28 0.82 >130 4.56 Unassigned 2.98 Subtotal 3.30 1.44 2.52 7.54 Total 4.74 10.06 14.80 IAEA Red Book 2005
  • 15. Global Uranium Resources & Production Uranium Production (total 41.360 tU in 2005) USA Other 2% 9% Uzbekistan 6% Canada 28% Namibia 7% Russian Federation Identified (RAR+Inferred) Uranium Resources below $130 /kgU (total=4 743 000 t in 2005) 8% Other Niger Uzbekistan 2% 20% A ustralia 8% A ustralia 24% Russian Kazakhstan 22% Federation 10% 4% Niger 5% Kazakhstan’s large resource is Kazakhstan planned to be utilized by in-situ 17% leaching. Brazil 6% Namibia 6% USA Canada 7% 9%
  • 16. Nuclear Fuel Cycle and Waste Generation LLW 1,000 drums ~0.2 ton U 27.3 ton 26 ton U 27.5 ton 0.95 ton FP 0.27 ton Ac 0.24 ton Pu 26 ton ~ 0.5 ton U TRU/LLW < 0.26 ton U 165 ton 0.95 ton FP (0.3%U-235) 167 ton 0.27 ton Ac 100,000 ton ore 1 GWe, LWR, 1 year Reprocessing scheme 0.2% U3O8 Thermal efficiency 0.325 ~ 1 ton U = 181 ton U Capacity factor 0.8 Mill tailings U7% Ra, Th Airborne Rn Th-230 100%, Ra 98%
  • 20. uranium mines, enrichment plants, and Yucca mountain repository Portsmouth, OH Oak Ridge, TN Parducah, KY Yucca Mountain Repository
  • 21. Presently, 704,000 tons of DU stored in UF6 form in the US.
  • 22. Nuclear Fuel Cycle and Waste Generation LLW 1,000 drums ~0.2 ton U 27.3 ton 26 ton U 27.5 ton 0.95 ton FP 0.27 ton Ac 0.24 ton Pu 26 ton ~ 0.5 ton U TRU/LLW < 0.26 ton U 165 ton 0.95 ton FP (0.3%U-235) 167 ton 0.27 ton Ac 100,000 ton ore 1 GWe, LWR, 1 year Reprocessing scheme 0.2% U3O8 Thermal efficiency 0.325 ~ 1 ton U = 181 ton U Capacity factor 0.8 Mill tailings U7% Ra, Th Airborne Rn Th-230 100%, Ra 98%
  • 23. Interim Storage of Spent Fuel
  • 24. Spent Fuel Accumulation in US YMR capacity September 2007
  • 25. Repository Availability in US • Repository capacity, 63,000 ton SF. • Assume that: – The present annual electricity generation (G = 70 GWy/year) is maintained (no growth). – The spent fuel generation per GWy is calculated by W = 38,000 ton SF/1420 GWy = 27 ton/ GWy. – The electricity generation C supported by this capacity: C = 63000/27=2330 GWy • The YM repository availability is obtained as – C/G = 2330/70 = 33 years. • 3 YM repositories will be necessary for one century.
  • 26. Reprocessing of Spent Nuclear Fuel Step 1: Decladding and Step 3: Extraction of U and Pu Chopping by Tri Butyl Phosphate Step 2: Dissolution into HNO3 (TBP) Step 4: Pu Recovery from TBP to Aqueous phase
  • 27. Treatment of spent fuel with reprocessing High Level Waste
  • 28. COMMERCIAL SPENT URANIUM OXIDE FUEL REPROCESSING PLANTS IN OPERATION AND UNDER CONSTRUCTION IN THE WORLD Capacity Country / Company Facility / Location Fuel Type (tHM/year) 1700 France, COGEMA UP2 and UP3, La Hague LWR 1200 UK, BNFL Thorp, Sellafield LWR, AGR 1500 UK, BNFL B205 Magnox Magnox GCR RT-1 / Tcheliabinsk-65 Russian Federation, Minatom Mayak 400 VVER 400 90 Japan, JNC Tokai-Mura LWR, ATR Rokkasho-Mura Japan, JNFL (under construction) LWR 800 PREFRE-1, Tarapur PHWR 100 India, BARC PREFRE-2, Kalpakkam PHWR 100 China, CNNC Diowopu (Ganzu) LWR 25-50
  • 29. Storage of High-Level Waste solidified with Borosilicate Glass Storage pit at R7 COGEMA (France)
  • 30. Radioactivity of HLW • Fission Products – Sr-90, Cs-137, Cs-135, I- 129, Tc-99, ... • Trans-uranic + U, and their decay daughters – Am-243, Am-241, Np-237, Pu-239, Pu-240, Pu-242, Cm-245, Cm-244, ... • Activated materials – H-3, C-14, Zr-95, Ni-63, Fe-55, Co-60, ...
  • 32. Yucca Mountain HUMBOLDT ELKO COUNTY COUNTY • Location: 100 WASHOE COUNTY miles NW of Las PERSHING COUNTY COUNTY LANDER EUREKA COUNTY Vegas in Nye CHURCHILL COUNTY County CARSON CITY LYON STOREY WHITE PINE COUNTY • Withdrawal Area: DOUGLAS NYE MINERAL 230 sq. miles COUNTY COUNTY (150,000 acres) ESMERALDA COUNTY NELLIS LINCOLN • Distance: 14 miles AIR FORCE COUNTY RANGE NV from nearest year- TEST SITE CLARK round population YUCCA COUNTY MOUNTAIN INYO COUNTY CALIFORNIA LAS VEGAS 1 acre = 4,046.86 m2 = 1,224坪
  • 33. Yucca Mountain • Geology: Composed of ash tuff deposited 10 million years ago • Elevation: 4950 ft. at crest • Climate: receives less than 7.5 inches rain annually • Resources: none of commercial value
  • 34. Yucca Mountain Repository 63,000 ton HM for CSNF 7,000 ton HM for Defense wastes 4,500 ton HM equivalent HLW 2,500 ton HM SNF (15 categories)
  • 36. Three Types of Waste Packages Number of packages CSNF 7886 Co-disp 3564 DW Naval 300
  • 37. Program Key Milestones • Design for License Application – Completed December 1, 2007 • License Support Network Certification – October 19, 2007 (two months earlier than schedule) – Recertification: June 3, 2008 • Supplemental EIS – Draft issued October 2007/hearings completed • License Application – Submitted to NRC on June 3, 2008 – Submittal included 208 references – Will be “docketed” within 90 days (8/31) from the submittal date – Review by NRC will be completed within 3 years (2011).
  • 38. Program Key Milestones (cont’d) • Start Nevada Rail Construction - October 2009 – Delayed - Inadequate funding to proceed with design • YM Construction Authorization - September 2011 – Depends on NRC decision • Operating License Submittal - March 2013 – Predicated on funding and construction schedule • Rail Line Operational - June 2014 – 2016 is achievable only if adequate funding is provided • Begin Receipt - March 2017 (Best Achievable Date) – Currently under evaluation due to FY 07 and 08 actual funding shortfalls and expected near term funding limitations – Firm date cannot be set until funding issue resolved
  • 39. Waste Isolation Pilot Plant (WIPP), Carlsbad, NM • The world's first underground repository licensed to permanently dispose of transuranic (TRU) waste left from the research and production of nuclear weapons. • After more than 20 years of scientific study, public input, and regulatory struggles, WIPP began operations on March 26, 1999. • Located in the remote Chihuahuan Desert of Southeastern New Mexico • undertaken by DOE • disposal rooms mined 2,150 feet • Waste from defense activities underground in a 2,000-foot thick salt formation that has been stable • Exempted from NRC regulation for more than 200 million years. (EPA Certificate) • Transuranic waste is currently • Bedded salt stored at 23 locations nationwide. • 176,000 m3 Contact-Handled • Over a 35 year period, WIPP is (CH)TRU, expected to receive about 19,000 • 71,000 m3 Remote-Handled shipments. (RH)TRU
  • 40.
  • 41.
  • 42.
  • 43. $ 410,000 per TRUPACT-II
  • 44. Waste package located in WIPP Inside the package
  • 45. Geologic Disposal Concept in Sweden/Finland • water-saturated granite • LWR spent fuel • copper canister (lined with titanium) • bentonite buffer
  • 46. HLW Geologic Disposal Concept in Japan Tunnel type water-saturated granite Vitrified waste carbon-steel overpack bentonite buffer
  • 47. Functional requirements for Geologic Disposal (OECD, 1989) • The goal of final disposal is to protect human health and the environment and to limit the burdens on future generations. • The waste must not be released to the biosphere at concentrations deemed to present an unacceptable hazard. – Health risks and effects on the environment from waste disposal, at any time in the future, shall be low and not greater than would be acceptable today. The judgment of the acceptability of a disposal option shall be based on radiological impacts irrespective of any national boundaries. • The waste must be removed and isolated from the effects of human activity or catastrophic natural events, • the technology to implement disposal must be readily available as well as achievable at a reasonable cost, • The burden on future generations shall be limited by implementing “at an appropriate time” a final disposal option which does not rely for its safety on long-term institutional controls or remedial actions. – in some countries, the retrieval of some types of disposed nuclear wastes must be technologically and economically feasible, if so desired by future generations, • The processes which control safe performance of nuclear waste disposal must be well-characterized by modeling. • Sufficient, relevant data should be obtained and used in such models to demonstrate predicted performance reliably.
  • 48. Week 2 (7/1): Performance assessment of geologic disposal Performance assessment Can the environmental impact be reduced by recycling?
  • 50. Performance Assessment (PA) , Total System Performance Assessment (TSPA), Safety Assessment • PA: method for evaluation system, subsystem or component performance • TSPA: a system-level PA; subsystems and components are linked into a single analysis • Safety Assessment: if the result of TSPA is compared with a safety standard and judgment is made, TSPA is called safety assessment. (For YMR, TSPA = SA)
  • 51. Annual Dose as the repository performance measure Biosphere Biosphere Annual dose, dose conversion BiCi mrem/yr factor, Bi (mrem/yr)/(Ci/m3) Repository well Geosphere Plum Release, Local nuclide e of r Fi(t) adion concentration, Ci(r,t) u clide s Near field Far field
  • 52. Barriers Evaluated in the Analysis • Surficial soils and topography • Unsaturated rock layers overlying the repository • Drip shield • Waste package • Spent fuel cladding • Waste form / concentration limits • Drift invert • Unsaturated rock layers below repository • Tuff and alluvial aquifers
  • 53. Emplacement Drift Emplacement drifts 5.5 m diameter 50-90 drifts, each ~ 1 km long
  • 54. The Emplacement Environment at Yucca Mountain
  • 55. Thermal hydraulic conditions around emplacement drifts
  • 56. Thermal Design Goals Requirement Description Tclad < 350°C Limit to prevent clad failure by increase in creep rupture. TDW < 200°C Prevents alteration of rock crystalline structure. Tcenter < 96°C Pillar Drainage requirement, creates flow path for water.
  • 57. Natural System of Yucca Mountain Repository located: ~1,000 ft. Below Surface ~1,000 ft. Above Water Table Desert Environment Unsaturated Overburden Unsaturated Host Rock Repository Horizon Underlying Unsaturated Rock Deep Water Table
  • 58. Estimating Dose to Hypothetical Future Humans
  • 59. Total System Performance Assessment Architecture
  • 60. Total System Performance Assessment Results Total Mean and Median Annual Dose (Draft Supplemental EIS, Oct. 2007)
  • 61. Total Expected Dose: 10,000 years (Draft Supplemental EIS, Oct. 2007)
  • 62. Radionuclides Contributing to Total Mean Dose at 10,000 Years (Draft Supplemental EIS, Oct. 2007)
  • 63. Summary of 10,000-year Results (Draft Supplemental EIS, Oct. 2007) • Total mean dose determined by contribution from seismic scenario class – Probability of damage to co-disposed waste packages within 10,000 yr < 0.2 • Largest contribution to mean dose from 99Tc • Magnitude of mean dose determined by – Probability of events (seismic, igneous) – Diffusion of radionuclides through cracks in waste package outer barrier • Total estimated peak mean annual dose for 10,000 years: 0.24 mrem/yr – Well below regulatory limit of 15 mrem/yr
  • 64. Total Expected Dose: 1 million years (Draft Supplemental EIS, Oct. 2007)
  • 65. Radionuclides Contributing to Total Mean Dose at 1 million Years (Draft Supplemental EIS, Oct. 2007)
  • 66. Summary of 1 million-year Results (Draft Supplemental EIS, Oct. 2007) • Total mean dose determined by occurrence of igneous events, seismic damage and general corrosion • Major contributors to dose are 99Tc, 129I, 239Pu, 242Pu, 226Ra, and 237Np • Waste package outer barrier has primary influence on releases of technetium and iodine • Chemistry influences release of plutonium from waste package • Total estimated peak median annual dose for 1 million years: 0.96 mrem/yr – Well below proposed regulatory limit of 350 mrem/yr
  • 67. Steps for TSPA Detail models –– A calculation typically includes only a subset of the repository system. The calculation produces predictions that can be compared with laboratory or field data. System models ––A calculation produces assessment of regulatory performance measures and the uncertainty in the performance measures caused by the parameter and model uncertainties in the analysis.
  • 69. Model Development for TSPA Abstraction Process Model Data
  • 70. Two Major Issues with Geologic Disposal • Repository Capacity for future nuclear- power utilization • Uncertainty and Confidence building in long-term performance assessment
  • 71. Types of uncertainty • Aleatory: – arises from an inherent randomness – Stochastic, irreducible, Type A • Epistemic: – Derives from a lack of knowledge about the appropriate value to use for a quantity that is assumed to have a fixed value. – Subjective, reducible, Type B • Examples – Regulatory uncertainty (Epistemic) – Conceptual-model uncertainty (Epistemic) – Model parameter uncertainty (Epistemic) – Stochastic uncertainty (Aleatory)
  • 72. Regulatory uncertainty • How can “repository performance” be measured? • How can a technical safety case be justified within the regulatory framework? – Safety criteria are themselves uncertain.
  • 73. Congress, EPA, NRC, DOE 1980-85 1985-90 1990-95 1995-00 2000-05 2005-10 EnPA NWPA NWPAA 1992 VA Report for Cong- 1982 1987 1996 Site Rec 2nd repository By Energy Sec. ress WIPPLWA 2002 2008-10 1992 40CFR 40CFR194 40CFR197 Part 191 WIPP DENIAL 1985 40CFR191 1998 EPA amended 2004 Mass of stored SF (Standard) 40CFR191 1993 40CFR197 40CFR197 Exceeds YMR YMR proposal DENIAL capacity 2001 2005 1987 2014 10CFR60 10CFR60 10CFR60 Procedure Un-satu’d Pre-closure 10CFR63 NRC 1981 1985 1996 YMR (Regulation) 10CFR60 10CFR60 2001 Technical NEPA 1983 1989 TSPA TSPA 10CFR963 1991 1995 2001 DOE 10CFR960 TSPA-VA License (Guideline) 1984 TSPA Application 1998 1993 TSPA-SR And review 2001 2008-2011
  • 74. Nuclear Waste Policy Act (1982) • Set the schedule for siting 2 repositories. • EPA was charged with issuing generally applicable limits on radioactivity releases to the environment. (40CFR191) • NRC was directed to develop regulations and criteria for construction, operation, and closure. (10CFR60) • 1986: 9 sites ––> 5 sites ––> 3 sites – Deaf Smith, Hanford, Yucca Mountain
  • 75. NWPA Amendment Act (1987) • Only Yucca Mountain be characterized to evaluate its suitability as a repository. • No site-specific work for a second repository. • Nullified the DOE proposal for MRS at the Clinch River, TN. • Site Characterization Plan for YM (1988)
  • 76. 10CFR60 (1983) • Waste-package lifetime > ~1000 yr • Radionuclide fractional release rate from EBS < 1/100,000 of its 1,000 yr inventory • Groundwater travel time > 1,000 yr • Overall performance: radionuclide release to the accessible environment (40CFR191).
  • 77. 40CFR191 (1985) • Disposal systems shall be designed so that for 10,000 years the following limits will not be exceeded at the accessible environment with the likelihood of – < 1 chance in 10 of exceeding the limit, and – < 1 chance in 1000 of exceeding 10 times the limit. • Release limits are set on the basis of 1,000 MTHM. – I-129: 100 Ci, Sr-90: 1000 Ci, – Np-237: 100 Ci, Th-230: 10 Ci
  • 78. Energy Policy Act (1992) • Mandated a separate process for setting a standard specifically for YMR. • Required EPA to arrange for an analysis by National Academy of Sciences (NAS). – Can scientifically justifiable analyses of repository behavior over many thousands of years in the future be made? • EPA reissued revised 40CFR191 in 1993.
  • 79. Recommendations by NAS Report (1995) • Denial of release limits, i.e., 1000 incremental fatalities over 10,000 years – The use of a standard that sets a limit on the risk to individuals of adverse health effects from releases from the repository is recommended. – The critical-group approach should be used. • Extension of time frame from 10,000 yr to a million yr – The compliance with the standard measured at the time of peak risk, within the limits imposed by the long-term stability of the geologic environment, which is of the order of one million years. • Denial of risk-based calculation of the adverse effect of human intrusion into the repository – The consequence of an intrusion should be calculated to assess the resilience of the repository to intrusion.
  • 80. 10 CFR Part 63 was rejected by the federal appeals court due to a lawsuit by Nevada State, July 2004. • Post Closure Performance Assessment – Computer simulation of repository performance over 10,000 years to: • Consider geologic and engineered barriers • Determine capabilities and time period to prevent or retards movement of water and radionuclides • Calculate radiological dose at 18 km (using lab and field evidence for simulations) – DOE must demonstrate using performance assessment, that for 10,000 years the “reasonably, maximally exposed individual” receives no more than 15 mrem per year from all pathways releases of undisturbed YM disposal system.
  • 81. Nominal Performance case with proposed standard (TSPA-VA) 350mrem/year 15mrem/year
  • 82. Total System Performance Assessment Results Total Mean and Median Annual Dose (Draft Supplemental EIS, Oct. 2007)
  • 83. Some thoughts about geologic disposal • Retrievability of wastes from a repository – Final disposal vs. interim storage • Fairness/Equity to future generations – Who are “future generations”? • Fairness/Equity to the local community around the repository site – Why Nevada, where no nuclear power plants exist? • “Natural Barrier” – May we contaminate rocks? • Relationship with recycle/reprocessing – Is recycle effective in improving repository performance?
  • 84. Some thoughts about performance assessment (PA) • Performance assessment is: – based on scientific facts and abstracted reality, and – used as a tool for objective and optimized societal decision. – a good way to communicate with the public? • Annual dose as the performance measure for judgment of long-term “environmental” safety. – Should be understood as a “stylized” measure. • The biosphere part of PA model is based on hypothetical assumptions. • This is actually not a measure for environmental safety, but radiological safety. – What kind of (technical) information needs to be provided by PA for societal decision-making?
  • 85. Can the environmental impact be reduced by recycling?
  • 86. Nuclear Fuel Cycle System parameters d1, d2, p2, αf, γ1,γ2, … Solidification Fuel cycle Matrix M System parameters Reactor v, D, C*, ε, εp, d, Uranium Process L, R, K, N, … Loss waste Fuel Separation Fabrication Process Repository Nuclear system “IMPACT” Environment
  • 87. Generation of long-lived FPs in LWRs (3410 MWt, 33,000 MWD/MT, 150-day cooling) Half-lives fraction (%) nuclides < 1 yr 4.8 1 to 10 yr 1.3 Ru-106, Sb-125, Cs-134, Pm-147, Eu-154, Eu-155 10 to 30 yr 5.3 Kr-85 (11 yr), Sr-90 (29 yr), Cs-137 (30 yr) 30 to 100 yr 0.03 Sm-151 100 to 10,000 yr 0.0 N.A. 1E4 to 5E9 yr 6.6 Se-79, Zr-93, Tc-99 (2.1E5), Pd-107, Sn-126, I-129(1.6E7) Cs-135 (2.3E6) > 5E9 yr 7.6 Rb-87, In-115, Ce-142, Nd-144, Sm-147, Sm-148, Sm-149 Stable 78.1 Total 100.0
  • 88. Generation of minor actinides (MA) per year Nuclide 3410 MWt PWR 3 yr cooling 10 yr cooling Np-237 57.9 % 41.3 Am-241 27.4 48.8* Am-243 11.9 8.33 Cm-243 0.03 0.02 Cm-244 2.67 1.44 Cm-245 0.15 0.10 Total 100 100 *Am-241 increases due to beta decay of Pu-241.
  • 89. Partitioning and Transmutation of HLW • By destruction of long-lived radionuclides in HLW, – Radioactivity and radiotoxicity of long-lived HLW are reduced – risk for future recovery of nuclear weapons materials from a final repository is reduced – additional nuclear energy is gained by fissioning minor actinides • For P-T, – Reprocessing is a prerequisite – Total radiological hazard arising from nuclear energy production must be reduced. – Secondary wastes from P-T processes must be taken into account. – Net energy production is desirable. – System must be economical.
  • 90. Processes for P-T • Partitioning – Conventional PUREX process + additional chemical partitioning process ex. for Np, TRUEX has been developed. – A process where separation of uranium and plutonium is combined with recovery of elements to be transmuted. ex. pyrochemical processing • Transmutation – Reactors • LWR, FBR for electricity generation + actinide burners • Th-U fuel cycle – Accelerator • high-energy proton spallation (n, fission), (n, gamma), (n, 2n), (n, p) reactions photo-nuclear reaction (gamma, n) – Fusion reactor
  • 92. Toxicity Index λ i Ni Toxicity index =Σ [m3] i Ci,k where Ci,k : radioactivity concentration limit for nuclide i in medium k (k = water or air) [Bq/m3], Ni: the number of atoms of nuclide I If more than one radionuclide is involved, a summation is performed over all the isotopes present in the mixture. Toxicity index is the volume of air or water with which the mixture of radionuclides must be diluted so that breathing the air or drinking the water will result in accumulation of radiation dose at a rate no greater than 0.5 rem/year.
  • 94. Geologic disposal and P&T (1) • 1970s – Several disposal concepts were investigated and compared from scientific viewpoints. – Geologic repository concept • 1977 Polvani Report (OECD/NEA) • 1977 Stripa Project in Sweden – Partitioning and Transmutation was proposed as an alternative to geologic disposal • 1980s – Scientific studies to demonstrate the safety of geologic disposal • OECD International Symposium on Safety assessment of radioactive waste repositories, Paris 1989 – Denial of P&T concepts as an alternative to geologic disposal • International Conference on Partitioning and Transmutation, Ispra, 1980 • UCBNE4176, Prof. T.H. Pigford, Paper presented at MIT conference • L. D. Ramspott, et al., “Impacts of New Developments in Partitioning and Transmutation on the Disposal of High-Level Nuclear Waste in a Mined Geologic Repository,” UCRL ID-109203, LLNL, March 1992.
  • 95. UCBNE4176, 1990 by Pigford (In the framework of 40CFR191) 1. By recycling actinides, the length of time that needs to be considered for geologic disposal would not decrease from 100,000 yr to 1000yr, as claimed by P&T studies. 2. P&T is not necessary to satisfy 40CFR191 requirement for cumulative release of radionuclides to the environment at 10,000yr. 3. To have significant reduction of actinide inventory in a cycle, it will require more than 1000 yr of operation of P&T system to reach a steady state. Even in such a case, reduction better than 1/1000 is not possible.
  • 96. Geologic disposal and P&T (2) • 1990s – Demonstration of geologic disposal concepts (more site specific studies) – Shifting from natural barrier to engineered barriers • TSPA studies in US for Yucca Mountain Repository • SKB report, Sweden, 1991 • H3 and H12 reports, Japan, 1991, 1999 – P&T to improve repository performance • EC/EU Framework • France: SPIN project • OECD/Japan OMEGA project • US Liquid metal cooled actinide burner with pyroprocessing at ANL • 2000s – Sites for repositories announced • YMR (US), Olkiluoto (Finland) – Repository capacity issue has emerged. – P&T and advanced fuel cycle • Generation IV • AFCI/GNEP
  • 97. Results of Swedish repository-performance study Dose limit (0.15mSv/y) I-129
  • 98. Water-Saturated repository (Japanese repository concept, H12) 4 10 3 10 Engineered Barrier System Calculated dose[μSv y -1] 2 Geosphere 10 1 Surface Environment 10 Lifestyle Total 0 10 Dose [ Sv/y] -1 10 Np-237 U-234 U-238 μ -2 10 -3 10 Th-229 -4 10 -5 10 -6 Se-79 Pb-210 10 -7 10 Cs-135 -8 10 100 101 102 103 104 105 106 107 108 Time after disposal [y] Time after disposal [y]
  • 99. Effects of P&T in terms of exposure dose rate (H12) 1.0E+00 1.0E-01 1.0E-02 Reference case 総線量 [μSv/y] 1.0E-03 1.0E-04 1.0E-05 99% actinide removed 1.0E-06 1.0E-07 1.0E+03 1.0E+04 1.0E+05 1.0E+06 1.0E+07 1.0E+08 Time after emplacement in repository, year 処分後の時間 [y] Wakasugi, et al., Personal communications
  • 100. Repository performance is insensitive to P/T application -- L. D. Ramspott, et al., “Impacts of New Developments in Partitioning and Transmutation on the Disposal of High-Level Nuclear Waste in a Mined Geologic Repository,” UCRL ID- 109203, LLNL, March 1992. All other things being equal, less inventory means less risk. However, the risk reduction benefits that P-T might offer depend on the release scenario involved, and in many cases, may not be as great as a 99.9% reduction in actinide inventory might suggest.
  • 101. So, can the environmental impact be reduced by recycle? • Yes, it can. • However, whether reduction is meaningful or not depends on – combination of (a) waste form, (b) separation efficiency, and (c) performance measures, suitable for geo-hydrological and geochemical conditions of the repository. • Environmental impact reduction would not necessarily be the motivation for recycle; – U resource utilization and proliferation resistance of the repository could be more important. • Environmental impacts from other parts of the fuel cycle would directly be imposed on the current people, not those in 10,000 years in future. Thus, comparison or combination with other EI should be done carefully.
  • 102. Week 3 (7/8): Societal and ethical issues of geologic disposal Development of societal agreement for geologic disposal Ethics of geologic disposal
  • 103. Development of societal agreement for geologic disposal
  • 104. The Repository World • Disposal in a geologic repository remains the preferred ultimate solution, with or without reprocessing • Much of the technical community has confidence in determining site suitability • A number of geologic media are being pursued • Most programs have experienced substantial difficulties • Siting remains the biggest hurdle • Increasing recognition of multi-disciplinary nature • Select ideas have become prominent, e.g. volunteer/veto, retrievability, monitoring, phased management • We will have storage for decades
  • 105. Some Highlights and Lowlights • National programs have been abandoned or siting stopped – France, U.K., Canada, Germany, Spain, Switzerland, U.S.A. • National (re)reviews have been undertaken – Canada, France, U.K.,… • Schedules have been delayed – Almost everywhere • Some countries have moved forward and others have restarted – Finland, Sweden, U.S.A., France, Canada, Japan, U.K….
  • 106. An (Optimistic) Current Snapshot • Countries with candidate sites – Finland, Sweden, U.S.A., France • Countries with programs underway – Canada, Belgium, Japan, U.K., Switzerland,… • Countries “thinking about it” – Spain, South Korea, China, India,… • Countries starting out – Argentina, Slovakia, Slovenia, South Africa,…
  • 107. The Seaborn Panel Conclusions (1998) --Canada-- • “From a technical perspective, safety of the AECL concept has been on balance adequately demonstrated for a conceptual stage of development. But from a social perspective, it has not.” • “As it stands, the AECL concept for deep geological disposal has not been demonstrated to have broad public support. The concept in its current form does not have the required level of acceptability to be adopted as Canada’s approach for managing nuclear fuel wastes.”
  • 108. NWMO Techniques for Broad Engagement
  • 109. “Choosing a Way Forward”: The Foundation • “…this generation of citizens which has enjoyed the benefits of nuclear energy has an obligation to begin provision for managing that waste.” • “…our obligation is to give them (succeeding generations) a real choice and the opportunity to shape their own decisions while at the same time not imposing a burden which future generations may not be able to manage.”
  • 110. “Choosing a Way Forward”: Some Key Recommendations • Sequential decision-making and flexibility in the pace and manner of implementation through “Adaptive Phased Management” • Ultimate centralized isolation in a deep geologic repository • Option for interim step of shallow underground storage at the central site • Program of continuous learning and R&D • Long-term monitoring with potential for retrievability • Seek an informed, willing community as host
  • 111. What makes nuclear waste management special? • The technical challenge – Performance over geological time – “Proof” not possible – Central role of “ologists” • The institutional challenge – The extraordinary time frame – Siting – Linkage to other agendas – Values and ethics in conflict – Political implications – Nuclear stigma and fears » But there are unique advantages…
  • 112. Virtues of a Repository • Passive • Occurrences will be slow • No inherent energy to release materials • Retrievable • Only a repository upon closure, when future generations are comfortable
  • 113. Some Key Enduring Features • Core, stable goal • Roles and responsibilities clear • Clear, open, and transparent decision making process • Respect for fairness and societal consent apparent • Sequential decision-making and contingency planning • Possibility of altering or reversing course • Appropriate compensation
  • 114. Some Potential Lessons Learned • Take the necessary time - go slow in order to go fast • Assign importance to the societal considerations as well as the technical ones • There are many ways to effectively engage the public and key stakeholders • Listening, respecting, and then responding can build trust and even advocacy, particularly with local community • Plan carefully and involve the right experts • Be prepared to respond in real time to unexpected events • Promise, then deliver, then do it again and again
  • 115. Ethics of geologic disposal
  • 116. three main virtues that have withstood the test of time • Humility • Charity • Veracity
  • 117. Humility Humility means you should treat yourself fully as one, but not more than one. • How does this apply when you have a group of people (a corporation/government) that want to install a nuclear plant/geologic repository? • Is it considering that that group of people may have different priorities than the group of people that they are affecting by installing the plant? • Is it the mentality that installing a power plant will affect each person in their own situation differently? • How do we reconcile these differences?
  • 118. Charity Charity means that you should treat others as fully one, just the same as you treat yourself. • Should the groups of people that run corporations consider the groups of people that are affected by their projects as equal to them? • Should the people that are affected consider the corporations equal? • Who’s right is it to decide whether a project should go forward? The people affected? Corporations? Government?
  • 119. Veracity Veracity simply means telling the truth. • It has already proven successful for some countries to be completely open and honest with the people who will be affected by power plant projects. • It has been shown that when the company or government that is planning the project takes the time to sit down and discuss the plans with the people, they are more receptive to the project. • How important is it when it comes to these issues for corporations? The government?
  • 120. Consequentialism (帰結主義) G.E.M. Anscombe, quot;Modern Moral Philosophyquot; (1958) • Actions are evaluated based on the results they achieve. • A morally right action is one that produces a good outcome, or consequence. • The ethical action is the one that maximizes overall good. • Such theories are labeled teleological(目的論的). • A consequentialist may argue that lying is wrong because of the negative consequences produced by lying — though a consequentialist may allow that certain foreseeable consequences might make lying acceptable.
  • 121. Utilitarianism(功利主義) John Stuart Mill's essay Utilitarianism (1861) • “the greatest good for the greatest number”(最大多数の最大幸福) • the moral worth of an action is solely determined by its contribution to overall utility, that is, its contribution to happiness or pleasure as summed among all persons.
  • 122. Deontology(義務論) • Actions are evaluated based on the motivation behind them. • Deontology derives the rightness or wrongness of an act from the character of the act itself. • A deontologist might argue that lying is always wrong, regardless of any potential quot;goodquot; that might come from lying.
  • 123. Kant’s three significant formulations of the categorical imperative (deontological) • Act only according to that maxim by which you can also will that it would become a universal law. • Act in such a way that you always treat humanity, whether in your own person or in the person of any other, never simply as a means, but always at the same time as an end. • Act as though you were, through your maxims, a law-making member of a kingdom of ends.
  • 124. Conflicting motives • Consequentialism seeks the best outcome, despite the action. • Deontology seeks the best action, despite the consequences.
  • 125. ANS Code of Ethics http://www.ans.org/about/coe/ 1. We hold paramount the safety, health, and welfare of the public and fellow workers, work to protect the environment, and strive to comply with the principles of sustainable development in the performance of our professional duties. 2. We will formally advise our employers, clients, or any appropriate authority and, if warranted, consider further disclosure, if and when we perceive that pursuit of our professional duties might have adverse consequences for the present or future public and fellow worker health and safety or the environment. (veracity)
  • 126. ANS Code of Ethics http://www.ans.org/about/coe/ 3. We act in accordance with all applicable laws and these Practices, lend support to others who strive to do likewise, and report violations to appropriate authorities. (veracity, humility) 4. We perform only those services that we are qualified by training or experience to perform, and provide full disclosure of our qualifications. (humility) 5. We present all data and claims, with their bases, truthfully, and are honest and truthful in all aspects of our professional activities. We issue public statements and make presentations on professional matters in an objective and truthful manner. (veracity)
  • 127. ANS Code of Ethics http://www.ans.org/about/coe/ 6. We continue our professional development and maintain an ethical commitment throughout our careers, encourage similar actions by our colleagues, and provide opportunities for the professional and ethical training of those persons under our supervision. 7. We act in a professional and ethical manner towards each employer or client and act as faithful agents or trustees, disclosing nothing of a proprietary nature concerning the business affairs or technical processes of any present or former client or employer without specific consent, unless necessary to abide by other provisions of this Code or applicable laws.
  • 128. ANS Code of Ethics http://www.ans.org/about/coe/ 8. We disclose to affected parties, known or potential conflicts of interest or other circumstances, which might influence, or appear to influence, our judgment or impair the fairness or quality of our performance. 9. We treat all persons fairly. (Charity) 10. We build our professional reputation on the merit of our services, do not compete unfairly with others, and avoid injuring others, their property, reputation, or employment. 11. We reject bribery and coercion in all their forms.
  • 129. ANS Code of Ethics http://www.ans.org/about/coe/ 12. We accept responsibility for our actions; are open to and acknowledge criticism of our work; offer honest criticism of the work of others; properly credit the contributions of others; and do not accept credit for work not our own. (humility, veracity)
  • 130. Ethics in Nuclear Engineering • ANS Code of Ethics reflects a Deontological approach of obeying a set of rules or principles. 9th point specifically mirrors Kant’s Categorical Imperative. • This contrasts, however, with the Consequentialism approach which is taken in the matter of waste disposal. • The potential for greater good for the greater number of people is considered more important than the action, which puts people at risk.
  • 131. Yucca Mountain • Yucca Mountain seemingly contradicts two tenets of the ANS Code of Ethics: – 1) welfare of the public, and – 9) We treat all persons fairly • is it fair that Nevada gets a site when they have no nuclear power, and have been lied to in the past? • Utilitarianism is the basis for ethics (greatest good for the greatest #), but we still shouldn’t violate the code of ethics, (#9)? • In utilitarianistic consideration, is future generation included?
  • 132. Week 4 (7/15): International aspects of nuclear power utilization (Introductory summary for nuclear activities in India) (Comparative discussions among Japan, US, and India)
  • 133. (Introductory summary for nuclear activities in India by Dr. R. K. Dayal, IGCAR)
  • 134. Topics to be Discussed in This Week • As Asian economy expands rapidly, so does energy demand in Asia. – Why is this so important to us (or the US)? • Nuclear Energy is an indispensable choice for Asian countries. – Are they ready for nuclear energy? – How will it influence the world in the future? – What is needed most there? And how can the US respond to such needs?
  • 135. http://www.peakoil.net/ (Association for the Study of Peak Oil & Gas)
  • 136.
  • 137.
  • 138.
  • 139. Chinese Development Plan of Nuclear Power Units to 2020 NPPs in operation and under construction 50000 Power Capacity (MWe) 45000 under construction 40000 in operation 35000 30000 25000 9,068MW 20000 7,860MW 1981-2007 15000 2004- 2014 10000 5000 0 19 1 1 1 1 2 2 2 2 2 8 2年 98 6年 99 0年 99 4年 99 8年 00 2年 00 6年 01 0年 01 4年 01 8年 26,000MW 2008- 2020 1.8% 4.0%
  • 140. Scenarios for Total Installed Power Capacity in India (DAE-2004 and Planning Commission-2006 studies) 1600 1400 1200 1000 GWe 800 600 400 200 0 1990 2000 2010 2020 2030 2040 2050 2060 Year DAE PC_GDP-Growth 8% PC_GDP-Growth 9%
  • 141. Electricity growth rate – a scenario Primary Electricity Period energy % annual % annual growth 2002-2022 growth 4.6 6.3 2022-2032 4.5 4.9 2032-2042 4.5 4.6 2042-2052 3.9 3.9 Per Capita Generation (kWh) 6000 5305 5000 3699 4000 3000 2454 2000 1620 1000 1000 613 0 2002 2012 2022 2032 2042 2052 Time period
  • 142. GDP/capita vs. kWh/capita US (2006) ($44,000, 13,000 kWh) 10000 Singapore Brunei Japan From 1999 to 2006 Hong Kong South Korea Malaysia kWh/capita China Thailand 1000 Philippines India Indonesia Sri Lanka 100 100 1000 10000 100000 GDP/capita (US$)
  • 143. By Increase in Energy Consumption in Asia .... • Global Environment – CO2, SOx, NOx emissions • Greenhouse effect, Acid Rain, etc. • Competition for Limited Resources • Nuclear Safety and Security • International System – If nuclear energy is developed on a large scale, restructuring of international organizations for safeguards will be necessary.
  • 144. The Global Nuclear Energy Partnership Objectives are Stated in The National Security Strategy • The United States “will build the Global Nuclear Energy Partnership to work with other nations to develop and deploy advanced nuclear recycling and reactor technologies. • This initiative will help provide reliable, emission-free energy with less of the waste burden of older technologies and without making available separated plutonium that could be used by rogue states or terrorists for nuclear weapons. • These new technologies will make possible a dramatic expansion of safe, clean nuclear energy to help meet the growing global energy demand.”
  • 146. Spent fuel accumulation in South Korea 90 Spent Fuel Accumulation (ktHM) Accumulated SF Arisings (ktHM) 80 70 60 50 PWR 40 30 20 CANDU 10 0 2005 2015 2025 2035 2045 2055 2065 2075 2085 2095 Year
  • 148. Discussion topics • Developed vs. developing countries – Resources – Global environment – Proliferation resistance – Access to technologies • For whom? Why? • Current vs. future generations – Resources – Global environment • Nuclear vs. non-nuclear communities – Public perception and communication – Decision making processes