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Nuclear Fuels Storage & Transportation Planning Project
Office of Fuel Cycle Technologies
Nuclear Energy
Overview of DOE-NE’s
Nuclear Fuels Storage
and Transportation
Planning Project (NFST)
Joe Carter
Storage Control Account Manager of the DOE-NE’s
Nuclear Fuels Storage and Transportation
Planning Project
(Savannah River National Laboratory)
UFD R&D Working Group Meeting
June 7, 2016
Las Vegas, NV
2
DOE-NE’s NFST Program is Planning for
Interim Storage and Transportation as
Part of an Integrated Waste Management
System
Mission
 Lay the groundwork for implementing interim storage, including
associated transportation, per the Administration’s Strategy for the
Management and Disposal of Used Nuclear Fuel and High-Level
Radioactive Waste
 Develop the foundation for a new nuclear waste management
organization
Purpose
 Make progress on this important national issue within existing
legislative and budget authorizations
June 7, 2016 UFD R&D Working Group Meeting
3
Strategy for the Management and
Disposal of Used Nuclear Fuel and
High-Level Radioactive Waste Guides
NFST’s Activities
 “With the appropriate authorizations from Congress, the
Administration currently plans to implement a program
… that:
 Sites, designs and licenses, constructs and begins operations of
a pilot interim storage facility … with an initial focus on
accepting used nuclear fuel from shut-down reactor sites;
 Advances toward the siting and licensing of a larger interim
storage facility … that will have sufficient capacity to provide
flexibility in the waste management system and allows for
acceptance of enough used nuclear fuel to reduce expected
government liabilities; and
 Makes demonstrable progress on the siting and characterization of
repository sites to facilitate the availability of a geologic repository”
June 7, 2016 UFD R&D Working Group Meeting
4
Near-Term Objectives to Lay the
Groundwork for Strategy Implementation
 Develop and maintain an integrated plan to accomplish the Strategy goals
 Improve integration of storage as a planned part of the waste management
system, including evaluating standardization of dry cask storage systems
 Develop and evaluate facility design options for an integrated waste
management system
 Develop and apply systems analyses to provide quantitative estimates of
system impacts of utility and federal actions and inform future decisions
 Establish the basis and identify options for management decisions on an
integrated waste management system
 Prepare for the large-scale transportation of SNF and HLW, with an initial
focus on removing SNF from the shutdown reactor sites
 Establish and maintain a unified and integrated SNF database and analysis
system to characterize the input to the waste management system
June 7, 2016 UFD R&D Working Group Meeting
5
DOE-NE’s NFST Program is Organized
into Four Key Elements
* Indicates areas that are
not currently active
Consent-Based
Siting
• Siting process design
• Communication products
• Site evaluation and selection*
• Site acquisition*
Transportation
• Institutional
• Operational
• Hardware
Storage
• Design
• NEPA
• Regulatory
• Construction*
• Operations*
Strategic
Crosscuts
• Project management
• Systems analyses
• Data/document access
• Standardization/
integration
• Characterization and
Assessment
June 7, 2016 UFD R&D Working Group Meeting
6
Supporting the Development of a
Publicly Accepted Consent-
Based Siting Process
 To launch the consent-based siting
effort, the DOE issued an Invitation for
Public Comment in the Federal
Register soliciting input on important
considerations in designing a fair and
effective process for siting
• Input can be provided in response to
the Invitation for Public Comment in the
Federal Register or via email at
consentbasedsiting@hq.doe.gov
 DOE is holding public meetings
around the country to hear from the
public, communities, states, Tribes,
and all interested stakeholders on
what matters to them in moving
forward in developing a consent-based
process
http://www.energy.gov/ne/consent-based-siting
June 7, 2016 UFD R&D Working Group Meeting
7
Supporting the Development of a
Publicly Accepted Consent-
Based Siting Process
 Continue populating and maintaining a database of prior siting efforts
• http://curie.ornl.gov/SED/pages/sed-homepage
 Continue gaining additional insights on public preference
 Developing communication products to support public interactions
June 7, 2016 UFD R&D Working Group Meeting
8
 Evaluating interim storage design concepts,
with input from industry contractors
• Generic Design Alternatives for Dry Storage of
Used Nuclear Fuel (CB&I)
 Preparing to develop a generic pilot ISF
design and Topical Safety Analysis Report
• Procurement underway
 Initiating development of a draft licensing
strategy for a pilot ISF
 Initiating development of an environmental
considerations document
 Continuing efforts related to Aging
Management at an ISF
• Participation in EPRI ESCP
• ASME code case: Examination Requirements and
Acceptance Standards for Spent Fuel Storage and
Transportation Canisters
Laying the Groundwork for
Consolidated Interim Storage
June 7, 2016 UFD R&D Working Group Meeting
9
Dry Storage Design Concepts for
Consolidated Interim Storage
(Flexible, Adaptable, and Expandable)
 Dry Storage Alternatives
• Pad storage using currently licensed storage
overpacks
– New concrete overpacks
• Vault configurations
– Horizontal, vertical
– Above and below grade
 Canister Receipt
• Commercially available transfer systems
– Mobile cranes, no weather enclosure
– Installed cranes, weather enclosure
• Canister transfer building
• Canister transfer building with remote operations
 Tradeoffs associated with each concept
 Input to integrated waste management
system analysis
June 7, 2016 UFD R&D Working Group Meeting
10
Developing the Large-Scale
Transportation System
 Continuing interaction and collaboration with
stakeholders
• Developing plans for transportation operations
• Understanding rail route selection and rail inspection options
• Working to finalize DOE’s Section 180(c) Policy
 Continuing development of the Stakeholder
Tool for Assessing Radioactive
Transportation (START)
 DOE is developing a railcar to comply with the Association of
American Railroads Standard S-2043
• Contract with AREVA to design S-2043-compliant cask and buffer railcars, and to
fabricate prototypes
• Future contract for prototype testing
• DOE is evaluating several possible contracting options for large-scale fleet fabrication
and operations
Note: Route shown for illustrative purposes only
June 7, 2016 UFD R&D Working Group Meeting
11
Potential Transportation
Routes Generated by
START
 START generates potential routes for possible future transportation operations
• Web-based application of geographic information system (GIS) data and analysis
• Includes transportation infrastructure for rail, truck, and barge
• Uses data related to populations, land uses, emergency response, etc.
• Ability to generate multiple routes based on user requests
Min population
Min travel time
(with restrictions)
Min travel time
Example route is for illustrative purposes only and does not reflect a selected destination site
June 7, 2016 UFD R&D Working Group Meeting
12
Developing the Large-Scale
Transportation System
 Planning efforts to remove SNF from shutdown
reactor sites
• Collecting and documenting information related to site
inventory, site conditions, and near-site transportation
infrastructure and experience
• Visited 12 of the 13 shutdown sites: Vermont Yankee
visit May 10-12
• Updating the shutdown sites report
• Preparing initial site-specific de-inventory analysis for
five shutdown sites
– Understanding of the tasks and interfaces necessary for the
complete de-inventory
• Connecticut Yankee, Big Rock Point, Humbolt Bay, Trojan, Maine
Yankee
MP187 Transportation Cask Heavy Haul to Rancho Seco
June 7, 2016 UFD R&D Working Group Meeting
13
Integrated Waste Management
System Analysis Tool Hierarchy
June 7, 2016 UFD R&D Working Group Meeting
14
 Used Nuclear Fuel Storage, Transportation, & Disposal Analysis
Resource and Data System (UNF-ST&DARDS)
• Data and SNF characteristics
 Transportation Storage and Logistics (TSL) & Next Generation System
Analysis Model (NGSAM)
• Alternative configurations and concepts of operations
 Stakeholder Tool for Assessing Radioactive Transportation (START)
• Identification of potential transportation routes
 Execution Strategy Analysis (ESA)
• Alternative implementation strategies
 Multi-Evaluation Objective Framework (MOEF)
• Assessing alternatives against objectives and stakeholder perspectives
 Centralized Used Fuel Resource for Information Exchange (CURIE)
• Sharing data, analysis, and reports
Integrated Waste Management
System Analysis Tool Hierarchy
June 7, 2016 UFD R&D Working Group Meeting
15
Consistent, Reliable Data is
Maintained in UNF-ST&DARDS
 The consistency, quality, and traceability of the information and data
used by our system tools is paramount.
 The Unified Database in UNF-ST&DARDS
• Provides for consolidation, collection, archival, and distribution of
traceable SNF data
 UNF-ST&DARDS (Used Nuclear Fuel Storage, Transportation, &
Disposal Analysis Resource and Data System)
• Builds the foundation for all future SNF and system analysis
• Enables SNF characterization
• Enables realistic safety margins
June 7, 2016 UFD R&D Working Group Meeting
16
UNF-ST&DARDS Performs the SNF
Characterization that is Required
by All Other Tools
Models
• Depletion:
Triton,
ORIGEN
• Thermal:
COBRA-SFS
• Criticality:
KENO-VI
• Dose
• Containment
• Fuel
Performance
• Assembly ID
• Assembly
type
• Initial
enrichment
• Discharge
burnup
• Cycle start
and end
dates
• Geometric
configuration
• Materials of
construction
• Design
dimensions
• Control
components
• Cycle
specific
burnup
• Soluble
boron
• Rod insertion
history
• Batch
loadings
• Axial burnup
profiles
• Moderator
temperature
• Geometric
configuration
• Materials of
construction
• Design
dimensions
• Cask
loading
patterns
• Component
loading
859 data
Assembly data
Reactor data
Cask data
 Depletion
• How much and which
isotopes are in the SNF at
a given time?
 Shielding
• What are the dose rates in
storage and transportation
configurations?
 Criticality
• What are margins to
criticality?
 Thermal
• What are the SNF components (e.g., cladding, basket, fuel)
temperature?
June 7, 2016 UFD R&D Working Group Meeting
17
System Architecture Analysis is
Used to Answer Many Important
Questions
 What are the strategies for removing SNF from the reactor sites?
 What are the transportation assets needed and facilities that must be
constructed for different alternatives?
 How much will it cost to
construct and operate?
 How would multiple ISFs
impact system performance
metrics?
• Costs
• Transportation
• Etc.
Utilizes Transportation
Storage and Logistics
(TSL) & Next
Generation System
Analysis Model
(NGSAM) tools
June 7, 2016 UFD R&D Working Group Meeting
18
Current Capabilities Provide
Rough-Order-of-Magnitude
Estimates of Costs, Materials,
Asset Needs, etc.
 The Transportation Storage
Logistics (TSL) simulator models
the following activities
• Assembly discharges
• Transfer of SNF to dry storage
• At-reactor and ISF pool capacity
• Canister/Cask loading
• Canister/Cask /Overpack thermal
limits
• Some ISF and repository
operational requirements
• Acceptance rates from reactors
• Allocation strategies (i.e., which
reactors go when)
June 7, 2016 UFD R&D Working Group Meeting
19
Improve Waste Management
System Architecture Analysis
Capabilities
 A new tool, NGSAM, designed to simulate a broad range of scenarios to:
• Provide quantitative information about alternatives
• Evaluate at-reactor constraints on system performance
• Evaluate multiple ISFs with different operational profiles
• More accurately model system-wide impacts of:
– Repository emplacements limits
– Transportation requirements
– Facility operational limitations
 Current Capabilities
• Detailed at-reactor operations
– benchmarking ongoing
• High-level modeling of the ISF, disposal
canister packaging, and repository
• Linked with Unified Database
• Platform/Operating System independent
– Mac, Windows, Linux
June 7, 2016 UFD R&D Working Group Meeting
20
ESA Analyzes Alternative
Implementation Strategies,
Including the Impacts of Risks
and Uncertainties
 The ESA approach builds on traditional project management tools
(i.e., Gantt Charts, WBS) and provides additional insight
• Constraints
– Policy, legislation, regulatory
• Explicitly models
– uncertainty and its impacts
– risks and opportunities
• Allows for the assessment of alternative
implementation scenarios
ESA improves understanding of
the effects of uncertainty and the
potential impacts of risks and
opportunities
June 7, 2016 UFD R&D Working Group Meeting
21
Multi-Objective Evaluation
Framework to Evaluate
Alternatives in a Structured
Manner
 Nuclear waste management is a
complex socio-technical problem
 Multi-objective evaluation is based
on the principles and methods of
decision analysis
• Used in engineering, business, and
policy analysis
 Objective is to apply a systematic methodology to evaluation alternatives
for consideration by decision makers.
Loading standard transportation,
aging, and disposal canisters
(STADs) at Reactor Sites
Reactor Priority Perspective
June 7, 2016 UFD R&D Working Group Meeting
22
Data, Analyses, and Reports are
Shared Using the CURIE Website
 Advanced search functionality
 Public and private collaboration
environments
 Up-to-date, permissions-based
event calendar
 Image galleries
 Automated, live news feed
 Siting Experience Database
• BRC near-term recommendation
 Map-based visualization of
reactor- and site-specific storage
information
June 7, 2016 UFD R&D Working Group Meeting
23
Users Can Display UNF-
ST&DARDS Data Using the Map
Function on CURIE
 The initial integration of CURIE and UNF-ST&DARDS provides user access
and visualization of SNF data not otherwise available in a centralized
location
• Visualization of numerous SNF data and reactor sites
• Data can be filtered by site, state, operating status, etc.
June 7, 2016 UFD R&D Working Group Meeting
24
Laying the Groundwork for
Standardization
 Furthering the quantitative assessment of
relevant options to establish basis for future
decision making
• Standardization at an ISF and alternative SNF
acceptance approaches
• Included representative repository concepts
 Utilized industry contracts to obtain
needed additional information
• Generic design for small size STAD canister system
(EnergySolutions)
• Investigated operational aspects for implementation
of STAD canister systems at operating reactors
(EnergySolutions)
 Developed a Standardized Transportation, Aging,
and Disposal (STAD) canister specification and
specification rationale to support system studies
and potential research, development, and
demonstration activities
Comparison of ROM system cost of different initial
canister loading strategies and disposal in small (4 PWR)
canisters
June 7, 2016 UFD R&D Working Group Meeting
25
Questions & Discussion
June 7, 2016 UFD R&D Working Group Meeting

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5 june 7 nfstpp overview and relationship to ufd_carter

  • 1. Nuclear Fuels Storage & Transportation Planning Project Office of Fuel Cycle Technologies Nuclear Energy Overview of DOE-NE’s Nuclear Fuels Storage and Transportation Planning Project (NFST) Joe Carter Storage Control Account Manager of the DOE-NE’s Nuclear Fuels Storage and Transportation Planning Project (Savannah River National Laboratory) UFD R&D Working Group Meeting June 7, 2016 Las Vegas, NV
  • 2. 2 DOE-NE’s NFST Program is Planning for Interim Storage and Transportation as Part of an Integrated Waste Management System Mission  Lay the groundwork for implementing interim storage, including associated transportation, per the Administration’s Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste  Develop the foundation for a new nuclear waste management organization Purpose  Make progress on this important national issue within existing legislative and budget authorizations June 7, 2016 UFD R&D Working Group Meeting
  • 3. 3 Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste Guides NFST’s Activities  “With the appropriate authorizations from Congress, the Administration currently plans to implement a program … that:  Sites, designs and licenses, constructs and begins operations of a pilot interim storage facility … with an initial focus on accepting used nuclear fuel from shut-down reactor sites;  Advances toward the siting and licensing of a larger interim storage facility … that will have sufficient capacity to provide flexibility in the waste management system and allows for acceptance of enough used nuclear fuel to reduce expected government liabilities; and  Makes demonstrable progress on the siting and characterization of repository sites to facilitate the availability of a geologic repository” June 7, 2016 UFD R&D Working Group Meeting
  • 4. 4 Near-Term Objectives to Lay the Groundwork for Strategy Implementation  Develop and maintain an integrated plan to accomplish the Strategy goals  Improve integration of storage as a planned part of the waste management system, including evaluating standardization of dry cask storage systems  Develop and evaluate facility design options for an integrated waste management system  Develop and apply systems analyses to provide quantitative estimates of system impacts of utility and federal actions and inform future decisions  Establish the basis and identify options for management decisions on an integrated waste management system  Prepare for the large-scale transportation of SNF and HLW, with an initial focus on removing SNF from the shutdown reactor sites  Establish and maintain a unified and integrated SNF database and analysis system to characterize the input to the waste management system June 7, 2016 UFD R&D Working Group Meeting
  • 5. 5 DOE-NE’s NFST Program is Organized into Four Key Elements * Indicates areas that are not currently active Consent-Based Siting • Siting process design • Communication products • Site evaluation and selection* • Site acquisition* Transportation • Institutional • Operational • Hardware Storage • Design • NEPA • Regulatory • Construction* • Operations* Strategic Crosscuts • Project management • Systems analyses • Data/document access • Standardization/ integration • Characterization and Assessment June 7, 2016 UFD R&D Working Group Meeting
  • 6. 6 Supporting the Development of a Publicly Accepted Consent- Based Siting Process  To launch the consent-based siting effort, the DOE issued an Invitation for Public Comment in the Federal Register soliciting input on important considerations in designing a fair and effective process for siting • Input can be provided in response to the Invitation for Public Comment in the Federal Register or via email at consentbasedsiting@hq.doe.gov  DOE is holding public meetings around the country to hear from the public, communities, states, Tribes, and all interested stakeholders on what matters to them in moving forward in developing a consent-based process http://www.energy.gov/ne/consent-based-siting June 7, 2016 UFD R&D Working Group Meeting
  • 7. 7 Supporting the Development of a Publicly Accepted Consent- Based Siting Process  Continue populating and maintaining a database of prior siting efforts • http://curie.ornl.gov/SED/pages/sed-homepage  Continue gaining additional insights on public preference  Developing communication products to support public interactions June 7, 2016 UFD R&D Working Group Meeting
  • 8. 8  Evaluating interim storage design concepts, with input from industry contractors • Generic Design Alternatives for Dry Storage of Used Nuclear Fuel (CB&I)  Preparing to develop a generic pilot ISF design and Topical Safety Analysis Report • Procurement underway  Initiating development of a draft licensing strategy for a pilot ISF  Initiating development of an environmental considerations document  Continuing efforts related to Aging Management at an ISF • Participation in EPRI ESCP • ASME code case: Examination Requirements and Acceptance Standards for Spent Fuel Storage and Transportation Canisters Laying the Groundwork for Consolidated Interim Storage June 7, 2016 UFD R&D Working Group Meeting
  • 9. 9 Dry Storage Design Concepts for Consolidated Interim Storage (Flexible, Adaptable, and Expandable)  Dry Storage Alternatives • Pad storage using currently licensed storage overpacks – New concrete overpacks • Vault configurations – Horizontal, vertical – Above and below grade  Canister Receipt • Commercially available transfer systems – Mobile cranes, no weather enclosure – Installed cranes, weather enclosure • Canister transfer building • Canister transfer building with remote operations  Tradeoffs associated with each concept  Input to integrated waste management system analysis June 7, 2016 UFD R&D Working Group Meeting
  • 10. 10 Developing the Large-Scale Transportation System  Continuing interaction and collaboration with stakeholders • Developing plans for transportation operations • Understanding rail route selection and rail inspection options • Working to finalize DOE’s Section 180(c) Policy  Continuing development of the Stakeholder Tool for Assessing Radioactive Transportation (START)  DOE is developing a railcar to comply with the Association of American Railroads Standard S-2043 • Contract with AREVA to design S-2043-compliant cask and buffer railcars, and to fabricate prototypes • Future contract for prototype testing • DOE is evaluating several possible contracting options for large-scale fleet fabrication and operations Note: Route shown for illustrative purposes only June 7, 2016 UFD R&D Working Group Meeting
  • 11. 11 Potential Transportation Routes Generated by START  START generates potential routes for possible future transportation operations • Web-based application of geographic information system (GIS) data and analysis • Includes transportation infrastructure for rail, truck, and barge • Uses data related to populations, land uses, emergency response, etc. • Ability to generate multiple routes based on user requests Min population Min travel time (with restrictions) Min travel time Example route is for illustrative purposes only and does not reflect a selected destination site June 7, 2016 UFD R&D Working Group Meeting
  • 12. 12 Developing the Large-Scale Transportation System  Planning efforts to remove SNF from shutdown reactor sites • Collecting and documenting information related to site inventory, site conditions, and near-site transportation infrastructure and experience • Visited 12 of the 13 shutdown sites: Vermont Yankee visit May 10-12 • Updating the shutdown sites report • Preparing initial site-specific de-inventory analysis for five shutdown sites – Understanding of the tasks and interfaces necessary for the complete de-inventory • Connecticut Yankee, Big Rock Point, Humbolt Bay, Trojan, Maine Yankee MP187 Transportation Cask Heavy Haul to Rancho Seco June 7, 2016 UFD R&D Working Group Meeting
  • 13. 13 Integrated Waste Management System Analysis Tool Hierarchy June 7, 2016 UFD R&D Working Group Meeting
  • 14. 14  Used Nuclear Fuel Storage, Transportation, & Disposal Analysis Resource and Data System (UNF-ST&DARDS) • Data and SNF characteristics  Transportation Storage and Logistics (TSL) & Next Generation System Analysis Model (NGSAM) • Alternative configurations and concepts of operations  Stakeholder Tool for Assessing Radioactive Transportation (START) • Identification of potential transportation routes  Execution Strategy Analysis (ESA) • Alternative implementation strategies  Multi-Evaluation Objective Framework (MOEF) • Assessing alternatives against objectives and stakeholder perspectives  Centralized Used Fuel Resource for Information Exchange (CURIE) • Sharing data, analysis, and reports Integrated Waste Management System Analysis Tool Hierarchy June 7, 2016 UFD R&D Working Group Meeting
  • 15. 15 Consistent, Reliable Data is Maintained in UNF-ST&DARDS  The consistency, quality, and traceability of the information and data used by our system tools is paramount.  The Unified Database in UNF-ST&DARDS • Provides for consolidation, collection, archival, and distribution of traceable SNF data  UNF-ST&DARDS (Used Nuclear Fuel Storage, Transportation, & Disposal Analysis Resource and Data System) • Builds the foundation for all future SNF and system analysis • Enables SNF characterization • Enables realistic safety margins June 7, 2016 UFD R&D Working Group Meeting
  • 16. 16 UNF-ST&DARDS Performs the SNF Characterization that is Required by All Other Tools Models • Depletion: Triton, ORIGEN • Thermal: COBRA-SFS • Criticality: KENO-VI • Dose • Containment • Fuel Performance • Assembly ID • Assembly type • Initial enrichment • Discharge burnup • Cycle start and end dates • Geometric configuration • Materials of construction • Design dimensions • Control components • Cycle specific burnup • Soluble boron • Rod insertion history • Batch loadings • Axial burnup profiles • Moderator temperature • Geometric configuration • Materials of construction • Design dimensions • Cask loading patterns • Component loading 859 data Assembly data Reactor data Cask data  Depletion • How much and which isotopes are in the SNF at a given time?  Shielding • What are the dose rates in storage and transportation configurations?  Criticality • What are margins to criticality?  Thermal • What are the SNF components (e.g., cladding, basket, fuel) temperature? June 7, 2016 UFD R&D Working Group Meeting
  • 17. 17 System Architecture Analysis is Used to Answer Many Important Questions  What are the strategies for removing SNF from the reactor sites?  What are the transportation assets needed and facilities that must be constructed for different alternatives?  How much will it cost to construct and operate?  How would multiple ISFs impact system performance metrics? • Costs • Transportation • Etc. Utilizes Transportation Storage and Logistics (TSL) & Next Generation System Analysis Model (NGSAM) tools June 7, 2016 UFD R&D Working Group Meeting
  • 18. 18 Current Capabilities Provide Rough-Order-of-Magnitude Estimates of Costs, Materials, Asset Needs, etc.  The Transportation Storage Logistics (TSL) simulator models the following activities • Assembly discharges • Transfer of SNF to dry storage • At-reactor and ISF pool capacity • Canister/Cask loading • Canister/Cask /Overpack thermal limits • Some ISF and repository operational requirements • Acceptance rates from reactors • Allocation strategies (i.e., which reactors go when) June 7, 2016 UFD R&D Working Group Meeting
  • 19. 19 Improve Waste Management System Architecture Analysis Capabilities  A new tool, NGSAM, designed to simulate a broad range of scenarios to: • Provide quantitative information about alternatives • Evaluate at-reactor constraints on system performance • Evaluate multiple ISFs with different operational profiles • More accurately model system-wide impacts of: – Repository emplacements limits – Transportation requirements – Facility operational limitations  Current Capabilities • Detailed at-reactor operations – benchmarking ongoing • High-level modeling of the ISF, disposal canister packaging, and repository • Linked with Unified Database • Platform/Operating System independent – Mac, Windows, Linux June 7, 2016 UFD R&D Working Group Meeting
  • 20. 20 ESA Analyzes Alternative Implementation Strategies, Including the Impacts of Risks and Uncertainties  The ESA approach builds on traditional project management tools (i.e., Gantt Charts, WBS) and provides additional insight • Constraints – Policy, legislation, regulatory • Explicitly models – uncertainty and its impacts – risks and opportunities • Allows for the assessment of alternative implementation scenarios ESA improves understanding of the effects of uncertainty and the potential impacts of risks and opportunities June 7, 2016 UFD R&D Working Group Meeting
  • 21. 21 Multi-Objective Evaluation Framework to Evaluate Alternatives in a Structured Manner  Nuclear waste management is a complex socio-technical problem  Multi-objective evaluation is based on the principles and methods of decision analysis • Used in engineering, business, and policy analysis  Objective is to apply a systematic methodology to evaluation alternatives for consideration by decision makers. Loading standard transportation, aging, and disposal canisters (STADs) at Reactor Sites Reactor Priority Perspective June 7, 2016 UFD R&D Working Group Meeting
  • 22. 22 Data, Analyses, and Reports are Shared Using the CURIE Website  Advanced search functionality  Public and private collaboration environments  Up-to-date, permissions-based event calendar  Image galleries  Automated, live news feed  Siting Experience Database • BRC near-term recommendation  Map-based visualization of reactor- and site-specific storage information June 7, 2016 UFD R&D Working Group Meeting
  • 23. 23 Users Can Display UNF- ST&DARDS Data Using the Map Function on CURIE  The initial integration of CURIE and UNF-ST&DARDS provides user access and visualization of SNF data not otherwise available in a centralized location • Visualization of numerous SNF data and reactor sites • Data can be filtered by site, state, operating status, etc. June 7, 2016 UFD R&D Working Group Meeting
  • 24. 24 Laying the Groundwork for Standardization  Furthering the quantitative assessment of relevant options to establish basis for future decision making • Standardization at an ISF and alternative SNF acceptance approaches • Included representative repository concepts  Utilized industry contracts to obtain needed additional information • Generic design for small size STAD canister system (EnergySolutions) • Investigated operational aspects for implementation of STAD canister systems at operating reactors (EnergySolutions)  Developed a Standardized Transportation, Aging, and Disposal (STAD) canister specification and specification rationale to support system studies and potential research, development, and demonstration activities Comparison of ROM system cost of different initial canister loading strategies and disposal in small (4 PWR) canisters June 7, 2016 UFD R&D Working Group Meeting
  • 25. 25 Questions & Discussion June 7, 2016 UFD R&D Working Group Meeting