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By:
Inderjit Birdee
Tsvetoslav Pavlov
Marino Panayiotou
Laura Hare
Zhi Xiong Chong
Problem - Sizewell B
 A pressurized water reactor (PWR) nuclear power plant
    Net electrical output of 1191MW (Supplies 2.5 million
     homes)
    East Coast of England near Sizewell town
 Storage pool for spent fuel to reach max capacity by 2015
 Hence the need for reprocessing
    97% recyclability of spent fuel


  Devise a mean for transporting the 50 fuel assemblies/ year
   which have been stored for 5 years in the wet storage
   facility at Sizewell B
Solution- spent nuclear fuel transport
cask
  Essentially a container which facilitates the
   transportation of spent nuclear fuel from power plants
   to nuclear reprocessing sites
  Maintains integrity &provides safety




 Constor- Spent Nuclear Fuel Storage and Transport Cask System. Peters, Dr. Ralf, et
al., et al. 1999.
Radiation
 Spent nuclear fuel produces radiation
    High penetration: Neutron and Gamma
    Low penetration: Alpha and Beta


   How to stop radiation?              Main Concern
   How to contain the radioactivity?
   How to prevent leakage?
Coolant
 Purpose: Transfer heat efficiently
 Material: Water
 Features: Recombiner
Basket
 Purpose: sub-criticality &
 structural integrity
 Material: Neutronit
  A976 (Type 316)
 Features: holes and
  discs
 Manufacturing: powder
  metallurgy and welding
Inner Vessel
 Purpose: Dissipates heat efficiently
 Material: INCONEL Alloy 22
 Manufacturing:
   Hot Rolled at 1100oC for 2hrs
   Air cooled at 800oC for 4 hrs, then at 700oC for 3 hours




                                      http://www.jignasteel.net/metal-
                                      sheets-plates.html
Sandwich Layer



             Purpose: Radiation Shielding
             Materials: DUCRETE
             Features: Solid Uniform Layer
             Manufacturing: DUF6 is converted
              to DUO2. Encapsulation of synthetic-
              basalt-based binder by sintering to
              prevent further oxidation.
 Manufacturing: DUF6 is converted to DUO2.
 Encapsulation of synthetic-basalt-based binder by
 sintering to prevent further oxidation.
Depleted uranium as aggregate in concrete shielding material. Lese
Dole, Catherine Mattus, Juan Ferrada. s.l. : Oak ridge national laboratory.
Outer Layer
 Purpose: Provide structural integrity
 Materials: Stainless Steel with Ti
 Features:
    Impact resistance
    Rapid heat dissipation
    Corrosion resistance
Honeycomb-structured Overlay
 Purpose:
    Heat dissipation through air convection
    Flame resistance
 Materials: Slotted Honeycomb Structure – Stainless
  Steel
 Manufacturing: corrugation + annealing with
  polymer-based cement
Lids
 Purpose: Structural integrity, maintain internal
  pressure, prevent leakages
 Features:
   3 lid system
   Metallic and elastomeric O-rings
                                                                                                  Basic O-Ring Elastomers. Ltd, Toparts PTE.
                                                                                                  2007, Toparts.
   B0lts (12.9 A4 stainless steel)
   Pressure sensors
   Resin




            Development of 300oc heat resitant borno-loaded resin for neutron sheilding.
            Morioka, Atsuhiko, et al., et al. 2007, Journal of Nuclear Materials, pp. 1085-1089
 Materials:
   Primary lid – INCONEL alloy 22
   Secondary/Tertiary lid – Stainless Steel 316-Ti
   Elastomeric O-ring - Perfluorinated Elastomer
 Manufacturing: Mainly Press Forging with welding




           http://www.kimbermills.co.uk/processes/press_forging.
Cross section of Lids
Trunnions
 Two main purposes: - Lifting – Securing
 Material: stainless steel grade 316
    Corrosion resistance –Strength – Compatibility
 Features
    Four present on cask
    Many bolts used to disperse load
 Good suitability for all common forming methods and
 has a well defined heat treatment programme
Trunnions
Impact limiters
 Purpose: Acts like packaging to absorb energy and
  minimise damage during accident conditions
 Materials:
   Al 6061 shell
       Light weight alloy and good corrosion resistance
   Closed cell polystyrene foam inner
       Excellent energy absorbance per unit volume
       Very low density
   TWIP steel reinforcing
       Very high strength and very ductile
Logistics summary
 1.4 mile journey by road and remainder by rail
 Rail dictates 65 tonne weight limit and constrains
 dimensions to 2.8 m diameter and 26 m long
Tests- Radiation calculations and FEA
 Radiation calculations – combined dose of around
  10mSv/h, 1m away from the cask
 Finite Element Analysis
  Water immersion test   1 m drop test       9m drop test
Safety features
   Time

   Distance

   Protection

   Monitoring


                                http://www.skoda-js.cz/
                  http://rampac.energy.gov/PCN/P12.pdf
Summary of design
 Bespoke cask design
 Efficient
 Safe
 Well understood technology
Conclusion
 Transferring spent nuclear fuel assemblies from
  Sizewell B nuclear reactor to a reprocessing plant via
  network rail
 Safety considerations by far the most important
   Heat dissipation
   Impact resistance
   Sub-criticality


  A secure method to transport spent nuclear fuel achieved
    by our materials selection, structural design & efficient
    logistics

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Design Study on Nuclear Transportation Cask

  • 1. By: Inderjit Birdee Tsvetoslav Pavlov Marino Panayiotou Laura Hare Zhi Xiong Chong
  • 2. Problem - Sizewell B  A pressurized water reactor (PWR) nuclear power plant  Net electrical output of 1191MW (Supplies 2.5 million homes)  East Coast of England near Sizewell town  Storage pool for spent fuel to reach max capacity by 2015  Hence the need for reprocessing  97% recyclability of spent fuel Devise a mean for transporting the 50 fuel assemblies/ year which have been stored for 5 years in the wet storage facility at Sizewell B
  • 3. Solution- spent nuclear fuel transport cask  Essentially a container which facilitates the transportation of spent nuclear fuel from power plants to nuclear reprocessing sites  Maintains integrity &provides safety Constor- Spent Nuclear Fuel Storage and Transport Cask System. Peters, Dr. Ralf, et al., et al. 1999.
  • 4. Radiation  Spent nuclear fuel produces radiation  High penetration: Neutron and Gamma  Low penetration: Alpha and Beta How to stop radiation? Main Concern How to contain the radioactivity? How to prevent leakage?
  • 5. Coolant  Purpose: Transfer heat efficiently  Material: Water  Features: Recombiner
  • 6. Basket  Purpose: sub-criticality & structural integrity  Material: Neutronit A976 (Type 316)  Features: holes and discs  Manufacturing: powder metallurgy and welding
  • 7. Inner Vessel  Purpose: Dissipates heat efficiently  Material: INCONEL Alloy 22  Manufacturing:  Hot Rolled at 1100oC for 2hrs  Air cooled at 800oC for 4 hrs, then at 700oC for 3 hours http://www.jignasteel.net/metal- sheets-plates.html
  • 8. Sandwich Layer  Purpose: Radiation Shielding  Materials: DUCRETE  Features: Solid Uniform Layer  Manufacturing: DUF6 is converted to DUO2. Encapsulation of synthetic- basalt-based binder by sintering to prevent further oxidation.
  • 9.  Manufacturing: DUF6 is converted to DUO2. Encapsulation of synthetic-basalt-based binder by sintering to prevent further oxidation.
  • 10. Depleted uranium as aggregate in concrete shielding material. Lese Dole, Catherine Mattus, Juan Ferrada. s.l. : Oak ridge national laboratory.
  • 11. Outer Layer  Purpose: Provide structural integrity  Materials: Stainless Steel with Ti  Features:  Impact resistance  Rapid heat dissipation  Corrosion resistance
  • 12. Honeycomb-structured Overlay  Purpose:  Heat dissipation through air convection  Flame resistance  Materials: Slotted Honeycomb Structure – Stainless Steel  Manufacturing: corrugation + annealing with polymer-based cement
  • 13. Lids  Purpose: Structural integrity, maintain internal pressure, prevent leakages  Features:  3 lid system  Metallic and elastomeric O-rings Basic O-Ring Elastomers. Ltd, Toparts PTE. 2007, Toparts.  B0lts (12.9 A4 stainless steel)  Pressure sensors  Resin Development of 300oc heat resitant borno-loaded resin for neutron sheilding. Morioka, Atsuhiko, et al., et al. 2007, Journal of Nuclear Materials, pp. 1085-1089
  • 14.  Materials:  Primary lid – INCONEL alloy 22  Secondary/Tertiary lid – Stainless Steel 316-Ti  Elastomeric O-ring - Perfluorinated Elastomer  Manufacturing: Mainly Press Forging with welding http://www.kimbermills.co.uk/processes/press_forging.
  • 16. Trunnions  Two main purposes: - Lifting – Securing  Material: stainless steel grade 316  Corrosion resistance –Strength – Compatibility  Features  Four present on cask  Many bolts used to disperse load  Good suitability for all common forming methods and has a well defined heat treatment programme
  • 18. Impact limiters  Purpose: Acts like packaging to absorb energy and minimise damage during accident conditions  Materials:  Al 6061 shell  Light weight alloy and good corrosion resistance  Closed cell polystyrene foam inner  Excellent energy absorbance per unit volume  Very low density  TWIP steel reinforcing  Very high strength and very ductile
  • 19. Logistics summary  1.4 mile journey by road and remainder by rail  Rail dictates 65 tonne weight limit and constrains dimensions to 2.8 m diameter and 26 m long
  • 20. Tests- Radiation calculations and FEA  Radiation calculations – combined dose of around 10mSv/h, 1m away from the cask  Finite Element Analysis Water immersion test 1 m drop test 9m drop test
  • 21. Safety features  Time  Distance  Protection  Monitoring http://www.skoda-js.cz/ http://rampac.energy.gov/PCN/P12.pdf
  • 22. Summary of design  Bespoke cask design  Efficient  Safe  Well understood technology
  • 23. Conclusion  Transferring spent nuclear fuel assemblies from Sizewell B nuclear reactor to a reprocessing plant via network rail  Safety considerations by far the most important  Heat dissipation  Impact resistance  Sub-criticality A secure method to transport spent nuclear fuel achieved by our materials selection, structural design & efficient logistics

Editor's Notes

  1. Another important thing that we will need to consider is the residual radiation produced by the spent nuclear fuel. The radioactive elements in spent fuel emit both the high penetrating neutron and gamma ray, as well as the low penetrating alpha and beta radiation. So our concern would be “how to stop the radiation? How to contain the radioactivity? How to prevent radiation leakage?” These are all the issue that we need to take into account for. The measurement of biological dosage, also known as the dose equivalent, is expressed in the unit of Sievert (Sv).
  2. So outer layer. The outer layer here basically encases all the layers mentioned. It serves to provide structural integrity to the cask. It is made up of stainless steel, with Ti additives. It is able to resist impact, resist corrosion, and dissipate heat due to its high thermal conductivity.
  3. On top of this outer layer, we added a layer of honeycomb structure made up of stainless steel. The reason being, it enhances the heat dissipation through efficient air convection, and at the same time, it is able to protect the cask against fire transient, due to its porosity. The manufacturing of the layer involves corrugating the stainless steel sheets, and annealing them with the polymer-based cement.