Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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DEVELOPMENT OF THE ENIGMA FUEL PERFORMANCE CODE FOR WHOLE CORE ANALYSIS AND DRY STORAGE ASSESSMENTS

  • Rossiter, Glyn (Fuel Cycle Solutions, UK National Nuclear Laboratory (NNL))
  • Received : 2011.11.16
  • Published : 2011.12.25
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Abstract

UK National Nuclear Laboratory's (NNL's) version of the ENIGMA fuel performance code is described, including details of the development history, the system modelled, the key assumptions, the thermo-mechanical solution scheme, and the various incorporated models. The recent development of ENIGMA in the areas of whole core analysis and dry storage applications is then discussed. With respect to the former, the NEXUS code has been developed by NNL to automate whole core fuel performance modelling for an LWR core, using ENIGMA as the underlying fuel performance engine. NEXUS runs on NNL's GEMSTONE high performance computing cluster and utilises 3-D core power distribution data obtained from the output of Studsvik Scandpower's SIMULATE code. With respect to the latter, ENIGMA has been developed such that it can model the thermo-mechanical behaviour of a given LWR fuel rod during irradiation, pond cooling, drying, and dry storage - this involved: (a) incorporating an out-of-pile clad creep model for irradiated Zircaloy-4; (b) including the ability to simulate annealing out of the clad irradiation damage; (c) writing of additional post-irradiation output; (d) several other minor modifications to allow modelling of post-irradiation conditions.

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References

  1. P. A. Jackson, J. A. Turnbull and R. J. White, "A Description of the ENIGMA Fuel Performance Code", Proc. IAEA Technical Committee Meeting on Water Reactor Fuel Element Computer Modelling in Steady-State, Transient and Accident Conditions, Preston, UK, Sep. 19-22, 1988.
  2. P. A. Jackson, J. A. Turnbull and R. J. White, "ENIGMA Fuel Performance Code", Nuclear Energy, 29, 107 (1990).
  3. W. J. Kilgour, J. A. Turnbull, R. J. White, A. J. Bull, P. A. Jackson and I. D. Palmer, "Capabilities and Validation of the ENIGMA Fuel Performance Code", Proc. ANS/ENS International Topical Meeting on LWR Fuel Performance, Avignon, France, Apr. 21-24, 1991.
  4. J. C. Killeen, "Comparison of the ENIGMA Code with Experimental Data on Thermal Performance, Stable Fission Gas and Iodine Release at High Burn-Up", Proc. IAEA Technical Committee Meeting on Water Reactor Fuel Element Modelling at High Burnup and Its Experimental Support, Windermere, UK, Sep. 19-23, 1994.
  5. G. A. Gates, P. M. A. Cook, P. de Klerk, P. Morris and I. D. Palmer, "Thermal Performance Modelling with the ENIGMA Code", Proc. NEA/CEA Seminar on Thermal Performance of High Burn-Up LWR Fuel, Cadarache, France, Mar. 3-6, 1998.
  6. I. Palmer, G. Rossiter and R. White, "Development and Validation of the ENIGMA Code for MOX Fuel Performance Modelling", Proc. IAEA International Symposium on MOX Fuel Cycle Technologies for Medium and Long Term Deployment: Experience, Advances, Trends, Vienna, Austria, May 17-21, 1999.
  7. J. Rhodes, K. Smith and D. Lee, "CASMO-5 Development and Applications", Proc. ANS Topical Meeting on Reactor Physics (PHYSOR-2006), Vancouver, Canada, Sep. 10-14, 2006.
  8. T. Bahadir and S-O Lindahl, "Studsvik's Next Generation Nodal Code SIMULATE-5", Proc. Advances in Nuclear Fuel Management IV (ANFM 2009), Hilton Head Island, South Carolina, USA, Apr. 12-15, 2009.
  9. J. Mullen, C. Brown, I. D. Palmer and P. Morris, "Performance of SBR MOX Fuel in the Callisto Experiment", Proc. TopFuel'97, Manchester, UK, Jun. 9-11, 1997.
  10. R. J. White, S. B. Fisher, P. M. .A. Cook, R. Stratton, C. T. Walker and I. D. Palmer, "Measurement and Analysis of Fission Gas Release from BNFL's SBR MOX fuel", J. Nucl. Mat., 288, 43 (2001). https://doi.org/10.1016/S0022-3115(00)00591-2
  11. R. Weston, I. D. Palmer, J. M. Wright, G. D. Rossiter, R. C. Corcoran, T. C. Gilmour, C. T. Walker and S. Bremier, "Progress on SBR MOX Fuel Development", Proc. TopFuel 2001, Stockholm, Sweden, May 27-30, 2001.
  12. S. B. Fisher, R. J. White, P. M. A. Cook, S. Bremier, R. C. Corcoran, R. Stratton, C. T. Walker, P. K. Ivison and I. D. Palmer, "Microstructure of Irradiated SBR MOX Fuel and its Relationship to Fission Gas Release", J. Nucl. Mat., 306, 153 (2002). https://doi.org/10.1016/S0022-3115(02)01247-3
  13. M. Barker, P. Cook, R. Weston, G. Dassel, C. Ott, R. Stratton, D. Papaioannou and C. Walker, "Ramp Testing of SBR MOX Fuel", Proc. NEA Seminar on Pellet-Clad Interaction in Water Reactor Fuels, Aix-en-Provence, France, Mar. 9-11, 2004.
  14. M. A. Barker, K. Stephenson and R. Weston. "The Manufacture and Performance of Homogeneous- Microstructure SBR MOX Fuel", Proc. 2007 International LWR Fuel Performance Meeting, San Francisco, California, USA, Sep. 30 - Oct. 3, 2007.
  15. M. A. Barker and C. P. Chatwin, "Fuel Performance Activities at Sellafield Ltd and the UK's National Nuclear Laboratory", Proc. 2008 Water Reactor Fuel Performance Meeting, Seoul, Korea, Oct. 19-23, 2008.
  16. A. Worrall, T. J. Abram, R. W. H. Gregg, K. W. Hesketh, I. D. Palmer, G. D. Rossiter and G. M. Thomas, "Plutonium Utilization Options in Future UK PWRs Using MOX and Inert Matrix Fuels", Proc. Global 2007, Boise, Idaho, USA, Sep. 9-13, 2007.
  17. A. Alapour, R. M. Joyce, A. S. DiGiovine, S. Tarves, N. Patino, A. Worrall, R. Gregg and G. Rossiter, "Robust PCI Monitoring During PWR Operation at Southern Nuclear", Proc. 2010 LWR Fuel Performance/TopFuel/WRFPM, Orlando, Florida, USA, Sep. 26-29, 2010.
  18. G. D. Rossiter, P. M. A. Cook and R. Weston, "Isotopic Modelling Using the ENIGMA-B Fuel Performance Code", Proc. IAEA Technical Committee Meeting on Nuclear Fuel Behaviour Modelling at High Burnup and Its Experimental Support, Windermere, UK, Jun. 19-23, 2000.
  19. R. Gregg, "Whole Core Fuel Performance Modelling", Proc. IAEA Technical Meeting on Fuel Behaviour Modelling Under Normal, Transient and Accident Conditions, and High Burnups, Kendal, UK, Sep. 5-8, 2005.
  20. G. Thouvenin, P. Thévenin, N. Tallet, S. Aunay and S. Lemercier, "High Performance Computing of PWR Simulations with Fuel Code CYRANO3 Running on IBM System Blue Gene/P", Proc. TopFuel 2009, Paris, France, Sep. 6-10, 2009.
  21. A. Worrall and A. S. DiGiovine, "ONUS: On-line Fuel Performance Surveillance - Linking Studsvik's CMS with UK NNL's ENIGMA-B", Proc. Advances in Nuclear Fuel Management IV (ANFM 2009), Hilton Head Island, South Carolina, USA, Apr. 12-15, 2009.
  22. R. F. Burstall, "FISPIN: A Computer Code for Nuclide Inventory Calculations", ND-R-328R, United Kingdom Atomic Energy Authority (1979).
  23. http://www.ansys.com/Products/Simulation+Technology/ Fluid+Dynamics/ANSYS+FLUENT
  24. H. G. Kim, Y. H. Jeong and K. T. Kim, "The Effects of Creep and Hydride on Spent Fuel Integrity During Interim Dry Storage", Nucl. Eng. Technol., 42, 249 (2010). https://doi.org/10.5516/NET.2010.42.3.249
  25. "Final Safety Analysis Report for the HI-STORM 100 Cask System", HI-2002444 Revision 8, Holtec International (2010).
  26. M. Peehs and J. Fleisch, "LWR Spent Fuel Storage Behaviour", J. Nucl. Mat., 137, 190 (1986). https://doi.org/10.1016/0022-3115(86)90219-9
  27. "Further Analysis of Extended Storage of Spent Fuel: Final Report of a Coordinated Research Programme on the Behaviour of Spent Fuel Assemblies during Extended Storage (BEFAST-III), 1991-1996", IAEA-TECDOC- 944, International Atomic Energy Agency (1997).
  28. J. P. Piron, M. Pelletier and J. Pavageau, "Helium Behaviour in Spent UO2 and MOX Fuels", Proc. NEA Seminar on Fission Gas Behaviour in Water Reactor Fuels, Cadarache, France, Sep. 26-29, 2000.
  29. L. O. Werme, L. H. Johnson, V. M. Oversby, F. King, K. Spahiu, B. Grambow and D. W. Shoesmith, "Spent Fuel Performance Under Repository Conditions: A Model for Use in SR-Can", TR-04-19, Svensk Karnbranslehantering AB (2004).
  30. P. Bouffioux, S. Leclercq, C. Cappelaere and T. Bredel, "Interim Dry Storage of PWR Spent Fuel Assemblies -Development of a Long Term Creep Law to Assess the Fuel Cladding Integrity", Proc. 8th International Conference on Radioactive Waste Management and Environmental Remediation (ICEM'01), Bruges, Belgium, Sep. 30 - Oct. 4, 2001.
  31. R. Limon, C. Cappelaere, T. Bredel and P. Bouffioux, "A Formulation of the Spent Fuel Cladding Creep Behaviour for Long Term Storage", Proc. ANS International Topical Meeting on LWR Fuel Performance, Park City, Utah, USA, Apr. 10-13, 2000.
  32. C. Ferry, C. Poinssot, P. Lovera and J. M. Gras, "Key Issues from the French R&D Project on the Long Term Evolution of the Spent Nuclear Fuel in Conditions of Interim Dry Storage", Proc. IAEA International Conference on Storage of Spent Fuel from Power Reactors, Vienna, Austria, Jun. 2-6, 2003.
  33. J. Y. R. Rashid and A. J. Machiels, "Examination of the Creep Rupture Phenomenon and the Development of an Acceptance Criterion for Spent Fuel Dry Storage", Proc. IAEA International Conference on Storage of Spent Fuel from Power Reactors, Vienna, Austria, Jun. 2-6, 2003.
  34. F. Feria and L. E. Herranz, "Review and Adaptation of FRAPCON-3 Creep Model to Dry Storage Conditions", Proc. Global 2009, Paris, France, Sep. 6-11, 2009.
  35. K. Ito, K. Kamimura and Y. Tsukuda, "Evaluation of Irradiation Effect on Spent Fuel Cladding Creep Properties", Proc. 2004 International Meeting on LWR Fuel Performance, Orlando, Florida, USA, Sep. 19-22, 2004.
  36. http://www.ife.no/hrp
  37. J. Killeen, E. Sartori and T. Tverberg, "FUMEX-III: A New IAEA Coordinated Research Project on Fuel Modelling at Extended Burnup", Proc. TopFuel 2009, Paris, France, Sep. 6-10, 2009.
  38. T. J. Abram, "Modelling the Waterside Corrosion of PWR Fuel Rods", Proc. IAEA Technical Committee Meeting on Water Reactor Fuel Element Modelling at High Burnup and Its Experimental Support, Windermere, UK, Sep. 19- 23, 1994.