57
Views
0
CrossRef citations to date
0
Altmetric
Technical Paper

French and United Kingdom Experience of High-Burnup Mixed-Oxide Fuel in Sodium-Cooled Fast Breeder Reactors

, , &
Pages 35-44 | Published online: 10 Apr 2017

REFERENCES

  • J. H. KITTEL, B. R. T. FROST, J. P. MUSTELLIER, K. Q. BAGLEY, G. C. CRITTENDEN, and J. VAN DIEVOET, “History of Fast Reactor Development,” J. Nucl. Mater., 204, 1 (1993).
  • I. SATO, F. LEMOINE, and D. STRUWE, “Transient Fuel Behavior and Failure Condition in the CABRI-2 Experiments.” Nucl. Technol., 145, 115 (2004).
  • P. MILLET, P. COURCON, R. MARINOT, C. BROWN, and G. C. CRITTENDEN, “Improvement of Fuel Sub-Assembly Endurance in the Prototype Fast Reactors PHENIX and PFR,” Proc. Int. Conf. Fast Reactors and Related Fuel Cycles, Kyoto, Japan, October 27–November 1, 1991, Japan Nuclear Cycle Development Institute (1991).
  • D. R. OLANDER, “Fundamental Aspects of Nuclear Reactor Fuel Elements,” TID 26711-P1, U.S. Department of Energy (1976).
  • G. MARBACH and P. MILLET, “Optimisation of FBR Fuel Element for High Burn-Up Nuclear Fuel Performance,” Proc. Nuclear Fuel Performance Int. Conf., Stratford-upon-Avon, United Kingdom, March 25–29, 1985.
  • A. MATHIOT, J. P. HAIRION, H. PLITZ, P. WEIMAR, and P. CECCHI, “Failure Evolution in Sodium Loops—Results of the SILOE Experimental Program,” Proc. Int. Conf. Reliable Fuels for Liquid Metal Reactors, Tucson, Arizona, September 7–11, 1986, American Nuclear Society (1986).
  • H. MATZKE, Science of Advanced LMFBR Fuels, North Holland Physics Publishing, Amsterdam (1986).
  • B. T. BRADBURY and B. R. T. FROST, “Radiation Performance of Plutonium-Uranium Monocarbide Fast Reactor Fuels,” Metall. Soc. Conf., 42, 329 (1966).
  • K. Q. BAGLEY, W. BATEY, R. PARIS, W. M. SLOSS, and G. P. SNAPE, “UK Irradiation Experience Relevant to Advanced Carbide Concepts for LMFBRs,” Proc. Int. Mtg. Advanced LMFBR Fuels, Tucson, Arizona, October 10–13, 1977, American Nuclear Society (1977).
  • E. EDMONDS, W. M. SLOSS, K. Q. BAGLEY, and W. BATEY, “Mixed Oxide Fuel Performance,” Proc. Int. Conf. Fast Breeder Reactor Fuel Performance, Monterey, California, March 5–8, 1979, American Nuclear Society (1979).
  • E. A. AITKEN, “Thermal Diffusion in Closed Oxide Fuel System,” J. Nucl. Mater., 30, 62 (1969).
  • M. TOURASSE, M. BOIDRON, and B. PASQUET, “Fission Product Behaviour in PHENIX Fuel Pins at High Burn-Up,” J. Nucl. Mater., 188, 49 (1992).
  • J. C. MÉLIS, J. P. PIRON, and L. ROCHE, “Fuel Modelling at High Burn-Up: Recent Development of the GERMINAL Code,” J. Nucl. Mater., 204, 188 (1993).
  • D. G. MARTIN, R. PARIS, and J. NEEDHAM, “Some Experimental and Theoretical Studies of the Power to Initiate Melting in Various Fast Reactor Fuel Pin Designs,” Proc. Int. Conf. Reliable Fuels for Liquid Metal Reactors, Tucson, Arizona, September 7–11, 1986, American Nuclear Society (1986).
  • L. ROCHE and M. PELLETIER, “Modelling of the Thermo-Mechanical and Physical Processes in FR Fuel Pins Using the GERMINAL Code,” Proc. Int. Symp. MOX Fuel Cycle Technologies for Medium and Long Deployment, IAEA-SM-358/25, Vienna, Austria, May 17–20, 1999, International Atomic Energy Agency (1999).
  • J. R. MATTHEWS, P. E. COLEMAN, R. THETFORD, A. W. GARDNER, and C. W. CAWTHORNE, “The Application of the TRAFIC Code to Fuel Performance Evaluation,” Proc. Int. Conf. Reliable Fuels for Liquid Metal Reactors, Tucson, Arizona, September 7–11, 1986, American Nuclear Society (1986).
  • M. A. MIGNANELLI, R. THETFORD, and D. A. WILLIAMS, “Fuel Performance Modelling of Nitride Fuels,” Proc. Int. Conf. Future Nuclear Systems (Global ’99), Jackson Hole, Wyoming, August 29–September 3, 1999, American Nuclear Society (1999) (CD-ROM).
  • J. L. RATIER, “Phénomènes de corrosion des gaines d’éléments combustibles de réacteurs à neutrons rapides,” presented at EUROCORR Conf., Epsoo, Finland, June 4, 1992.
  • G. YATES and G. A. B. LINEKAR, “Fuel/Clad Chemical Interaction in PFR Fuel Pins,” Proc. Int. Conf. Materials for Nuclear Reactor Core Applications, Bristol, United Kingdom, October 27–29, 1987, pp. 329–333, British Nuclear Energy Society (1987).
  • P. F. CECCHI, R. B. JONES, P. MILLER, D. I. R. NORRIS, A. PAY, and W. TOBBE, “Life Limiting Features and Technical Problems to Reach High Burn-Up in Fast Reactor Fuel,” Proc. Int. Conf. Reliable Fuels for Liquid Metal Reactors, Tucson, Arizona, September 7–11, 1986, American Nuclear Society (1986).
  • M. G. ADAMSON, E. A. AITKEN, and T. B. LINDEMER, “Chemical Thermodynamics of Cs and Te Fission Product Interactions in Irradiated LMFBR Mixed Oxide Fuel Pins,” J. Nucl. Mater., 130, 375 (1985).
  • I C. CAWTHORNE and E. J. FULTON, “Voids in Irradiated Stainless Steel,” Nature, 216, 575 (1967).
  • R. CAUVIN et al., “Mechanical Properties of Irradiated Inconel 706,” Proc. Int. Conf. Materials for Nuclear Reactor Core Applications, Bristol, United Kingdom, October 27–29, 1987, p. 187, British Nuclear Energy Society (1987).
  • F. LE NAOUR et al., “Swelling and Microstructure of Neutron Irradiated Inconel 706,” Proc. Int. Conf. Materials for Nuclear Core Applications, Bristol, United Kingdom, October 27–29, 1987, p. 211, British Nuclear Energy Society (1987).
  • J. L. SÉRAN and J. M. DUPOUY, “The Swelling of Solution Annealed 316 Cladding in RAPSODIE and PHENIX,” Proc. Int. Conf. Effects of Radiation on Materials, Scottsdale, Arizona, June 28–30, 1982, ASTM STP 782, American Society for Testing and Materials (1982).
  • J. I. BRAMMAN and C. BROWN, “The Temperature Dependence of Void Swelling of Fast Reactor Irradiated 316 Stainless Steel,” Proc. Int. Conf. Irradiation Behaviour of Metallic Materials for Fast Reactor Core Components, Ajaccio, Corsica, France, June 4–8, 1979, Commissariat à l’Energie Atomique (1979).
  • J. L. SÉRAN et al., “Swelling and Microstructure of Neutron Irradiated Titanium Modified Type 316 SS,” Proc. 12th Int. Symp. Effects of Radiation on Materials, Williamsburg, Virginia, June 18–20, 1984, ASTM STP 870, American Society for Testing and Materials (1985).
  • A. MAILLARD, H. TOURON, J. L. SÉRAN, and A. CHALONY, “Swelling and Irradiation Creep of Neutron Irradiated 316 Ti and 15-15 Ti Steels,” Proc. 16th Int. Symp. Effects of Radiation on Materials, Denver, Colorado, June 20–25, 1992, ASTM STP 870, A. S. KUMAR, D. S. GELLES, R. K. NANSTAD, and E. A. LITTLE, Eds., American Society for Testing and Materials (1993).
  • M. NAGANUMA, K. MAEDA, N. NAKAE, J. ROUAULT, J. NOIROT, G. C. CRITTENDEN, and C. BROWN, “Irradiation Performance of High Burn-Up Annular Fuel in PFR,” 6th Int. Conf. Nuclear Engineering (ICONE 6), May 10–15, 1998, American Society of Mechanical Engineers (1998).
  • G. McAREAVEY and B. D. WILLIAMS, “Validation of DISCO Thermal Hydraulic Calculations for Distorted Fast Reactor Sub-Assemblies Against Post-Irradiation Results,” Proc. Int. Conf. Reliable Fuels for Liquid Metal Reactors, Tucson, Arizona, September 7–11, 1986, American Nuclear Society (1986).
  • C. BROWN et al., “Cladding and Wrapper Development for Fast Breeder Reactor High Performance,” Proc. Int. Conf. Fast Reactors and Related Fuel Cycles, Vol. 1, Kyoto, Japan, October 27–November 1, 1991, Japan Nuclear Cycle Development Institute (1991).
  • P. DUBUISSON et al., “Microstructural Evolution of Ferritic-Martensitic Steels Irradiated in the Fast Reactor PHENIX,” J. Nucl. Mater., 205, 178 (1993).
  • M. PELLETIER, P. BLANCHARD, T. MARTELLA, and A. RAVENET, “Mechanical Tests on an Irradiated PHENIX Sub-Assembly,” Proc. Int. Conf. Fast Reactor Core and Fuel Structural Behaviour, Inverness, United Kingdom, June 4–6, 1990, British Nuclear Energy Society (1990).
  • J. L. SÉRAN et al., Proc. 15th Int. Symp. Effects of Radiation on Materials, Nashville, Tennessee, June 19–21, 1990, ASTM STP 1125, p. 1209, American Society for Testing and Materials (1992).
  • A. ALAMO et al., “Effect on Processing on Textures and Tensile Properties of ODS Ferritic Alloys Obtained by Mechanical Alloying,” Adv. Powder Metall. Part. Mater., 7, 169 (1992).
  • C. J. JONES and A. C. DARKE, “Operation of the Chardis 2 Rig and Comparisons with CRAMP Calculations,” Proc. Int. Conf. Fast Reactor Core and Fuel Structural Behaviour, Inverness, United Kingdom, June 4–6, 1990, British Nuclear Energy Society (1990).
  • A. C. DARKE, M. E. LeBORGNE, and H. D. COORS, “Chardis 3 Rig and Its Contribution to European Core Static Mechanics,” Proc. Int. Conf. Fast Reactor Core and Fuel Structural Behaviour, Inverness, United Kingdom, June 4–6, 1990, British Nuclear Energy Society (1990).
  • J. C. DUTHIE, R. G. ANDERSON, G. C. CRITTENDEN, R. J. BARTON, and A. J. BROOK, “Use of PFR PIE Data for the Validation of CRAMP,” Proc. Int. Conf. Fast Reactor Core and Fuel Structural Behaviour, Inverness, United Kingdom, June 4–6, 1990, British Nuclear Energy Society (1990).

Reprints and Corporate Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

To request a reprint or corporate permissions for this article, please click on the relevant link below:

Academic Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

Obtain permissions instantly via Rightslink by clicking on the button below:

If you are unable to obtain permissions via Rightslink, please complete and submit this Permissions form. For more information, please visit our Permissions help page.