Challenges Associated with the Mitigation of Unprotected Loss of Flow in Sodium-Cooled Fast Reactor Cores

References

• S. Beil et al., “Safety for the Future Sodium Cooled Fast Reactors,” Proc. Int. Conf. Fast Reactors and Related Fuel Cycles: Challenges and Opportunities (FR09), Kyoto, Japan, December 7–11, 2009, International Atomic Energy Agency (2009).
   Google Scholar
• F. Justin, J. Petit, and P. F. Tanguy, “Safety Assessment for Severe Accidents in Fast Breeder Reactors,” Nucl. Saf., 27, 3 (July–Sep. 1986).
   Google Scholar
• G. Rimpault et al., “The ERANOS Code and Data System for Fast Reactor Neutronic Analyses,” Proc. Int. Conf. New Frontiers of Nuclear Technology (PHYSOR 2002), Seoul, Korea, October 7–10, 2002, American Nuclear Society (2002).
   Google Scholar
• T. Cadiou, W. Maschek, and A. Rineiski, “SIMMER-III: Applications to Reactor Accident Analysis,” Proc. Joint IAEA/NEA Tech. Mtg., Pisa, Italy, November 11–14, 2002, International Atomic Energy Agency.
   Google Scholar
• G. Mignot et al., “Studies on French SFR Advanced Core Designs,” Proc. Int. Congress on Advances in Nuclear Power Plants (ICAPP ’08), Anaheim, California, June 8–12, 2008, American Nuclear Society (2008).
   Google Scholar
• P. Sciora et al., “A Break Even Oxide Fuel Core for an Innovative French Sodium-Cooled Fast Reactor Neutronics Studies Results,” Proc. GLOBAL ’09, Paris, France, September 6–11, 2009.
   Google Scholar
• L. Buiron, D. Verrier, and S. Massara, “A Break Even Oxide Fuel Core for an Innovative Sodium-Cooled French Fast Reactor: Core Flexibility,” Proc. Int. Congress on Advances in Nuclear Power Plants (ICAPP ’10), San Diego, California, June 13–17, 2010, American Nuclear Society (2010).
   Google Scholar
• V. M. Poplavski et al., “Prospects For The Bn-1800 Sodium-Cooled Fast Reactor Satisfying 21st Century Nuclear Power Requirements,” At. Energy, 96, 5 (2004).
   Google Scholar
• P. Fougeras, A. Chabre, and C. Mergui, “The Place of EOLE, MINERVE and MASURCA Facilities in the R&D Activities of the CEA,” International Group On Research Reactors (IGORR 10), Gaitherburg, Maryland, September 1216, 2005.
   Google Scholar
• I. Matveenko, A. Tsibulya, and V. Dvukhsherst-Nov, “Research Trends at the BFS Facilities and the Principal Results of 1986-2011,” International Conference Dedicated to 50th Anniversary of BFS Critical Facility, Obninsk, Russia, February 28–30, 2012.
   Google Scholar
• M. Edelmann, G. Kussmaul, and W. VÀth, “Improved Fast Reactor Safety by Passive Shut-Down,” Prog, Nucl. Energy, Vol. 29 suppl., p. 379 (1995).
   Google Scholar
• S. Nakanishi et al. “Development of Advanced Loop-Type Fast Reactor in Japan: Adoption of Self Actuated Shutdown System (SASS) in JSFR,” Proc. Int. Congress on Advances in Nuclear Power Plants (ICAPP ’08), Anaheim, California, June 8–12, 2008, American Nuclear Society (2008).
   Google Scholar
• M. Takamatsu et al., “Demonstration of Control Rod Holding Stability of the Self Actuated Shutdown System (SASS) in Joyo for Enhancement of Fast Reactor Inherent Safety,” J. Nucl. Sci. Technol., 44, 3, 511 (2007).
   Web of Science ®Google Scholar
• S. Beils et al. “Interest of SEPIA (Sentinel for Passive Insertion of Anti-Reactivity) Systems For Sodium Cooled Fast Reactor (SFR) Safety,” Proc. Int. Congress on Advances in Nuclear Power Plants (ICAPP ’10), San Diego, California, June 13–17, 2010, American Nuclear Society (2010).
   Google Scholar
• W. Maschek et al., “Prevention and Mitigation of Severe Accident Developments and Recriticalities in Advanced Fast Reactor Systems,” Prog. Nucl. Energy, 53, 835 (2011).
   Google Scholar
• H. Endo et al., “Elimination of Recriticality Potential for the Self-Consistent Nuclear Energy System,” Prog. Nucl. Energy, 40, 3–4, (Apr.-May 2002).
   Google Scholar
• Y. Tobita, H. Yamano, and I. Sato, “Analytical Study on Elimination of Severe Recriticalities in Large Scale LMFBRS with Enhancement of Fuel Discharge,” Nucl. Eng. Des., 238, 57 (2008).
   Web of Science ®Google Scholar
• A. M. Tentner et al., “The SAS4A LMFBR Whole Core Accident Analysis Code,” Proc. Int. Topl. Mtg. Fast Reactor Safety, Knoxville, Tennessee, April 21–25, 1985.
   Google Scholar
• P. Royl, W. Pfrang, and D. Struwe, “Reactivity Feedback Evaluation of Material Relocations in the Cabri-1 Experiments with Fuel Worth Distributions from SNR-300,” Nucl. Eng. Des., 147, 1, 85 (Jan. 1994).
   Google Scholar
• S. A. Kondo et al., “Current Status and Validation of the SIMMER-IIILMFR Safety Analysis Code,” Proc. 7th Int. Conf. Nuclear Engineering (ICONE-7), No. 7249, Kyoto, Japan, April 1999.
   Google Scholar
• Y. Tobita et al., “The Development of SIMMER-III, An Advanced Computer Program for LMFR Safety Analysis and Its Application to Sodium Experiments,” Nucl. Technol., 153, 245 (2006).
   Web of Science ®Google Scholar
• H. Yamano et al., “SIMMER-III: A Coupled Neutronics Thermohydraulics Computer Code for Safety Analysis,” Proc. 15th Int. Conf. Nucl. Eng. (ICONE-15), ICONE15-10462, Nagoya, Japan, April 22–26, 2007.
   Google Scholar
• I. Sato et al., “Analysis of ULOF Accident in Monju Reflecting the Knowledge from CABRI In-Pile Experiments and Others,” Research Safety Group, FBR System Engineering Unit, JAEA-Research 2007–055, May 2007.
   Google Scholar
• G. Kayser and J. Papin, “The Reactivity Risk in Fast Reactors and the Related International Experimental Programmes Cabri and Scarabee,” Prog. Nucl. Energy, 32, 314, 631 (1998).
   Google Scholar
• M. Boidron et al., “Phenomena Related to Fuel Melting in CABRI Experiments,” International Fast Reactor Safety Meeting, Snowbird, Utah, August 1990.
   Google Scholar
• J. C. MELIS et al., “GERMINAL—A Computer Code for Predicting Fuel Pin Behaviour,” J. Nucl. Mater., 188, 303 (1992).
   Web of Science ®Google Scholar
• Peppler et al., “Investigation of Material Relocation Phenomena During Severe Accidents in Fast Breeder Reactors,” Nucl. Eng. Des., 100, 3, 409 (Mar. 1987).
   Google Scholar
• P. Coste, S. Pigny, and R. Meignen, “Current Status of Thermohydraulic Validation Studies at CEA-Grenoble for the SIMMER-III Code,” Proc. AIEA TC Mtg., Obninsk, Russia, August 1998.
   Google Scholar
• F. Helm, G. Henneges, and W. Maschek, “Measurements and Computation of the Reactivity Effects of Accident-Caused Core Distortions in Liquid-Metal Fast Breeder Reactors,” Nucl. Sci. Eng., 87, 295 (1984).
   Web of Science ®Google Scholar
• H. Yamano and Y. Tobita, “Experimental Analyses by SIMMER-III on Fuel-Pin Disruption and Low-Energy Disrupted Core Motion,” J. Power Energy Syst., 4, 1, 164 (2010).
   Google Scholar
• K. Morita et al., “Development of Multicomponent Vaporization/Condensation Model for a Reactor Safety Analysis Code SIMMER-III: Theoretical Modelling and Basic Verification,” Nucl. Eng. Des., 220, 3, 224 (2003).
   Google Scholar