Fast Reactors and Accelerator Driven Systems Knowledge Base
Working Materials of the Technical Working Group on Fast Reactors
| Technical Meeting on “Primary Coolant Pipe Rupture Event in Liquid Metal Cooled Fast Reactors”, Indira Gandhi Centre for Atomic Research (IGCAR), Kalpakkam, India, 13–17 January 2003 |
| report nr.: TWGFR/112 IAEA-TM-26027 |
| In Liquid Metal cooled Fast Reactors (LMFR) or in accelerator driven sub-critical systems (ADS) with LMFR like sub-critical cores, the primary coolant pipes (PCP) connect the primary coolant pumps to the grid plate. A rupture in one of these pipes could cause significant loss of coolant flow to the core with severe consequences. In loop type reactors, all primary pipelines are provided with double envelopes and inter-space coolant leak monitoring systems that permit leak detection before break. Thus, the PCP rupture event can be placed in the beyond design basis event (BDBE) category. Such an arrangement is difficult to incorporate for pool type reactors, and hence it could be argued that the PCP rupture event needs to be analysed in detail as a design basis event (DBE, category 4 event). The primary coolant pipes are made of ductile austenitic stainless steel material and operate at temperatures of the cold pool and at comparatively low pressures. For such low stressed piping with negligible creep and embrittlement effects, it is of interest to discuss under what design provisions, for pool type reactors, the guillotine rupture of PCP could be placed in the BDBE category. The topical Technical Meeting (TM) on “Primary Coolant Pipe Rupture Event in Liquid Metal Cooled Reactors” was called to enable the specialists to present the philosophy and analyses applied on this topic in the various Member States for different LMFRs. The scope of the Technical Meeting was to provide a global forum for information exchange on the philosophy applied in the various participating Member States and the analyses performed for different LMFRs with regard to the primary coolant pipe rupture event. More specifically, the objectives of the Technical Meeting were to review the safety philosophy for the PCP rupture event in pool type LMFR, to assess the structural reliability of the PCP and the probability of rupture under different conditions (with/without in-service inspection), to review the classification of the PCP rupture event in DBE/BDBE categories and discuss the applicable design safety limits, to assess the need for consequential analysis like pipe whip effects, primary pump seizure and multiple pipe rupture, and, last but not least, to present the results of analyses of the event per se for flows and/or temperatures and improved design concepts for minimizing the consequences to the core. The TM was attended by 25 participants from six Member States and one international organization. The Russian representative had to cancel his participation at the last moment due to health reasons. Presentations The Status of Fast Reactor Technology Development in ChinaH. Yang Status of French Fast Reactor Program Ph. Dufour Status of Japanese FR Programs Presented by T. Wakai Status of National Programs on Fast Reactors in Korea H.-y. Jeong, D. Hahn Safety Philosophy of Primary Pipe Rupture Event in Prototype Fast Breeder Reactor S.B. Bhoje Philosophy of Leak before Break Assessment for Japanese Prototype FBR T. Wakai, K. Aoto, M. Ichimiya, K. Ito Main Pipe Rupture Accident Analysis for China Experiment Fast Reactor H. Yang, M. Xu Rupture of LIPOSO in SuperPhenix Ph. Dufour Theoretical and Experimental Assessment of Structural Integrity of Primary Pipe P. Chellapandi, A. Biswas, S.C. Chetal, S.B. Bhoje A simplified Crack Growth Assessment Procedure for PCP in FBR T. Wakai, K. Aoto Thermal Hydraulic Consequences of Primary Pipe Rupture in PFBR N. Kasinathan, K. Natesan, P. Selvaraj, P. Chellapandi, S.C. Chetal Analysis of Primary Pipe Break for Korea Advanced Liquid Metal Reactor H.-y. Jeong Safety Philosophy of Primary Pipe Rupture Event in Prototype Fast Breeder Reactor S.B. Bhoje Philosophy of Leak before Break Assessment for Japanese Prototype FBR T. Wakai, K. Aoto, M. Ichimiya, K. Ito Main Pipe Rupture Accident Analysis for China Experimental Fast Reactor H. Yang, M. Xu Rupture of LIPOSO in Superphenix Ph. Dufour, J. Louvet, P. Lo Pinto Theoretical and Experimental Assessment of Structural Integrity of Primary Pipe P. Chellapandi, A. Biswas, S.C. Chetal, S.B. Bhoje A Simplified Crack Growth Assessment Procedure for PCP in FBR T. Wakai, K. Aoto Thermal Hydraulic Consequences for Primary Pipe Rupture N. Kasinathan, K. Natesan, P. Selvaraj, P. Chellapandi, S.C. Chetal Analysis of Primary Pipe Break for Korea Advanced Liquid Metal Reactor H.Y. Jeong, W.P. Chang, Y.B. Lee, D. Hahn Analysis of Emergency Situations Caused by BN-800 Primary Circuit Pressure Pipe Depressurization V.S. Gorbunov, V.A. Zamiatin, Y.L. Kamanin, N.G. Kuzavkov, V.A. Sobolev Improved Primary Pipe Design Concepts for Future FBR S.C. Chetal, P. Chellapandi |
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