Analysis of accumulators configuration in LB-LOCA for Bushehr NPP

Annals of Nuclear Energy - Tập 92 - Trang 96-106 - 2016
M.M. Shoushtari1, J. Jafari2, M. Aghaie3, N. Vosoughi1, M. Nemati1
1Department of Energy Engineering, Sharif University of Technology, Tehran 8639-11365, Iran
2Reactor & Accelerators Research and Development School, Nuclear Science and Technology Research Institute (NSTRI), Iran
3Engineering Department, Shahid Beheshti University, G.C, P.O. Box 1983963113, Tehran, Iran

Tài liệu tham khảo

Aghaie, 2012, Coupled neutronic thermal–hydraulic transient analysis of accidents in PWRs, Ann. Nucl. Energy, 50, 158, 10.1016/j.anucene.2012.07.013 Bushehr NPP final safety analysis report (BNPP FSAR), 2008. Atomic Energy Organization of Iran. Fletcher, G.D., Schultz, R.R., 1999. RELAP5/MOD3.3 code manual, Idaho National Engineering Laboratory Idaho. Garsia, A., Gago, J.L., D’Auria, F., 1998. Study supporting the uncertainty evaluation in WWER-1000. In: Nuclear Energy in Central Europe’98, Terme Catez. Kim, 2007, Integral loop test and assessment of modified RELAP5/MOD3.3 for RCS coolant inventory during a LBLOCA, J. Nucl. Eng. Des., 237, 182, 10.1016/j.nucengdes.2006.05.010 Lee, 2008, An integral loop test and MARS code analysis for a DVI line break LOCA in the APR1400, J. Nucl. Eng. Des., 238, 3336, 10.1016/j.nucengdes.2008.06.018 Lin, 2005, Development of a thermal–hydraulic system code for simulators based on RELAP5 code, J. Nucl. Eng. Des., 235, 925, 10.1016/j.nucengdes.2004.10.003 Micaelli, 1995, CATHARE code development and assessment methodologies, Trans. ANS, Winter Meeting San Francisco, 73, 509 Petrangeli, 2006 Plit, H., Kontio, H., Kantee, H., Tuomisto, H., 2000. LBLOCA analyses with APROS to improve safety and performance of Loviisa NPP. In: OECD/CSNI Workshop on Advanced Thermal–Hydraulic and Neutronic Codes: Current and Future Applications Barcelona, Spain. Prosek, A., Mavko, B., Stritar, A., 1994. Effect of pump trip delay on LOCA transient. In: Annual Meeting of Nuclear Society of Slovenia, Rogaska Slatina, Slovenia. Tong, 1996 Wolfert, K., Teschendorff, V., Lerchl, G., Miro, J., Burwell, M.J., 1989. The thermal–hydraulic code ATHLET for analysis of PWR and BWR systems. In: Proceedings of NURETH-4, Proceedings Fourth International Topical Meeting on Nuclear Reactor Thermal–Hydraulics, Karlsruhe, vol. 2, pp. 1234–1239.