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RELAP5 Code Study of ROSA/LSTF Experiments on PWR Safety System Using Steam Generator Secondary-Side Depressurization 被引量:1

RELAP5 Code Study of ROSA/LSTF Experiments on PWR Safety System Using Steam Generator Secondary-Side Depressurization
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出处 《Journal of Energy and Power Engineering》 2015年第5期426-442,共17页 能源与动力工程(美国大卫英文)
关键词 RELAP5 蒸汽发生器 安全系统 ROSA PWR 程序 实验 二次侧 PWR, safety system, ROSAILSTF, small-break loss-of-coolant accident, SG depressurization, RELAP5 code.
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  • 1Hirano, M., Yonomoto, T., and Ishigaki, M. 2012. “Insights from Review and Analysis of the Fukushima Dai-ichi Accident.” Journal of Nuclear Science and Technology 49(1): 1-17.
  • 2Morimoto, T., Ohnuki, A., and Nishi, H. 2014. “Study on PWR Safety System Using SG Secondary-Side Depressurization.” Presented at the NUTHOS-IO (10th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety), Okinawa, Japan.
  • 3Asaka, H., and Kukita, Y. 1995. “Intentional Depressurization of Steam Generator Secondary Side during a PWR Small-Break Loss-of-Coolant Accident.” Journal of Nuclear Science and Technology 32 (2): 101-10.
  • 4The ROSA-V Group. 2003. “ROSA-V LSTF (Large Scale Test Facility) System Description for the Third and Fourth Simulated Fuel Assemblies, Report JAERI-Tech 2003-037.” Japan Atomic Energy Research Institute.
  • 5Takeda, T., Ohwada, A., and Nakamura, H. 2013. “Measurement of Non-condensable Gas in a PWR Small-Break LOCA Simulation Test with LSTF for OECD/NEA ROSA Project and RELAP5 Post-Test Analysis.” Experimental Thermal and Fluid Science 51 (November): 112-21.
  • 6Takeda, T. 2014. “RELAP5 Analyses of ROSA/LSTF Experiments on AM Measures during PWR Vessel Bottom Small-Break LOCAs with Gas Inflow.” International Journal of Nuclear Energy 2014 (September): 1-17.
  • 7Aksan, N. 2008. “International Standard Problems and SBLOCA (Small Break Loss-of-Coolant Accident).” Science and Technology of Nuclear Installations 2008: 1-22.
  • 8Clement, P., Chataing, T., and Deruaz, R. 1993. “PWR Accident Management Related Tests: Some BETHSY Results.” Presented at the NURETH-6 (6th InternationalTopical Meeting on Nuclear Reactor Thermal Hydraulics), Grenoble, France.
  • 9Umminger, K., Dennhardt, L., Schoen, B., and Schollenberger, S. 2013. “Overview on Test Results from the OECD/NEA PKL 2 Project.” Presented at the NURETH-15 (15th International Topical Meeting on Nuclear Reactor Thermal Hydraulics), Pisa, Italy.
  • 10Kukita, Y., Yonomoto, T., and Nakamura, H. 1996. “ROSA/AP6OO Testing: Facility Modifications and Initial Test Results.” Journal of Nuclear Science and Technology 33 (3): 259-65.

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