Study on Design of 600 MW PWR Accumulator

FENG Jin-jun; FENG Wen-qing; ZHOU Ke-feng; YANG Zhi-yi; SHI Jun-ying; CHONG Yi-min; CHAI Guo-han

doi:10.7538/yzk.2015.49.09.1611

Atomic Energy Science and Technology > 2015 > 49(9): 1611-1618. > DOI: 10.7538/yzk.2015.49.09.1611

FENG Jin-jun, FENG Wen-qing, ZHOU Ke-feng, YANG Zhi-yi, SHI Jun-ying, CHONG Yi-min, CHAI Guo-han. Study on Design of 600 MW PWR Accumulator[J]. Atomic Energy Science and Technology, 2015, 49(9): 1611-1618. DOI: 10.7538/yzk.2015.49.09.1611

Citation:

PDF (2959 KB)

Study on Design of 600 MW PWR Accumulator

1.
Nuclear and Radiation Safety Center, Ministry of Environmental Protection, Beijing 100082, China
2.
China Nuclear Power Engineering Co., Ltd., Beijing 100840, China

More Information

Graphical Abstract

Abstract

Abstract

In this paper, the TRACE and SNAP were used to establish twoloop PWR thermal hydraulic system analysis model. The different accumulator design schemes were calculated and analyzed under LBLOCA. The safety injection effect was accessed according to simulation results by comparing peak cladding temperature of each design under LBLOCA. In the end, the possible way to optimize design was found through this study. The research results show that the upper plenum and downcomer injection at the same time is more effective than the cold leg injection or the downcomer injection, and the proper selection of initial accumulator pressure can lower peak cladding temperature and increase LOCA safety margin.
- TRACE,
- SNAP,
- PWR,
- LBLOCA,
- accumulator

FullText(HTML)

References (10)

References

[1]	冯进军，柴国旱，周克峰，等. TRACE和SNAP程序在深水池式低温供热堆中的应用[J]. 核安全，2013，12（2）：7-12.FENG Jinjun, CHAI Guohan, ZHOU Kefeng, et al. The application of TRACE and SNAP code to DLHGR[J]. Nuclear Safety, 2013, 12（2）: 7-12(in Chinese).
[2]	周克峰，陈召林，冯进军，等. MELCOR程序在HTGR事故分析中的最新进展[J]. 核安全，2013，12(3)：62-67.ZHOU Kefeng, CHEN Zhaolin, FENG Jinjun, et al. Latest progress of HTGR accident analysis in MELCOR[J]. Nuclear Safety, 2013, 12(3): 62-67(in Chinese).
[3]	US Nuclear Regulatory Commission. TRACE V 5.0 theory manual[M]. Washington: Division of Safety Analysis Office, 2010.
[4]	US Nuclear Regulatory Commission. TRACE V 5.0 user’s manual[M]. Washington: Division of Safety Analysis Office, 2010.
[5]	US Nuclear Regulatory Commission, Applied Programming Technology Inc．Symbolic Nuclear Analysis Package (SNAP) user’s manual[M]．Bloomsburg: Applied Programming Technology Inc, 2007.
[6]	柴国旱，石俊英，贾宝山，等. TRAC-PF1程序的发展和应用研究，75-19-03-03[R]. 北京：清华大学，1990.
[7]	陈严，贾宝山. TRAC-PF1在大破口LOCA分析中的应用[J]. 原子能科学技术，1989，23(5)：75-80.CHEN Yan, JIA Baoshan. The application of TRAC-PF1 to the analysis of large break LOCA[J]. Atomic Energy Science and Technology, 1989, 23(5): 75-80(in Chinese).
[8]	李经纬. 秦山核电二期工程反应堆热工水力设计[J]. 核动力工程，1999，20(4)：308-312.LI Jingwei. Reactor thermal-hydraulic design for Qinshan Phase 2 nuclear power project[J]. Nuclear Power Engineering, 1999, 20(4): 308312(in Chinese).
[9]	殷煜皓，林支康，梁国兴，等. 核电厂大破口事故建模与初始参数不确定性分析[J]. 扬州大学学报：自然科学版，2012，15(1)：42-46.YIN Yuhao, LIN Zhikang, LIANG Guoxing, et al. Large-break loss of coolant accident modeling and the uncertainty analysis of initial parameters[J]. Journal of Yangzhou University: Natural Science Edition, 2012, 15(1): 42-46(in Chinese).
[10]	杨兰和. 秦山核电二期扩建工程最终安全分析报告[R]. 杭州：中核集团核电秦山联营有限公司，2009.

Cited By

Get Citation

PDF

XML

Article views (312) PDF downloads (1125)

Turn off MathJax

Article Contents

Abstract

References

Study on Design of 600 MW PWR Accumulator

Abstract

References

Catalog

Export File

Citation

Format

Content