Severe accident analysis induced by secondary pipeline break in a small modular PWR

被引:2
作者
Bi, Xiaolong [1 ,2 ]
Chen, Jie [3 ]
Sun, Peiwei [1 ,2 ]
Wei, Xinyu [1 ,2 ]
机构
[1] Xi An Jiao Tong Univ, Shaanxi Key Lab Adv Nucl Energy & Technol, Xian 710049, Peoples R China
[2] Xi An Jiao Tong Univ, Shaanxi Engn Res Ctr Adv Nucl Energy, Xian 710049, Peoples R China
[3] China Nucl Power Engn Co Ltd, Instrument & Control Design Inst, Beijing Nucl Engn Res & Design Inst, Beijing 100840, Peoples R China
关键词
Small modular PWR; MELCOR; Severe accident; Secondary pipeline break; High pressure; CORE DEGRADATION; MODEL; MIXTURES; REACTOR;
D O I
10.1016/j.net.2024.05.032
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The small modular PWR (SMPWR) usually adopts integral design. Under severe accident, the system responses are different from those large PWRs. It is necessary to study the severe accident behavior of the SMPWR. A MELCOR model is developed for SMPWR and its steady-state results are in good agreement with the design values. Severe accidents induced by secondary pipeline break accidents are simulated, and no pressure relief measures are taken to keep the primary loop under high pressure. The mitigation effects of passive containment air cooling system (PAS) and passive cavity injection system (PCIS) are evaluated under different cases. The results show that under high pressure conditions, PCIS can effectively cool the lower head. The earlier the PCIS operates, the more significant the mitigation effect can be. In addition, PAS can effectively reduce the peak pressure and temperature in the containment. This study can provide a reference for the formulation of severe accident management guidelines on SMPWRs.
引用
收藏
页码:4263 / 4279
页数:17
相关论文
共 36 条
[1]   COCOSYS: Status of development and validation of the German containment code system [J].
Allelein, H. -J. ;
Arndt, S. ;
Klein-Hessling, W. ;
Schwarz, S. ;
Spengler, C. ;
Weber, G. .
NUCLEAR ENGINEERING AND DESIGN, 2008, 238 (04) :872-889
[2]   Strategic analysis on sizing of flooding valve for successful accident management of small modular reactor [J].
An, Hyo Jun ;
Park, Jae Hyung ;
Song, Chang Hyun ;
Lee, Jeong Ik ;
Kim, Yonghee ;
Kim, Sung Joong .
NUCLEAR ENGINEERING AND TECHNOLOGY, 2024, 56 (03) :949-958
[3]  
Chang M., 2002, Basic Design Report of SMART
[4]   Research on level 1 PSA and risk-informed design for ACP100 [J].
Deng, Jian ;
Xu, Youyou ;
Qiu, Zhifang ;
Zhang, Hang ;
Wu, Lingjun ;
Wang, Xiaoji ;
Peng, Huanhuan ;
Du, Zhengyu .
ANNALS OF NUCLEAR ENERGY, 2020, 144
[5]   Analysis of post-LOCA long-term core safety characteristics for the Small Modular Reactor ACP100 [J].
Deng, Jian ;
Dang, Gaojian ;
Ding, Shuhua ;
Qiu, Zhifang .
ANNALS OF NUCLEAR ENERGY, 2020, 142
[6]   Heat transfer of air turbulent mixed convection in the passive containment air-cooling system of a modular small nuclear reactor [J].
Dong, Chunhui ;
Lu, Guoqing ;
Chen, Ronghua ;
Zhang, Kui ;
Liu, Changliang ;
Tian, Wenxi ;
Qiu, Suizheng ;
Su, G. H. .
INTERNATIONAL JOURNAL OF THERMAL SCIENCES, 2022, 182
[7]   Theoretical study on the Passively Decay Heat Removal System and the primary loop flow rate of NuScale SMR [J].
Fakhrarei, A. ;
Faghihi, F. ;
Dast-Belaraki, M. A. .
ANNALS OF NUCLEAR ENERGY, 2021, 161
[8]   CAREM project:innovative small PWR [J].
Fukami, MVI ;
Santecchia, A .
PROGRESS IN NUCLEAR ENERGY, 2000, 37 (1-4) :265-270
[9]  
Gauntt R., 2000, MELCOR Computer Code Manuals, V6119, P785
[10]   Assessment of VVER 1000 core degradation for bounding cases with ASTEC 2.1.1.0 [J].
Groudev, Pavlin ;
Stefanova, Antoaneta ;
Gencheva, Rositsa .
NUCLEAR ENGINEERING AND DESIGN, 2019, 351 :80-86