Simulations of unprotected loss of heat sink and combination of events accidents for a molten salt reactor

被引:27
作者
Guo, Zhangpeng
Zhang, Dalin
Xiao, Yao
Tian, Wenxi
Su, Guanghui
Qiu, Suizheng [1 ]
机构
[1] Xi An Jiao Tong Univ, Dept Nucl Sci Technol, Xian 710049, Peoples R China
关键词
Molten salt reactor; Safety analysis code; Unprotected loss of heat sink; Combination of events; FLUID-FUEL SYSTEMS; DYNAMICS CODE; SAFETY; SCRAM;
D O I
10.1016/j.anucene.2012.09.009
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 molten salt reactor (MSR) is one of the Generation IV reactors. The fuel is dissolved in the carrier salt and circulates in the loop. The technologies are different from that in the solid-fuel reactors. In this work, the attention is focused on development of safety analysis tool for the MSRs. A single channel model, a heat transfer model, a heat sink model and a liquid-fuel point kinetic model that takes into account the effect of circulation are employed. The validation of this code is done with the experimental data of pump coastdown and startup in MSRE. The unprotected loss of heat sink (ULOHS), combination of ULOHS and unprotected loss of flow (ULOF) are performed on the Molten Salt Actinide Recycler and Transmuter (MOSART). This work aims to study temperature fluctuation, corresponding power change, effect of flow delayed neutron precursors and temperature reactivity feedback in transient accident to examine the inherent safety design of MOSART. The transient results reveal that the large negative temperature feedback coefficients guarantee MOSART inherent safety and the range of temperature is within the safety margin in case of combination of accidental events. (C) 2012 Elsevier Ltd. All rights reserved.
引用
收藏
页码:309 / 319
页数:11
相关论文
共 25 条
[1]  
[Anonymous], 2000, IAEA SAF STAND SER
[2]   A multi-physics modelling approach to the dynamics of Molten Salt Reactors [J].
Cammi, Antonio ;
Di Marcello, Valentino ;
Luzzi, Lelio ;
Memoli, Vito ;
Ricotti, Marco Enrico .
ANNALS OF NUCLEAR ENERGY, 2011, 38 (06) :1356-1372
[3]  
Cooke J.W., 1973, ORNL-TM-4079
[4]   Neutron kinetics of fluid-fuel systems by the quasi-static method [J].
Dulla, S ;
Ravetto, P ;
Rostagno, MM .
ANNALS OF NUCLEAR ENERGY, 2004, 31 (15) :1709-1733
[5]  
Forsberg C.W., 2007, INT C ADV NUCL POW P, P7596
[6]  
Gear C.W., 1971, NUMERICAL INITIAL VA, P126
[7]  
Generation IV International Forum, 2002, GIF-002-00
[8]  
Haubenreich P.N., 1962, Technical Report ORNL-TM-0380
[9]  
IGNATIEV V, 2003, P 2003 ANS ENS INT W
[10]   Safety of the super LWR [J].
Ishiwatari, Yuki ;
Oka, Yoshiaki ;
Koshizuka, Selichi .
NUCLEAR ENGINEERING AND TECHNOLOGY, 2007, 39 (04) :257-272