发布时间：2025-04-30

论文名称：No-core-melt assessment for Canadian-SCWR under LOCA/LOECC

发表刊物：NUCLEAR SCIENCE AND TECHNIQUES

摘要：The safety analysis code SCTRAN for SCWR (Super CriticalWater Reactor) is modified to own the capability
to assess the radiation heat transfer with developing a two-dimensional heat conduction solution scheme and
incorporating a radiation heat transfer model. The verification of the developed radiation heat transfer model
is conducted through code-to-code comparison with CATHENA. The results show that the modified SCTRAN
code is successful for that the maximum absolute error and relative error of the surface temperature between
results of SCTRAN and CATHENA are 6:1 C and 0.9%, which are acceptable in temperature prediction. Then,
with the modified SCTRAN code, the loss of coolant accident with a total loss of emergency core cooling system
(LOCA/LOECC) of Canadian-SCWR is carried out to evaluate its “no-core-melt” concept. The following
conclusions are achieved: 1) in the process of LOCA, the decay heat can be totally removed by the radiation
heat transfer and the natural convection of the high-temperature coolant, even without an intervention of ECCS
(Emergency Core Cooling System); 2) The peak cladding temperature of the fuel pins in the inner and outer rings
of the high power group are 1236 C and 1177 C respectively, which are much lower than the melting point of
the fuel sheath. It indicates that the Canadian-SCWR can achieve “no-core-melt” concept under LOCA/LOECC.

合写作者：WU Pan,SHAN Jian-Qiang, GOU Jun-Li, ZHANG Bin,ZHANG Bo, and WANG He

卷号：26

页面范围：020601-1-12

是否译文：否

发表时间：2015-04-20