基于带定位格架类三角形子通道超临界水流动传热试验,数值研究了棒径为8 mm,栅距比为1.4的超临界水冷堆(Supercritical Water Cooled Reactor,SCWR)类三角形通道超临界流动传热定位格架结构影响,分析了同型定位格架典型结构参数和不同...基于带定位格架类三角形子通道超临界水流动传热试验,数值研究了棒径为8 mm,栅距比为1.4的超临界水冷堆(Supercritical Water Cooled Reactor,SCWR)类三角形通道超临界流动传热定位格架结构影响,分析了同型定位格架典型结构参数和不同定位格架型式对堆芯通道超临界流动传热特性的影响规律。研究结果表明:定位格架可强化堆芯通道超临界水传热,同型格架本体厚度越大,压力损失越高,格架处壁面温度越低,局部换热能力越好,当增大格架本体厚度,弱化程度无明显差异;阻流片型定位格架下游局部换热能力提高显著,阻流片直径越大,上游压力越大,局部壁温越低,换热系数越高,增大阻流片直径可减小传热弱化区域大小,强化传热能力;不同定位格架型式对比研究发现交错叶片型弱化区域最大,阻流片型定位格架弱化区域最小,阻流片型定位格架具有最佳的传热强化效果。展开更多
The safety analysis code SCTRAN for SCWR(Super Critical Water Reactor) is modified to own the capability to assess the radiation heat transfer with developing a two-dimensional heat conduction solution scheme and inco...The safety analysis code SCTRAN for SCWR(Super Critical Water 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.展开更多
文摘基于带定位格架类三角形子通道超临界水流动传热试验,数值研究了棒径为8 mm,栅距比为1.4的超临界水冷堆(Supercritical Water Cooled Reactor,SCWR)类三角形通道超临界流动传热定位格架结构影响,分析了同型定位格架典型结构参数和不同定位格架型式对堆芯通道超临界流动传热特性的影响规律。研究结果表明:定位格架可强化堆芯通道超临界水传热,同型格架本体厚度越大,压力损失越高,格架处壁面温度越低,局部换热能力越好,当增大格架本体厚度,弱化程度无明显差异;阻流片型定位格架下游局部换热能力提高显著,阻流片直径越大,上游压力越大,局部壁温越低,换热系数越高,增大阻流片直径可减小传热弱化区域大小,强化传热能力;不同定位格架型式对比研究发现交错叶片型弱化区域最大,阻流片型定位格架弱化区域最小,阻流片型定位格架具有最佳的传热强化效果。
基金Supported by the Doctoral Program of Higher Education of China(No.20120201110043)Atomic Energy of Canada Limited(AECL)
文摘The safety analysis code SCTRAN for SCWR(Super Critical Water 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.
