Assessments of RELAP5/MOD3.2 and RELAP5/CANDU in a Reactor Inlet Header Break Experiment B9401 of RD-14M
Assessments of RELAP5/MOD3.2 and RELAP5/CANDU in a Reactor Inlet Header Break Experiment B9401 of RD-14M
复制标题
DOI：
--
复制
发表时间：
2003-10
影响因子：
2.7
通讯作者：
Yongjin Cho;Gyoodong Jeun
中科院分区：
文献类型：
--
作者：
Yongjin Cho;Gyoodong Jeun
使用RELAP 5/MOD 3.2和RELAP 5/CANDU[1]分析了在RD-14 M多通道试验设备中进行的反应堆入口集管破裂实验B 9401。RELAP 5是为了分析压水反应堆的瞬态行为而开发的。最近的一项研究表明，RELAP 5甚至可以用于CANDU反应堆热工水力行为的模拟。然而，RELAP 5评估中确定了燃料鞘层温度预测和燃烧室顶盖瞬态行为的一些不足之处。RELAP 5/CANDU是为了解决RELAP 5的不足和提高CANDU堆热工水力特性的可预测性而开发的。在RELAP 5/CANDU中，对临界热流密度模型、水平流态图、水平通道传热模型等进行了修改或添加到RELAP 5/MOD 3.2中。本研究的目的是确定这两个代码的适用性，特别是在CANDU反应堆的多通道模拟。RELAP 5/MOD3.2和RELAP 5/CANDU的分析表明，代码的能力，合理地预测在瞬态过程中发生的主要现象。两个代码的热工水力行为几乎相同，但是，RELAP 5/CANDU预测更好的加热器护套温度比RELAP 5/MOD 3.2。集管之间的压差决定了通过加热段的流量特性，特别是在ECI之后。在确定集箱压力时，由于稳态压力分布等复杂因素的影响，存在许多不确定性。因此，可以得出结论，需要进一步的工作，以减少这些不确定性，从而预测适当的热工水力行为在反应堆冷却剂系统在失水事故分析。
A reactor inlet header break experiment, B9401, performed in the RD-14M multi channel test facility was analyzed using RELAP5/MOD3.2 and RELAP5/CANDU[1]. The RELAP5 has been developed for the use in the analysis of the transient behavior of the pressurized water reactor. A recent study showed that the RELAP5 could be feasible even for the simulation of the thermal hydraulic behavior of CANDU reactors. However, some deficiencies in the prediction of fuel sheath temperature and transient behavior in athe headers were identified in the RELAP5 assessments. The RELAP5/CANDU has been developing to resolve the deficiencies in the RELAP5 and to improve the predictability of the thermal-hydraulic behaviors of the CANDU reactors. In the RELAP5/CANDU, critical heat flux model, horizontal flow regime map, heat transfer model in horizontal channel, etc. were modified or added to the RELAP5/MOD3.2. This study aims to identify the applicability of both codes, in particular, in the multi-channel simulation of the CANDU reactors. The RELAP5/MOD3.2 and the RELAP5/CANDU analyses demonstrate the code's capability to predict reasonably the major phenomena occurred during the transient. The thermal-hydraulic behaviors of both codes are almost identical, however, the RELAP5/CANDU predicts better the heater sheath temperature than the RELAP5/MOD3.2. Pressure differences between headers govern the flow characteristics through the heated sections, particularly after the ECI. In determining header pressure, there are many uncertainties arisen from the complicated effects including steady state pressure distribution. Therefore, it would be concluded that further works are required to reduce these uncertainties, and consequently predict appropriately thermal-hydraulic behaviors in the reactor coolant system during LOCA analyses.