RELAP5 Simulation of Thermal-Hydraulic Behavior in a CANDU Reactor—Assessments of RD-14 Experiments
RELAP5 Simulation of Thermal-Hydraulic Behavior in a CANDU Reactor—Assessments of RD-14 Experiments
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DOI：
10.13182/nt00-a3074
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发表时间：
2000-04
影响因子：
1.5
通讯作者：
Sukho Lee;Ingoo Kim
中科院分区：
文献类型：
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作者：
Sukho Lee;Ingoo Kim
用RELAP 5/MOD3.1程序对RD-14试验装置上的临界堆顶盖破裂和热虹吸实验进行了模拟。RELAP 5代码已开发的最佳估计的瞬态模拟的压水反应堆和相关系统，但它还没有被评估为加拿大氘铀（CANDU）反应堆。因此，本研究已经开始，旨在通过模拟RD-14设施中进行的一些试验，确定CANDU反应堆中代码的适用性。白壳核研究机构的RD-14试验设施是一个全尺寸的加压水回路。RD-14不是任何特定CANDU反应堆的比例模型。相反，它具有CANDU反应堆传热系统的许多几何特征，并且能够在与正常运行和一些假设事故条件下反应堆中预期发生的情况类似的条件下运行。在这项研究中，两个关键的反应堆顶盖破裂试验（B8711和B8713）和三个热虹吸试验（T8513，T8515和T8517）进行了分析与RELAP 5代码。实验数据和CATHENA的加拿大原子能有限公司进行的RELAP 5分析的结果进行了比较，证明代码的能力，合理地预测在瞬态中发生的主要现象，在定性和定量的观点。然而，一些差异后，紧急冷却剂注入的临界断裂的情况下，也与行为的质量流量和热虹吸的情况下的主压力进行了观察。
The critical reactor header break and the thermosiphoning experiments in the RD-14 test facility were simulated with the RELAP5/MOD3.1 code. The RELAP5 code has been developed for best-estimate transient simulation of pressurized water reactors and associated systems, but it has not been assessed for a Canada deuterium uranium (CANDU) reactor. Therefore, this study has been initiated with an aim to identify the code applicability in a CANDU reactor by simulating some of the tests performed in the RD-14 facility. The RD-14 test facility at Whiteshell Nuclear Research Establishment is a full-scale pressurized-water loop. The RD-14 is not a scale model of any particular CANDU reactor. Rather, it possesses many geometric features of a CANDU reactor heat transport system and is capable of operating at conditions similar to those expected to occur in a reactor under normal operation and some postulated accident conditions. In this study, two critical reactor header break tests (B8711 and B8713) and three thermosiphoning tests (T8513, T8515, and T8517) were analyzed with the RELAP5 code. The results were compared with experimental data and those of CATHENA performed by Atomic Energy of Canada Ltd. The RELAP5 analyses demonstrate the code’s capability to predict reasonably the main phenomena occurring in the transient, in both the qualitative and the quantitative view. However, some discrepancies after the emergency coolant injection for the critical break case and also related to the behaviors of the mass flow rate and the primary pressure for the thermosiphoning case were observed.