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首页> 外文期刊>Nuclear Technology >Performance Evaluation Of The Safety Analysis Codes For Subcooled Boiling In A Nuclear Reactor Downcomer During The Late Reflood Phase Of An Lbloca
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Performance Evaluation Of The Safety Analysis Codes For Subcooled Boiling In A Nuclear Reactor Downcomer During The Late Reflood Phase Of An Lbloca

机译：Lbloca后期洪灾阶段核反应堆降液管过冷沸腾安全分析代码的性能评估

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摘要

The reflood rate in a core is an important parameter for core cooling during a large-break loss-of-coolant-accident (LBLOCA) reflood period, and it strongly depends on the thermal-hydraulic conditions in the down-comer. During this period, downcomer boiling has an important influence on the transient behavior of a postulated LBLOCA because it can degrade the hydraulic head in a downcomer and consequently affect the reflood flow rate for core cooling. Although it is recognized that downcomer boiling is critical to correctly predict the reflood phenomena of an LBLOCA transient, especially for a direct vessel injection adapted system like the advanced power reactor APR1400, the amount of experimental data and code assessment in this area is relatively limited. To improve the state of knowledge relative to downcomer boiling, a test program at the Downcomer Boiling (DOBO) facility is progressing for the reflood phase of a postulated LBLOCA. The DOBO facility was designed to meet a full scale for the height and gap of a reactor downcomer. The DOBO test revealed a strong multidimensional boiling behavior, which induces the need for performance evaluation of the best-estimate codes that are used to analyze a nuclear reactor's thermal-hydraulic safety, since they have mostly been used for one-dimensional system behavior. In this study, RELAP, MARS, and TRACE are evaluated by using measured two-phase-flow data. Based on the assessments, the modeling capability and weak points of the safety analysis codes are addressed for multidimensional downcomer boiling phenomena. Two models for a downcomer are considered to assess the codes for the DOBO tests, which are also applied to a plant analysis.
机译：在大断裂冷却剂意外事故（LBLOCA）的再灌注期中，堆芯的回油率是堆芯冷却的重要参数，并且在很大程度上取决于下导管的热工条件。在此期间，降液管沸腾对假定的LBLOCA的瞬态行为具有重要影响，因为它可能会使降液管中的液压压头降级，从而影响堆芯冷却的回油流量。尽管人们认识到降液管沸腾对于正确预测LBLOCA瞬态的回潮现象至关重要，特别是对于采用直接容器注入的系统，例如先进的动力反应堆APR1400，该领域的实验数据和代码评估相对有限。为了提高与降液管沸腾有关的知识水平，在升空管沸腾（DOBO）设施的测试程序正在进行中，用于假定的LBLOCA的回注阶段。 DOBO设施旨在满足反应堆降液管高度和间隙的全面要求。 DOBO测试显示出强大的多维沸腾行为，这导致需要对用于分析核反应堆热工安全性的最佳估算代码进行性能评估，因为它们主要用于一维系统行为。在这项研究中，RELAP，MARS和TRACE通过使用测得的两相流数据进行了评估。在评估的基础上，针对多维降液管沸腾现象解决了安全分析代码的建模能力和弱点。考虑使用降液管的两个模型来评估DOBO测试的代码，这些代码也适用于工厂分析。

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