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An open calculation of RD-14M small-break LOCA experiments using CATHENA code

机译:使用CATHENA代码对RD-14M小断裂LOCA实验进行开放式计算

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摘要

The open calculations of two Small Break Loss of Coolant Accident (SBLOCA) experiments in the RD-14M integral test facility are performed as an International Atomic Energy Agency (IAEA) activity of International Collaborative Standard Problem (1CSP) with the objective to benchmark and validate the thermalhydraulic analysis code against qualified data for Heavy Water Reactor (HWR) systems. This ICSP started with the first meeting of the participants in Vienna in 2007 November. Two tests were selected for this activity, test B9006, a 7-mm inlet header break experiment with pressurized accumulator emergency coolant injection, performed in 1990, and test B9802, a 3-mm inlet header break experiment, performed in 1998, to provide data with full channel power to study boiling in the channels and condensation in the steam generators. The previously performed blind simulations demonstrated that the CATHENA code is capable of adequately predicting the primary pressure depressurization, channel flow rate, channel voiding for tests B9006 and B9802, and the high pressure core injection flow by CATHENA accumulator model and switching time from high pressure to low pressure injections for test B9006. However, several significant discrepancies between the code predictions and the measurement data were noted, and attributed to the input errors and the code models relevant to post-dryout (PDO) heat transfer phenomena in the heated channels of test B9802. Therefore, the open calculations are performed to allow correction of previous blind calculations in the present study. These open calculations include the Senaratne and Leung model with the optimized coefficients of its correlation for the test B9802, which can predict more accurately the onset of sustained dryout on the surface of the heater rods. The improvement of the open calculation results are shown by comparing them with the test data and also with the blind calculation results.
机译:作为国际原子能机构(IAEA)开展的国际合作标准问题(1CSP)活动,对RD-14M整体测试设施中的两次冷却剂事故小断裂损失(SBLOCA)实验进行了公开计算,目的是进行基准测试和验证针对重型反应堆(HWR)系统的合格数据的热工水力分析代码。该国际公务员制度委员会从2007年11月在维也纳举行的第一次会议开始。为此,选择了两项测试:测试B9006(使用加压蓄能器紧急冷却剂注入的7毫米进口集管断裂实验)和测试B9802(使用1998年进行的3毫米进口集管断裂试验),以提供数据。具有全通道功率,以研究通道中的沸腾和蒸汽发生器中的冷凝。先前执行的盲模拟表明,CATHENA代码能够充分预测测试B9006和B9802的一次压力降压,通道流速,通道空隙以及CATHENA蓄能器模型的高压岩心注入流量以及从高压到高压的切换时间。测试B9006的低压注入。但是,代码预测和测量数据之间存在一些显着差异,这归因于与测试B9802加热通道中的干燥后(PDO)传热现象相关的输入错误和代码模型。因此,进行开放计算可以校正本研究中先前的盲目计算。这些开放式计算包括具有针对测试B9802的最佳相关系数的Senaratne和Leung模型,该模型可以更准确地预测加热棒表面持续变干的开始。通过将开放计算结果与测试数据以及盲计算结果进行比较,可以显示出改进的结果。

著录项

  • 来源
    《Annals of nuclear energy》 |2012年第2012期|p.63-75|共13页
  • 作者

    Hyoung Tae Kim;

  • 作者单位

    Severe Accident and PHWR Safety Research Division, Korea Atomic Energy Research Institute, 1045 Daedeok-daero, Yuseong-Gu, Daejeon 305-353, Republic of Korea;

  • 收录信息
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    RD-14M; CATHENA; SB-LOCA; CANDU; open calculation;

    机译:E设为-14;卡特娜;胖乎乎的视图;开胶体;

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