首页> 外文期刊>Nuclear Engineering and Design >Integral loop test and assessment of modified RELAP5/MOD3.3 for RCS coolant inventory during a LBLOCA
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Integral loop test and assessment of modified RELAP5/MOD3.3 for RCS coolant inventory during a LBLOCA

机译:在LBLOCA期间对RCS冷却液清单进行修改的RELAP5 / MOD3.3的整体回路测试和评估

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摘要

This study investigates experimentally and analytically the thermal hydraulic phenomena during the transition from design basis accident (DBA) to beyond-DBA, particularly, the depletion of core coolant inventory. To investigate the overall thermal hydraulic behavior after safety injection (SI) failure during a large-break loss-of-coolant accident (LBLOCA) in a cold leg, an integral loop test was performed at the Seoul National University Integral Test Facility (SNUF), which was scaled down to 1/6.4 in length and 1/178 in area from the advanced power reactor 1400 MWe (APR1400) according to the three-level scaling method. The plant condition at 200.0 s as the base case and those at 625.0 and 1950.0 s as test cases after the initiation of LBLOCA were applied as initial conditions in the experiments, respectively. The experimental results showed that the sweepout increased the coolant flow discharged to the break depending on the steam flow rate in intact cold legs and the initial downcomer coolant level and expedited the depletion of the core coolant inventory. In the meantime, since RELAP5/MOD3.3 uses the average properties of donor volume as those of its connected junction, this scheme causes the mass and the energy flux in a junction to be calculated incorrectly if significant phase separation occurs in the donor volume such as in the downcomer during the LBLOCA. The sweepout model was developed and implemented in RELAP5/MOD3.3 to improve its calculation of coolant inventory during the LBLOCA. To assess the applicability of the modified RELAP5/MOD3.3 to the actual system, the experiments in SNUF were simulated by both the original and the modified RELAP5/MOD3.3. The original one predicted the discharge flow rate at the break larger than that of the experiment. On the other hand, the modified one calculated the discharge flow rate more similar to that of the experiment than the original one did. As a result, the modified RELAP5/MOD3.3 reduced the coolant flow discharged to the break to delay the initiation time of heater heat-up after SI failure during LBLOCA in a cold leg. This improved RELAP5/MOD3.3 will support a more realistic thermal hydraulic analysis in an integrated analysis system.
机译:这项研究通过实验和分析方法研究了从设计基准事故(DBA)过渡到DBA以外的过程中的热水现象,尤其是堆芯冷却剂库存的消耗。为了研究冷腿大破口失水事故(LBLOCA)期间安全注射(SI)失效后的整体热液压行为,首尔国立大学综合测试设施(SNUF)进行了整体回路测试根据三级缩放方法,它从先进的功率反应堆1400 MWe(APR1400)缩减为长度的1 / 6.4和面积的1/178。在实验中,分别以LBLOCA起始后200.0 s的植物条件和6250.0和1950.0 s的植物条件作为初始条件。实验结果表明,取决于完整冷段中的蒸汽流量和初始降液管冷却剂液位,清扫气增加了排放到断裂处的冷却剂流量,并加快了堆芯冷却剂库的消耗。同时,由于RELAP5 / MOD3.3使用施主体的平均性质作为其连接结的性质,因此如果施主体中发生明显的相分离,此方案将导致错误地计算接合处的质量和能量通量,例如就像在LBLOCA的降液管中一样。清扫模型是在RELAP5 / MOD3.3中开发和实现的,以改善LBLOCA期间冷却剂存量的计算。为了评估修改后的RELAP5 / MOD3.3在实际系统中的适用性,在SNUF中通过原始和修改后的RELAP5 / MOD3.3进行了仿真。原始的预测断裂时的排放流量大于实验的排放流量。另一方面,与原始实验相比,修改后的实验计算出的排放流量与实验更为相似。结果,修改后的RELAP5 / MOD3.3减少了冷却剂流到断裂处的流量,从而延迟了冷腿LBLOCA中SI失效后加热器加热的启动时间。改进后的RELAP5 / MOD3.3将在集成分析系统中支持更逼真的热力水力分析。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2007年第2期|p.182-198|共17页
  • 作者单位

    EnEsys Co., Pianetta Bldg-337, Jangdae-Dong, Yuseong-Gu, Daejeon 151-818, Republic of Korea;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类 原子能技术;
  • 关键词

  • 入库时间 2022-08-18 00:46:09

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