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首页> 外文期刊>Science and technology of nuclear installation >RELAP5 Analysis of OECD/NEA ROSA Project Experiment Simulating a PWR Loss-of-Feedwater Transient with High-Power Natural Circulation
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RELAP5 Analysis of OECD/NEA ROSA Project Experiment Simulating a PWR Loss-of-Feedwater Transient with High-Power Natural Circulation

机译:OECD / NEA ROSA项目实验的RELAP5分析,模拟具有大功率自然循环的压水堆给水暂态损失

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A ROSA/LSTF experiment was conducted for OECD/NEA ROSA Project simulating a PWR loss-of-feedwater (LOFW) transient with specific assumptions of failure of scram that may cause natural circulation with high core power and total failure of high pressure injection system. Auxiliary feedwater (AFW) was provided to well observe the long-term high-power natural circulation. The core power curve was obtained from a RELAP5 code analysis of PWR LOFW transient without scram. The primary and steam generator (SG) secondary-side pressures were maintained, respectively, at around 16 and 8 MPa by cycle opening of pressurizer (PZR) power-operated relief valve and SG relief valves for a long time. Large-amplitude level oscillation occurred in SG U-tubes for a long time in a form of slow fill and dump while the two-phase natural circulation flow rate gradually decreased with some oscillation. RELAP5 post-test analyses were performed to well understand the observed phenomena by employing a fine-mesh multiple parallel flow channel representation of SG U-tubes with a Wallis counter-current flow limiting correlation at the inlet of U-tubes. The code, however, has remaining problems in proper predictions of the oscillative primary loop flow rate and SG U-tube liquid level as well as PZR liquid level.
机译:针对OECD / NEA ROSA项目进行了ROSA / LSTF实验,模拟了压水堆给水失水(LOFW)瞬态,并假设了摇篮故障的具体假设,这可能会导致具有高堆芯功率的自然循环以及高压喷射系统的整体故障。提供辅助给水(AFW)以很好地观察长期的大功率自然循环。核心功率曲线是通过不加扰码的PWR LOFW瞬态的RELAP5代码分析获得的。通过长时间打开增压器(PZR)电动溢流阀和SG溢流阀,主泵和蒸汽发生器(SG)的二次侧压力分别保持在16和8 MPa左右。 SG U型管长时间以慢速充填和倾倒的形式发生大幅度的振荡,而两相自然循环流量随着振荡而逐渐降低。通过使用SG U型管的细网状多个平行流道表示法以及U型管入口处的Wallis逆流限流关系,进行了RELAP5后测试分析,以很好地理解所观察到的现象。但是,该代码在正确预测振荡主回路流量和SG U型管液位以及PZR液位方面仍然存在问题。

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