先进PWR堆腔淹没情况下的自然循环研究

发布时间：2018-11-16 11:59

【摘要】：在先进压水堆核电厂中,堆腔注水是重要的严重事故管理措施之一。采用RELAP5程序对堆腔淹没情况下反应堆压力容器(RPV)外壁与保温层间隙内的自然循环进行研究。通过对韩国APR1400堆腔注水系统实验的模拟,证明RELAP5程序模拟此类自然循环的适用性。对美国AP1000堆腔自然循环的分析表明,保温层间隙内建立的自然循环有足够的热量排出能力,可以有效防止RPV下封头的热失效。敏感性分析结果表明,冷却水入口面积越大,自然循环的流量越大;为了使产生的蒸汽顺利排出以建立稳定的自然循环,汽-水出口面积应足够大,且汽-水出口应布置在不会被堆腔水淹没的位置;在堆腔注水措施的实施中,应保证堆腔被淹没到足够高的位置以提供足够的循环静压驱动力。
[Abstract]:In the advanced PWR nuclear power plant, reactor cavity water injection is one of the important serious accident management measures. The natural circulation between (RPV) outer wall and insulation layer of reactor pressure vessel under submerged reactor cavity was studied by RELAP5 program. The simulation of APR1400 reactor cavity injection system in South Korea proves the applicability of RELAP5 program to simulate this kind of natural circulation. The analysis of the natural circulation of the AP1000 reactor cavity in the United States shows that the natural circulation established in the gap of the insulation layer has sufficient heat discharge capacity and can effectively prevent the thermal failure of the head under the RPV. The sensitivity analysis results show that the larger the inlet area of cooling water, the larger the flow rate of natural circulation. In order to discharge the generated steam smoothly to establish a stable natural cycle, the steam-water outlet area should be large enough, and the steam-water outlet should be arranged in a position that will not be submerged by the water in the reactor chamber; In the implementation of reactor cavity injection measures, it should be ensured that the reactor cavity is submerged to a sufficiently high position to provide sufficient circulating static pressure driving force.
【作者单位】：中科华核电技术研究院;中广核工程设计有限公司;
【分类号】：TL364.4

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