發(fā)布時(shí)間：2018-06-13 13:22

  本文選題：堆芯熔融物 + 壓力容器內(nèi)滯留�。� 參考：《核動(dòng)力工程》2015年06期

【摘要】：基于堆芯熔融物與壓力容器傳熱的機(jī)理分析模型,采用風(fēng)險(xiǎn)導(dǎo)向事故分析方法(ROAAM)分析壓水堆在嚴(yán)重事故情況下通過冷卻壓力容器外部的手段來實(shí)施堆芯熔融物滯留在壓力容器內(nèi)(IVR)策略的有效性。以核電廠一級(jí)概率安全評(píng)價(jià)(PSA)分析結(jié)果為參考,計(jì)算ACP1000典型嚴(yán)重事故序列,分析影響熔融物傳熱的重要參數(shù)不確定性。概率分析結(jié)果表明:ACP1000發(fā)生假象的嚴(yán)重事故情況下,IVR策略有效性概率大于99%;由于熔融池頂部的金屬層出現(xiàn)集熱效應(yīng),下封頭發(fā)生傳熱危險(xiǎn)的主要位置出現(xiàn)在金屬層。
[Abstract]:Based on the mechanism analysis model of heat transfer between core melt and pressure vessel, Risk-oriented accident analysis (ROAAM) is used to analyze the effectiveness of the IVR strategy of pressurized water reactor (PWR) by cooling the outside of the pressure vessel to implement the retention of core melt in the pressure vessel. Based on the PSA-analysis results of first-order probabilistic safety assessment of nuclear power plants, the typical serious accident sequence of ACP1000 is calculated, and the uncertainty of important parameters affecting the heat transfer of molten matter is analyzed. The results of probabilistic analysis show that the probability of effectiveness of IVR strategy is greater than 99 in the case of serious false accident, and the main position of heat transfer hazard in the lower head occurs in the metal layer due to the heat collecting effect at the top of the melting pool.
【作者單位】： 中國核動(dòng)力研究設(shè)計(jì)院核反應(yīng)堆系統(tǒng)設(shè)計(jì)技術(shù)重點(diǎn)實(shí)驗(yàn)室;
【分類號(hào)】：TL364.4

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本文編號(hào)：2014158