本文選題：概率安全評(píng)價(jià) + 正常余熱排出系統(tǒng)��； 參考：《核科學(xué)與工程》2015年04期

【摘要】：基于對(duì)AP1000一級(jí)概率安全分析(PSA)的結(jié)果,發(fā)現(xiàn)正常余熱排出系統(tǒng)(RNS)的設(shè)計(jì)不足可能會(huì)導(dǎo)致安注管線破裂(SI-LB)始發(fā)事件對(duì)堆芯損壞頻率(CDF)貢獻(xiàn)較高。對(duì)正常余熱排出系統(tǒng)進(jìn)行適當(dāng)?shù)南到y(tǒng)改進(jìn),采用概率安全分析的方法重新構(gòu)建了改進(jìn)后的RNS系統(tǒng)故障樹(shù)及相關(guān)事件樹(shù)模型,對(duì)RNS系統(tǒng)可靠性進(jìn)行分析,并對(duì)改進(jìn)后核電廠CDF、進(jìn)行了計(jì)算,結(jié)果表明,RNS系統(tǒng)改進(jìn)后可大大減少安注管破裂始發(fā)事件導(dǎo)致的堆芯損壞,改進(jìn)后電廠堆芯損壞頻率(CDF)降低29.1%。
[Abstract]:Based on the results of the first-order probabilistic safety analysis (AP1000), it is found that the inadequate design of the normal residual heat discharge system may lead to a higher contribution of the SI-LB incident to the core damage frequency. The improved RNS system fault tree and related event tree model are constructed by using probabilistic safety analysis method. The reliability of RNS system is analyzed. The results show that the improved RNS system can greatly reduce the core damage caused by the rupture of the injection pipe, and the core damage frequency of the improved power plant can be reduced by 29.1.
【作者單位】： 中廣核工程設(shè)計(jì)有限公司上海分公司;
【分類號(hào)】：TM623
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本文編號(hào)：1887822