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全厂断电严重事故自然循环和蠕变失效分析 被引量:2
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作者 向清安 邓纯锐 +1 位作者 陈宝文 冯进军 《核动力工程》 EI CAS CSCD 北大核心 2014年第5期17-21,共5页
使用MELCOR 2.1程序建立ACP1000自然循环模型,选取全厂断电叠加辅助给水丧失严重事故(TMLB'),分析主冷却剂管道热段和蒸汽发生器(SG)传热管自然循环现象,采用蠕变失效模型评价主冷却剂系统(RCS)部件失效时间。结果表明,压力容器(RPV... 使用MELCOR 2.1程序建立ACP1000自然循环模型,选取全厂断电叠加辅助给水丧失严重事故(TMLB'),分析主冷却剂管道热段和蒸汽发生器(SG)传热管自然循环现象,采用蠕变失效模型评价主冷却剂系统(RCS)部件失效时间。结果表明,压力容器(RPV)出口接管比有裂纹的SG最热传热管先失效。 展开更多
关键词 自然循环 蠕变失效 tmlb' MELCOR 2.1程序
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压水堆核电厂自然循环对一回路卸压策略的影响 被引量:3
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作者 张琨 佟立丽 曹学武 《核动力工程》 EI CAS CSCD 北大核心 2009年第2期70-74,共5页
以我国秦山二期核电厂为研究对象,使用SCDAP/RELAP5程序建立了核电厂的自然循环模型。选取高压溶堆严重事故(TMLB’事故)为基准事故序列,分析了高压熔堆严重事故中自然循环的机理现象。通过计算在有无自然循环情况下一回路卸压措施的实... 以我国秦山二期核电厂为研究对象,使用SCDAP/RELAP5程序建立了核电厂的自然循环模型。选取高压溶堆严重事故(TMLB’事故)为基准事故序列,分析了高压熔堆严重事故中自然循环的机理现象。通过计算在有无自然循环情况下一回路卸压措施的实施情况,对比分析了自然循环对一回路卸压策略的影响。结果表明,自然循环能有效延缓一回路卸压的启动时间和整体事故进程,但对一回路卸压的效果影响较小。 展开更多
关键词 自然循环 tmlb’事故 一回路卸压策略 SCDAP/RELAP5程序
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Analysis of hot leg natural circulation under station blackout severe accident 被引量:2
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作者 DENG Jian CAO Xuewu 《Nuclear Science and Techniques》 SCIE CAS CSCD 2007年第2期123-128,共6页
Under severe accidents, natural circulation flows are important to influence the accident progression and result in a pressurized water reactor (PWR). In a station blackout accident with no recovery of steam generator... Under severe accidents, natural circulation flows are important to influence the accident progression and result in a pressurized water reactor (PWR). In a station blackout accident with no recovery of steam generator (SG) auxiliary feedwater (TMLB' severe accident scenario), the hot leg countercurrent natural circulation flow is analyzed by using a severe-accident code, to better understand its potential impacts on the creep-rupture timing among the surge line, the hot leg, and SG tubes. The results show that the natural circulation may delay the failure time of the hot leg. The recirculation ratio and the hot mixing factor are also calculated and discussed. 展开更多
关键词 压水堆 全场断电 严重事故 热管段 自然循环
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Effect analysis of the intentional depressurization on fission product behavior during TMLB' severe accident
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作者 HUANG Gaofeng LI Jingxi TONG Lili CAO Xuewu 《Nuclear Science and Techniques》 SCIE CAS CSCD 2009年第6期373-379,共7页
It has been found that the pressure in the reactor coolant system (RCS) remains high in some severe accident sequences at the time of reactor vessel failure, with the risk of causing direct containment heating (DCH). ... It has been found that the pressure in the reactor coolant system (RCS) remains high in some severe accident sequences at the time of reactor vessel failure, with the risk of causing direct containment heating (DCH). Intentional depressurization is an effective accident management strategy to prevent DCH or to mitigate its consequences. Fission product behavior is affected by intentional depressurization, especially for inert gas and volatile fission product. Because the pressurizer power-operated relief valves (PORVs) are latched open, fission product will transport into the containment directly. This may cause larger radiological consequences in containment before reactor vessel failure. Four cases are selected, including the TMLB' base case and the opening one, two and three pressurizer PORVs. The results show that inert gas transports into containment more quickly when opening one and two PORVs, but more slowly when opening three PORVs; more volatile fission product deposit in containment and less in reactor coolant system (RCS) for intentional depressurization cases. When opening one PORV, the phenomenon of revaporization is strong in the RCS. 展开更多
关键词 裂变产物 控制产品 严重事故 减压 故意 行为 反应堆冷却剂系统 雷达散射截面
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