| 秦山一期核电站未能紧急停堆的预期瞬变导致堆芯熔化的进程及事故缓解措施研究 |
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| 引用本文： | 车济尧,曹学武. 秦山一期核电站未能紧急停堆的预期瞬变导致堆芯熔化的进程及事故缓解措施研究[J]. 核动力工程, 2005, 26(3): 209-213,218 |
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| 作者姓名： | 车济尧 曹学武 |
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| 作者单位： | 上海交通大学核科学与系统工程系,200030;上海交通大学核科学与系统工程系,200030 |
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| 摘 要： | 选择失去主给水、失去厂外电和正常运行情况下控制棒失控提升3个典型的导致未能紧急停堆的预期瞬变(ATWS)的初因事故，采用自行研制的基于SCDAP／RELAP5／MOD3．1的核反应堆严重事故分析平台，对秦山一期核电站ATWS初因导致堆芯熔化严重事故进程进行了分析研究，对防止ATWS导致堆芯熔化进程的缓解措施的有效性进行了验证。计算分析结果表明，二回路补水和一回路卸压的事故缓解措施能有效地阻止堆芯熔化进程。
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| 关 键 词： | 秦山一期核电站 未能紧急停堆的预期瞬变 严重事故 缓解措施 |
| 文章编号： | 0258-0926(2005)03-0209-06 |
Studyon Severe Core Damage Progression Induced by Anticipated Transients without Scram and Its Mitigation in Qinshan NPP Unit1 |
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| CHE Ji-yao,CAO Xue-wu. Studyon Severe Core Damage Progression Induced by Anticipated Transients without Scram and Its Mitigation in Qinshan NPP Unit1[J]. Nuclear Power Engineering, 2005, 26(3): 209-213,218 |
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| Authors: | CHE Ji-yao CAO Xue-wu |
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| Abstract: | By using a simulator based on SCDAP/RELAP5/MOD3.1 computer code, the core damage progression and theeffectiveness of preventive and mitigation measures are analyzed with the anticipated transients without scram (ATWS) sequences caused by the loss of main feed water (LOFW), the loss of off-site power (LOOP) and uncontrolled rod cluster control assembly (RCCA) bank withdrawal, combined with the failure of reactor control and protection system in Qinshan Nuclear Power Plant (NPP) unit1. |
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| Keywords: | Anticipated transients without scram(ATWS) Severe accident Mitigation measurement Qinshan NPP |
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