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Evaluation of management measures on a hypothetical accident in Unit-1 of bushehr nuclear power plant
Progress in Nuclear Energy ( IF 2.7 ) Pub Date : 2021-03-27 , DOI: 10.1016/j.pnucene.2021.103709
Navid Vahman , Reza Amrollahi , Mehdi Sohrabi , Maryam Qasemi

The evaluation of various measures on the thermohydraulic conditions of the circuit and especially the fuel conditions of the reactor in order to minimize the accident effects is vital. Therefore, this work examines the effect of the operator's actions on controlling loss of heat removal through the turbine condenser accident with failure of feedwater supply to steam generators.

The BNPP parameters during this accident has been analyzed considering two scenarios (with and without operator action) using the RELAP5 code. The simulation results showed that in case 1, the fuel cladding temperature has risen to 1200 °C within 11,000 s, which is more than the allowed temperature. The operator's actions in case 2 maintain the fuel cladding temperature in the permissible range level. Moreover, these results determine the available time for the operator's actions to prevent further core damage under the conditions that have been considered in the selected scenarios.



中文翻译:

布什尔核电站1号机组假设事故的管理措施评价

为了使事故影响最小化,对回路的热液工况,特别是反应堆的燃料工况进行各种措施的评估至关重要。因此,这项工作研究了操作员的行为对控制由于汽轮机冷凝器事故而导致的排热损失的影响,而汽轮机冷凝器事故导致给蒸汽发生器的给水供应失败。

已使用RELAP5代码考虑了两种情况(有和没有操作员采取行动)对事故期间的BNPP参数进行了分析。仿真结果表明,在情况1中,燃料包壳温度已升高至1200摄氏在11,000 s内,高于允许的温度。在情况2中,操作员的动作将燃油包壳温度保持在允许的范围内。此外,这些结果确定了操作员可采取的行动,以防止在所选方案中考虑的条件下进一步造成岩心损坏。

更新日期:2021-03-27
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