{"title":"Computational analysis of a blackout accident at a decomissioned RBMK","authors":"I. A. Tupotilov, A. K. Smirnova, A. V. Kraushkin","doi":"10.1007/s10512-024-01065-z","DOIUrl":null,"url":null,"abstract":"<div><p>In order to improve the safety of operating nuclear power plants with RBMK-1000 reactors, work is underway for developing and substantiating the control actions of personnel under severe accident conditions for all possible initial states of the power unit, including shutdown for decommissioning. An accident is considered using the STEPAN‑T 3D program developed specifically for simulating an accident with the complete blackout of a RBMK reactor. The time dependence of the temperature in the core, metal structures, and OR scheme is given. Quantitative estimates of the hydrogen formation during an accident are shown. The possibility of re-criticality and release of radioactive substances occurring during the accident are discussed. Possible measures to mitigate the consequences of the accident are given.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"134 5-6","pages":"352 - 360"},"PeriodicalIF":0.4000,"publicationDate":"2024-04-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Atomic Energy","FirstCategoryId":"5","ListUrlMain":"https://link.springer.com/article/10.1007/s10512-024-01065-z","RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q4","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0
Abstract
In order to improve the safety of operating nuclear power plants with RBMK-1000 reactors, work is underway for developing and substantiating the control actions of personnel under severe accident conditions for all possible initial states of the power unit, including shutdown for decommissioning. An accident is considered using the STEPAN‑T 3D program developed specifically for simulating an accident with the complete blackout of a RBMK reactor. The time dependence of the temperature in the core, metal structures, and OR scheme is given. Quantitative estimates of the hydrogen formation during an accident are shown. The possibility of re-criticality and release of radioactive substances occurring during the accident are discussed. Possible measures to mitigate the consequences of the accident are given.
为了提高运行中的 RBMK-1000 反应堆核电站的安全性，目前正在开展工作，针对机组所有可能的初始状态（包括为退役而停机），开发和验证人员在严重事故条件下的控制行动。使用专门为模拟 RBMK 反应堆完全停电事故而开发的 STEPAN-T 3D 程序对事故进行了考虑。给出了堆芯、金属结构和 OR 方案的温度随时间变化的情况。显示了事故期间氢形成的定量估计值。讨论了事故期间发生再临界和放射性物质释放的可能性。给出了减轻事故后果的可能措施。
期刊介绍：
Atomic Energy publishes papers and review articles dealing with the latest developments in the peaceful uses of atomic energy. Topics include nuclear chemistry and physics, plasma physics, accelerator characteristics, reactor economics and engineering, applications of isotopes, and radiation monitoring and safety.
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