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Review of modeling experience during operation and decommissioning of RBMK-1500 reactors. I. Safety improvement studies during operation
Nuclear Engineering and Design ( IF 1.9 ) Pub Date : 2021-01-19 , DOI: 10.1016/j.nucengdes.2020.110952
V. Remeikis , J. Grineviciute , G. Duškesas , L. Juodis , R. Plukienė , A. Plukis

This review article presents the research done on the modeling of the RBMK-1500 reactor and its practical applications during reactor’s operation. Studies of the modeling for reactor safety improvement and research on Ignalina NPP during the normal and accidental conditions are reviewed: reactor neutronics, depletion of nuclear fuel, thermal-hydraulics, nuclear fuel thermo-mechanical behavior, fission product release and contamination of reactor circuit, nuclear fuel composition for design and increased enrichment with burnable poison, burn-up credit and benchmark calculations. Important findings and key modeling techniques are highlighted and the need of scientific input is discussed. The survey of the research done on modeling for decommissioning of the RBMK-1500 reactor is presented in the part II of the review Remeikis et al. (to be published).



中文翻译:

回顾RBMK-1500反应堆运行和退役期间的建模经验。一,运营过程中的安全改进研究

这篇综述文章介绍了RBMK-1500反应堆建模的研究及其在反应堆运行期间的实际应用。审查了在正常和偶然条件下改进反应堆安全性的模型研究和对Ignalina NPP的研究:反应堆中子学,核燃料的消耗,热工水力,核燃料的热机械行为,裂变产物的释放以及反应堆回路的污染,核燃料成分,用于设计和可燃毒物,燃尽信用和基准计算的增加浓缩。重点介绍了重要发现和关键建模技术,并讨论了科学投入的需求。在评论Remeikis等人的第二部分中介绍了RBMK-1500反应堆退役模型研究的概况。(待发布)。

更新日期:2021-01-19
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