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Multi-module program for small-leak sodium–water reaction analysis in steam generators of sodium-cooled fast reactors
Progress in Nuclear Energy ( IF 3.3 ) Pub Date : 2020-08-01 , DOI: 10.1016/j.pnucene.2020.103400
L.L. Tong , T.L. Wang , J. Deng , X.W. Cao

Abstract To analyze the process of a small-leak sodium–water reaction (SWR) in the secondary loop of the steam generator (SG) in sodium-cooled fast reactors (SFRs), a multi-module program is developed herein. This program is developed by evaluating the models of heat transfer tube self-wastage, target tube wastage, and hydrogen migration and dissolution, which are involved in the small-leak SWR accident caused by a heat transfer tube with leakage in a single-module SG. The developed program could be used to investigate the time of occurrence of the heat transfer tube self-wastage, adjacent tube wastage, and the response time of the hydrogen concentration detectors at different leakage rates. The program can further provide the reasonable positions of hydrogen concentration detectors. The results of this study provide a reference for designing the secondary loops of small-leak accident protection systems for SFRs.

中文翻译:

钠冷快堆蒸汽发生器小泄漏钠水反应分析多模块程序

摘要 为了分析钠冷快堆(SFR)蒸汽发生器(SG)二次回路中小泄漏钠水反应(SWR)的过程,本文开发了一个多模块程序。该程序是通过评估传热管自损耗、靶管损耗、氢迁移和溶解等模型而开发的,这些模型涉及单模块SG中传热管泄漏引起的小泄漏SWR事故。 . 开发的程序可用于研究传热管自身损耗、相邻管损耗的发生时间以及氢浓度检测器在不同泄漏率下的响应时间。该程序可以进一步提供氢浓度检测器的合理位置。
更新日期:2020-08-01
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