Analysis of nitrogen intrusion from ECCS accumulators in SBLOCA scenarios at LSTF test facility

IF 3.2 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Tomás Ten-Gallardo , Sergio Gallardo , María Lorduy-Alós , Gumersindo Verdú
{"title":"Analysis of nitrogen intrusion from ECCS accumulators in SBLOCA scenarios at LSTF test facility","authors":"Tomás Ten-Gallardo ,&nbsp;Sergio Gallardo ,&nbsp;María Lorduy-Alós ,&nbsp;Gumersindo Verdú","doi":"10.1016/j.pnucene.2025.105954","DOIUrl":null,"url":null,"abstract":"<div><div>After the injection of borated water during accidental sequences, the intrusion of nitrogen gas from the accumulators once emptied can degrade heat transfer mechanisms and thus hinder core cooling. The non-condensable gas that enters the cold legs transfers and accumulates in the U-tubes of the steam generators and their outlet plenums. This can cause flow stagnation and even prevent reflux cooling. Furthermore, a temporary and fluctuating increase in primary pressure may occur, disabling the low-pressure injection system pumps to restore the inventory. In this scenario, it is essential to confirm the effectiveness of the accident management measures under the influence of non-condensable gas. To date, several experimental studies have been conducted within the framework of OECD/NEA programs at experimental facilities such as LSTF, PKL, or ATLAS (all related to PWR-type designs) where the issue of non-condensable gas intrusion has been studied, but always as a secondary objective of the analyzed sequences. In this work, three SBLOCA in the reactor pressure vessel of the LSTF facility are analyzed to determine the effect of nitrogen intrusion in the primary system. For calculations, the thermal-hydraulic code TRACE5 patch 5 is used. Results include the evolution of the main thermal-hydraulic parameters (pressures, mass flow rates and temperatures) and sensitivity cases for different scenarios of nitrogen intrusion. Based on the analysis of three experiments, it can be concluded that while nitrogen accumulation in the U-tubes is a common effect, the activation of safety systems such as LPIS depends on the location, size of the break and action management measures.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"189 ","pages":"Article 105954"},"PeriodicalIF":3.2000,"publicationDate":"2025-08-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Progress in Nuclear Energy","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S014919702500352X","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0

Abstract

After the injection of borated water during accidental sequences, the intrusion of nitrogen gas from the accumulators once emptied can degrade heat transfer mechanisms and thus hinder core cooling. The non-condensable gas that enters the cold legs transfers and accumulates in the U-tubes of the steam generators and their outlet plenums. This can cause flow stagnation and even prevent reflux cooling. Furthermore, a temporary and fluctuating increase in primary pressure may occur, disabling the low-pressure injection system pumps to restore the inventory. In this scenario, it is essential to confirm the effectiveness of the accident management measures under the influence of non-condensable gas. To date, several experimental studies have been conducted within the framework of OECD/NEA programs at experimental facilities such as LSTF, PKL, or ATLAS (all related to PWR-type designs) where the issue of non-condensable gas intrusion has been studied, but always as a secondary objective of the analyzed sequences. In this work, three SBLOCA in the reactor pressure vessel of the LSTF facility are analyzed to determine the effect of nitrogen intrusion in the primary system. For calculations, the thermal-hydraulic code TRACE5 patch 5 is used. Results include the evolution of the main thermal-hydraulic parameters (pressures, mass flow rates and temperatures) and sensitivity cases for different scenarios of nitrogen intrusion. Based on the analysis of three experiments, it can be concluded that while nitrogen accumulation in the U-tubes is a common effect, the activation of safety systems such as LPIS depends on the location, size of the break and action management measures.
LSTF试验装置SBLOCA工况下ECCS蓄能器氮侵入分析
在意外序列中注入硼酸水后,一旦排空,来自蓄能器的氮气侵入会降低传热机制,从而阻碍堆芯冷却。进入冷腿的不凝气体在蒸汽发生器的u型管及其出口全气室中转移和积聚。这可能导致流动停滞,甚至阻止回流冷却。此外,可能会出现一次压力的暂时波动增加,导致低压注入系统泵无法恢复库存。在这种情况下,确认不凝性气体影响下事故管理措施的有效性至关重要。迄今为止,在OECD/NEA计划的框架内,在LSTF、PKL或ATLAS等实验设施(都与pwr型设计有关)进行了几项实验研究,其中研究了不凝性气体侵入的问题,但始终作为分析序列的次要目标。本文对LSTF设施反应堆压力容器中的三个SBLOCA进行了分析,以确定氮侵入对主系统的影响。计算时使用热工代码TRACE5 patch 5。结果包括主要热工参数(压力、质量流量和温度)的演变以及不同氮气入侵情景下的敏感性案例。通过对三个实验的分析,可以得出结论,虽然u型管中的氮积累是一种常见的效应,但LPIS等安全系统的激活取决于断裂的位置、大小和行动管理措施。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
求助全文
约1分钟内获得全文 求助全文
来源期刊
Progress in Nuclear Energy
Progress in Nuclear Energy 工程技术-核科学技术
CiteScore
5.30
自引率
14.80%
发文量
331
审稿时长
3.5 months
期刊介绍: Progress in Nuclear Energy is an international review journal covering all aspects of nuclear science and engineering. In keeping with the maturity of nuclear power, articles on safety, siting and environmental problems are encouraged, as are those associated with economics and fuel management. However, basic physics and engineering will remain an important aspect of the editorial policy. Articles published are either of a review nature or present new material in more depth. They are aimed at researchers and technically-oriented managers working in the nuclear energy field. Please note the following: 1) PNE seeks high quality research papers which are medium to long in length. Short research papers should be submitted to the journal Annals in Nuclear Energy. 2) PNE reserves the right to reject papers which are based solely on routine application of computer codes used to produce reactor designs or explain existing reactor phenomena. Such papers, although worthy, are best left as laboratory reports whereas Progress in Nuclear Energy seeks papers of originality, which are archival in nature, in the fields of mathematical and experimental nuclear technology, including fission, fusion (blanket physics, radiation damage), safety, materials aspects, economics, etc. 3) Review papers, which may occasionally be invited, are particularly sought by the journal in these fields.
×
引用
GB/T 7714-2015
复制
MLA
复制
APA
复制
导出至
BibTeX EndNote RefMan NoteFirst NoteExpress
×
提示
您的信息不完整,为了账户安全,请先补充。
现在去补充
×
提示
您因"违规操作"
具体请查看互助需知
我知道了
×
提示
确定
请完成安全验证×
copy
已复制链接
快去分享给好友吧!
我知道了
右上角分享
点击右上角分享
0
联系我们:info@booksci.cn Book学术提供免费学术资源搜索服务,方便国内外学者检索中英文文献。致力于提供最便捷和优质的服务体验。 Copyright © 2023 布克学术 All rights reserved.
京ICP备2023020795号-1
ghs 京公网安备 11010802042870号
Book学术文献互助
Book学术文献互助群
群 号:604180095
Book学术官方微信