{"title":"Analysis of nitrogen intrusion from ECCS accumulators in SBLOCA scenarios at LSTF test facility","authors":"Tomás Ten-Gallardo , Sergio Gallardo , María Lorduy-Alós , 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.
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.