{"title":"Research on the Short-Term Heat Release and Pressure Relief System of HPR1000-based suppressive containment system under typical accidents","authors":"Qiunan Sun , Rui Wang , Xiangjie Qi , Minxin Jiang , Jiejun Ouyang , Peihan Zhou , Baihui Duan , Zhaoming Meng","doi":"10.1016/j.pnucene.2025.105943","DOIUrl":null,"url":null,"abstract":"<div><div>To address the contradiction between safety and economy in double-layer concrete containment systems for nuclear power plants, this study focuses on China's third-generation nuclear technology. Based on the HPR1000 reactor design, a suppression containment system was previously proposed, and its response characteristics under typical accidents scenario were analyzed. However, parametric studies on factors influencing the heat removal capacity of the short-term heat release and pressure relief system (SHRPRS) were not conducted. Therefore, this paper investigates the effects of key parameters—including the gas space volume of the Multi-Functional Pool (MFP), cross-sectional area of the depressurization discharge pipes, and pipeline submersion depth—on the system's ability to suppress pressure and store non-condensable gases. Furthermore, configuration schemes for SHRPRS under different containment volumes to address Beyond-Design-Basis Accidents (BDBAs) are explored. Results indicate that for units without SHRPRS, containment volumes of 86,000 m<sup>3</sup> and 70,000 m<sup>3</sup> meet BDBA mitigation standards, while volumes of 60,000 m<sup>3</sup> and 49,000 m<sup>3</sup> fail to comply. For units equipped with SHRPRS, appropriate configurations of gas space volume and pipeline cross-sectional area enable all four containment volumes (86,000 m<sup>3</sup>, 70,000 m<sup>3</sup>, 60,000 m<sup>3</sup>, and 49,000 m<sup>3</sup>) to handle BDBA.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"189 ","pages":"Article 105943"},"PeriodicalIF":3.3000,"publicationDate":"2025-07-24","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/S0149197025003415","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
To address the contradiction between safety and economy in double-layer concrete containment systems for nuclear power plants, this study focuses on China's third-generation nuclear technology. Based on the HPR1000 reactor design, a suppression containment system was previously proposed, and its response characteristics under typical accidents scenario were analyzed. However, parametric studies on factors influencing the heat removal capacity of the short-term heat release and pressure relief system (SHRPRS) were not conducted. Therefore, this paper investigates the effects of key parameters—including the gas space volume of the Multi-Functional Pool (MFP), cross-sectional area of the depressurization discharge pipes, and pipeline submersion depth—on the system's ability to suppress pressure and store non-condensable gases. Furthermore, configuration schemes for SHRPRS under different containment volumes to address Beyond-Design-Basis Accidents (BDBAs) are explored. Results indicate that for units without SHRPRS, containment volumes of 86,000 m3 and 70,000 m3 meet BDBA mitigation standards, while volumes of 60,000 m3 and 49,000 m3 fail to comply. For units equipped with SHRPRS, appropriate configurations of gas space volume and pipeline cross-sectional area enable all four containment volumes (86,000 m3, 70,000 m3, 60,000 m3, and 49,000 m3) to handle BDBA.
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.