Zinan Huang , Yuxing Liu , Song Li , You-Peng Zhang , Lu Meng , Yunxiang Li , Wenjun Hu , Yang Yu , Xing-Kang Su , Lu Zhang
{"title":"Transients analysis of the offshore fixed multi-purpose integrated all-natural-cycle small lead-cooled reactor with the FRTAC code","authors":"Zinan Huang , Yuxing Liu , Song Li , You-Peng Zhang , Lu Meng , Yunxiang Li , Wenjun Hu , Yang Yu , Xing-Kang Su , Lu Zhang","doi":"10.1016/j.anucene.2025.111331","DOIUrl":null,"url":null,"abstract":"<div><div>The offshore fixed multi-purpose integrated all-natural circulation small lead-cooled reactor is one of the safest and most economical offshore nuclear power plant solution. In order to verify the safety and rationality of the reactor design, this study used the lead-cooled reactor safety analysis code FRTAC to complete the construction of the offshore reactor loop model and simulated unprotected transient overpower accidents (UTOP) and unprotected Loss of Heat Sink accidents (ULOHS). The reactor physics parameters of the offshore reactor and the fission gas yield were calculated by the neutron transport calculation code Serpent. Based on the transient accident calculation results, we can preliminarily confirm that the offshore reactor can withstand the introduction of reactivity of up to 0.42$ under UTOP scenario; and under different degrees of ULOHS scenario, the maximum operating temperature of the offshore reactor core will not exceeds its failure limits.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"217 ","pages":"Article 111331"},"PeriodicalIF":1.9000,"publicationDate":"2025-03-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Annals of Nuclear Energy","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0306454925001483","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
The offshore fixed multi-purpose integrated all-natural circulation small lead-cooled reactor is one of the safest and most economical offshore nuclear power plant solution. In order to verify the safety and rationality of the reactor design, this study used the lead-cooled reactor safety analysis code FRTAC to complete the construction of the offshore reactor loop model and simulated unprotected transient overpower accidents (UTOP) and unprotected Loss of Heat Sink accidents (ULOHS). The reactor physics parameters of the offshore reactor and the fission gas yield were calculated by the neutron transport calculation code Serpent. Based on the transient accident calculation results, we can preliminarily confirm that the offshore reactor can withstand the introduction of reactivity of up to 0.42$ under UTOP scenario; and under different degrees of ULOHS scenario, the maximum operating temperature of the offshore reactor core will not exceeds its failure limits.
期刊介绍:
Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.