利用TRACE软件建立了宽盛核电站退役过渡阶段的分析模型

IF 0.4 4区工程技术 Q4 NUCLEAR SCIENCE & TECHNOLOGY

Kerntechnik Pub Date : 2023-03-15 DOI:10.1515/kern-2022-0103

W. Hsu, Jung-Hua Yang, Hsuan-Che Chen, Shao-Wen Chen, Jong-Rong Wang

{"title":"利用TRACE软件建立了宽盛核电站退役过渡阶段的分析模型","authors":"W. Hsu, Jung-Hua Yang, Hsuan-Che Chen, Shao-Wen Chen, Jong-Rong Wang","doi":"10.1515/kern-2022-0103","DOIUrl":null,"url":null,"abstract":"Abstract The Unit 1 of Kuosheng nuclear power plant is in the decommissioning transition phase and still has spent fuel in the core of reactor now. The time to reach the TAF (top of active fuel) for water level and reach 600/800 °C for cladding temperature are the key parameters in the safety analysis, these affect that the plant has how much time to handle transients. Therefore, to study the water level and cladding temperature for station blackout (SBO) and loss of coolant accident (LOCA) transients in the decommissioning transition phase, the analysis model of Kuosheng nuclear power plant was established by using TRACE code. To evaluate the effect of the decay heat of spent fuel on the water level and cladding temperature, the sensitivity analysis of decay heat was also performed in this study.","PeriodicalId":17787,"journal":{"name":"Kerntechnik","volume":"28 1","pages":"213 - 220"},"PeriodicalIF":0.4000,"publicationDate":"2023-03-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Using TRACE to establish the analysis model of Kuosheng nuclear power plant for decommissioning transition phase\",\"authors\":\"W. Hsu, Jung-Hua Yang, Hsuan-Che Chen, Shao-Wen Chen, Jong-Rong Wang\",\"doi\":\"10.1515/kern-2022-0103\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"Abstract The Unit 1 of Kuosheng nuclear power plant is in the decommissioning transition phase and still has spent fuel in the core of reactor now. The time to reach the TAF (top of active fuel) for water level and reach 600/800 °C for cladding temperature are the key parameters in the safety analysis, these affect that the plant has how much time to handle transients. Therefore, to study the water level and cladding temperature for station blackout (SBO) and loss of coolant accident (LOCA) transients in the decommissioning transition phase, the analysis model of Kuosheng nuclear power plant was established by using TRACE code. To evaluate the effect of the decay heat of spent fuel on the water level and cladding temperature, the sensitivity analysis of decay heat was also performed in this study.\",\"PeriodicalId\":17787,\"journal\":{\"name\":\"Kerntechnik\",\"volume\":\"28 1\",\"pages\":\"213 - 220\"},\"PeriodicalIF\":0.4000,\"publicationDate\":\"2023-03-15\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Kerntechnik\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://doi.org/10.1515/kern-2022-0103\",\"RegionNum\":4,\"RegionCategory\":\"工程技术\",\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"Q4\",\"JCRName\":\"NUCLEAR SCIENCE & TECHNOLOGY\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Kerntechnik","FirstCategoryId":"5","ListUrlMain":"https://doi.org/10.1515/kern-2022-0103","RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q4","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}

引用次数: 0

摘要

国胜核电站1号机组目前处于退役过渡阶段，堆芯内仍有乏燃料残留。达到TAF(活性燃料顶部)水位的时间和达到600/800°C包层温度的时间是安全性分析中的关键参数，这些参数影响电站有多少时间来处理瞬态。为此，为了研究停运过渡阶段电站停电(SBO)和失冷剂事故(LOCA)瞬态的水位和包层温度，利用TRACE程序建立了国胜核电站的分析模型。为了评价乏燃料衰变热对水位和包层温度的影响，本研究还进行了衰变热的敏感性分析。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

查看原文本刊更多论文

Using TRACE to establish the analysis model of Kuosheng nuclear power plant for decommissioning transition phase

Abstract The Unit 1 of Kuosheng nuclear power plant is in the decommissioning transition phase and still has spent fuel in the core of reactor now. The time to reach the TAF (top of active fuel) for water level and reach 600/800 °C for cladding temperature are the key parameters in the safety analysis, these affect that the plant has how much time to handle transients. Therefore, to study the water level and cladding temperature for station blackout (SBO) and loss of coolant accident (LOCA) transients in the decommissioning transition phase, the analysis model of Kuosheng nuclear power plant was established by using TRACE code. To evaluate the effect of the decay heat of spent fuel on the water level and cladding temperature, the sensitivity analysis of decay heat was also performed in this study.

求助全文

通过发布文献求助，成功后即可免费获取论文全文。去求助

来源期刊

Kerntechnik 工程技术-核科学技术

CiteScore

0.90

自引率

20.00%

发文量

审稿时长

6-12 weeks

期刊介绍： Kerntechnik is an independent journal for nuclear engineering (including design, operation, safety and economics of nuclear power stations, research reactors and simulators), energy systems, radiation (ionizing radiation in industry, medicine and research) and radiological protection (biological effects of ionizing radiation, the system of protection for occupational, medical and public exposures, the assessment of doses, operational protection and safety programs, management of radioactive wastes, decommissioning and regulatory requirements).