{"title":"蓄能器对PMK-2试验装置SB - LOCA瞬态的影响","authors":"S. Petelin, I. Parzer","doi":"10.1115/imece1998-1131","DOIUrl":null,"url":null,"abstract":"\n In 1993 the International Atomic Energy Agency Standard Problem Exercise no.4 (IAEA-SPE-4), a small break LOCA scenario simulation with no high pressure injection system available, was performed on the PMK-2 integral test facility in Budapest. Later, in 1994, another SB LOCA experiment was performed. The analyses of the PMK-2 facility response, a model of WER-440 nuclear power plant, have been performed using the MOD3.2.1.2 version of the RELAP5 thermal-hydraulic computer code.","PeriodicalId":49736,"journal":{"name":"Nuclear Engineering International","volume":null,"pages":null},"PeriodicalIF":0.6000,"publicationDate":"1998-11-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Hydroaccumulator Influence on SB LOCA Transients at PMK-2 Test Facility\",\"authors\":\"S. Petelin, I. Parzer\",\"doi\":\"10.1115/imece1998-1131\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"\\n In 1993 the International Atomic Energy Agency Standard Problem Exercise no.4 (IAEA-SPE-4), a small break LOCA scenario simulation with no high pressure injection system available, was performed on the PMK-2 integral test facility in Budapest. Later, in 1994, another SB LOCA experiment was performed. The analyses of the PMK-2 facility response, a model of WER-440 nuclear power plant, have been performed using the MOD3.2.1.2 version of the RELAP5 thermal-hydraulic computer code.\",\"PeriodicalId\":49736,\"journal\":{\"name\":\"Nuclear Engineering International\",\"volume\":null,\"pages\":null},\"PeriodicalIF\":0.6000,\"publicationDate\":\"1998-11-15\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Nuclear Engineering International\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://doi.org/10.1115/imece1998-1131\",\"RegionNum\":4,\"RegionCategory\":\"工程技术\",\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"Q4\",\"JCRName\":\"Engineering\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Engineering International","FirstCategoryId":"5","ListUrlMain":"https://doi.org/10.1115/imece1998-1131","RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q4","JCRName":"Engineering","Score":null,"Total":0}
Hydroaccumulator Influence on SB LOCA Transients at PMK-2 Test Facility
In 1993 the International Atomic Energy Agency Standard Problem Exercise no.4 (IAEA-SPE-4), a small break LOCA scenario simulation with no high pressure injection system available, was performed on the PMK-2 integral test facility in Budapest. Later, in 1994, another SB LOCA experiment was performed. The analyses of the PMK-2 facility response, a model of WER-440 nuclear power plant, have been performed using the MOD3.2.1.2 version of the RELAP5 thermal-hydraulic computer code.
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