DC Field | Value | Language |
---|---|---|
dc.contributor.author | Kim, Ho Sik | ko |
dc.contributor.author | No, Hee-Cheon | ko |
dc.contributor.author | Jo, Yugwon | ko |
dc.contributor.author | Wibisono, Andhika Feri | ko |
dc.contributor.author | Park, Byung Ha | ko |
dc.contributor.author | Choi, Jinyoung | ko |
dc.contributor.author | Lee, Jeong-Ik | ko |
dc.contributor.author | Jeong, Yong Hoon | ko |
dc.contributor.author | Cho, Nam-Zin | ko |
dc.date.accessioned | 2015-06-25T06:27:29Z | - |
dc.date.available | 2015-06-25T06:27:29Z | - |
dc.date.created | 2015-04-28 | - |
dc.date.created | 2015-04-28 | - |
dc.date.created | 2015-04-28 | - |
dc.date.issued | 2015-04 | - |
dc.identifier.citation | NUCLEAR ENGINEERING AND TECHNOLOGY, v.47, no.3, pp.293 - 305 | - |
dc.identifier.issn | 1738-5733 | - |
dc.identifier.uri | http://hdl.handle.net/10203/199067 | - |
dc.description.abstract | In this paper, we suggest the conceptual design of a water-cooled reactor system for a low-pressure inherent heat sink nuclear desalination plant (LIND) that applies the safety-related design concepts of high temperature gas-cooled reactors to a water-cooled reactor for inherent and passive safety features. Through a scoping analysis, we found that the current LIND design satisfied several essential thermal-hydraulic and neutronic design requirements. In a thermal-hydraulic analysis using an analytical method based on the Wooton-Epstein correlation, we checked the possibility of safely removing decay heat through the steel containment even if all the active safety systems failed. In a neutronic analysis using the Monte Carlo N-particle transport code, we estimated a cycle length of approximately 6 years under 200 MWth and 4.5% enrichment. The very long cycle length and simple safety features minimize the burdens from the operation, maintenance, and spent-fuel management, with a positive impact on the economic feasibility. Finally, because a nuclear reactor should not be directly coupled to a desalination system to prevent the leakage of radioactive material into the desalinated water, three types of intermediate systems were studied: a steam producing system, a hot water system, and an organic Rankine cycle system. Copyright (C) 2015, Published by Elsevier Korea LLC on behalf of Korean Nuclear Society. | - |
dc.language | English | - |
dc.publisher | KOREAN NUCLEAR SOC | - |
dc.subject | UAE | - |
dc.title | FEASIBILITY STUDY OF A DEDICATED NUCLEAR DESALINATION SYSTEM: LOW-PRESSURE INHERENT HEAT SINK NUCLEAR DESALINATION PLANT (LIND) | - |
dc.type | Article | - |
dc.identifier.wosid | 000354911500007 | - |
dc.identifier.scopusid | 2-s2.0-84928627555 | - |
dc.type.rims | ART | - |
dc.citation.volume | 47 | - |
dc.citation.issue | 3 | - |
dc.citation.beginningpage | 293 | - |
dc.citation.endingpage | 305 | - |
dc.citation.publicationname | NUCLEAR ENGINEERING AND TECHNOLOGY | - |
dc.identifier.doi | 10.1016/j.net.2014.12.013 | - |
dc.contributor.localauthor | No, Hee-Cheon | - |
dc.contributor.localauthor | Lee, Jeong-Ik | - |
dc.contributor.localauthor | Jeong, Yong Hoon | - |
dc.contributor.localauthor | Cho, Nam-Zin | - |
dc.contributor.nonIdAuthor | Wibisono, Andhika Feri | - |
dc.type.journalArticle | Article | - |
dc.subject.keywordAuthor | Dedicated nuclear desalination system | - |
dc.subject.keywordAuthor | High temperature gas-cooled reactor | - |
dc.subject.keywordAuthor | Inherent safety feature | - |
dc.subject.keywordAuthor | Intermediate heat transport system | - |
dc.subject.keywordAuthor | Water-cooled reactor | - |
dc.subject.keywordAuthor | Dedicated nuclear desalination system | - |
dc.subject.keywordAuthor | High temperature gas-cooled reactor | - |
dc.subject.keywordAuthor | Inherent safety feature | - |
dc.subject.keywordAuthor | Intermediate heat transport system | - |
dc.subject.keywordAuthor | Water-cooled reactor | - |
dc.subject.keywordPlus | UAE | - |
dc.subject.keywordPlus | UAE | - |
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