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dc.citation.endPage 769 -
dc.citation.number 2 -
dc.citation.startPage 764 -
dc.citation.title NUCLEAR ENGINEERING AND TECHNOLOGY -
dc.citation.volume 54 -
dc.contributor.author Alnaqbi, Jwaher -
dc.contributor.author Hartanto, Donny -
dc.contributor.author Alnuaimi, Reem -
dc.contributor.author Imron, Muhammad -
dc.contributor.author Gillette, Victor -
dc.date.accessioned 2023-12-21T14:38:32Z -
dc.date.available 2023-12-21T14:38:32Z -
dc.date.created 2022-02-24 -
dc.date.issued 2022-02 -
dc.description.abstract The United Arab Emirates is currently building and operating four units of the APR-140 0 developed by a South Korean vendor, Korea Electric Power Corporation (KEPCO). This paper attempts to perform APR 140 0 reactor core analysis by using the well-known two-step method. The two-step method was applied to the APR-140 0 first cycle using the open-source nodal diffusion code, KOMODO. In this study, the group constants were generated using CASMO-4 fuel transport lattice code. The simulation was performed in Hot Zero Power (HZP) at steady-state and transient conditions. Some typical parameters necessary for the Nuclear Design Report (NDR) were evaluated in this paper, such as effective neutron multiplication factor, control rod worth, and critical boron concentration for steady-state analysis. Other parameters such as reactivity insertion, power, and fuel temperature changes during the Reactivity Insertion Accident (RIA) simulation were evaluated as well. The results from KOMODO were verified using PARCS and SIMULATE-3 nodal core simulators. It was found that KOMODO gives an excellent agreement. -
dc.identifier.bibliographicCitation NUCLEAR ENGINEERING AND TECHNOLOGY, v.54, no.2, pp.764 - 769 -
dc.identifier.doi 10.1016/j.net.2021.08.012 -
dc.identifier.issn 1738-5733 -
dc.identifier.scopusid 2-s2.0-85112528741 -
dc.identifier.uri https://scholarworks.unist.ac.kr/handle/201301/62058 -
dc.identifier.url https://www.sciencedirect.com/science/article/pii/S1738573321005003?via%3Dihub -
dc.identifier.wosid 000752500200017 -
dc.language 영어 -
dc.publisher KOREAN NUCLEAR SOC -
dc.title Static and transient analyses of Advanced Power Reactor 1400 (APR1400) initial core using open-source nodal core simulator KOMODO -
dc.type Article -
dc.description.isOpenAccess TRUE -
dc.relation.journalWebOfScienceCategory Nuclear Science & Technology -
dc.relation.journalResearchArea Nuclear Science & Technology -
dc.type.docType Article -
dc.description.journalRegisteredClass scie -
dc.description.journalRegisteredClass scopus -
dc.description.journalRegisteredClass kci -
dc.subject.keywordAuthor CASMO-4 -
dc.subject.keywordAuthor KOMODO -
dc.subject.keywordAuthor Open-source nodal code -
dc.subject.keywordAuthor Steady-state calculation -
dc.subject.keywordAuthor Transient simulation -
dc.subject.keywordAuthor APR-140 0 -

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