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Lee, Deokjung
Computational Reactor physics & Experiment Lab.
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dc.citation.endPage 2173 -
dc.citation.number 6 -
dc.citation.startPage 2163 -
dc.citation.title NUCLEAR ENGINEERING AND TECHNOLOGY -
dc.citation.volume 56 -
dc.contributor.author Jang, Jaerim -
dc.contributor.author Lee, Deokjung -
dc.date.accessioned 2024-07-15T11:35:13Z -
dc.date.available 2024-07-15T11:35:13Z -
dc.date.created 2024-07-08 -
dc.date.issued 2024-06 -
dc.description.abstract This study introduces a transient analysis module developed for RAST-V and validates it using the Kalinin-3 benchmark problem. For the benchmark analysis, RAST-V standalone and STREAM/RAST-V calculations were performed. STREAM supplies the few-group constants and RAST-V conducts a 3D core simulation utilizing fewgroup cross-sectional data. To improve accuracy, the main solver was developed based on the advanced semianalytic nodal method. To evaluate the computational capability of the transient analysis module in RAST-V, Kalinin-3 benchmark is employed. Kalinin-3 represents a coolant transient benchmark that offers experimental data during the deactivation of the Main Circulation Pumps. Consequently, the transient calculations reflected the changes in the reactor flow rate. Benchmark comprising steady-state and transient calculations. During the steady state, the STREAM/RAST-V combination demonstrated a 30 ppm root mean square difference from 0 to 128.50 EFPD. For the transient calculations, STREAM/RAST-V showed power differences within +/- 7 % over a range of 0-300 s. Axial offset differences were within +/- 3 %, and the RMS difference in radial power ranged within 2.596 % at both 0 and 300 s. Overall, this study effectively demonstrated the newly developed transient solver in RAST-V and validated it using the Kalinin-3 benchmark problem. -
dc.identifier.bibliographicCitation NUCLEAR ENGINEERING AND TECHNOLOGY, v.56, no.6, pp.2163 - 2173 -
dc.identifier.doi 10.1016/j.net.2024.01.024 -
dc.identifier.issn 1738-5733 -
dc.identifier.scopusid 2-s2.0-85184224803 -
dc.identifier.uri https://scholarworks.unist.ac.kr/handle/201301/83148 -
dc.identifier.wosid 001248350500006 -
dc.language 영어 -
dc.publisher KOREAN NUCLEAR SOC -
dc.title Development and validation of transient analysis module in nodal diffusion code RAST-V with Kalinin-3 coolant transient benchmark -
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 Kalinin-3 -
dc.subject.keywordAuthor Transient -
dc.subject.keywordAuthor Two-step method -
dc.subject.keywordAuthor PWR -
dc.subject.keywordAuthor VVER -

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