Full metadata record
DC Field | Value | Language |
---|---|---|
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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