dc.citation.conferencePlace |
US |
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dc.citation.title |
M&C 2019 (The International Conference on Mathematics and Computational Methods applied to Nuclear Science and Engineering) |
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dc.contributor.author |
Choe, Jiwon |
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dc.contributor.author |
Choi, Sooyoung |
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dc.contributor.author |
Park, Jinsu |
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dc.contributor.author |
Lee, Hyunsuk |
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dc.contributor.author |
Lemaire, Matthieu |
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dc.contributor.author |
Shin, Ho Cheol |
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dc.contributor.author |
Lee, Hwan Soo |
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dc.contributor.author |
Lee, Deokjung |
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dc.date.accessioned |
2024-01-31T23:41:28Z |
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dc.date.available |
2024-01-31T23:41:28Z |
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dc.date.created |
2019-12-24 |
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dc.date.issued |
2019-08-26 |
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dc.description.abstract |
This paper presents the treatment of asymmetric fuel assemblies in the deterministic two-step STREAM/RAST-K 2.0 code system developed by the COmputational Reactor physics and Experimental group of Ulsan National Institute of Science and Technology. Few group constants are generated separately as 2×2 sub-assemblies through calculations of a single fuel assembly with full 2D geometry in the neutron-transport lattice code, STREAM. The nodal diffusion code, RAST-K 2.0, reads the generated FGC and perform the neutron-diffusion whole-core simulation. The in-house Monte Carlo code, MCS, makes a reference solution for verification. The paper presents two kinds of asymmetric fuel assembly treatment: one-node nodal simulation without sub-assemblies and four-node nodal simulation with four types of FGC generated by the newly implemented method described above. Verification results include the critical boron concentration and radial assembly power distributions for Cycle 1 of the Benchmark for Evaluation And Validation of Reactor Simulations (BEAVRS) core benchmark. |
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dc.identifier.bibliographicCitation |
M&C 2019 (The International Conference on Mathematics and Computational Methods applied to Nuclear Science and Engineering) |
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dc.identifier.scopusid |
2-s2.0-85075385786 |
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dc.identifier.uri |
https://scholarworks.unist.ac.kr/handle/201301/79346 |
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dc.publisher |
American Nuclear Society |
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dc.title |
VERIFICATION OF ASYMMETRIC FUEL ASSEMBLY TREATMENT IN STREAM/RAST-K 2.0 |
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dc.type |
Conference Paper |
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dc.date.conferenceDate |
2019-08-25 |
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