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Showing results 1 to 6 of 6

Assessment of the dose rate from neutrons and gamma for spent fuel storage pool loaded with ATF spent nuclear fuelsGo to Link

Zafar, Zafar Iqbal; Ta, Duy Long; Jin Ho Jeong; Hong, Ser Gi

ArticleIssue Date2022Citation대한방사선방어학회 추계학술대회 논문집, pp.85 - 86Publisher대한방사선방어학회
OTHER
Effectiveness of the Modified Predictor-Corrector Scheme in the point depletion code BESNAGo to Link

Ta, Duy Long; Hong, Ser Gi; Yook, Dae Sik

ArticleIssue Date2022CitationTRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, v.127, no.1, pp.1016 - 1019PublisherAmerican Nuclear Society
SCIESCOPUSKCI
Evaluation of source terms using the BESNA code for reference spent fuels for future underground disposal system of South KoreaGo to Linkopen access

Choi, Kyu Jung; Ta, Duy Long; Oh, Shin Sung; Hong, Ser Gi

ArticleIssue Date2024CitationNuclear Engineering and Technology, v.56, no.11, pp 4804 - 4812Publisher한국원자력학회
OTHER
Validation of Decay Heat Estimation Capability of BESNAGo to Link

Ta, Duy Long; Hong, Ser Gi; Yook, Dae Sik; Seo, Bo Kyun

ArticleIssue Date2022CitationTransactions of the Korean Nuclear Society Spring Meeting, pp.1 - 4Publisher한국원자력학회
SCIESCOPUSKCI
Validation of UNIST Monte Carlo code MCS for criticality safety calculations with burnup credit through MOX criticality benchmark problemsGo to Linkopen access

Ta, Duy Long; Hong, Ser Gi; Lee, Deokjung

ArticleIssue Date2021CitationNUCLEAR ENGINEERING AND TECHNOLOGY, v.53, no.1, pp.19 - 29PublisherKOREAN NUCLEAR SOC
OTHER
Verification of the radiation source terms generated by BESNA through shielding calculation problemGo to Link

Ta, Duy Long; Hong, Ser Gi; Yook, Dae Sik; Seo, Bo Gyun

ArticleIssue Date2022CitationTransactions of the Korean Nuclear Society Autumn Meeting , pp.1 - 4PublisherKorean Nuclear Society
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