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Showing results 10 to 16 of 16

Use of Monte Carlo code MCS for multigroup cross section generation for fast reactor analysis File File

Nguyen, Tung Dong Cao , Lee, Hyunsuk , Lee, Deokjung

Article Issue Date2021-09 View11
Validation of nuclide depletion capabilities in Monte Carlo code MCS File File

Ebiwonjumi, Bamidele , Lee, Hyunsuk , Kim, Wonkyeong , Lee, Deokjung

Article Issue Date2020-09 View5
Validation of UNIST Monte Carlo code MCS for criticality safety analysis of PWR spent fuel pool and storage cask File

Jang. Jaerim , Kim, Wonkyeong , Jeong, Sanggeol , Jeong, Eun , Park, Jinsu , Lemaire, Matthieu , Lee, Hyunsuk , Jo, Yongmin , Zhang, Peng , Lee, Deokjung

Article Issue Date2018-04 View5
Validation of UNIST Monte Carlo code MCS for criticality safety calculations with burnup credit through MOX criticality benchmark problems File File

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

Article Issue Date2021-01 View5
Validation of UNIST Monte Carlo Code MCS using VERA Progression Problems File File

Nguyen, Tung Dong Cao , Lee, Hyunsuk , Choi, Sooyoung , Lee, Deokjung

Article Issue Date2020-05 View4
Verification of a two-step code system MCS/RAST-F to fast reactor core analysis File File

Tran, Tuan Quoc , Cherezov, Alexey , Du, Xianan , Lee, Deokjung

Article Issue Date2022-05 View9
Verification of Graphite Isotope Ratio Method Combined With Polynomial Regression for the Estimation of Cumulative Plutonium Production in a Graphite-Moderated Reactor File

Kim, Kyeongwon , Han, Jinseok , Lee, Hyun Chul , Jang, Junkyung , Lee, Deokjung

Article Issue Date2021-12 View5
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