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Analysis of VVER-1000 mock-up criticality experiments with nuclear data library ENDF/B-VIII.0 and Monte Carlo code MCS File File

Setiawan, Fathurrahman , Lemaire, Matthieu , Lee, Deokjung

Article Issue Date2021-01 View3

Coupled neutronics/thermal-hydraulic analysis of ANTS-100e using MCS/RAST-F two-step code system File

Nguyen, Tung Dong Cao , Tran, Tuan Quoc , Lee, Deokjung

Article Issue Date2023-11 View23

Coupling of FRAPCON for fuel performance analysis in the Monte Carlo code MCS File

Yu, Jiankai , Lee, Hyunsuk , Kim, Hanjoo , Zhang, Peng , Lee, Deokjung

Article Issue Date2020-06 View4

Criticality benchmark of Monte Carlo code MCS for light water reactor fuel in transportation and storage packages File

Lee, Hochul , Jang, Jaerim , Jang, Junkyung , Kang, Hyunwook , Kim, Wonkyeong , Lee, Deokjung , Lee, Hyun Chul

Article Issue Date2021-02 View7

Determination of the activity inventory and associated uncertainty quantification for the CROCUS zero power research reactor File

Kim, Wonkyeong , Hursin, Mathieu , Pautz, Andreas , Vincent, Lamirand , Pavel, Frajtag , Lee, Deokjung

Article Issue Date2020-02 View3

MCS based neutronics/thermal-hydraulics/fuel-performance coupling with CTF and FRAPCON File

Yu, Jiankai , Lee, Hyunsuk , Lemaire, Matthieu , Kim, Hanjoo , Zhang, Peng , Lee, Deokjung

Article Issue Date2019-05 View3

Neutronic simulation of China experimental fast reactor start-up tests- part II: MCS code Monte Carlo calculation File

Tuan Quoc Tran , Choe, Jiwon , Du, Xianan , Lee, Hyunsuk , Lee, Deokjung

Article Issue Date2020-12 View5

Performance evaluation of CMFD on inter-cycle correlation reduction of Monte Carlo simulation File

Park, Jinsu , Zhang, Peng , Lee, Hyunsuk , Choi, Sooyoung , Yu, Jiankai , Lee, Deokjung

Article Issue Date2019-02 View4

Preliminary coupling of the Thermal/Hydraulic solvers in the Monte Carlo code MCS for practical LWR analysis File

Yu, Jiankai , Lee, Hyunsuk , Kim, Hanjoo , Zhang, Peng , Lee, Deokjung

Article Issue Date2018-08 View3

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 View4

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 View4

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 View8

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 View4

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