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LPPT Analysis of APR1400 Reactor Core by UNIST Monte Carlo Code MCS

Nguyen, Tung Dong Cao , Lee, Hyunsuk , Choe, Jiwon , Shin, Ho Cheol , Lee, Hwan Soo , Lee, Deokjung

Conference Paper Issue Date2017-08-24 View3
Macroscopic Cross Sections Generation by Monte Carlo Code MCS for Fast Reactor Analysis File

Nguyen, Tung Dong Cao , Lee, Hyunsuk , Du, Xianan , Dos, Vutheam , Tran, Tuan Quoc , Lee, Deokjung

Conference Paper Issue Date2020-03-29 View3
MCS Multi-group Cross Sections Generation for Fast Reactor Analysis

Nguyen, Tung Dong Cao , Lee, Hyunsuk , Du, Xianan , Dos, Vutheam , Tran, Tuan Quoc , Lee, Deokjung

Conference Paper Issue Date2019-12-03 View4
MicroURANUS: Core design for long-cycle lead-bismuth-cooled fast reactor for marine applications File

Nguyen, Tung Dong Cao , Khandaq, Muhammad Farid , Jung, Eun , Choe, Jiwon , Lee, Deokjung , Fynan, Douglas A.

Article Issue Date2021-06 View12
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 View10
Use of the Super Homogenization Method for Fast Reactor Analysis

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

Conference Paper Issue Date2020-05-12 View3
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 View3
Verification of a depletion solver in RAST-K for Fast Reactor Analysis

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

Conference Paper Issue Date2020-12-16 View4
Verification of Two-Step Code MCS/RAST-F for ANTS-100e

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

Conference Paper Issue Date2023-08-15 View4
Whole-core Neutronic Analysis of MOX-1000 MW th in NEA-SFR Benchmark Using MCS Code

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

Conference Paper Issue Date2023-05-18 View4
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