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Application of Monte Carlo Neutronics and Fuel Performance Coupled Codes to Whole-core Depletion of OPR-1000

Tran, Tuan Quoc , Lee, Hyunsuk , Choe, Jiwon , Cherezov, Alexey , Yu, Jiankai , Shin, Ho Cheol , Lee, Deokjung

Conference Paper Issue Date2019-05-13 View6

CEFR Control Rod Drop Simulation using RAST-F Nodal Diffusion Code System

Tran, Tuan Quoc , Huo, Xingkai , Lee, Deokjung

Conference Paper Issue Date2023-08-15 View5

Coupled Fuel Depletion/Thermal Hydraulic Analysis of a Liquid Metal Fast Reactor ANST100e

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

Conference Paper Issue Date2023-10-25 View8

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 View27

Development of a Nodal Diffusion Code for Fast Reactor Analysis and Design File

Tran, Tuan Quoc

Thesis Issue Date2023-08 View12

Development of Hexagonal-Z Geometry Capability in RAST-K for Fast Reactor Analysis

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

Conference Paper Issue Date2019-10-07 View6

Development Status of MCS as Cross-section Generation Tool for Fast Reactor Analysis

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

Conference Paper Issue Date2023-05-18 View6

Group Constants Generation using MCS Monte Carlo Code for Fast Reactor Analysis

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

Conference Paper Issue Date2020-12-16 View6

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 View6

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

MOX-1000MWth NEA-SFR Benchmark Simulation by MCS at EOC

Mohanty, Saisundar , Tran, Tuan Quoc , Lee, Deokjung

Conference Paper Issue Date2023-10-25 View8

Neutronic simulation of China Experimental Fast Reactor start-up tests. Part I: SARAX code deterministic calculation File

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

Article Issue Date2020-02 View8

Neutronic simulation of the CEFR experiments with the nodal diffusion code system RAST-F File File

Tran, Tuan Quoc , Lee, Deokjung

Article Issue Date2022-07 View9

On the GPU Acceleration of a 3D MOC Code STREAM Using OpenACC

Dzianisau, Siarhei , Khandaq, Muhammad Farid , Tran, Tuan Quoc , Lee, Deokjung

Conference Paper Issue Date2023-08-15 View8

Preliminary CEFR analysis by Monte Carlo codes

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

Conference Paper Issue Date2019-08-26 View4

Recent Progress on Fast Reactor Analysis in UNIST CORE Laboratory

Du, Xianan , Choe, Jiwon , Choi, Sooyoung , Cherezov, Alexey , Lee, Woonghee , Tran, Tuan Quoc , Park, Jinsu , Lee, Deokjung

Conference Paper Issue Date2019-05-24 View4

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 View6

Validation of Transient Module in RAST-F Code for Fast Reactor Analysis

Tran, Tuan Quoc , Lee, Deokjung

Conference Paper Issue Date2023-05-18 View7

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 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 View11

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