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Analysis of several VERA benchmark problems with the photon transport capability of STREAM File File

Mai, Nhan Nguyen Trong , Kim, Kyeongwon , Lemaire, Matthieu , Nguyen, Tung Dong Cao , Lee, Woonghee , Lee, Deokjung

Article Issue Date2022-07 View6

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

Application of UNIST Monte Carlo Code MCS for Nuclear Fuel Transport Cask Analysis

Nguyen, Trong Mai Nhan , Kong, Chidong , Lemaire, Matthieu , Zhang, Peng , Shin, Ho Cheol , Lee, Deokjung

Conference Paper Issue Date2018-09-30 View3

APR-1400 WHOLE-CORE DEPLETION ANALYSIS WITH MCS

Nguyen, Tung Dong Cao , Lee, Hyunsuk , Choe, Jiwon , Lemaire, Matthieu , Lee, Deokjung

Conference Paper Issue Date2019-08-26 View5

Assessment on PWR Fuel Depletion and Neutron Multiplication Factors for High Density Spent Fuel Pool

Jeong, Sanggeol , Kim, Wonkyeong , Lemaire, Matthieu , Lee, Deokjung

Conference Paper Issue Date2018-10-25 View4

Comment on "Vanadium, rhodium, silver and cobalt self-powered neutron detector calculations by RAST-K v2.0" Reply File

Khoshahval, Farrokh , Zhang, Peng , Lemaire, Matthieu , Lee, Deokjung

Article Issue Date2018-05 View5

Conceptual Core Design of a Small Modular Fast Reactor Cooled by Lead-Bismuth Eutectic

Nguyen, Dong Cao Tung , Choe, Jiwon , Ebiwonjumi, Bamidele , Lemaire, Matthieu , Lee, Deokjung

Conference Paper Issue Date2018-04-22 View3

Conceptual design of long-cycle boron-free small modular pressurized water reactor with control rod operation File

Jang, Jaerim , Choe, Jiwon , Choi, Sooyoung , Lemaire, Matthieu , Lee, Deokjung , Shin, Ho Cheol

Article Issue Date2020-06 View3

Core design of long-cycle small modular lead-cooled fast reactor File

Tung Dong Cao Nguyen , Choe, Jiwon , Ebiwonjumi, Bamidele , Lemaire, Matthieu , Lee, Deokjung

Article Issue Date2019-01 View4

Criticality Analysis of VVER-1000 Mock-up with the Monte Carlo code MCS

Setiawan, Fathurrahman , Lemaire, Matthieu , Lee, Hyunsuk , Lee, Deokjung

Conference Paper Issue Date2019-10-25 View3

Depletion chain optimization of lattice code STREAM for LWR fuel assembly burnup analysis File

Khang Hoang Nhat Nguyen , Choi, Sooyoung , Lemaire, Matthieu , Lee, Deokjung

Article Issue Date2019-01 View4

DEVELOPMENT AT UNIST OF MONTE CARLO MULTI-PHYSICS CODE MCS FOR POWER REACTOR ANALYSIS

Lee, Hyunsuk , Lee, Woonghee , Zhang, Peng , Lemaire, Matthieu , Khassenov, Azamat , Jo, Yunki , Park, Jinsu , Yu, Jiankai , Lee, Deokjung

Conference Paper Issue Date2019-08-26 View5

DEVELOPMENT OF A NEW WEIGHT WINDOW GENERATOR BASED ON MARKOV DECISION PROCESS

Zhang, Peng , Lee, Hyunsuk , Mai, Nhan Nguyen Trong , Lemaire, Matthieu , Lee, Deokjung

Conference Paper Issue Date2019-08-26 View4

Development of a Variance Reduction Scheme in the MCS Monte Carlo Code

Zhang, Peng , Lemaire, Matthieu , Lee, Hyunsuk , Nguyen, Trong Mai Nhan , Lee, Deokjung

Conference Paper Issue Date2018-10-25 View4

Development of AutoCASK Code System for PWR Spent Nuclear Fuel Cask Analysis at UNIST

Kim, Wonkyeong , Jang, Jaerim , Ebiwonjumi, Bamidele , Lee, Hyunsuk , Lemaire, Matthieu , Zhang, Peng , Kang, Seung-gu , Lee, Deokjung

Conference Paper Issue Date2019-10-24 View4

Development of integral type spent fuel pool storage rack with gadolinium and europium-containing structure materials File

Kim, Mi Jin , Kim, Wonkyeong , Lee, Deokjung , Lemaire, Matthieu , Lee, Hee-Jae , Sohn, Dong-Seong , Kwon, Hyukjoo

Article Issue Date2019-08 View4

Development of Photon-Transport Capability in UNIST Monte Carlo Code MCS

Lemaire, Matthieu , Lee, Hyunsuk , Ebiwonjumi, Bamidele , Kong, Chidong , Kim, Wonkyeong , Jo, Yunki , Park, Jinsu , Lee, Deokjung

Conference Paper Issue Date2018-04-22 View3

ENDF/B-VII Depletion Library Compression to Optimize the Computational Efficiency in STREAM Code

Nguyen, Hoang Nhat Khang , Choi, Sooyoung , Lemaire, Matthieu , Lee, Deokjung

Conference Paper Issue Date2018-04-22 View0

Experimental Validation of STREAM for Spent Nuclear Fuel Applications

Ebiwonjumi, Bamidele , Choi, Sooyoung , Lemaire, Matthieu , Lee, Deokjung , Shin, Ho Cheol

Conference Paper Issue Date2017-08-24 View4

Extension of Monte Carlo code MCS to spent fuel cask shielding analysis File

Mai, Nhan Nguyen Trong , Zhang, Peng , Lemaire, Matthieu , Ebiwonjumi, Bamidele , Kim, Wonkyeong , Lee, Hyunsuk , Lee, Deokjung

Article Issue Date2020-08 View4

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