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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

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

Development of a Spent Nuclear Fuel Radiation Source Term Framework File

Ebiwonjumi, Bamidele

Thesis Issue Date2022-02 View1

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 high-fidelity neutron transport code STREAM? File

Choi, Sooyoung , Kim, Wonkyeong , Choe, Jiwon , Lee, Woonghee , Kim, Hanjoo , Ebiwonjumi, Bamidele , Jeong, Eun , Kim, Kyeongwon , Yun, Dongmin , Lee, Hyunsuk , et al

Article Issue Date2021-07 View11

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

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

Functional Expansion Tallies in Monte Carlo High Fidelity LWR Analysis

Ebiwonjumi, Bamidele , Lee, Hyunsuk , Zhang, Peng , Lee, Deokjung

Conference Paper Issue Date2019-12-03 View4

Implementation of On-The-Fly Energy Release per Fission Model in STREAM

Lee, Woonghee , Choi, Sooyoung , Ebiwonjumi, Bamidele , Lemaire, Matthieu , Lee, Deokjung

Conference Paper Issue Date2017-08-24 View2

Introduction to UNIST Spent Nuclear Fuel Transportation Package Analysis Code System

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

Conference Paper Issue Date2017-08-24 View3

Machine learning of LWR spent nuclear fuel assembly decay heat measurements File File

Ebiwonjumi, Bamidele , Cherezov, Alexey , Dzianisau, Siarhei , Lee, Deokjung

Article Issue Date2021-11 View11

MCS Analysis of IAEA Lead-Cooled Fast Reactor Core Neutronics Benchmark

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

Conference Paper Issue Date2018-04-22 View4

MCS Analysis of Westinghouse 3-loop PWR Multi-cycle Operation

Ebiwonjumi, Bamidele , Lee, Hyunsuk , Choe, Jiwon , Lee, Deokjung , Shin, Ho Cheol

Conference Paper Issue Date2018-10-25 View4

MCS/FRAPCON Multi-physics Coupled Simulation of Westinghouse 3-loop PWR Wholecore Analysis

Ebiwonjumi, Bamidele , Lee, Hyunsuk , Zhang, Peng , Cherezov, Alexey , Lee, Deokjung , Shin, Ho Cheol , Lee, Hwan Soo

Conference Paper Issue Date2019-05-13 View1

Modeling the response of a diamond detector in the zero power reactor CROCUS File

Kong, Chidong , Ebiwonjumi, Bamidele , Lee, Deokjung , Kavrigin, Pavel , Weiss, Christina , Griesmayer, Erich , Frajtag, Pavel , Lamirand, Vincent , Hursin, Mathieu , Pautz, Andreas

Article Issue Date2022-01 View4

Monte Carlo Code MCS Multi-cycle Depletion Analysis of Westinghouse 3-loop PWR

Ebiwonjumi, Bamidele , Lee, Hyunsuk , Choe, Jiwon , Lemaire, Matthieu , Lee, Deokjung

Conference Paper Issue Date2018-09-30 View3

On-the-fly energy release per fission model in STREAM with explicit neutron and photon heating File File

Mai, Nhan Nguyen Trong , Lee, Woonghee , Kim, Kyeongwon , Ebiwonjumi, Bamidele , Kim, Wonkyeong , Lee, Deokjung

Article Issue Date2023-03 View6

Propagation of radiation source uncertainties in spent fuel cask shielding calculations File File

Ebiwonjumi, Bamidele , Mai, Nhan Nguyen Trong , Lee, Hyun Chul , Lee, Deokjung

Article Issue Date2022-08 View10

Recent Development Status of Neutron Transport Code STREAM

Choi, Sooyoung , Choe, Jiwon , Nguyen, Khang Hoang Nhat , Lee, Woonghee , Kim, Wonkyeong , Kim, Hanjoo , Ebiwonjumi, Bamidele , Jeong, Eun , Lee, Hyunsuk , Kim, Kyeongwon , et al

Conference Paper Issue Date2019-05-24 View3

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