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Analysis of Statistical Uncertainties in Monte Carlo Functional Expansion Tallies

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

Conference Paper Issue Date2020-03-15 View20

Bayesian method and polynomial chaos expansion based inverse uncertainty quantification of spent fuel using decay heat measurements File

Ebiwonjumi, Bamidele , Lee, Deokjung

Article Issue Date2021-07 View23

Boron-free SMPWR Analysis with MCS and STREAM codes

Jang, Jaerim , Choe, Jiwon , Choi, Sooyoung , Lee, Hyunsuk , Ebiwonjumi, Bamidele , Shin, Ho Cheol , Lee, Deokjung

Conference Paper Issue Date2017-08-24 View17

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 View13

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 View23

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 View12

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 View17

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 View20

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 View11

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 View24

Functional Expansion Tallies in Monte Carlo High Fidelity LWR Analysis

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

Conference Paper Issue Date2019-12-03 View20

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 View10

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 View15

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 View24

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 View23

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 View10

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 View11

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 View19

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 View20

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 View57

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 View24

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 View11

Recent Work on Photon Transport with UNIST Monte Carlo Code MCS

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

Conference Paper Issue Date2017-08-24 View12

Sensitivity Analysis of PWR Spent Nuclear Fuel Due to Modelling Parameter Uncertainties Using Surrogate Models File

Ebiwonjumi, Bamidele , Zhang, Peng , Lee, Deokjung

Conference Paper Issue Date2020-03-29 View16

Uncertainties of PWR spent nuclear fuel isotope inventory for back-end cycle analysis with STREAM/RAST-K File

Jang, Jaerim , Kong, Chidong , Ebiwonjumi, Bamidele , Jo, Yunki , Lee, Deokjung

Article Issue Date2021-08 View14

Uncertainty quanti fi cation of PWR spent fuel due to nuclear data and modeling parameters File File

Ebiwonjumi, Bamidele , Kong, Chidong , Zhang, Peng , Cherezov, Alexey , Lee, Deokjung

Article Issue Date2021-03 View23

Uncertainty quantification in decay heat calculation of spent nuclear fuel by STREAM/RAST-K File File

Jang, Jaerim , Kong, Chidong , Ebiwonjumi, Bamidele , Cherezov, Alexey , Jo, Yunki , Lee, Deokjung

Article Issue Date2021-09 View25

Validation of lattice physics code STREAM for predicting pressurized water reactor spent nuclear fuel isotopic inventory File

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

Article Issue Date2018-10 View13

Validation of nuclide depletion capabilities in Monte Carlo code MCS File File

Ebiwonjumi, Bamidele , Lee, Hyunsuk , Kim, Wonkyeong , Lee, Deokjung

Article Issue Date2020-09 View28

Validation of Nuclide Depletion Capabilities in Monte Carlo Code MCS using Spent Fuel Isotopic Measurements

Ebiwonjumi, Bamidele , Lee, Hyunsuk , Kim, Wonkyeong , Choi, Sooyoung , Lee, Deokjung

Conference Paper Issue Date2019-08-26 View26

Validation of spent nuclear fuel decay heat calculation by a two-step method File

Jang, Jaerim , Ebiwonjumi, Bamidele , Kim, Wonkyeong , Park, Jinsu , Choe, Jiwon , Lee, Deokjung

Article Issue Date2021-01 View17

Verification and validation of isotope inventory prediction for back-end cycle management using two-step method File File

Jang, Jaerim , Ebiwonjumi, Bamidele , Kim, Wonkyeong , Cherezov, Alexey , Park, Jinsu , Lee, Deokjung

Article Issue Date2021-07 View22

Verification and validation of radiation source term capabilities in STREAM File

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

Article Issue Date2019-02 View21

Verification and Validation of STREAM Source Term Calculation Capability

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

Conference Paper Issue Date2017-04-16 View11

Verification of photon transport capability of UNIST Monte Carlo code MCS File

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

Article Issue Date2018-10 View16

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