PUBLICATION

A CNN-Based PINNs Framework for Solving the 2D Neutron Diffusion Equation

Jaeguk Lee and Hyung Jin Shim

2025

Conference(Domestic)

Transactions of the Korean Nuclear Society Spring Meeting. Jeju, May 22-23 (2025)

McCARD/G Transient Analysis for CABRI-Like Benchmark

Jae Young Kwon and Hyung Jin Shim

2025

Conference(Domestic)

Transactions of the Korean Nuclear Society Spring Meeting. Jeju, May 22-23 (2025)

Sample Variance Estimation for Fission Source Distribution in Monte Carlo Eigenvalue Calculations with Cross Section Feedback

Heon Woo Jang, Sang Bin Im, and Hyung Jin Shim

2025

Conference(Domestic)

Transactions of the Korean Nuclear Society Spring Meeting. Jeju, May 22-23 (2025)

A CNN-Based Physics-Informed Neural Networks for Solving the Neutron Diffusion Equation

Jaeguk Lee, Hyung Jin Shim

2025

Conference(Oversea)

M&C 2025 – International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering, Denver, CO, Apr. 27-30, 2025 (2025)

Evaluation of tritium production capability of the 5 MWe gas-cooled graphite-moderated reactor at Yongbyon using tritium-producing burnable absorber rods

Dokyun Kim, Seong Jeong Jeong, Hyung Jin Shim

2025

Journal

Nucl. Eng. Technol. (2025.02)

Kinetics Parameters Estimation for the Coupled Neutron-Photon Point Kinetics Model in Monte Carlo Eigenvalue Calculations

Young In Kim and Hyung Jin Shim

2025

Journal

Nucl. Sci. Eng. (2025.04)

Design of open-tank-in-pool-type educational critical assemblies using UO2 and U-7Mo fuels

Kyoseong Song, Cheol Ho Pyeon, and Hyung Jin Shim

2025

Journal

Annals of Nuclear Energy, 213, 111139 (2025)

Verification of the nTRACER/CTF code system for full core high resolution cycle analysis with the OECD/NEA TVA Watts Bar Unit 1 benchmark

Sung Joon Kwon et. al.

2025

Journal

Ann. Nucl. Energy, 220, 111532 (2025.09)

Comparison of BANDI-60 core designs using Pyrex burnable absorber and annular fuel embedding gadolinia wire

Dokyun Kim, Jong Tae Seo, Hyung Jin Shim

2024

Journal

Annals of Nuclear Energy, 195, 110119 (2024)

Sensitivity of a control rod worth estimate to neutron detector position by time-dependent Monte Carlo simulations of the rod drop experiment

Jong Min Park, Cheol Ho Pyeon, Hyung Jin Shim

2024

Journal

Nucl. Eng. Technol., 56(3), 916-921 (2024)

Evaluation of the impact of plasma operation scenarios on the fusion reactor blanket design using an integrated numerical plasma and neutronics analysis suite

Choi, Rin, et al.

2024

Journal

Fusion Engineering and Design, 202, 114350 (2024)

Discrimination of dicentric chromosome from radiation exposure patient data using a pretrained deep learning model

Soon Woo Kwon, Won il Jang, Mi-Sook Kim, …, Hyung Jin Shim

2024

Journal

Nucl. Eng. Technol., 56(8), 3123 (2024)

Development of a GPU-enhanced time-dependent Monte Carlo neutron transport version of McCARD

Woo Kyoung Ko, Seong Jeong Jeong, Young In Kim, and Hyung Jin Shim

2024

Journal

EPJ Nuclear Sci. Technol., 10, 28 (2024). (not SCI)

2D/3D GPU-accelerated deterministic neutronics solver based on planar method of characteristics and hybrid finite element method

Kyung Min Kim, Han Gyu, Lee, Jaeuk Im and Hyung Jin Shim

2024

Conference(Oversea)

EPJ Web of Conferences 302, 02001 (2024)

Monte Carlo sensitivity analyses of isothermal temperature coefficient in solid-moderated and solid-reflected cores at Kyoto University critical assembly

Kyoseong Song, Cheol Ho Pyeon, and Hyung Jin Shim

2023

Journal

Annals of Nuclear Energy, 180, 109491 (2023)

Advances for the time-dependent Monte Carlo neutron transport analysis in McCARD

Sang Hoon Jang and Hyung Jin Shim

2023

Journal

Nucl. Eng. Technol., vol. 55, 2712-2722 (2023)

Development of deep convolutional neural network for prediction of cycle maximum pin power peaking factor in pressurized water reactor

Younduk Nam, and Hyung Jin Shim

2023

Journal

Annals of Nuclear Energy, 194, 110083 (2023)

Estimation of Kinetics Parameters for Point Kinetics Equation Considering Delayed Photoneutrons

Young In Kim, Hyung Jin Shim

2023

Conference(Oversea)

M&C 2023 – International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering, Niagara Falls, Ontario, Canada, August 13-17, 2023 (2023)

Development of GPU Based Depletion Module by CRAM

Woo Kyoung Ko and Hyung Jin Shim

2023

Conference(Oversea)

Proceedings of the Reactor Physics Asia 2023 (RPHA2023) Conference, Gyeongju, Korea, Oct. 24-26 (2023)

Equilibrium Core Design for 170MWe PWR-Type SMR Applying a Two-Batch Fuel Management Concept

Dokyun Kim and Hyung Jin Shim

2023

Conference(Domestic)

Transactions of the Korean Nuclear Society Spring Meeting, Jeju, May 18-19 (2023)