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Hong, Ser Gi

원자력공학과

공과대학

연구분야

연도별 연구 활동 현황

전체 71건 중 61번부터 70번까지의 결과를 표시합니다.

2020

Article

An estimation of weapon-grade plutonium production from 5 MWe YongByon reactor through MCNP6 core depletion analysis

Article

Conceptual design of a long cycle small modular reactor core with annular UO2 and FCM (TRU) fuels

Conference

New mesh-based R2S method in shutdown dose rates analysis in the fusion energy systems

Article

Implementation and verification of adjoint neutron transport calculation in MUST code

Article

Verification of new mesh-based rigorous 2 step computational approach for the shutdown dose rate distributions in the fusion facilities

2019

Conference

APPLICATION OF PRECONDITIONED CONJUGATE GRADIENT METHOD TO FINE MESH REBALANCE FOR ACCELERATING DSA EQUATION ON TETRAHEDRAL MESHES

2018

Article

TRU Multi-Recycling Analysis in SMR Core with MOX Rods and FCM Rods

Article

Effective Use of the Linear Fine Mesh Rebalance for the DSA of SN Transport Equation with Tetrahedral Meshes

2015

Article

Monte Carlo Simulations for High-rate Fast Neutron Flux Measurements Made at the RAON Neutron Science Facility by Using MICROMEGAS

2014

Article

Sub-cell balanced nodal expansion methods using S4 eigenfunctions for multi-group SN transport problems in slab geometry

상세 보기

홍서기

연구분야

자료유형

발행연도

키워드

언어

An estimation of weapon-grade plutonium production from 5 MWe YongByon reactor through MCNP6 core depletion analysis

Conceptual design of a long cycle small modular reactor core with annular UO2 and FCM (TRU) fuels

New mesh-based R2S method in shutdown dose rates analysis in the fusion energy systems

Implementation and verification of adjoint neutron transport calculation in MUST code

Verification of new mesh-based rigorous 2 step computational approach for the shutdown dose rate distributions in the fusion facilities

APPLICATION OF PRECONDITIONED CONJUGATE GRADIENT METHOD TO FINE MESH REBALANCE FOR ACCELERATING DSA EQUATION ON TETRAHEDRAL MESHES

TRU Multi-Recycling Analysis in SMR Core with MOX Rods and FCM Rods

Effective Use of the Linear Fine Mesh Rebalance for the DSA of SN Transport Equation with Tetrahedral Meshes

Monte Carlo Simulations for High-rate Fast Neutron Flux Measurements Made at the RAON Neutron Science Facility by Using MICROMEGAS

Sub-cell balanced nodal expansion methods using S4 eigenfunctions for multi-group SN transport problems in slab geometry