An Advanced Sodium-Cooled Fast Reactor Core Concept Using Uranium-Free Metallic Fuels for Maximizing TRU Burning Rate

by Wuseong You, Ser Gi Hong
Published 2017-12-01

Diffusion synthetic acceleration with the fine mesh rebalance of the subcell balance method with tetrahedral meshes for SN transport calculations

by Habib Muhammad, Ser Gi Hong
Published 2020-03-01

Physics analysis of new TRU recycling options using FCM and MOX fueled PWR assemblies

by Ye Seul Cho, Ser Gi Hong
Published 2020-04-01

An ultra-long-life small safe fast reactor core concept having heterogeneous driver-blanket fuel assemblies

by Kyu Jung Choi, Yeonguk Jo, Ser Gi Hong
Published 2021-11-01

Validation of UNIST Monte Carlo code MCS for criticality safety calculations with burnup credit through MOX criticality benchmark problems

by Duy Long Ta, Ser Gi Hong, Deokjung Lee
Published 2021-01-01

COMPUTATIONAL EFFICIENCY OF A MODIFIED SCATTERING KERNEL FOR FULL-COUPLED PHOTON-ELECTRON TRANSPORT PARALLEL COMPUTING WITH UNSTRUCTURED TETRAHEDRAL MESHES

by JONG WOON KIM, SER GI HONG, YOUNG-OUK LEE
Published 2014-04-01

iBEST: a program for burnup history estimation of spent fuels based on ORIGEN-S

by Do-Yeon Kim, Ser Gi Hong, Gil Hoon Ahn
Published 2015-08-01

A Criticality Analysis of the GBC-32 Dry Storage Cask with Hanbit Nuclear Power Plant Unit 3 Fuel Assemblies from the Viewpoint of Burnup Credit

by Hyungju Yun, Do-Yeon Kim, Kwangheon Park, Ser Gi Hong
Published 2016-06-01

Improvement and verification of the DeCART code for HTGR core physics analysis

by Jin Young Cho, Tae Young Han, Ho Jin Park, Ser Gi Hong, Hyun Chul Lee
Published 2019-02-01