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Ser Gi Hong
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Ser Gi Hong
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Ser Gi Hong
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1
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
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Article
2
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
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Article
3
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
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Article
4
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
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Article
5
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
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Article
6
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
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Article
7
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
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Article
8
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
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Article
9
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
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Article
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