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S

Ser Gi Hong

hanyang university

14H指数
107论文数
757被引数
收录论文 17
发表时间
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New method for estimating uranium and plutonium masses using differential die-away signals
errNuclear Engineering and Technology
IF2.6
err2025-12-30
err0
errOAAI
errSehwan Seol; Jae Chang Kim; Junehyung Lee Bernaski; Yong Kyun Kim; Ser Gi Hong
err分享
err收藏
Application and Analysis of Cr-Coated GdN-CBA to i-SMR Core with Two Control Rod Patterns for Load-Following OperationsCr涂层GdN-CBA在采用两种控制棒布置的i-SMR堆芯中对变负荷运行的应用与分析
errNuclear Engineering and Technology
IF2.6
err2025-11-13
err0
errOAAI
errWoo Jin Lee; Sung Hyun Cho; Seung Hyeon Choi; Ser Gi Hong
err分享
err收藏
A core physics design and analysis of micro-modular lead cooled fast reactor (MMLFR) cores for autonomous ultra-long-life operation微模块铅冷快堆(MMLFR)堆芯实现自主超长寿命运行的核心物理设计与分析
errNuclear Engineering and Technology
IF2.6
err2025-08-22
err0
errOAAI
errSeungnam Lee; Ser Gi Hong
err分享
err收藏
Activation analysis capability of the STRAUM and BESNA coupled system for pressurized water reactors压水堆的STRAUM和BESNA耦合系统的活化分析能力
errProgress in Nuclear Energy
IF3.2
err2025-08-15
err0
PREAI
errAo Zhang; Ser Gi Hong; Seungil Jeong; Jingen Chen
err分享
err收藏
GPU-based multi-group discrete ordinates transport calculations: Parallel computing implementation in STRAUM基于GPU的多群离散纵标输运计算：STRAUM中的并行计算实现
errNUCLEAR ENGINEERING AND TECHNOLOGY
IF2.6
err2025-06-04
err0
errOAAI
errZhang, Ao; Hong, Ser Gi; Jeong, Seungil; Chen, Jingen
err分享
err收藏
An estimation of weapon-grade plutonium production from 5 MWe YongByon reactor through MCNP6 core depletion analysis
errPROGRESS IN NUCLEAR ENERGY
IF3.2
err2020-12-01
err3
PREAI
errPark, Geon Hee; Hong, Ser Gi
err分享
err收藏
Conceptual design of a long cycle small modular reactor core with annular UO2 and FCM (TRU) fuels具有环形UO2和FCM (TRU) 燃料的长周期小型模块化反应堆堆芯的概念设计
errINTERNATIONAL JOURNAL OF ENERGY RESEARCH
IF4.2
err2020-09-14
err8
errOAAI
errChoi, Jae Yeon; Hong, Ser Gi; Kwon, Hyuk
err分享
err收藏
Neutronic design and analysis of advanced long-cycle boron-free operation of a small modular reactor core with particle type burnable poison rods
errINTERNATIONAL JOURNAL OF ENERGY RESEARCH
IF4.2
err2018-09-19
err6
errOAAI
errYoo, Ho Seong; Hong, Ser Gi
err分享
err收藏
An Advanced Sodium-Cooled Fast Reactor Core Concept Using Uranium-Free Metallic Fuels for Maximizing TRU Burning Rate
errSUSTAINABILITY
IF3.3
err2017-12-01
err5
errOAAI
errYou, Wuseong; Hong, Ser Gi
err分享
err收藏
Design and performance analysis of a 500-W heat source for radioisotope thermophotovoltaic converters
errINTERNATIONAL JOURNAL OF ENERGY RESEARCH
IF4.2
err2017-09-14
err12
errOAAI
errCheon, Seong Jae; Hong, Ser Gi; Lee, Jung Hun; Nam, Young Suk
err分享
err收藏
Core design options of an ultra-long-cycle sodium cooled reactor with effective use of PWR spent fuel for sustainable energy supply
errINTERNATIONAL JOURNAL OF ENERGY RESEARCH
IF4.2
err2016-11-02
err3
errOAAI
errHong, Ser Gi; Hyun, HaeLee; You, Wuseung
err分享
err收藏
A sodium-cooled ultra-long-life reactor core having improved inherent safety with new driver-blanket burning strategy
errINTERNATIONAL JOURNAL OF HYDROGEN ENERGY
IF8.3
err2016-05-01
err4
PREAI
errHyun, HaeLee; Hong, Ser Gi
err分享
err收藏
Coupling of an innovative small PWR and advanced sodium-cooled fast reactor for incineration of TRU from once-through PWRs
errINTERNATIONAL JOURNAL OF ENERGY RESEARCH
IF4.2
err2015-11-25
err7
errOAAI
errKim, Do-Yeon; Hong, Ser Gi; Park, Chang Je
err分享
err收藏
Feasibility study on ultralong-cycle operation and material performance for compact liquid metal-cooled fast reactors: a review work
errINTERNATIONAL JOURNAL OF ENERGY RESEARCH
IF4.2
err2015-09-10
err18
errOAAI
errTak, Taewoo; Choe, Jiwon; Jeong, Yongjin; Lee, Deokjung; Kim, T. K.; Hong, Ser Gi
err分享
err收藏
Innovations in the ENHS reactor design and fuel cycleENHS反应堆设计和燃料循环的创新
errPROGRESS IN NUCLEAR ENERGY
IF3.2
err2008-03-01
err17
PREAI
errGreenspan, Ehud; Hong, Ser Gi; Lee, Ki Bog; Monti, Lanfranco; Okawa, Tsuyoshi; Susplugas, Arnaud; Fratoni, Massimiliano; Kim, Lance; Mattafirri, Sara; Petroski, Robert
err分享
err收藏
Power flattening options for the ENHS (Encapsulated Nuclear Heat Source) coreENHS (封装核热源) 核心的功率展平选项
errPROGRESS IN NUCLEAR ENERGY
IF3.2
err2005-01-01
err3
PREAI
errHong, SG; Greenspan, E
err分享
err收藏
Molten salt cooled encapsulated nuclear heat source (ENHS)-like reactors熔盐冷却封装核热源 (ENHS) 类反应堆
errPROGRESS IN NUCLEAR ENERGY
IF3.2
err2005-01-01
err8
PREAI
errHong, SG; Greenspan, E
err分享
err收藏

研究方向

暂时未获取到该数据
合作学者
合作期刊
Y
Yong Kyun Kim
H 指数: 42 · 论文数: 442
D
Deokjung Lee
H 指数: 24 · 论文数: 272
J
Jung Hun Lee
H 指数: 21 · 论文数: 84
E
E. Greenspan
H 指数: 21 · 论文数: 263
M
Massimiliano Fratoni
H 指数: 18 · 论文数: 152
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