ScholarWorks@Hanyang University: Hong, Ser Gi

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Hong, Ser Gi (홍서기)

COLLEGE OF ENGINEERING (DEPARTMENT OF NUCLEAR ENGINEERING)

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Tel 02-2220-2365
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MCNP6:4||KARMA:4||TRU transmutation:2||small longcycle PWR:2||ORIGENS:2||FCM particle fuel:2||사용후핵연료:2||PWR spent fuel:2||Small Modular Reactor:2||DDA:2||TRU burning:2||Ultralonglife core:2||TRU consumption:2||Resonance:2||Critical experiment:1||DFEM:1||DFEMLDEMSCB:1||Dancoff factor:1||DeCART:1||Depletion calculation:1||Depletion uncertainty:1||Differential DieAway (DDA):1||Diffusion equation:1||Direct iteration method with resonance integral tables:1||Discrete ordinates transport calculation:1||Dose rate:1||Dry Storage Cask:1||Dry storage cask:1||Dynamic rod worth:1||ENDF:1||Effective atomic number:1||End effect:1||Excore detector response:1||Explosives:1||FCM fuel:1||FISPACTII:1||Forensics:1||Gamma transport/diffusion calculation:1||Heterogeneous assemblies:1||Inverse point kinetics:1||Iteration methods with resonance integral tables:1||KDEMO:1||KENO:1||Krylov subspace method:1||LMR:1||Lattice transport calculation:1||Leadbismuth coolant:1||Light watercooled SMR:1||Long Cycle Operation:1||Low boron operation:1||MATXST:1||MCNP:1||MCS:1||MERIT:1||MICROMEGAS:1||MOX and FCM (TRU) fuel pins:1||MOX fuel:1||MOXFCM fuel assembly:1||Matrix exponential:1||McCARD:1||Meshbased R2S method:1||Modified Scattering Kernel:1||Monte Carlo NParticle Transport Code, Version 6:1||Monte Carlo depletion:1||Monte Carlo simulation:1||Monte Carlo uncertainty sampling method:1||Multiangle:1||Multigroup library generation:1||Net TRU consumption rate:1||Neutron flux:1||Neutron transport equation:1||Nuclear Criticality Safety Analysis:1||Nuclear spent fuel:1||ORIGEN:1||Optimization:1||PHYSICS:1||PWR type reactor:1||Parallel Computing:1||Photon attenuation coefficient:1||Photonelectron Fullcoupling:1||PuO2 fuel:1||RTPV (radioisotope thermophotovoltaic):1||Reactivity decomposition:1||RegionII:1||Resonance interference:1||Resonance treatment:1||SCALE 6.1/STandardized Analysis of Reactivity for Burnup Credit using SCALE:1||SMART reactor:1||SMRlongcycle operationbreedandburnmaterial performance:1||STRAUM:1||Safety:1||Selfcontrollability:1||Selfshielded:1||Shutdown dose rate:1||Slowing down equation:1||Small Modular Reactor (SMR):1||Small modular reactor:1||Sodium void worth:1||Sodiumcooled fast reactor:1||Source term:1||Spent fuel:1||Spent fuel cask:1||Spent nuclear fuel:1||Statistical Ftest:1||TRU multirecycling:1||TRU recyclin:1||Tetrahedral mesh:1||The method of characteristics:1||Threedimensional Discrete Ordinates Method:1||Transport lattice:1||Transport lattice calculation:1||Transport lattice code:1||Ultralong Cycle Fast Reactor:1||Ultralonglife small fast reactor:1||Unstructured Tetrahedral Mesh:1||Validation:1||Weapongrade plutonium:1||Xray inspection:1||annular fuel:1||boronfree operation:1||burning of PWR spent fuel TRU:1||cross section:1||discrete ordinates method:1||eigenfunction expansion:1||equivalence theory:1||fast reactor:1||fuel escape probability:1||g FCM fuel:1||highly anisotropic:1||incident beam:1||long cycle length:1||nonnegative scattering cross sections:1||nuclear fuel cycle:1||particletype burnable poison:1||power conversion efficiency:1||priority concept method:1||radiation shielding:1||resonance:1||resonance integral:1||resonance treatment:1||selfshielding:1||small modular reactor:1||small modular reactor (SMR):1||sodiumcooled fast reactor (SFR):1||sodiumcooled reactor:1||source term:1||subcell balances:1||thorium–uranium fuel cycle:1||three dimensional geometry:1||ultralongcycle:1||upscattering:1||uraniumfree fuel:1||대기 검출:1||방사능비:1||방사성:1||방사화 평가:1||방출 시점:1||안전조치:1||제논 동위원소:1||주변국 핵활동:1||중성자 계측:1||중성자 발생장치:1||5 MWe Yongbyon reactor:1||플루토늄:1||Axial Burnup Distribution:1||Axial burnup:1||BESNA:1||Block preconditioners for thermal:1||Breedandburn:1||Burnable poison rods:1||Burnup Credit:1||Burnup credit:1||Burnup history estimation:1||CE critical:1||CRAM:1||Compton scattering:1||Computational Efficiency:1||

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