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COLLEGE OF ENGINEERING[S](공과대학)
NUCLEAR ENGINEERING(원자력공학과)
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Results 1-10 of 11 (Search time: 0.002 seconds).
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Issue Date
Title
Author(s)
2020-03
Diffusion synthetic acceleration with the fine mesh rebalance of the subcell balance method with tetrahedral meshes for SN transport calculations
홍서기
2020-10
Development of multi-group cross section processing program for MUST unstructured discrete ordinate transport code
홍서기
2020-10
Neutronic analysis of the moderator effect for an ultra long cycle SMSFR (Small Modular Sodium-cooled Fast Reactor)
홍서기
2020-10
Update of AMORES programs for automatic criticality safety evaluation of the transport cask
홍서기
2021-02
A shutdown dose rates analysis of the Korean fusion demonstration reactor using MCNP5 mesh-based R2S approach
홍서기
2020-07
Implementation and verification of adjoint neutron transport calculation in MUST code
홍서기
2020-07
Verification of new mesh-based rigorous 2 step computational approach for the shutdown dose rate distributions in the fusion facilities
홍서기
2020-04
Physics analysis of new TRU recycling options using FCM and MOX fueled PWR assemblies
홍서기
2020-12
Analysis of the criticality of the spent fuel pool on the consideration of the spent fuels having axial blankets
홍서기
2020-06
Validation of UNIST Monte Carlo code MCS for criticality safety calculations with burnup credit through MOX criticality benchmark problems
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Critical experiment
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DFEM
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Diffusion equation
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FCM fuel
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K-DEMO; Shutdown dose rate; Mesh-...
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LDEM-SCB
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MCNP6
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MCS
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MOX fuel
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Neutron transport equation
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2021
10
2020
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