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Implementation and Verification of Three-Dimensional MOC Transient Solver in Whole-core Transport code STREAM File

Nguyen

Thesis Issue Date2019-08 View1
Investigation of ZrN Non-Reactively Sputtered Diffusion Barrier Coating for U-Mo Dispersion Fuel File

Kim, Ji Hyeon

Thesis Issue Date2019-02 View3
Measurements and Modeling of Thermal Conductivity of U-Mo/Al Dispersion Fuel for Research Reactor File

Cho, Tae Won

Thesis Issue Date2018-08 View5
Monte Carlo Code MCS as Cross-section Generation Tool for Reactor Core Analysis File

NGUYEN, Tung Dong Cao

Thesis Issue Date2023-02 View9
Neutron XS Library Generation of ENDF/B-VIII.0 for MOC code STREAM and Monte Carlo code MCS File

Kim, Kiho

Thesis Issue Date2019-08 View4
New Burnable Absorber and Zirconium Reflector for Advanced PWRs File

Choe, Jiwon

Thesis Issue Date2015-08 View4
Pin-based Pointwise Energy Slowing-down Method for Resonance Self-shielding Calculation File

Choi, Sooyoung

Thesis Issue Date2017-02 View6
The Angle-dependent Linear Source Approximation for the Three-Dimensional Method of Characteristics/Diamond-Differencing Neutron Transport Simulation File

Choe, Jiwon

Thesis Issue Date2021-08 View0
The initial implementation of MCS on graphics processing unit using CUDA fortran File

Park, Jeehoon

Thesis Issue Date2024-02 View4
Verification and Validation for Transient Calculation of STREAM/RAST-K 2.0 File

Jeong, Eun

Thesis Issue Date2018-08 View8
Verification and Validation of Monte Carlo Code MCS for the Multi-physics High-fidelity Analysis of OPR-1000 Multi-cycle Operation File

Dos, Vutheam

Thesis Issue Date2020-08 View3
Verification of STREAM3D for APR1400 Reactor Core Benchmark File

RanLee

Thesis Issue Date2022-08 View15
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