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가 나 다 라 마 바 사 아 자 차 카 타 파 하

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

Khang Hoang Nhat Nguyen

Thesis Issue Date2019-08 View7

Investigation of ZrN Non-Reactively Sputtered Diffusion Barrier Coating for U-Mo Dispersion Fuel File File

Thesis Issue Date2019-02 View9

Measurements and Modeling of Thermal Conductivity of U-Mo/Al Dispersion Fuel for Research Reactor File File

Thesis Issue Date2018-08 View7

Monte Carlo Code MCS as Cross-section Generation Tool for Reactor Core Analysis File File

TUNG DONG CAO NGUYEN

Thesis Issue Date2023-02 View16

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

Thesis Issue Date2019-08 View8

New Burnable Absorber and Zirconium Reflector for Advanced PWRs File File

Thesis Issue Date2015-08 View14

Pin-based Pointwise Energy Slowing-down Method for Resonance Self-shielding Calculation File File

Thesis Issue Date2017-02 View27

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

Thesis Issue Date2021-08 View8

The initial implementation of MCS on graphics processing unit using CUDA fortran File

Thesis Issue Date2024-02 View26

Verification and Validation for Transient Calculation of STREAM/RAST-K 2.0 File File

Thesis Issue Date2018-08 View12

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

Thesis Issue Date2020-08 View12

Verification of STREAM3D for APR1400 Reactor Core Benchmark File File

Thesis Issue Date2022-08 View22

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