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Development and validation of multiphysics PWR core simulator KANT
Nuclear Engineering and Technology
2023 .06
Approximate core sizing of PWR600 MWe based on APR1400
대한기계학회 춘추학술대회
2016 .12
Simulation of reactivity-initiated accident transients on UO2 -M5® fuel rods with ALCYONE V1.5 fuel performance code
Nuclear Engineering and Technology
2018 .01
Creep Model for PWR Spent Nuclear Fuel
한국방사성폐기물학회 학술대회
2015 .01
Impact of fuel temperature on nuclear core design calculations
Nuclear Engineering and Technology
2024 .09
Design and analysis of RIF scheme to improve the CFD effi ciency of rod-type PWR core
Nuclear Engineering and Technology
2021 .10
Solution of OECD/NEA PWR MOX/UO2 benchmark with a high-performance pin-by-pin core calculation code
Nuclear Engineering and Technology
2024 .09
Uncertainty quantifi cation of the power control system of a small PWR with coolant temperature perturbation
Nuclear Engineering and Technology
2022 .06
Transient Diagnosis and Prognosis for Secondary System in Nuclear Power Plants
Nuclear Engineering and Technology
2016 .01
마그네슘/공기연료전지의 과도특성에 관한 연구
전기학회논문지 P
2016 .09
Fast Neutron Detection for Spent PWR Fuel in Dry Storage
한국방사성폐기물학회 학술대회
2017 .01
Transportation Analysis of the 14OFA PWR Fuel Assembly
한국방사성폐기물학회 학술대회
2019 .01
CTF/DYN3D multi-scale coupled simulation of a rod ejection transient on the NURESIM platform
Nuclear Engineering and Technology
2017 .01
Grouping of Radioactive Wastes During the Decommissioning of PWR NPPs
한국방사성폐기물학회 학술대회
2018 .01
The JFNK method for the PWR's transient simulation considering neutronics, thermal hydraulics and mechanics
Nuclear Engineering and Technology
2020 .01
Design of the flexible switching controller for small PWR core power control with the multi-model
Nuclear Engineering and Technology
2021 .03
Review on Revision History of ANSI/ANS-18.1 and PWR-GALE Along With Its Potential Impact to Anticipated Radioactive Source Terms to Environment From PWRs
한국방사성폐기물학회 학술대회
2019 .01
Generation Characterization of Metal Wastes During the Decommissioning of PWR NPPs
한국방사성폐기물학회 학술대회
2018 .01
CFD simulation of flow and heat transfer characteristics in a 5×5 fuel rod bundles with spacer grids of advanced PWR
Nuclear Engineering and Technology
2020 .01
Preliminary Study on the Development of a Horizontal Disposal Concept for PWR Spent Fuels
한국방사성폐기물학회 학술대회
2019 .01
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