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논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
Determination of Plutonium Present in Highly Radioactive Irradiated Fuel Solution by Spectrophotometric Method
Nuclear Engineering and Technology
2016 .06
Experimental Validation of a Nuclear Forensics Methodology for Source Reactor-Type Discrimination of Chemically Separated Plutonium
Nuclear Engineering and Technology
2019 .01
Spectrometry Analysis of Fumes of Mixed Nuclear Fuel (U 0.8 Pu 0.2 )O 2 Samples Heated up to 2,000° C and Evaluation of Accidental Irradiation of Living Organisms by Plutonium as the Most Radiotoxic Fission Product of Mixed Nuclear Fuel
Nuclear Engineering and Technology
2016 .01
Time Dependent Heat Transfer of Proliferation Resistant Plutonium
Nuclear Engineering and Technology
2019 .01
Study of the Effect of (U0.8Pu0.2)O2 Uranium-Plutonium Mixed Fuel Fission Products on a Living Organism
Nuclear Engineering and Technology
2016 .01
Laser-Based Spectroscopic Studies of Actinide Complexes: Plutonium
한국방사성폐기물학회 학술대회
2018 .01
Determination of Plutonium and Uranium Content and Burnup Using Six Group Delayed Neutrons
Nuclear Engineering and Technology
2019 .01
Conceptual design of a high neutron fl ux research reactor core with low enriched uranium fuel and low plutonium production
Nuclear Engineering and Technology
2020 .01
Conceptual design study on Plutonium-238 production in a multi-purpose high flux reactor
Nuclear Engineering and Technology
2024 .01
Calculation of the fission products for neutron-induced fission of 235U
Nuclear Engineering and Technology
2024 .05
Accurate determination of minor isotope ratios in individual plutonium – uranium mixed particles by thermal ionization mass spectrometry
Nuclear Engineering and Technology
2018 .01
Design of a Mixed-Spectrum Reactor With Improved Proliferation Resistance for Long-Lived Applications
방사성폐기물학회지
2018 .01
The thermal conducting properties of UO2 pallets
대한기계학회 춘추학술대회
2020 .07
UO₂ 소결체 끝단 형상 변경에 따른 연료봉 설계 영향 평가
대한기계학회 춘추학술대회
2019 .11
Sensitivity Studies on a Novel Nuclear Forensics Methodology for Source Reactor-Type Discrimination of Separated Weapons Grade Plutonium
Nuclear Engineering and Technology
2019 .01
Study on the effect of long-term high temperature irradiation on TRISO fuel
Nuclear Engineering and Technology
2022 .08
Material attractiveness of irradiated fuel salts from the Seaborg Compact Molten Salt Reactor
Nuclear Engineering and Technology
2024 .09
Determination of Uranium, Plutonium, Neodymium, Cesium, Cerium and Europium Isotopes in Irradiated Dual-cooled Annular Fuel by Isotope Dilution Mass Spectrometry and γ-Ray Spectrometry
한국방사성폐기물학회 학술대회
2017 .01
Thermodynamic and experimental analyses of the oxidation behavior of UO2 pellets in damaged fuel rods of pressurized water reactors
Nuclear Engineering and Technology
2020 .12
A comparative study on the impact of Gd2O3 burnable neutron absorber in UO2 and (U, Th)O2 fuels
Nuclear Engineering and Technology
2020 .01
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