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Towards grain-scale modelling of the release of radioactive fission gas from oxide fuel. Part I: SCIANTIX
Nuclear Engineering and Technology
2022 .08
Calculation of the fission products for neutron-induced fission of 235U
Nuclear Engineering and Technology
2024 .05
Study on the effect of long-term high temperature irradiation on TRISO fuel
Nuclear Engineering and Technology
2022 .08
Acceleration method of fission source convergence based on RMC code
Nuclear Engineering and Technology
2020 .01
Assessment of three European fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment
Nuclear Engineering and Technology
2021 .10
Analytical criteria for fuel fragmentation and burst FGR during a LOCA
Nuclear Engineering and Technology
2020 .10
Assessment of INSPYRE-extended fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment
Nuclear Engineering and Technology
2023 .03
A new burn-up module for application in fuel performance calculations targeting the helium production rate in (U,Pu)O2 for fast reactors
Nuclear Engineering and Technology
2021 .06
Development of a Fission Product Transport Module Predicting the Behavior of Radiological Materials during Severe Accidents in a Nuclear Power Plant
방사선방어학회지
2016 .01
Towards a physics-based description of intra-granular helium behaviour in oxide fuel for application in fuel performance codes
Nuclear Engineering and Technology
2021 .02
초고온가스로 핵분열생성물 거동해석용 전산 소프트웨어의 화학반응 모듈 개발
대한기계학회 춘추학술대회
2016 .12
Effect of central hole on fuel temperature distribution
Nuclear Engineering and Technology
2017 .01
Study of fission gas products effect on thermal hydraulics of the WWER1000 with enhanced subchannel method
Advances in energy research
2017 .01
Fission counter array for pulse-mode measurements of high-flux and high-energy neutrons
Nuclear Engineering and Technology
2024 .09
Adsorption of radioactive particulates by zeolite in nuclear power plants
대한설비공학회 학술발표대회논문집
2024 .06
Validation of the fuel rod performance analysis code FRIPAC
Nuclear Engineering and Technology
2019 .01
Study on producing radioisotopes based on fission or radiative capture method in a high flux reactor
Nuclear Engineering and Technology
2024 .09
Systems Engineering Approach to the Heat Transfer Analysis of PLUS 7 Fuel Rod Using ANSYS FEM Code
시스템엔지니어링학술지
2017 .01
Experimental simulation of activity release from leaking fuel rods
Nuclear Engineering and Technology
2018 .01
A Study on the Demonstration Evaluation of Fuel Cell for Building by Fuel Gas Composition
AFORE
2019 .11
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