지원사업
학술연구/단체지원/교육 등 연구자 활동을 지속하도록 DBpia가 지원하고 있어요.
커뮤니티
연구자들이 자신의 연구와 전문성을 널리 알리고, 새로운 협력의 기회를 만들 수 있는 네트워킹 공간이에요.
이용수
등록된 정보가 없습니다.
논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
Design Information Analysis of TRU Fuel Manufacturing Facility
한국방사성폐기물학회 학술대회
2017 .01
항공기용 TRU 전원장치 설계
한국조명·전기설비학회 학술대회논문집
2016 .05
Physics analysis of new TRU recycling options using FCM and MOX fueled PWR assemblies
Nuclear Engineering and Technology
2020 .01
Neutronics study on small power ADS loaded with recycled inert matrix fuel for transuranic elements transmutation using Serpent code
Nuclear Engineering and Technology
2021 .07
Thermal Conductivity Modeling of U-TRU-RE-Zr Metal Fuel for PGSFR
한국방사성폐기물학회 학술대회
2017 .01
인터리빙 기법을 적용한 항공기용 병렬 TRU 전원장치 설계
한국조명·전기설비학회 학술대회논문집
2016 .05
Technical Issues of Remote Assembler for TRU Fuel Assembly
한국방사성폐기물학회 학술대회
2017 .01
Preliminary Evaluation of Rare Earth Effect on Burnup Limit in TRU Fuel
한국방사성폐기물학회 학술대회
2018 .01
Monte Carlo simulations of criticality safety assessments of transuranic element storage in a pyroprocess facility
Nuclear Engineering and Technology
2018 .01
Evaluation of microstructural development of W-Re transmutation using Phase-field modeling
대한기계학회 춘추학술대회
2022 .06
Evaluation of microstructural development of W-Re transmutation using Phase-field modeling
대한기계학회 춘추학술대회
2022 .06
Monte Carlo analysis of LWR spent fuel transmutation in a fusion-fi ssion hybrid reactor system
Nuclear Engineering and Technology
2018 .01
NEUTRONICS INVESTIGATION OF CANADA DEUTERIUM URANIUM 6 REACTOR FUELED (TRANSURANICeTH) O2 USING A COMPUTATIONAL METHOD
Nuclear Engineering and Technology
2015 .01
The Effect of Target Material and the Neutron Spectrum on Nuclear Transmutation of Tc and I in Nuclear Reactors
한국방사성폐기물학회 학술대회
2018 .01
Uncertainty quantification based on similarity analysis of reactor physics benchmark experiments for SFR using TRU metallic fuel
Nuclear Engineering and Technology
2024 .09
구리밀봉 증기발생기 설계코드의 개발과 이를 이용한 TRU 함유 노심계통의 증기발생기 설계
한국유체기계학회 논문집
2020 .10
Metal Fuel Development and Verifi cation for Prototype Generation IV Sodium-Cooled Fast Reactor
Nuclear Engineering and Technology
2016 .01
Core design study of the Wielenga Innovation Static Salt Reactor (WISSR)
Nuclear Engineering and Technology
2024 .03
Development of easy-to-use interface for nuclear transmutation computing, VCINDER code
Nuclear Engineering and Technology
2018 .01
0