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!
Calculation of kinetic parameters ? eff and ? with modifi ed open source Monte Carlo code OpenMC(TD)
Nuclear Engineering and Technology
2022 .03
Influence of nuclear data library on neutronics benchmark of China experimental fast reactor start-up tests
Nuclear Engineering and Technology
2022 .10
Implementation and benchmarking of the local weight window generation function for OpenMC
Nuclear Engineering and Technology
2022 .10
OpenMC를 활용한 초소형 이동형 원자로용기 방사화 선원항 평가
한국압력기기공학회 논문집
2024 .12
Development of transient Monte Carlo in a fissile system with β-delayed emission from individual precursors using modified open source code OpenMC(TD)
Nuclear Engineering and Technology
2023 .05
Neutronics modelling of control rod compensation operation in small modular fast reactor using OpenMC
Nuclear Engineering and Technology
2022 .03
Application of TULIP/STREAM code in 2-D fast reactor core high-fidelity neutronic analysis
Nuclear Engineering and Technology
2019 .01
On the cyclic change in the dynamics of the IBR-2M pulsed reactor
Nuclear Engineering and Technology
2023 .05
Risk-informed design optimization method and application in a lead-based research reactor
Nuclear Engineering and Technology
2023 .06
Supercritical CO2-cooled fast reactor and cold shutdown system for ship propulsion
Nuclear Engineering and Technology
2024 .03
An assessment of the applicability of multigroup cross sections generated with Monte Carlo method for fast reactor analysis
Nuclear Engineering and Technology
2020 .12
Assessment of N-16 activity concentration in Bangladesh Atomic Energy Commission TRIGA Research Reactor
Nuclear Engineering and Technology
2018 .01
Optimization of a Tilted-Slide Reactor Operation for the Fast Pyrolysis of Biomass
AFORE
2021 .10
Ultrasonic ranging technique for obstacle monitoring above reactor core in prototype generation IV sodium-cooled fast reactor
Nuclear Engineering and Technology
2020 .01
Development and verification of a Monte Carlo two-step method for lead-based fast reactor neutronics analysis
Nuclear Engineering and Technology
2023 .06
A simple method for estimating the major nuclide fractional ?ssion rates within light water and advanced gas cooled reactors
Nuclear Engineering and Technology
2020 .09
Robust feedback-linearization control for axial power distribution in pressurized water reactors during load-following operation
Nuclear Engineering and Technology
2018 .01
Neutronics analysis of JSI TRIGA Mark II reactor benchmark experiments with SuperMC3.3
Nuclear Engineering and Technology
2019 .01
Performance evaluation of the Floating Absorber for Safety at Transient (FAST) in the innovative Sodium-cooled Fast Reactor (iSFR) under a single control rod withdrawal accident
Nuclear Engineering and Technology
2020 .01
Kinetics calculation of fast periodic pulsed reactors using MCNP6
Nuclear Engineering and Technology
2018 .01
0