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FALCON code-based analysis of PWR fuel rod behaviour during RIA transients versus new U.S.NRC and current Swiss failure limits
Nuclear Engineering and Technology
2021 .11
Uncertainty quantification based on similarity analysis of reactor physics benchmark experiments for SFR using TRU metallic fuel
Nuclear Engineering and Technology
2024 .09
Improvement and application of DeCART/MUSAD for uncertainty analysis of HTGR neutronic parameters
Nuclear Engineering and Technology
2020 .01
RIA(Reactivity-Initiated Accident)-AOA(Axial Offset Anomaly) 평가용 자체 코드 개발 및 코드 통합 연구
한국유체기계학회 학술대회 논문집
2019 .11
A critical study on best methodology to perform UQ for RIA transients and application to SPERT-III experiments
Nuclear Engineering and Technology
2022 .05
Effect of central hole on fuel temperature distribution
Nuclear Engineering and Technology
2017 .01
Application case for phase III of UAM-LWR benchmark: Uncertainty propagation of thermal-hydraulic macroscopic parameters
Nuclear Engineering and Technology
2020 .08
Simulation of reactivity-initiated accident transients on UO2 -M5® fuel rods with ALCYONE V1.5 fuel performance code
Nuclear Engineering and Technology
2018 .01
Assessment of three European fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment
Nuclear Engineering and Technology
2021 .10
한국형발사체 개발사업 2단계에서의 제품보증 관리
항공우주시스템공학회 학술행사 논문집
2016 .11
A comparative study on the impact of Gd2O3 burnable neutron absorber in UO2 and (U, Th)O2 fuels
Nuclear Engineering and Technology
2020 .01
연료품질 및 연비계산 방법 변화에 따른 연비특성 분석
동력시스템공학회지
2016 .08
JSI TRIGA fuel rod reactivity worth experiments for validation of Serpent-2 and RAPID fuel burnup calculations
Nuclear Engineering and Technology
2024 .08
Vibration Control of a Nuclear Fuel Rod Maneuvering Under Water
제어로봇시스템학회 국제학술대회 논문집
2015 .10
탄소중립연료(E-Fuel) 연구개발 현황
한국연소학회지
2022 .03
Whole-core analysis of Watts bar benchmark with three-dimensional MOC code STREAM3D
Nuclear Engineering and Technology
2024 .08
냉각기능상실사고 시 사용후핵연료 저장조의 열수력적 거동 특성
대한기계학회 춘추학술대회
2016 .12
Benchmarking Studies for Template-Based Modeling of Protein Structures
한국생물공학회 학술대회
2019 .10
A Study on the Suitability of Safety Codes for Portable Fuel Cells by Transportation
AFORE
2022 .09
Integral nuclear data validation using experimental spent nuclear fuel compositions
Nuclear Engineering and Technology
2017 .01
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