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.
논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2022.11
- 수록면
- 4,030 - 4,048 (19page)
- DOI
- 10.1016/j.net.2022.06.023
이용수
초록· 키워드
오류제보하기
In this study, road transportation tests were conducted with surrogate fuel assemblies under normal conditions of transport to evaluate the vibration and shock load characteristics of spent nuclear fuel (SNF). The overall test data analysis was conducted based on the measured acceleration and strain data obtained from the speed bump, lane-change, deceleration, obstacle avoidance, and circular tests.
Furthermore, representative shock response spectrums and power spectral densities of each test mode were acquired. Amplification or attenuation characteristics were investigated according to the load transfer path. The load attenuated significantly as it transferred from the trailer to the cask. By contrast, the load amplified as it transferred from the cask to the surrogate SNF assembly. The fuel loading location on the cask disk assembly did not exhibit a significant influence on the strain measured from the fuel rods. The principal strain was in the vertical direction, and relatively large strain values were obtained in spans with large spacing between spacer grids. The influence of the lateral location of fuel rods was also investigated. The fuel rods located at the side exhibited relatively large strain values than those located at the center. Based on the strain data obtained from the test results, a hypothetical road transportation scenario was established. A fatigue evaluation of the SNF rod was performed based on this scenario. The evaluation results indicate that no fatigue damage occurred on the fuel rods.
목차
등록된 정보가 없습니다.
참고문헌 (0)
참고문헌 신청함께 읽어보면 좋을 논문
논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
-
Data analysis of simulated fuel-loaded sea transportation tests under normal conditions of transport
Nuclear Engineering and Technology
2024 .02
-
Change in radiation characteristics outside the SNF storage container as an indicator of fuel rod cladding destruction
Nuclear Engineering and Technology
2021 .11
-
정상운반조건 해석을 위한 사용후핵연료집합체 유한요소모델 최적화
한국압력기기공학회 논문집
2023 .12
-
Parametric study on the structural response of a high burnup spent nuclear fuel rod under drop impact considering post-irradiated fuel conditions
Nuclear Engineering and Technology
2020 .01
-
Vibration Control of a Nuclear Fuel Rod Maneuvering Under Water
제어로봇시스템학회 국제학술대회 논문집
2015 .10
-
Requirements for the Transportation of Spent Nuclear Fuel (SNF) in Terms of Fuel Integrity and Data Needed According to
한국방사성폐기물학회 학술대회
2017 .01
-
Structural Integrity Evaluation of Spent Nuclear Fuel Assembly Under Normal Transportation Drop Conditions
한국방사성폐기물학회 학술대회
2017 .01
-
Modal Analysis of Alternative Spent Nuclear Fuel Transportation Cask for Normal Conditions of Transport Test
한국방사성폐기물학회 학술대회
2018 .01
-
Effect of central hole on fuel temperature distribution
Nuclear Engineering and Technology
2017 .01
-
Equivalent Drop Analysis Model of Transportation Cask Including Spent Nuclear Fuel Assembly
한국방사성폐기물학회 학술대회
2018 .01
-
Experimental evaluation of fuel rod pattern analysis in fuel assembly using Yonsei single-photon emission computed tomography (YSECT)
Nuclear Engineering and Technology
2022 .06
-
15 m Drop Analysis for Spent Nuclear Fuel Transport Cask
한국방사성폐기물학회 학술대회
2018 .01
-
연료품질 및 연비계산 방법 변화에 따른 연비특성 분석
동력시스템공학회지
2016 .08
-
Thermal Analysis of Transportation and Storage Cask of Spent Nuclear Fuel for Forced Gas Drying Condition
한국방사성폐기물학회 학술대회
2017 .01
-
Factors Affecting Spent Nuclear Fuel Rod Resistance Against Impact
한국방사성폐기물학회 학술대회
2018 .01
-
Structural Evaluation under Off-normal Condition for Concrete Storage Cask of Spent Fuels
한국방사성폐기물학회 학술대회
2017 .01
-
Validation of the fuel rod performance analysis code FRIPAC
Nuclear Engineering and Technology
2019 .01
-
Criticality Safety Study for Loss of Single Fuel Rod From WH 14 Type Fuel
한국방사성폐기물학회 학술대회
2018 .01
-
핵연료집합체 기계적특성 시험시설 구축과 기능시험
한국압력기기공학회 논문집
2016 .06
-
Simplified Beam Model of Spent Nuclear Fuel Rod
한국방사성폐기물학회 학술대회
2018 .01
이 논문의 저자 정보
최근 본 자료
댓글(0)
0