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
- 2023.10
- 수록면
- 205 - 214 (10page)
이용수
초록· 키워드
오류제보하기
As the regulations on greenhouse gas emissions at sea become strict, efforts are being made to minimize environmental pollutants emitted from fossil fuels used by ships. Considering the large sizes of ships in conjunction with securing stable supplies of environment-friendly energy, interest in nuclear energy to power ships has been increasing. In this study, the neutron irradiation that occurs during the nuclear reactor operation and its effect on the structural responses of the stiffened-plate structures are investigated. This is done by changing the material properties of DH36 steel according to the research findings on the neutron-irradiated steels and then performing the structural response analyses of the structures using analytical and finite-element numerical solutions. Results reveal the influence of neutron irradiation on the structural responses of the structures. It is shown that both the strength and stiffness of the structures are affected by the neutron-irradiation phenomenon as their maximum flexural stress and deflection are increased with the increase in the amount of neutron irradiation. This implies that strength and stiffness need to be considered in the design of ships equipped with marine nuclear reactors.
목차
ABSTRACT
1. Introduction
2. Material Property Variation of Hull Steel due to the Neutron-Irradiation Phenomenon
3. Stiffened-Plate Structures and Their Analytical and Numerical Solutions
4. Structural Response Analysis of Stiffened-Plate Structures in the Reactor Operation Environment
5. Conclusions
References
참고문헌 (16)
참고문헌 신청
Ahn, S. B., Kim, Y. S., & Kim, J.K. (2002). Tensile behavior characteristics of CANDU pressure tube material degraded by neutron irradiations. Transactions of the Korean Society of Mechanical Engineers A, 26(1), 188–195. https://doi.org/10.3795/ksme-a.200
Clarkson, J. (1965). The elastic analysis of flat grillages: With particular reference to ship structures. Cambridge University Press.
Finnish-Swedish Ice Class Rules (FSICRS). (2008). The structural design and engine output required of ships for navigation in ice. Guidance for ships for navigation in ice.
Gil, Y., Yoo, S., Kim, Y., Oh, J., Byun, Y., Woo, I., Kim, J., & Choi, S. (2014, May 29–30). Concept design and risk assessment of nuclear propulsion ship. In Proceedings of the Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea.
Gravina, J., Blake, J. I. R., Shenoi, R. A., Turnock, S., & Hirdaris, S. (2013). Concepts for a modular nuclear powered containership. 7th International Conference on Ships and Shipping Research, Naples, Italy. http://eprints.soton.ac.uk/id/eprint/351357
Clarkson, J. (1965). The elastic analysis of flat grillages: With particular reference to ship structures. Cambridge University Press.
Finnish-Swedish Ice Class Rules (FSICRS). (2008). The structural design and engine output required of ships for navigation in ice. Guidance for ships for navigation in ice.
Gil, Y., Yoo, S., Kim, Y., Oh, J., Byun, Y., Woo, I., Kim, J., & Choi, S. (2014, May 29–30). Concept design and risk assessment of nuclear propulsion ship. In Proceedings of the Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea.
Gravina, J., Blake, J. I. R., Shenoi, R. A., Turnock, S., & Hirdaris, S. (2013). Concepts for a modular nuclear powered containership. 7th International Conference on Ships and Shipping Research, Naples, Italy. http://eprints.soton.ac.uk/id/eprint/351357
함께 읽어보면 좋을 논문
논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
-
연구용 원자로의 건전성 평가를 위한 수치해석적 중성자 조사 재료변형 예측기법 개발
한국압력기기공학회 논문집
2024 .06
-
Neutron irradiation impact on structural and electrical properties of polycrystalline Al2O3
Nuclear Engineering and Technology
2024 .02
-
Study on Nuclear Test Scheme and Test Results for Safety Neutron Measurement System in Research Reactor
한국방사성폐기물학회 학술대회
2017 .01
-
A Proposal on Evaluation Method of Neutron Absorption Performance to Substitute Conventional Neutron Attenuation Test
방사선방어학회지
2016 .01
-
중성자 조사를 받는 연구용 원자로 내부 구조물의 조사 거동 해석
대한기계학회 춘추학술대회
2018 .04
-
The Effect of Target Material and the Neutron Spectrum on Nuclear Transmutation of Tc and I in Nuclear Reactors
한국방사성폐기물학회 학술대회
2018 .01
-
Electrical characteristics and deep-level transient spectroscopy of a fast-neutron-irradiated 4H–SiC Schottky barrier diode
Nuclear Engineering and Technology
2023 .01
-
Adaptive energy group division in the few-group cross-section generation for full spectrum reactor modeling with deterministic method
Nuclear Engineering and Technology
2024 .06
-
Neutron activation analysis: Modelling studies to improve the neutron flux of Americiume-Beryllium source
Nuclear Engineering and Technology
2017 .06
-
용접잔류응력의 영향을 고려한 원자로 내부구조물 중성자 조사취화 평가
대한기계학회 춘추학술대회
2021 .04
-
Assessment of neutron-induced activation of irradiated samples in a research reactor
Nuclear Engineering and Technology
2023 .03
-
Facility to study neutronic properties of a hybrid thorium reactor with a source of thermonuclear neutrons based on a magnetic trap
Nuclear Engineering and Technology
2020 .11
-
Beryllium oxide utilized in nuclear reactors: Part II: A systematic review of the neutron irradiation effects
Nuclear Engineering and Technology
2023 .02
-
A high-stability neutron generator for industrial online elemental analysis
Nuclear Engineering and Technology
2024 .04
-
Time-frequency analysis of reactor neutron noise under bubble disturbance and control rod vibration
Nuclear Engineering and Technology
2021 .04
-
Monte Carlo simulation and optimization of neutron ray shielding performance of related materials
Nuclear Engineering and Technology
2024 .09
-
Improvement of Switching Speed of a 600-V Nonpunch-Through Insulated Gate Bipolar Transistor Using Fast Neutron Irradiation
Nuclear Engineering and Technology
2017 .01
-
Characterization of a Neutron Beam Following Reconfi guration of the Neutron Radiography Reactor (NRAD) Core and Addition of New Fuel Elements
Nuclear Engineering and Technology
2016 .01
-
Shielding design and analyses of the cold neutron guide hall for the KIPT neutron source facility
Nuclear Engineering and Technology
2018 .01
-
Calibration of digital wide-range neutron power measurement channel for open-pool type research reactor
Nuclear Engineering and Technology
2018 .01
이 논문의 저자 정보
이 논문과 함께 이용한 논문
최근 본 자료
댓글(0)
0
UCI(KEPA) : I410-151-24-02-088291154