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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2021.9
- 수록면
- 2,990 - 3,002 (13page)
- DOI
- https://doi.org/10.1016/j.net.2021.03.019
이용수
초록· 키워드
오류제보하기
The mechanical interaction between the fuel pellet and the cladding tube of a nuclear fuel rod is a veryimportant for safety studies as this phenomenon could lead to fuel failure and release of radioactivity. Toinvestigate the ductility of cladding tubes used in WWER type nuclear power plants, several mandreltests were performed in the Centre for Energy Research (EK). This modified mandrel test was used tomodel the mechanical interaction between the fuel pellet and the cladding using a segmented tool. Thetests were conducted at room temperature and at 300 C with inactive as-received and hydrogenatedcladding ring samples. The results show a gradual decrease in ductility as the hydrogen content increases,the ductile-brittle transition was seen above 1500 ppm hydrogen absorbed.
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참고문헌 (2)
참고문헌 신청
Marton Kiraly / 2018 / Evaluation of axial and tangential ultimate tensile strength of zirconium cladding tubes / Nuclear Engineering and Technology 50(3):425~431
M. Kir aly / 2019 / Impact of thermal and chemical treatment on the mechanical properties of E110 and E110G cladding tubes / Nuclear Engineering and Technology 51(2):518~525
M. Kir aly / 2019 / Impact of thermal and chemical treatment on the mechanical properties of E110 and E110G cladding tubes / Nuclear Engineering and Technology 51(2):518~525
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