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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2021.4
- 수록면
- 1,250 - 1,258 (9page)
- DOI
- https://doi.org/10.1016/j.net.2020.09.029
이용수
초록· 키워드
오류제보하기
In this paper, the mechanical performance of cracked surface-coated Zircaloy cladding, which hasdifferent coating materials, coating thicknesses and initial crack lengths, has been investigated. Byanalyzing the stress field near the crack tip, the safety zone range of initial crack length has been decided.
In order to determine whether the crack can propagate along the radial (r) or axial (z) directions, theenergy release rate has been calculated. By comparing the energy release rate with fracture toughness ofmaterials, we can divide the initial crack lengths into three zones: safety zone, discussion zone anddanger zone. The results show that Cr is suitable coating material for the cladding with a thin coatingwhile FeeCreAl have a better fracture mechanical performance in the cladding with thick coating. TheSi-coated and SiC-coated claddings are suitable for reactors with low power fuel elements. Conclusions inthis paper can provide reference and guidance for the cladding design of nuclear fuel elements.
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참고문헌 (33)
참고문헌 신청
Bowen Qiu / 2020 / A review on thermohydraulic and mechanical-physical properties of SiC, FeCrAl and Ti 3 SiC 2 for ATF cladding / Nuclear Engineering and Technology 52(1):1~13
H.G. Kim / 2015 / Application of coating technology on zirconium-based alloy to decrease high-temperature oxidation / ASTM Special Technical Publication :346~369
J. Wang / 2019 / Effectiveness of Cr-coated Zr-alloy clad in delaying fuel degradation for a PWR during a station blackout event / Nucl. Technol 206:467~477
이유호 / 2017 / Mechanical analysis of surface-coated zircaloy cladding / Nuclear Engineering and Technology 49(5):1031~1043
M. Wagih / 2018 / Fuel performance of chromiumcoated zirconium alloy and silicon carbide accident tolerant fuel claddings / Ann. Nucl. Energy 120:304~318
H.G. Kim / 2015 / Application of coating technology on zirconium-based alloy to decrease high-temperature oxidation / ASTM Special Technical Publication :346~369
J. Wang / 2019 / Effectiveness of Cr-coated Zr-alloy clad in delaying fuel degradation for a PWR during a station blackout event / Nucl. Technol 206:467~477
이유호 / 2017 / Mechanical analysis of surface-coated zircaloy cladding / Nuclear Engineering and Technology 49(5):1031~1043
M. Wagih / 2018 / Fuel performance of chromiumcoated zirconium alloy and silicon carbide accident tolerant fuel claddings / Ann. Nucl. Energy 120:304~318
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