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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2017.1
- 수록면
- 1,031 - 1,043 (13page)
이용수
초록· 키워드
오류제보하기
A structural model for stress distributions of coated Zircaloy subjected to realistic incore pressure difference,thermal expansion, irradiation-induced axial growth, and creep has been developed in thisstudy. In normal operation, the structural integrity of coating layers is anticipated to be significantlychallenged with increasing burnup. Strain mismatch between the zircaloy and the coated layer, due totheir different irradiation-induced axial growth, and creep deformation are found to be the mostdominant causes of stress. This study suggests that the compatibility of the high temperature irradiationinduced strains (axial growth and creep) between zircaloy and the coating layer and the capability to undergo plastic strain should be taken as key metrics, along with the traditional focus on chemical protectiveness.
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등록된 정보가 없습니다.
참고문헌 (28)
참고문헌 신청
A. M. Yacout / 2013 / Development and Testing of Nanolaminate Coatings for Conventional LWR Cladding / Transaction of TopFuel
AREVA Federal Services, LLC / 2013 / Analysis Report for Enhanced Accident Tolerant Fuels
B. A. Pint / 2
D. A. Bloore / 2013 / Reactor Physics Assessment of Thick Silicon Carbide Clad PWR Fuels
D. M. Carpenter / 2010 / An Assessment of Silicon Carbide as a Cladding Material for Light Water Reactors
AREVA Federal Services, LLC / 2013 / Analysis Report for Enhanced Accident Tolerant Fuels
B. A. Pint / 2
D. A. Bloore / 2013 / Reactor Physics Assessment of Thick Silicon Carbide Clad PWR Fuels
D. M. Carpenter / 2010 / An Assessment of Silicon Carbide as a Cladding Material for Light Water Reactors
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Circumferential steady-state creep test and analysis of Zircaloy-4 fuel cladding
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공간 균질화 된 나노초 레이저 빔을 활용한 지르코늄 합금(Zircaloy-4)의 표면 젖음성 변화 연구
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High-temperature oxidation behaviors of ZrSi2 and its coating on the surface of Zircaloy-4 tube by laser 3D printing
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Thermal creep effects of aluminum alloy cladding on the irradiation-induced mechanical behavior in U – 10Mo/Al monolithic fuel plates
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Effect of Long-term Cooling on the Hydride Reorientation of Non-irradiated Zircaloy-4 Cladding Tube : 1M, 3M & 6M
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Micro-cantilever Tests on Hydride Blister and Zirconium Matrix of Zircaloy-4 Cladding Tube
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Development of Cr cold spray – coated fuel cladding with enhanced accident tolerance
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Effects of Hydride Re-orientation and Hydride Rim on Fracture Energy of Zircaloy-4 Cladding
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Theoretical models of threshold stress intensity factor and critical hydride length for delayed hydride cracking considering thermal stresses
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Electrochemical corrosion study of helium ions implanted Zircaloy-4 in chloride media
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