Effects of Zr-hydride distribution of irradiated Zircaloy-3 cladding in RIA-simulating pellet-clad mechanical interaction testing

Per Magnusson; Anna-Maria Alvarez Holston; Katja Ammon; Guido Ledergerber; Marcus Nilsson; David Schrire; Klaus Nissen; Jonathan Wright

추천

검색

자료유형: 학술저널

저자정보: Per Magnusson Anna-Maria Alvarez Holston Katja Ammon Guido Ledergerber Marcus Nilsson David Schrire Klaus Nissen Jonathan Wright

저널정보: 한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제50권 제2호

발행연도: 2018.1

수록면: 246 - 252 (7page)

이용수

📌

연구주제

📖

연구배경

🔬

연구방법

🏆

연구결과

초록· 키워드

오류제보하기

A series of simulated reactivity-initiated accident (RIA) tests on irradiated fully recrystallized boilingwater reactor Zircaloy-2 cladding has been performed by means of the expansion-due-to-compression(EDC) test method. The EDC method reproduces fuel pelleteclad mechanical interaction (PCMI) conditionsfor the cladding during RIA transients with respect to temperature and loading rates by out-of-pilemechanical testing. The tested materials had a large variation in burnup and hydrogen content (up to907 wppm). The results of the EDC tests showed variation in the PCMI resistance of claddings withsimilar burnup and hydrogen content, making it difficult to clearly identify ductile-to-brittle transitiontemperatures. The EDC-tested samples of the present and previous work were investigated by lightoptical and scanning electron microscopy to study the influence of factors such as azimuthal variation ofthe Zr-hydrides and the presence of hydride rims and radially oriented hydrides. Two main characteristicswere identified in samples with low ductility with respect to hydrogen content and test temperature:hydride rims and radial hydrides at the cladding outer surface. Crack propagation and failuremodes were also studied, showing two general modes of crack propagation depending on distributionand amount of radially oriented hydrides. It was concluded that the PCMI resistance of irradiatedcladding under normal conditions with homogenously distributed circumferential hydrides is high, withgood margin to the RIA failure limits. To further improve safety, focus should be on conditions causingnonfavorable hydride distribution, such as hydride reorientation and formation of hydride blisters at thecladding outer surface.

참고문헌 (23)

참고문헌 신청

J. Papin / 2002 / Main outcomes from the CABRI test results / Proc. NEA CSNI Topical Meeting on RIA Fuel Safety Criteria 2:61~81

L. Yegorova / 1999 / Data base on the behavior of high burnup fuel rods with Zr-1%Nb cladding and UO2 fuel (VVR Type) under reactivity accident conditions;Reviewof Research Program and Analysis of Results NUREG/IA-0156, vol. 1

T. Nakamura / 1999 / FK test series with high burnup BWR fuel and analytical test program / Proc. of the 23rd NSRR Technical Review Meeting

T. Nakamura / 1994 / Boiling water reactor fuel behaviour at burnup of 26 MWd/kgU under reactivity-initiated accident conditions / Nucl. Technol. 108:45~59

T. Nakamura / 2002 / High burnup BWR fuel behavior under simulated reactivity-initiated accident conditions / Nucl. Technol. 138:246~259

함께 읽어보면 좋을 논문

논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!