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Volumn 41, Issue 12, 2004, Pages 1211-1217

Influence of hydride re-orientation on bwr cladding rupture under accidental conditions

Author keywords

Burst test; BWR type reactors; Cladding; Ductility; High burn up fuel; Hoop strain; Hydride; Light water reactor; Reactivity initiated accident; Zircaloy

Indexed keywords

BURST TEST; BWR TYPE REACTORS; HIGH BURN-UP FUEL; HOOP STRAIN; REACTIVITY-INITIATED ACCIDENT; ZIRCALOGY;

EID: 13244258438     PISSN: 00223131     EISSN: None     Source Type: Journal    
DOI: 10.1080/18811248.2004.9726350     Document Type: Article
Times cited : (27)

References (12)
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  • 4
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  • 5
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    • Combined effect of radiation damage and hydrides on the ductility of Zircaoy-2,'
    • S. B. Wisner, R. B. Adamson, “Combined effect of radiation damage and hydrides on the ductility of Zircaoy-2,'' Nucl. Eng. Des., 185, 33 (1998).
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    • Wisner, S.B.1    Adamson, R.B.2
  • 6
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    • External corrosion of cladding in PWRs
    • H. Stehle, W. Kaden, R. Manzel, “External corrosion of cladding in PWRs,” Nucl. Eng. Des., 33, 155 (1975).
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  • 7
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    • Stress-orientation of hydrides and hydride embrittlement of Zr-2.5 wt% Nb pressure tube alloy
    • R. N. Singh, R. Kishore, SS. Singh, et al., “Stress-orientation of hydrides and hydride embrittlement of Zr-2.5 wt% Nb pressure tube alloy,” J. Nucl. Mater., 325, 26 (2004).
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    • Singh, R.N.1    Kishore, R.2    Singh, S.S.3
  • 8
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    • A simple model for hydrogen re-distribution in zirconium lined fuel cladding
    • I. Takagi, S. Shimada, D. Kawasaki, K. Higashi, “A simple model for hydrogen re-distribution in zirconium lined fuel cladding,” J. Nucl. Sci. Technol., 39[1], 71 (2002).
    • (2002) J. Nucl. Sci. Technol. , vol.39 , Issue.1 , pp. 71
    • Takagi, I.1    Shimada, S.2    Kawasaki, D.3    Higashi, K.4
  • 9
    • 8844286736 scopus 로고
    • Terminal solubility and partitioning of hydrogen in the alpha phase of zirconium, Zircaloy-2 and Zircaloy-4
    • J. J. Kearns, “Terminal solubility and partitioning of hydrogen in the alpha phase of zirconium, Zircaloy-2 and Zircaloy-4,” J. Nucl. Mater., 22, 292 (1967).
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  • 10
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  • 12
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    • Brittle-fracture potential of irradiated Zircaloy-2 pressure tubes
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* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.