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Volumn 36, Issue 6, 1999, Pages 522-534

The occurrence of wear marks on fast reactor fuel pin cladding

Author keywords

Cladding; Contact mark; Design; EBR II reactor; Feasibility studies; Fuel pins; JOYO reactor; Spacer wire; Thermodynamic properties; Thermohydraulic vibration; Wear mark; Wear contact marking mechanism; Wear contact marking range

Indexed keywords

HYDRAULICS; NUCLEAR FUEL CLADDING; THERMODYNAMIC PROPERTIES; VIBRATIONS (MECHANICAL); WEAR OF MATERIALS;

EID: 0032658523     PISSN: 00223131     EISSN: None     Source Type: Journal    
DOI: 10.1080/18811248.1999.9726234     Document Type: Article
Times cited : (11)

References (12)
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  • 2
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  • 3
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    • Post irradiation examination of JOYO Mk-I core fuel
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  • 4
    • 25344476451 scopus 로고
    • Irradiation behavior of initially loaded fuel assemblies for JOYO Mk-II
    • Fukuoka, Japan, J, in Japanese
    • Koizumi, A., et al.: Irradiation behavior of initially loaded fuel assemblies for JOYO Mk-II, Preprint 1986 Fall Meeting of AESJ, Fukuoka, Japan, J30. (1986). [in Japanese].
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  • 5
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  • 6
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  • 7
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    • Wearing test of fuel pin cladding and w'ire in sodium
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    • Nakayama, K., et al.: Wearing test of fuel pin cladding and w'ire in sodium, Preprint 1983 Fall Meeting of AESJ, Sapporo, Japan, H4, (1983), [in Japanese].
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  • 8
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    • Deformation analysis method(III) on fuel pin bundle in wire type fuel assembly
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  • 9
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    • Flow distribution analysis on FBR wire type fuel assembly including deformation of fuel pin bundle
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    • Kiyono, T., et al.: Flow distribution analysis on FBR wire type fuel assembly including deformation of fuel pin bundle, Preprint 1979 Fall Meeting of AESJ. Ibaraki, Japan, B23, (1979), [in Japanese].
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  • 10
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  • 12
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* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.