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Volumn 42, Issue 3, 1999, Pages 438-446

Irradiation assisted mechanical cracking on cladding tubes of control rods in nuclear reactors

Author keywords

Fracture criterion; Inelasticity tensile properties; Iron and steel; Life prediction

Indexed keywords

CRACK INITIATION; ELASTICITY; FRACTURE MECHANICS; IRON ALLOYS; LIFE CYCLE; NEUTRON IRRADIATION; STEEL; STRAIN RATE; STRESS CORROSION CRACKING; SWELLING; TENSILE PROPERTIES; TUBES (COMPONENTS);

EID: 0032644799     PISSN: 13408046     EISSN: None     Source Type: Journal    
DOI: 10.1299/jsmea.42.438     Document Type: Article
Times cited : (7)

References (7)
  • 2
    • 0030263552 scopus 로고    scopus 로고
    • Crack initiating limit for cladding tubes of PWR RCCA rodlets subject to absorber swelling
    • Matsuoka, T., Mori, M., Nakamura, K., Myojin, H. and Nagata, T., Crack Initiating Limit for Cladding Tubes of PWR RCCA Rodlets Subject to Absorber Swelling, JSME International Journal, Series A, Vol. 39, No. 4 (1996), p. 555-564.
    • (1996) JSME International Journal, Series A , vol.39 , Issue.4 , pp. 555-564
    • Matsuoka, T.1    Mori, M.2    Nakamura, K.3    Myojin, H.4    Nagata, T.5
  • 3
    • 0012911059 scopus 로고
    • Deformability of austenitic stainless steels and Ni-base alloys in the core of a boiling and a pressurized water reactor, environmental degradation of materials in nuclear power systems-water reactors
    • Monterey, CA, 1985 American Nuclear Society, Hinsdale, IL
    • Garzarolli, F., Alter, D. and Dewes, P., Deformability of Austenitic Stainless Steels and Ni-Base Alloys in the Core of a Boiling and a Pressurized Water Reactor, Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (Proc. 2nd ANS Int. Symp. Monterey, CA, 1985), American Nuclear Society, (1985), p. 131-137, Hinsdale, IL.
    • (1985) Proc. 2nd ANS Int. Symp. , pp. 131-137
    • Garzarolli, F.1    Alter, D.2    Dewes, P.3


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.