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Volumn 2006, Issue , 2006, Pages

IN-pile SCC growth behavior of type 304 stainless steel in high temperature water at JMTR

Author keywords

[No Author keywords available]

Indexed keywords

IRRADIATION ASSISTED STRESS CORROSION CRACKING (IASCC); LIGHT WATER REACTORS (LWR); POST-IRRADIATION EXAMINATIONS (PIE);

EID: 33845754809     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: 10.1115/ICONE14-89338     Document Type: Conference Paper
Times cited : (3)

References (15)
  • 2
    • 0030420064 scopus 로고    scopus 로고
    • A modeling of radiation induced microstructural evolution under applied stress in austenitic alloys
    • H. Tanigawa, A. Kohyama and Y. Kato, "A Modeling of Radiation Induced Microstructural Evolution under Applied Stress in Austenitic Alloys", J. Nucl. Mater., 239, pp80-84 (1996).
    • (1996) J. Nucl. Mater. , vol.239 , pp. 80-84
    • Tanigawa, H.1    Kohyama, A.2    Kato, Y.3
  • 3
    • 0035400877 scopus 로고    scopus 로고
    • Overview of the OECD halden reactor project
    • C. Vitanza, "Overview of the OECD Halden Reactor Project", Nuclear Engineering and Design 207, pp.207-221 (2001).
    • (2001) Nuclear Engineering and Design , vol.207 , pp. 207-221
    • Vitanza, C.1
  • 5
    • 0035400809 scopus 로고    scopus 로고
    • Achievements and further plans for the OECD Halden reactor project materials programme
    • T. M. Karlsen, "Achievements and further plans for the OECD Halden reactor project materials programme", Nuclear Engineering and Design 207, pp.199-206 (2001).
    • (2001) Nuclear Engineering and Design , vol.207 , pp. 199-206
    • Karlsen, T.M.1


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.