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Volumn 82, Issue 3, 2005, Pages 195-200

Semi-mechanistic analytical model for radiation embrittlement and re-embrittlement data analysis

Author keywords

Modeling; Primary embrittlement and re embrittlement after annealing; Radiation damage mechanism

Indexed keywords

ANNEALING; DATA REDUCTION; EMBRITTLEMENT; FORGINGS; WELDS;

EID: 11344285996     PISSN: 03080161     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.ijpvp.2004.09.002     Document Type: Article
Times cited : (28)

References (9)
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    • Radiation damage of nuclear power plant pressure vessel steels
    • ISBN: 0-89448-564-4
    • Alekseenko NN, Amaev A, Gorynin I, Nikolaev VA. Radiation damage of nuclear power plant pressure vessel steels. ISBN: 0-89448-564-4
    • Alekseenko, N.N.1    Amaev, A.2    Gorynin, I.3    Nikolaev, V.A.4
  • 2
    • 0020830244 scopus 로고
    • On the dominant mechanism of irradiation embrittlement of reactor pressure vessel steel
    • G.R. Odette On the dominant mechanism of irradiation embrittlement of reactor pressure vessel steel Scr Mater 17 1983 1183-1188
    • (1983) Scr. Mater. , vol.17 , pp. 1183-1188
    • Odette, G.R.1
  • 3
    • 3242723864 scopus 로고
    • PNAE G-7-002-86
    • PNAE G-7-002-86 Energoatomizdat 1989 102-106
    • (1989) Energoatomizdat , pp. 102-106
  • 4
    • 0012272284 scopus 로고    scopus 로고
    • A review of formulas for predicting irradiation embrittlement of reactor pressure vessel materials
    • European Commission, EUR 16455, EN-AMES Report No. 6
    • Petrequin P. A review of formulas for predicting irradiation embrittlement of reactor pressure vessel materials. European Commission, EUR 16455, EN-AMES Report No. 6; 1996
    • (1996)
    • Petrequin, P.1
  • 5
    • 11344263552 scopus 로고
    • Irradiation embrittlement of RPV steel: Mechanisms, models and data correlation: An international review, 2
    • ASTM STP 909, Philadelphia, PA
    • Odette GR, Lucas GE. Irradiation embrittlement of RPV steel: Mechanisms, models and data correlation: An international review, 2. ASTM STP 909, Philadelphia, PA; 1986
    • (1986)
    • Odette, G.R.1    Lucas, G.E.2
  • 6
    • 0003620506 scopus 로고    scopus 로고
    • Improved embrittlement correlations for reactor pressure vessel steels
    • NUREG/CR-6551 November
    • E.D. Eason J.E. Wright G.R. Odette Improved embrittlement correlations for reactor pressure vessel steels NUREG/CR-6551 November 1998
    • (1998)
    • Eason, E.D.1    Wright, J.E.2    Odette, G.R.3
  • 7
    • 11344277277 scopus 로고    scopus 로고
    • Advanced model for the VVER RPV material re-embrittlement assessment
    • IAEA expert meeting on irradiation embrittlement, UK
    • A. Kryukov D. Erak Y. Shtrombakh L. Debarberis R. Ahlstrand M. Valo et al. Advanced model for the VVER RPV material re-embrittlement assessment IAEA expert meeting on irradiation embrittlement, UK 2002
    • (2002)
    • Kryukov, A.1    Erak, D.2    Shtrombakh, Y.3    Debarberis, L.4    Ahlstrand, R.5    Valo, M.6
  • 8
    • 11344277806 scopus 로고    scopus 로고
    • Manufacturing history and mechanical properties of japanese materials provided for the International Atomic Energy Agency
    • IAEA October CRP Sub-Committee of the Atomic Energy Research Committee of the Japan Welding Engineering Society
    • IAEA Manufacturing history and mechanical properties of japanese materials provided for the International Atomic Energy Agency October 1996 CRP Sub-Committee of the Atomic Energy Research Committee of the Japan Welding Engineering Society
    • (1996)


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.