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Volumn 53, Issue 6, 2005, Pages 769-773

Effect of irradiation temperature in PWR RPV materials and its inclusion in semi-mechanistic model

Author keywords

Ductile to brittle transition; Embrittlement; Modelling; Reactor pressure vessel steel; Thermal activated processes

Indexed keywords

EMBRITTLEMENT; EXTRAPOLATION; MATHEMATICAL MODELS; MATRIX ALGEBRA; PRESSURE VESSELS; PRESSURIZED WATER REACTORS; RADIATION DAMAGE; THERMAL EFFECTS;

EID: 21344433686     PISSN: 13596462     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.scriptamat.2005.05.026     Document Type: Article
Times cited : (18)

References (13)
  • 1
    • 0012272284 scopus 로고    scopus 로고
    • A review of formulas for predicting irradiation embrittlement of reactor vessel materials
    • EUR 16455, Luxembourg: EC
    • Petrequin P. A review of formulas for predicting irradiation embrittlement of reactor vessel materials, AMES Rep. No. 6, EUR 16455, Luxembourg: EC, 1996.
    • (1996) AMES Rep. No. 6 , vol.6
    • Petrequin, P.1


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.