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Volumn 437, Issue 2, 2006, Pages 306-312

The role of irradiation-induced phosphorus segregation in the ductile-to-brittle transition temperature in ferritic steels

Author keywords

Ductile to brittle transition temperature; Ferritic steel; Grain boundary segregation; Neutron irradiation

Indexed keywords

BRITTLENESS; DUCTILITY; FERRITE; GRAIN BOUNDARIES; NEUTRON IRRADIATION; PHOSPHORUS; PRESSURE VESSELS; SEGREGATION (METALLOGRAPHY);

EID: 33749548839     PISSN: 09215093     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.msea.2006.07.114     Document Type: Article
Times cited : (17)

References (25)
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    • Standards of calculation for strength of nuclear power plant equipment and pipelines, PNAE G-7-002-86, M: Energoatomizdat, 1989.
  • 3
    • 85161761463 scopus 로고    scopus 로고
    • U.S. Nuclear Regulatory Commission, Regulatory Guide 1.99, Radiation Embrittlement of Reactor Vessel Materials, Revision 2, Washington, 1988.
  • 4
    • 85168671194 scopus 로고
    • Proceedings of the 13th International Symposium on Effect of Radiation on Materials
    • Brillaud C., Hedin F., and Houssin B. Proceedings of the 13th International Symposium on Effect of Radiation on Materials. ASTM STP 956 (1987) 420-447
    • (1987) ASTM STP , vol.956 , pp. 420-447
    • Brillaud, C.1    Hedin, F.2    Houssin, B.3
  • 7
    • 85161779195 scopus 로고    scopus 로고
    • P. Petrequin, A Review of Formulas for Predicting Irradiation Embrittlement of Reactors Vessel Materials, AMES Report No. 6, 1996.


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.