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Volumn 164, Issue 10, 2009, Pages 647-655

Irradiation hardening of reactor pressure vessel steels due to the dislocation loop evolution

Author keywords

Irradiation hardening; Microstructural evolution modeling

Indexed keywords

ATHERMAL COMPONENTS; DISLOCATION LOOP; DISPLACEMENT CASCADES; DOSE RATE; EXPERIMENTAL DATA; GLIDING DISLOCATIONS; IRRADIATED MATERIALS; IRRADIATION DOSE; IRRADIATION HARDENING; IRRADIATION-INDUCED HARDENING; LOOP FORMATION; LOW POWER; MATERIAL PARAMETER; MODEL RESULTS; ORIGINAL MODEL; PRESSURE VESSEL STEELS; REACTOR PRESSURE VESSEL STEELS;

EID: 70349642477     PISSN: 10420150     EISSN: 10294953     Source Type: Journal    
DOI: 10.1080/10420150903115743     Document Type: Article
Times cited : (24)

References (19)
  • 7
    • 70349634378 scopus 로고
    • Reactor materials program - Microstructural and mechanical response of types 304, 304L, and 308 stainless steels to low temperature neutron irradiation (U WSRC-TR-93-196 TASK 89-023-31
    • Westinghouse Savannah River Company
    • Sindelar, R.L. Reactor materials program - microstructural and mechanical response of types 304, 304L, and 308 stainless steels to low temperature neutron irradiation (U), WSRC-TR-93-196 TASK 89-023-31, Savannah River Tech. Center, Aiken, SC 29808,Westinghouse Savannah River Company, 1993.
    • (1993) Savannah River Tech. Center, Aiken, SC 29808
    • Sindelar, R.L.1
  • 12


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.