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Volumn 27, Issue 4, 2008, Pages 271-277

A review on the potential use of austenitic stainless steels in nuclear fusion reactors

Author keywords

Austenitic stainless steel; Corrosion behavior; Fusion reactor; Irradiation behavior

Indexed keywords

AUSTENITIC; CORROSION BEHAVIOR; ENGINEERING MATERIALS; FERRITIC/MARTENSITIC STEELS; FIRST WALL; FUSION REACTOR; HIGH POWER DENSITY; IRRADIATION BEHAVIOR; LIQUID WALLS; LOWER COST; NEUTRON WALL LOAD; NUCLEAR FUSION; STRUCTURAL MATERIALS; TECHNOLOGICAL DATABASE;

EID: 53249094035     PISSN: 01640313     EISSN: None     Source Type: Journal    
DOI: 10.1007/s10894-008-9136-3     Document Type: Article
Times cited : (85)

References (79)
  • 64
    • 84916010192 scopus 로고
    • Flow and fracture of metals and alloys in nuclear environments
    • ASTM, Philadelphia, PA
    • W.R. Martin, J.R. Weir, in Flow and fracture of metals and alloys in nuclear environments, ASTM STP 380 (ASTM, Philadelphia, PA, 1965), p. 251
    • (1965) ASTM STP , vol.380 , pp. 251
    • Martin, W.R.1    Weir, J.R.2


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.