Impact property degradation of ferritic/martensitic steels after the fast reactor irradiation 'ARBOR 1'

Journal of Nuclear Materials

Volumn 367-370 A, Issue SPEC. ISS., 2007, Pages 544-549

  Petersen, C ^a   Povstyanko, A ^b   Prokhorov, V ^b   Fedoseev, A ^b   Makarov, O ^b   Dafferner, B ^a  

^a KARLSRUHE INSTITUTE OF TECHNOLOGY   (Germany)

^b RESEARCH INSTITUTE OF ATOMIC REACTORS   (Russian Federation)

Author keywords

[No Author keywords available]

Indexed keywords

BRITTLE TRANSITION TEMPERATURE; MARTENSITIC STEELS; POST IRRADIATION IMPACT TESTS; PROPERTY DEGRADATION;

BRITTLENESS; DUCTILITY; FAST REACTORS; FATIGUE OF MATERIALS; FUSION REACTORS; IRRADIATION; NEUTRON FLUX; THERMAL EFFECTS;

FERRITIC STEEL;

EID: 34447545549     PISSN: 00223115     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.jnucmat.2007.03.015     Document Type: Article

References (8)

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2. L.R. Greenwood, R.K. Smither, ANL/FPP/TM-197, 1985.
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8. C. Petersen, ARBOR 2: BOR 60 Irradiation Programme Status Report October 2005, End of irradiation, Internal Report, Fusion 300, 2007.