Positron study of radiation embrittlement of steels used in water cooled, water moderated energy reactors

Applied Surface Science

Volumn 252, Issue 9, 2006, Pages 3309-3315

  Slugeň, Vladimír ^a   Zeman, Andrej ^a   Petriska, Martin ^a   Kršjak, Vladimir ^a  

^a SLOVAK UNIVERSITY OF TECHNOLOGY   (Slovakia)

Author keywords

Neutron embrittlement; Positron annihilation; Reactor pressure steels; WWER

Indexed keywords

COPPER; DEGRADATION; HEAT TREATMENT; MICROSTRUCTURE; PARAMETER ESTIMATION; PRESSURE VESSELS; RADIATION; RAPID THERMAL ANNEALING; STEEL; WATER COOLED REACTORS;

NEUTRON EMBRITTLEMENT; REACTOR PRESSURE STEELS; WWER;

POSITRONS;

EID: 32644477035     PISSN: 01694332     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.apsusc.2005.08.076     Document Type: Article

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