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AbstractAbstract
[en] Irradiation may induce substantial evolution in mechanical behaviour of steels, these evolutions being favourable or unfavourable, depending on the phenomena considered and on the type of mechanical damage. Effects of irradiation are listed as well as their influence on the mechanical behaviour of the stainless steel to be considered for the internals of PWRs. Considering all the possible effects, it can be shown that loss of ductility is a major one. We have proposed to study on a practical case the possible damaging modes that may be due to this reduction in allowable strain. In the particular geometry of a screw, submitted to an axial load, it is shown that failure by loss of ductility must be envisioned but only in the core, and for strain controlled loadings. (orig.)
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Secondary Subject
Source
Stuttgart Univ. (Germany). Staatliche Materialpruefungsanstalt; [560 p.]; 1994; p. 41.1-41.18; 20. MPA seminar: Safety and reliability of plant technology with special emphasis on nuclear technology - approaches to lifetime extension; 20. MPA-Seminar: Sicherheit und Verfuegbarkeit in der Anlagentechnik mit dem Schwerpunkt Kerntechnik - Massnahmen zur Absicherung des Langzeitbetriebes; Stuttgart (Germany); 6-7 Oct 1994; Available from TIB Hannover: RN 5417(20,2)
Record Type
Miscellaneous
Literature Type
Conference
Country of publication
CARBON ADDITIONS, CHEMICAL REACTIONS, DEFORMATION, DOCUMENT TYPES, ENRICHED URANIUM REACTORS, HIGH ALLOY STEELS, IRON ALLOYS, IRON BASE ALLOYS, MECHANICAL PROPERTIES, NEUTRON FLUENCE, POWER REACTORS, RADIATION EFFECTS, REACTORS, STEELS, TENSILE PROPERTIES, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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