Published March 2002 | Version v1
Journal article

Thermally activated deformation of irradiated reactor pressure vessel steel

Description

Temperature and strain rate change tensile tests were performed on two VVER 1000-type reactor pressure vessel welds with different contents of nickel in unirradiated and irradiated conditions in order to determine the activation parameters of the contribution of the thermally activated deformation. There are no differences of the activation parameters in the unirradiated and the irradiated conditions as well as for the two different materials. This shows that irradiation hardening preferentially results from a friction hardening mechanism by long-range obstacles

Additional details

Identifiers

PII
S0022311502007092;

Publishing Information

Journal Title
Journal of Nuclear Materials
Journal Volume
301
Journal Issue
2-3
Journal Page Range
p. 227-232
ISSN
0022-3115
CODEN
JNUMAM

Optional Information

Copyright
Copyright (c) 2002 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.