Published March 2002
| Version v1
Journal article
Thermally activated deformation of irradiated reactor pressure vessel steel
Creators
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
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Israel
- INIS RN
- 33063100
- Subject category
- S36: MATERIALS SCIENCE;
- Descriptors DEI
- DEFORMATION; FRICTION; PHYSICAL RADIATION EFFECTS; PRESSURE VESSELS; STRAIN HARDENING; STRAIN RATE; TENSILE PROPERTIES; THERMAL STRESSES; WWER-1 REACTOR
- Descriptors DEC
- CONTAINERS; ENRICHED URANIUM REACTORS; HARDENING; MECHANICAL PROPERTIES; POWER REACTORS; PWR TYPE REACTORS; RADIATION EFFECTS; REACTORS; STRESSES; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS
Optional Information
- Copyright
- Copyright (c) 2002 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.