Published April 1996
| Version v1
Journal article
Application of the surface-mobility stress corrosion cracking mechanism to nuclear materials
Description
The surface-mobility stress corrosion cracking mechanism is of recent development, and one of its most promising properties, besides that of being a deterministic model, is that it allows the prediction of crack velocities at any temperature, if the value at a given temperature is known. This is particularly important when crack velocities as low as 1.10-12 m s-1 or even lower are relevant, as it happens in nuclear pressure vessels, nuclear repositories, nuclear steam generators, etc. (orig.)
Additional details
Publishing Information
- Journal Title
- Journal of Nuclear Materials
- Journal Volume
- 229
- Journal Issue
- 1-3
- Journal Page Range
- p. 139-148.
- ISSN
- 0022-3115
- CODEN
- JNUMAM
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 27047068
- Subject category
- S36: MATERIALS SCIENCE; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- AUSTENITIC STEELS; EMBRITTLEMENT; PRESSURE VESSELS; RADIOACTIVE WASTE STORAGE; REACTOR COMPONENTS; REVIEWS; SILVER ALLOYS; STAINLESS STEELS; STEAM GENERATORS; STEAM TURBINES; STRESS ANALYSIS; STRESS CORROSION; TURBINE BLADES
- Descriptors DEC
- ALLOYS; BOILERS; CARBON ADDITIONS; CHEMICAL REACTIONS; CONTAINERS; CORROSION; DOCUMENT TYPES; EQUIPMENT; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; MACHINERY; MANAGEMENT; STEELS; STORAGE; TRANSITION ELEMENT ALLOYS; TURBINES; TURBOMACHINERY; VAPOR GENERATORS; WASTE MANAGEMENT; WASTE STORAGE