Published 1974
| Version v1
Book
Dose dependence of irradiation creep of Zircaloy-2
Description
Periodic diameter measurements have been carried out on a number of the cold worked Zircaloy-2 pressure tubes in a steam generating heavy water reactor. Sufficient results are now available for statistical treatment, and they can be expressed as a function of the dose. The creep strain can be expressed equally well by two relationships, one involving a linear correlation with the dose and the other, a term of dose to the power of 0.6. After 30 years operation it is predicted that the pressure tube creep strains will be within the range of 1 to 3 percent. Observed differences in creep strain on tubes from different suppliers may be due to texture differences
Additional details
Publishing Information
- Publisher
- American Society for Testing and Materials.
- Imprint Place
- Philadelphia
- Imprint Title
- Properties of reactor structural alloys after neutron or particle irradiation
- Imprint Pagination
- p. 207-217.
Conference
- Title
- Symposium on the effects of radiation on structural materials.
- Dates
- 11 Jun 1974.
- Place
- Gatlinburg, Tennessee, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 7268170
- Subject category
- S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CORRELATIONS; CREEP; FAST NEUTRONS; NEUTRON BEAMS; PHYSICAL RADIATION EFFECTS; PRESSURE TUBES; RADIATION DOSES; SGHWR REACTOR; STRAINS; ZIRCALOY 2
- Descriptors DEC
- ALLOYS; BARYONS; BEAMS; CHROMIUM ADDITIONS; ELEMENTARY PARTICLES; ENRICHED URANIUM REACTORS; FERMIONS; HADRONS; HEAVY WATER MODERATED REACTORS; IRON ADDITIONS; MECHANICAL PROPERTIES; NEUTRONS; NUCLEON BEAMS; NUCLEONS; PARTICLE BEAMS; POWER REACTORS; PRESSURE TUBE REACTORS; RADIATION EFFECTS; REACTORS; THERMAL REACTORS; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; TUBES; WATER COOLED REACTORS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Notes
- Imprint:See ASTM-STP--570; CONF-740651--.