Published October 1972
| Version v1
Journal article
Effect of irradiation on the strain rate dependence of type 304 stainless-steel mechanical properties
Creators
Description
High strain rate tensile data have been obtained on Type 304 stainless steel which was irradiated in EBR-II to a maximum fluence of 0.7 × 1022 n/cm2 (E > 0.1 MeV) at a temperature of ∼950°F. Tests were performed over a range of strain rates from 3 × 10−5 to 1 × 101 sec−1 at 800 and 1000°F to provide mechanical properties information for safety analyses for the Fast Flux Test Facility. The results of these tests demonstrate that the strength of irradiated Type 304 stainless steel remains essentially constant with increasing strain rate and the ductility decreases with strain rate at a fluence of 0.2 × 1022 n/cm2 and increases with strain rate at a fluence of 0.7 × 1022 n/cm2.
Additional details
Identifiers
- DOI
- 10.13182/nt72-a31196;
Publishing Information
- Journal Title
- Nuclear Technology
- Journal Volume
- 16
- Journal Issue
- 1
- Series
- Nucl. Technol.
- Journal Page Range
- 308-315
- ISSN
- 0029-5450
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 4042806
- Subject category
- S36: MATERIALS SCIENCE;
- Descriptors DEI
- EBR-2 REACTOR; FAST NEUTRONS; HIGH TEMPERATURE; MECHANICAL PROPERTIES; RADIATION EFFECTS; REACTOR CORES; STAINLESS STEEL-304; STRAINS
- Descriptors DEC
- ALLOYS; BARYONS; BREEDER REACTORS; CHROMIUM-NICKEL STEELS; ELEMENTARY PARTICLES; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FERMIONS; HADRONS; IRON ALLOYS; LIQUID METAL COOLED REACTORS; NEUTRONS; NUCLEONS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SODIUM COOLED REACTORS; STAINLESS STEELS; STEELS
Optional Information
- Notes
- Updated automatically by Metadata and Full-Text Enrichment Agent