Published September 1987
| Version v1
Report
The development of austenitic stainless steels for fast induced-radioactivity decay
Creators
Description
During the operation of a fusion reactor, the structural material of the first-wall and blanket structure will become highly radioactive from activation by the fusion neutrons. Disposal of this material after the service lifetime will be a difficult radioactive waste-management problem. One way to minimize the disposal problem is to use structural materials in which radioactive isotopes induced by irradiation rapidly decay to levels that allow simplified disposal techniques. We are assessing the feasibility of developing such austenitic stainless steels. 4 refs., 2 figs., 4 tabs
Additional details
Publishing Information
- Imprint Title
- Fusion reactor materials: Semiannual progress report for period ending September 30, 1986
- Journal Page Range
- p. 286-290.
- Report number
- DOE/ER--0313/1
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19070525
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Progress Report
- Descriptors DEI
- AUSTENITIC STEELS; CHEMICAL COMPOSITION; FIRST WALL; LOW-LEVEL RADIOACTIVE WASTES; MICROSTRUCTURE; PROGRESS REPORT; STRESS ANALYSIS; TEMPERATURE DEPENDENCE; TENSILE PROPERTIES
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CRYSTAL STRUCTURE; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; MECHANICAL PROPERTIES; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; STEELS; THERMONUCLEAR REACTOR WALLS; WASTES