Published October 1975
| Version v1
Report
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Controlled thermonuclear materials technology program. Annual progress report for period ending June 30, 1975
Description
Detailed descriptions are given of research progress in the following areas: (1) microstructure of irradiated 316 stainless steel containing high helium concentrations, (2) temperature and fluence limitations for a type 316 stainless steel CTR first wall, (3) swelling and microstructural changes in irradiated vanadium alloys, (4) mechanical properties of irradiated V-20 wt percent Ti, (5) radiation damage calculations, (6) evaluation of irradiation facilities for CTR materials development, (7) surface studies, compatibility studies, (8) magnet development, (9) EPR design support, and (10) the influence of structural materials on fusion-reactor blanket response. (MOW)
Availability note (English)
MF available from INIS under the Report Number.Files
7226375.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 87 p.
- Report number
- ORNL--5082
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 7226375
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Progress Report
- Descriptors DEI
- ALUMINIUM OXIDES; COMPATIBILITY; CORROSION; LITHIUM ALLOYS; NIOBIUM ALLOYS; RESEARCH PROGRAMS; STAINLESS STEELS; THERMONUCLEAR REACTOR MATERIAL
- Descriptors DEC
- ALLOYS; ALUMINIUM COMPOUNDS; CARBON ADDITIONS; CHALCOGENIDES; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CORROSION RESISTANT ALLOYS; IRON ALLOYS; IRON BASE ALLOYS; OXIDES; OXYGEN COMPOUNDS; STEELS; TRANSITION ELEMENT ALLOYS