Published 1976
| Version v1
Report
Blanket design for the mirror fusion/fission hybrid reactor
Description
The evolution of the particular blanket concept is described. The geometry of the mirror reactor blanket and the replacement methods employed are discussed. The sub-module design and its thermal-hydraulic considerations are described. The nuclear model geometry and compositions are then described. The nuclear calculational method is discussed as well as the data used. The performance of the blanket fueled with three separate types of fuel is mentioned
Additional details
Publishing Information
- Imprint Title
- Proceedings of US--USSR symposium on fusion--fission reactors
- Imprint Pagination
- p. 27-35.
- Report number
- CONF-760733--
Conference
- Title
- Joint US-USSR symposium on fusion fission reactor.
- Dates
- 13 Jul 1976.
- Place
- Livermore, California, United States of America (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 8316762
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BREEDING; BREEDING BLANKETS; GEOMETRY; HYBRID REACTORS; MAGNETIC MIRRORS; THERMODYNAMICS
- Descriptors DEC
- MATHEMATICS; NUCLEAR FUEL CONVERSION; OPEN PLASMA DEVICES; REACTOR COMPONENTS; THERMONUCLEAR DEVICES