Published August 1975
| Version v1
Report
MIT solid blanket design studies
Creators
Description
A DT cycle tokamak reactor is assumed having a major radius of 10.5 meters and a minor radius of 3.5 meters yielding an inside torus surface area of 1450 m2. Two design thermal power outputs are examined. 2059 MW(t) for an energy multiplication of 1.42 and 1450 MW(t) for an energy multiplication of 1.0. Geometric and neutronic design analyses are presented for a blanket with LiAlO2 pellets. The blanket response under normal operating conditions is discussed
Additional details
Publishing Information
- Imprint Title
- Proceedings of the magnetic fusion energy blanket and shield workshop. A technical assessment. Vol. II
- Imprint Pagination
- p. 753-828.
- Report number
- ERDA--76/117/2
Conference
- Title
- technology workshop.
- Acronym
- Blanket/power systems for fusion reactors
- Dates
- 29 Mar 1976.
- Place
- Upton, New York, United States of America (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 8311804
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALUMINIUM OXIDES; BREEDING BLANKETS; GEOMETRY; LITHIUM; NEUTRON REACTIONS; SPECIFICATIONS; THERMONUCLEAR REACTORS
- Descriptors DEC
- ALKALI METALS; ALUMINIUM COMPOUNDS; BARYON REACTIONS; CHALCOGENIDES; ELEMENTS; HADRON REACTIONS; MATHEMATICS; METALS; NUCLEAR REACTIONS; NUCLEON REACTIONS; OXIDES; OXYGEN COMPOUNDS; REACTOR COMPONENTS