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