Published 1981 | Version v1
Journal article

TRACT reactor blanket study

Description

This paper presents the results of the blanket design of an EPRI-sponsored study for the TRACT reactor to investigate the technical feasibility of building a small fusion commerical power reactor based on the Triggered-Reconnection Compact Toroid (TRACT) confinement concept. Special attention has been given to design areas that are uniquely important to the TRACT reactor as a result of the high maximum neutron wall loading of 37.0 MW/m/sup 2/, the presence of the copper compression coil around the blanket and the requirement for an insulated first wall. The selected blanket, SiC first wall, a water-cooled Li/sub 17/Pb/sub 83b/lanket structure design that supports the cyclic magnet forces, and a PWR type power conversion system. Critical technology issues that are essential for the success of this blanket design are also identified

Additional details

Additional titles

Augmented title (English)
Triggered-reconnection, compact, toroid

Publishing Information

Journal Title
Proc. Symp. Eng. Probl. Fusion Res.
Journal Issue
p. 1855-1858
Series
Proc. Symp. Eng. Probl. Fusion Res.
ISSN
0145-5958

Conference

Title
9. symposium on engineering problems of fusion research.
Dates
26 - 29 Oct 1981.
Place
Chicago, IL (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
14766117
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BREEDING BLANKETS; COMPACT TORUS; ENERGY CONVERSION; FIRST WALL; MATERIALS HANDLING; THERMONUCLEAR REACTORS; TRITIUM
Descriptors DEC
BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CONVERSION; HYDROGEN ISOTOPES; ISOTOPES; LIGHT NUCLEI; NUCLEI; ODD-EVEN NUCLEI; RADIOISOTOPES; THERMONUCLEAR REACTOR WALLS; TORI; YEARS LIVING RADIOISOTOPES

Optional Information

Secondary number(s)
CONF-811040--.