Published February 1985 | Version v1
Book Metadata-only

Reactor technology utilizing the thorium fuel cycle

Creators

  • 1. General Atomic Co., San Diego, CA (USA)

Description

A survey of thorium fuel utilization programs indicates that the principal experience with thorium utilization is associated with high temperature gas-cooled reactors (HTGR's). Recent results of utilization and development work for thorium usage in HTGR's in the U.S. are reviewed, including work on coated-particle fuels, nuclear performance of thorium-fueled Fort St. Vrain nuclear power plant, HTGR core designs utilizing 20 % uranium/thorium fuel, development work on the ''back end'' of the HTGR fuel cycle, and scenarios for future deployment of nuclear power involving ''thorium symbiosis'' between advanced thermal converters and fast breeder reactors. (author)

Additional details

Publishing Information

Publisher
Atomic Energy Soc. of Japan.
Imprint Place
Tokyo (Japan)
Imprint Title
Proceedings of the Japan-U.S. seminar on thorium fuel reactors
Imprint Pagination
319 p.
Journal Page Range
p. 228-242.

Conference

Title
Japan-U.S. seminar on thorium fuel reactors.
Dates
18-22 Oct 1982.
Place
Nara (Japan).

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
17083322
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
REACTOR TECHNOLOGY; REPROCESSING; THORIUM; THORIUM CYCLE; USES; VRAIN REACTOR
Descriptors DEC
ACTINIDES; ELEMENTS; ENRICHED URANIUM REACTORS; FUEL CYCLE; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HTGR TYPE REACTORS; METALS; POWER REACTORS; REACTORS; SEPARATION PROCESSES

Optional Information

Notes
Imprint:Back title: Thorium fuel reactors.