Published 1976 | Version v1
Book

GCFR Program in the United States

Creators

  • 1. General Atomic Co., San Diego, CA

Description

The use of helium rather than sodium as a coolant for fast breeder reactors has a number of advantages. This has led to a significant effort to develop a gas-cooled fast breeder reactor as an alternate to the liquid metal fast breeder reactor. There are three interrelated programs being carried out: an industry program in the U.S. which is supported by a large number of electric utility companies, an ERDA-supported program, and an international program, primarily in Germany and Switzerland. The design of a 300-MW(e) demonstration plant, which is based on high-temperature gas-cooled reactor component and system technology and liquid metal fast breeder reactor fuel and physics technology is described along with the development program which is being carried out

Additional details

Publishing Information

Publisher
American Society of Mechanical Engineers.
Imprint Place
New York
Imprint Title
1976 ASME-ANS international conference on advanced nuclear energy systems
Journal Page Range
p. 307-317.

Conference

Title
ASME-ANS joint international conference on advanced nuclear energy systems.
Dates
13 Mar 1976.
Place
Pittsburgh, PA, USA.

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
9379808
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
GCFR REACTOR; GCFR TYPE REACTORS; RESEARCH PROGRAMS; SPECIFICATIONS; USA
Descriptors DEC
BREEDER REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; GAS COOLED REACTORS; NORTH AMERICA; REACTORS

Optional Information

Notes
Imprint:See CONF-760303--.