GCFR Program in the United States
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--.