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Title: Gas-Cooled FAst Breeder Reactor. Quarterly progress report, August 1, 1978--October 31, 1978. [Core assembly; fuels and materials; thermohydraulics; kinetics; shielding; systems and components; safety; alternate fuel cycles]

Abstract

Progress is summarized in the areas of GCFR fuel, fuel blanket, and control assemblies; development of the pressure equalization system for GCFR fuel; fuels and materials development; fuel blanket, and control rod analyses and development; nuclear analysis and reactor physics for GCFR core design; shielding requirements for the GCFR; reactor engineering to assess the thermal, hydraulic, and structural performance of the core and the core support structure; plant systems control; systems engineering; development of reactor components, including reactor vessel, control and locking mechanisms, fuel handling equipment, core support structure, shielding assemblies, main helium circulator, steam generator, and auxiliary circulator; development of a helium circulator test facility; reactor safety, environment, and risk analyses, including planning and support of an in-pile and out-of-pile safety test program; nuclear island engineering design; and development of alternate fuel cycles.

Publication Date:
Research Org.:
General Atomics, San Diego, CA (United States)
OSTI Identifier:
6528819
Report Number(s):
GA-A-15144
DOE Contract Number:  
EY-76-C-03-0167-023
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; GCFR REACTOR; DESIGN; ENGINEERING; BLOWERS; BREEDING BLANKETS; CONTROL ELEMENTS; FUEL ASSEMBLIES; FUEL CYCLE; FUEL ELEMENTS; REACTOR CHARGING MACHINES; REACTOR COMPONENTS; REACTOR CORES; REACTOR KINETICS; REACTOR MATERIALS; REACTOR SAFETY; RESEARCH PROGRAMS; SHIELDING; STEAM GENERATORS; SUPPORTS; BOILERS; BREEDER REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; GAS COOLED REACTORS; GCFR TYPE REACTORS; HELIUM COOLED REACTORS; KINETICS; MECHANICAL STRUCTURES; REACTORS; SAFETY; VAPOR GENERATORS; 210500* - Power Reactors, Breeding

Citation Formats

. Gas-Cooled FAst Breeder Reactor. Quarterly progress report, August 1, 1978--October 31, 1978. [Core assembly; fuels and materials; thermohydraulics; kinetics; shielding; systems and components; safety; alternate fuel cycles]. United States: N. p., 1978. Web. doi:10.2172/6528819.
. Gas-Cooled FAst Breeder Reactor. Quarterly progress report, August 1, 1978--October 31, 1978. [Core assembly; fuels and materials; thermohydraulics; kinetics; shielding; systems and components; safety; alternate fuel cycles]. United States. https://doi.org/10.2172/6528819
. 1978. "Gas-Cooled FAst Breeder Reactor. Quarterly progress report, August 1, 1978--October 31, 1978. [Core assembly; fuels and materials; thermohydraulics; kinetics; shielding; systems and components; safety; alternate fuel cycles]". United States. https://doi.org/10.2172/6528819. https://www.osti.gov/servlets/purl/6528819.
@article{osti_6528819,
title = {Gas-Cooled FAst Breeder Reactor. Quarterly progress report, August 1, 1978--October 31, 1978. [Core assembly; fuels and materials; thermohydraulics; kinetics; shielding; systems and components; safety; alternate fuel cycles]},
author = {},
abstractNote = {Progress is summarized in the areas of GCFR fuel, fuel blanket, and control assemblies; development of the pressure equalization system for GCFR fuel; fuels and materials development; fuel blanket, and control rod analyses and development; nuclear analysis and reactor physics for GCFR core design; shielding requirements for the GCFR; reactor engineering to assess the thermal, hydraulic, and structural performance of the core and the core support structure; plant systems control; systems engineering; development of reactor components, including reactor vessel, control and locking mechanisms, fuel handling equipment, core support structure, shielding assemblies, main helium circulator, steam generator, and auxiliary circulator; development of a helium circulator test facility; reactor safety, environment, and risk analyses, including planning and support of an in-pile and out-of-pile safety test program; nuclear island engineering design; and development of alternate fuel cycles.},
doi = {10.2172/6528819},
url = {https://www.osti.gov/biblio/6528819}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Wed Nov 01 00:00:00 EST 1978},
month = {Wed Nov 01 00:00:00 EST 1978}
}