ARMY GAS-COOLED REACTOR SYSTEMS PROGRAM. FINAL SUMMARY REPORT OF THE GAS- COOLED REACTOR EXPERIMENT-I

Technical Report · Tue Oct 01 04:00:00 EDT 1963

DOI:https://doi.org/10.2172/4134206· OSTI ID:4134206

Initial criticality of the GCRE-I reactor wss achieved on 23 February 1960 andd testing andd evaluation were continued until April 1961. The mission of the GCRE-I was the generation of neutronic and engineering data in support of the design and development of a nuclear energy source for a demonstration low- power gas-cooled, water-moderated power plant. The GCRE reactor was a heterogeneous, fully-enriched uranium-fueled unit operated in a pool of demineralized water which served as the moderator and primary radiological shield. Fuel elements were contained in a tube bundle, or calandria, which separated the fuel from the water moderator and provided passages for the gas coolant. Test operations and experimental evaluations were conducted with two core loadings of different design (one consisting of dispersion plate-type fuel elements and the other of pin-type elements) and two calandriss of similar design (one fabricated of aluminum andd the other of stainless steel). A description of the facility and the test reactor, a full account of the conduct and results of the experimental program, andd a discussion of the operating organization andd philosophy are summarized. A bibliography of reports covering the GCRE program is presented. (auth)

• Research Organization: Aerojet-General Nucleonics, San Ramon, Calif. (US)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• NSA Number: NSA-18-003184
• OSTI ID: 4134206
• Report Number(s): IDO-28598
• Country of Publication: United States
• Language: English

Related Subjects

AGR
ALUMINUM
BIBLIOGRAPHY
CRITICALITY
DISPERSIONS
ELECTRICITY
ENRICHMENT
FABRICATION
FUEL ELEMENTS
FUELS
GAS COOLANT
GCRE-1
IMPURITIES
ION EXCHANGE
Nuclear Criticality Safety Program (NCSP)
OPERATION
PLANNING
PLATES
POWER
POWER PLANTS
REACTOR FUELING
REACTOR TECHNOLOGY
REACTORS
RODS
SHIELDING
STAINLESS STEELS
TESTING
TRANSPORT
TUBES
URANIUM
WATER
WATER MODERATOR
ZONES