METAL-WATER REACTIONS: II. AN EVALUATION OF SEVERE NUCLEAR EXCURSIONS IN LIGHT WATER REACTORS

Technical Report · Mon Jun 15 00:00:00 EDT 1959

DOI:https://doi.org/10.2172/4210189· OSTI ID:4210189

Owens, J. I.

An evaluation of the power and temperature versus time histories of three typical water-cooled and moderated reacters during a nuclear excursion was made by applying a previously reported method of analysis. These reactors are characterized by one of the following types of fuel elements: U - Al alloy, highly enriched, aluminum jacketted, alat plate; U-Zr alloy, highly enriched, zirconium clad, flat plate; and UO/sub 2/, slightly enriched, zirconium clad rods. The validity of the method of analysis was evaluated by comparing the results with experimental data derived from the BORAX I and SPERT I tests. The effects of varying some of the input duta, such as heat transfer coefficients, and of considering various nuclear shutdown mechanisms were also obtained. (auth)

• Research Organization: General Electric Co. Atomic Power Equipment Dept., San Jose, Calif.
• Sponsoring Organization: US Atomic Energy Commission (AEC)
• DOE Contract Number: AT(04-3)-189
• NSA Number: NSA-14-002139
• OSTI ID: 4210189
• Report Number(s): GEAP-3178
• Resource Relation: Other Information: Orig. Receipt Date: 31-DEC-60
• Country of Publication: United States
• Language: English

Related Subjects

REACTOR TECHNOLOGY
ALUMINUM
ALUMINUM ALLOYS
BORAX-1
ENRICHMENT
EXCURSIONS
FUEL CANS
FUEL ELEMENTS
HEAT TRANSFER
INTERMETALLIC COMPOUNDS
PLATES
POWER
REACTORS
SHUTDOWN
SPERT-1
TEMPERATURE
TESTING
URANIUM ALLOYS
URANIUM OXIDES
VARIATIONS
WATER COOLANT
WATER MODERATOR
ZIRCONIUM
ZIRCONIUM ALLOYS