METAL-WATER REACTIONS: II. AN EVALUATION OF SEVERE NUCLEAR EXCURSIONS IN LIGHT WATER REACTORS
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)
- NSA Number:
- NSA-14-002139
- OSTI ID:
- 4210189
- Report Number(s):
- GEAP-3178
- Country of Publication:
- United States
- Language:
- English
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