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METAL-WATER REACTIONS: VIII. PRELIMINARY CONSIDERATIONS OF THE EFFECTS OF A ZIRCALOY-WATER REACTION DURING A LOSS OF COOLANT ACCIDENT IN A NUCLEAR REACTOR

J. I. Owens,R.W. Lockhart,D.R. Iltis,K. Hikido-1959-09-30-OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
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TL;DRAbstract

Two preliminary analyses were made to determine the effect of a chemical reaction between steam and the fuel cladding in a nuclear reactor during a severe loss of coolant accident and prior to melting of the cladding. A pressurized water reactor configuration with rod type, Zircaloy-clad, low-enrichinent UO/sub 2/ fuel elements was used to obtain core parameters for the evaluations. The results of the first analysis indicated core conditions such that the addition of chemical reaction heat would aggravate damage to the reactor, and provided a guide for evaluating various relationships and input data to develop an improved methcd of analysis. The second evaluation was somewhat more refined. The results of this analysis provided a preliminary evaluation of core conditions during a severe loss of coolant accident and indicated where additional improvements can be made in the methcd of analysis. It is apparent from the calculations that the heat generated by the oxidation of the Zircaloy s

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Two preliminary analyses were made to determine the effect of a chemical reaction between steam and the fuel cladding in a nuclear reactor during a severe loss of coolant accident and prior to melting of the cladding. A pressurized water reactor configuration with rod type, Zircaloy-clad, low-enrichinent UO/sub 2/ fuel elements was used to obtain core parameters for the evaluations. The results of the first analysis indicated core conditions such that the addition of chemical reaction heat would aggravate damage to the reactor, and provided a guide for evaluating various relationships and input data to develop an improved methcd of analysis. The second evaluation was somewhat more refined. The results of this analysis provided a preliminary evaluation of core conditions during a severe loss of coolant accident and indicated where additional improvements can be made in the methcd of analysis. It is apparent from the calculations that the heat generated by the oxidation of the Zircaloy s

Keywords

Cladding (metalworking)Zirconium alloyCoolantLoss-of-coolant accidentNuclear engineeringNuclear reactor coreMaterials sciencePressurized water reactor

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