A NOTE ON THE RESPONSE OF A CIRCULATING FUEL REACTOR TO RANDOM FLUCTUATION IN FUEL CONCENTRATION
Technical Report
·
OSTI ID:4237181
A simplified model of a uranium -- sodium --beryllium circulating fuel reactor was analyzed to determine the root mean square power and temperature fluctuations due to random variations in the inlet fuel concentration. The results indicate that limits of plus or minus 2% on the fuel concentration should reduce the mean square power excursion, due to this cause, to less than 1/ 2%. The calculations are based on assumptions only, as regards the specification of the statistical nature of the fuel concentration, but the method can be used to obtain more realistic estimates when experimental evidence becomes available. (auth)
- Research Organization:
- Australia. Atomic Energy Commission Research Establishment, Lucas Heights, New South Wales
- NSA Number:
- NSA-13-018641
- OSTI ID:
- 4237181
- Report Number(s):
- AAEC/E-30
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
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