LATTICE PARAMETERS DERIVED FROM NEUTRON DISTRIBUTION
Technical Report
·
OSTI ID:4315620
Radial distributions of U/sup 235/ and natural uranium fissions and of U/ sup 238/ neutron captures were experimentally determined in a variety of cylindrical solid, cored, and internally moderated, natural uranium fuel elements in graphite-modernted lattices. Together with suitable cadmium ratios and thermal flux traverses throughout the lattice cell, the data were reduced to yield the following parameters: thermal utilization, the fast to thermal fission ratio, the U/sup 238/ resonance to thermal capture ratio, and the initial conversion ratio. In terms of the above parameters, the resonance escape probability, and the fast effect, are determined. (auth)
- Research Organization:
- General Electric Co. Hanford Atomic Products Operation, Richland, Wahs.
- NSA Number:
- NSA-12-015016
- OSTI ID:
- 4315620
- Report Number(s):
- A/CONF.15/P/591
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
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