EXPERIMENTAL EFFECTIVE FISSION CROSS SECTIONS AND NEUTRON SPECTRA IN A URANIUM FUEL ROD. PART I. NRX URANIUM METAL RODS
Technical Report
·
OSTI ID:4019815
The radial variation of fission rates in U/sup 2//sup 3//sup 3/, U/sup 2/ /sup 3//sup 5/, a nd Pu/sup 2//sup 3//sup 9/ were measured in an NRX rod for two values of fractional epithermal neutron intensity. Cadmium ratios of manganese and indium were obtained. From comparison with calculations and from supporting measurements in the surrounding moderator it is concluded that an excess of neutrons in the region of 0.3 ev over the conventional dE/E model of the slowing down spectrum must be considered. The effective temperature of the thermal component appears to be slightly above the moderator temperature; the temperature excess is probably related to the epithermal intensity. The light water coolant in NRX and its temperature affects the neutron spectrum. (auth)
- Research Organization:
- Atomic Energy of Canada Ltd., Chalk River, Ont.
- NSA Number:
- NSA-15-017742
- OSTI ID:
- 4019815
- Report Number(s):
- CRRP-985-A; AECL-1186
- Country of Publication:
- Canada
- Language:
- English
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