EFFECTIVE CROSS-SECTIONS AND NEUTRON FLUX DISTRIBUTIONS IN A NATURAL URANIUM ROD. APPLICATION TO ROD 683
Technical Report
·
OSTI ID:4342816
Effective neutron cross-scctions of U/sup 235/, Pu/sup 239/, Pu/sup 240/ , Pu/ sup 241/, and Xe/sup 135/ and the 2200 mcters per sccond neutron flux distribution are calculated for an NRX natural U metal rod assuming that the neutron flux spectrum in a rod is maintained by a purely Maxwellian incurrent or a Maxwellian incurrent to which is added a l/E component. Results are presented for incurrent temperatures of 20.44, 38, 227 and 427 deg C and for two rod media, the unirradiated rod and a uniformly loaded, irradiated rod. Deviations of our values of the effective cross-sections from those presented in CHRP-680(TNCC(CAN)- 71 illustrate the effects that hardening of the Maxwellian spectrum and self- shielding in the Pu/sup 239/ and Pu/sup 240/ resonance regions have on the cross sections. An application of similar calculations to the analysis of rod 683 irradiation data is also discussed. (auth)
- Research Organization:
- Atomic Energy of Canada Ltd. Chalk River Project, Chalk River, Ont.
- NSA Number:
- NSA-12-003218
- OSTI ID:
- 4342816
- Report Number(s):
- CRT-725; AECL-497
- Country of Publication:
- Canada
- Language:
- English
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