Measurement of {sup 233}U fission spectrum-averaged cross sections for some threshold reactions
- Kyoto Univ., Osaka (Japan). Research Reactor Inst.
The {sup 233}U fission spectrum-averaged cross sections for twelve threshold reactions were measured relative to the average cross section of 0.688 {+-} 0.040 mb for the {sup 27}Al(n,{alpha}){sup 24}Na reaction. The reference value was obtained by calculation using the energy dependent cross section in the Japanese Evaluated Nuclear Data Library (JENDL) Dosimetry File and the Watt-type fission spectrum in ENDF/B-VI. General agreement was seen between the measured and the calculated fission-spectrum averaged cross sections. However, there exist discrepancies of more than 10% between the measured and the calculated average cross sections for the {sup 24}Mg(n,p){sup 24}Na, {sup 47}Ti(n,p){sup 47}Sc, and {sup 64}Zn(n,p){sup 64}Cu reactions. The tendencies in the calculated-to-measured ratios are similar to those for {sup 235}U fission spectrum-averaged cross sections the authors previously measured. The measured average cross sections were also applied for the spectrum adjustment of the {sup 233}U fission neutrons using the Neutron Unfolding Package Code (NEUPAC). The adjusted spectrum is close to the Watt-type fission spectrum of {sup 233}U within the uncertainties of the obtained spectrum, although there exist some fluctuations in the ratio spectrum of the adjusted to the Watt-type.
- OSTI ID:
- 55635
- Report Number(s):
- CONF-930809-; ISBN 0-8031-1899-6; TRN: 95:012880
- Resource Relation:
- Conference: 8. ASTM-EURATOM symposium on reactor dosimetry, Vail, CO (United States), 29 Aug - 3 Sep 1993; Other Information: PBD: 1994; Related Information: Is Part Of Reactor dosimetry. ASTM STP 1228; Farrar, H. IV; Lippincott, E.P.; Williams, J.G.; Vehar, D.W. [eds.]; PB: 871 p.
- Country of Publication:
- United States
- Language:
- English
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