Measurements of thermal neutron cross section and resonance integral for the {sup 237}Np(n,{gamma}){sup 238}Np reaction
- Kyoto Univ., Osaka (Japan)
- Hitachi Ltd., Ibaraki (Japan). Hitachi Works
- Kyoto Univ. (Japan). Dept. of Nuclear Engineering
Making use of a standard neutron spectrum field with a pure Maxwellian distribution at the heavy water thermal neutron facility of the Kyoto University Reactor (KUR), the thermal neutron cross section for the {sup 237}Np(n,{gamma}){sup 238}Np reaction was measured by the activation method, using a high purity Ge detector. The result is 158 {+-} 3 b, which is obtained relative to the reference value of 98.65 {+-} 0.09 b for the {sup 197}Au(n,{gamma}){sup 198}Au reaction. The present value is lower by about 13% than that of the ENDF/B-VI data. The data given by Mughabghab and obtained from JENDL-3 are larger by 11 to 14% than the present measurement. The resonance integral for the {sup 237}Np(n,{gamma}){sup 238}Np reaction was measured with a 1/E standard neutron spectrum in the cavity of the central graphite reflector region between the two-divided cores of the Kinki University Reactor (UTR-KINK), relative to the reference value of 1,550 {+-} 28 b for the {sup 197}Au(n,{gamma}){sup 198}Au reaction. By defining the Cd cut-off energy as 0.5 eV, the present resonance integral is 652 {+-} 24 b, which is in good agreement with the JENDL-3, ENDF/B-VI and Mughabghab data. However, most of the old experimental data are, in general, larger by 24 to 38% than the present measurement.
- OSTI ID:
- 55634
- Report Number(s):
- CONF-930809-; ISBN 0-8031-1899-6; TRN: 95:012879
- 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
Similar Records
Measurement of Absolute Fission Yields in the Fast Neutron-Induced Fission of Actinides: {sup 238}U, {sup 237}Np, {sup 238}Pu, {sup 240}Pu, {sup 243}Am, and {sup 244}Cm by Track-Etch-cum-Gamma Spectrometry
Integral Measurement of the 237Np($n$, γ)238Np Cross Section with Fast Neutrons