Energy-differential cross section measurement for the /sup 51/V(n,. cap alpha. )/sup 48/Sc reaction
Ikuo Kanno, J.W. Meadows, Dianne L. Smith
Abstract
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Ikuo Kanno, J.W. Meadows, Dianne L. Smith
Abstract
Open-access reader
The activation method was used to measure cross sections for the /sup 51/V(n,..cap alpha..)/sup 48/Sc reaction in the threshold region, from 5.515 MeV up to 9.567 MeV. Twenty approximately-monoenergetic cross section values were obtained in this experiment. These data points span the energy region at roughly equal intervals. The experimental resolutions were in the range 0.153 to 0.233 MeV (FWHM). The present differential data cover approx. 50% of the total integral response of this reaction for the standard /sup 235/U thermal-neutron-induced-fission neutron spectrum, and approx. 44% of the corresponding response for the standard /sup 252/Cf spontaneous-fission neutron spectrum. Over the range 7.6 to 9.5 MeV the present experimental cross sections are noticeably larger (e.g., by approx. 50% at approx. 8.6 MeV) than the corresponding values from the ENDF/B-V evaluation. From approx. 6.7 to 7.5 MeV, the present values are somewhat below those of ENDF/B-V. At still lower energies the agreement is reasonably good considering the uncertainties introduced by energy scale definition very near the effective threshold where the cross section varies rapidly with neutron energy. Calculated integral cross sections based in part on the present work agree reasonably well within errors with reported integral results, provided that the reported data are renormalized to conform with recently-accepted values for appropriate standard reactions. 70 references.
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The activation method was used to measure cross sections for the /sup 51/V(n,..cap alpha..)/sup 48/Sc reaction in the threshold region, from 5.515 MeV up to 9.567 MeV. Twenty approximately-monoenergetic cross section values were obtained in this experiment. These data points span the energy region at roughly equal intervals. The experimental resolutions were in the range 0.153 to 0.233 MeV (FWHM). The present differential data cover approx. 50% of the total integral response of this reaction for the standard /sup 235/U thermal-neutron-induced-fission neutron spectrum, and approx. 44% of the corresponding response for the standard /sup 252/Cf spontaneous-fission neutron spectrum. Over the range 7.6 to 9.5 MeV the present experimental cross sections are noticeably larger (e.g., by approx. 50% at approx. 8.6 MeV) than the corresponding values from the ENDF/B-V evaluation. From approx. 6.7 to 7.5 MeV, the present values are somewhat below those of ENDF/B-V. At still lower energies the agreement is reasonably good considering the uncertainties introduced by energy scale definition very near the effective threshold where the cross section varies rapidly with neutron energy. Calculated integral cross sections based in part on the present work agree reasonably well within errors with reported integral results, provided that the reported data are renormalized to conform with recently-accepted values for appropriate standard reactions. 70 references.
Key concepts: Physics, Neutron, Nuclear physics, Fission, Neutron temperature, Nuclear reaction, Approx, Energy (signal processing)