THE RATIO OF CAPTURE TO FISSION IN $sup 235$U AND $sup 239$Pu.
R.W. Durham, G. C. Hanna, M. Lounsbury, C. B. Bigham, R.G. Hart, R.W. Jones
Abstract
R.W. Durham, G. C. Hanna, M. Lounsbury, C. B. Bigham, R.G. Hart, R.W. Jones
Abstract
Thin samples of uranium and plutonium have been irradiated in the pneumatic carrier of the NRU reactor, and their changes in isotopic composition measured by a mass spectrometer, to obtain information in radiative capture in {sup 235}U at thermal and epithermal neutron energies and on capture and absorption in {sup 239}Pu. The irradiation position, a vacant lattice site of the NRU reactor (natural uranium fuelling) was characterized by a well-moderated high-intensity thermal flux ({approx}2,5 x 10{sup 14}n/cm{sup 2} s) with an epithermal component having a relatively small departure from a 1/E shape and an intensity r of 0.018 (Westcott convention). Two experimental irradiations were carried out, in the first of which a sample of natural uranium was irradiated bare and a sample enriched in {sup 235}U was irradiated under cadmium; the integrated flux was 0.32 n/kb and the neutron temperature 60 deg. C. In the second experiment (0.71 n/kb, 47 deg. C) similar uranium samples were irradiated, and, in addition, samples of {sup 239}Pu 'spiked' with {sup 242}Pu were irradiated in the same capsule. The change in {sup 235}U content of the bare sample relative to the almost constant {sup 238}U gave the integrated flux and, when combined with the measured {sup 236}U production, the value of {alpha} for {sup 235}U. In the cadmium-covered sample, measurement of the {sup 236}U, when combined with subsidiary silver-activation measurements of the epithermal flux, gave a value of the resonance integral for radiative capture in {sup 235}U. The change in {sup 239}Pu and ({sup 240}Pu + {sup 241}Pu) contents relative to the comparatively constant {sup 242}Pu content gave values of {alpha} and absorption cross-section for {sup 239}Pu; corrections for epithermal effects were made by calculation, but they introduce only minor uncertainties. Corrections from the measured values for a Maxwellian neutron distribution to a neutron velocity of 2200 m/s involve uncertainties that are comparable with the experimental errors. (author)
A significance statement is not available in the OpenAlex record.
A contribution statement is not available in the OpenAlex record.
Method details are not available in the OpenAlex metadata.
Findings are not separately available in the OpenAlex metadata.
Limitations are not available in the OpenAlex metadata.
Application details are not available in the OpenAlex metadata.
Thin samples of uranium and plutonium have been irradiated in the pneumatic carrier of the NRU reactor, and their changes in isotopic composition measured by a mass spectrometer, to obtain information in radiative capture in {sup 235}U at thermal and epithermal neutron energies and on capture and absorption in {sup 239}Pu. The irradiation position, a vacant lattice site of the NRU reactor (natural uranium fuelling) was characterized by a well-moderated high-intensity thermal flux ({approx}2,5 x 10{sup 14}n/cm{sup 2} s) with an epithermal component having a relatively small departure from a 1/E shape and an intensity r of 0.018 (Westcott convention). Two experimental irradiations were carried out, in the first of which a sample of natural uranium was irradiated bare and a sample enriched in {sup 235}U was irradiated under cadmium; the integrated flux was 0.32 n/kb and the neutron temperature 60 deg. C. In the second experiment (0.71 n/kb, 47 deg. C) similar uranium samples were irradiated, and, in addition, samples of {sup 239}Pu 'spiked' with {sup 242}Pu were irradiated in the same capsule. The change in {sup 235}U content of the bare sample relative to the almost constant {sup 238}U gave the integrated flux and, when combined with the measured {sup 236}U production, the value of {alpha} for {sup 235}U. In the cadmium-covered sample, measurement of the {sup 236}U, when combined with subsidiary silver-activation measurements of the epithermal flux, gave a value of the resonance integral for radiative capture in {sup 235}U. The change in {sup 239}Pu and ({sup 240}Pu + {sup 241}Pu) contents relative to the comparatively constant {sup 242}Pu content gave values of {alpha} and absorption cross-section for {sup 239}Pu; corrections for epithermal effects were made by calculation, but they introduce only minor uncertainties. Corrections from the measured values for a Maxwellian neutron distribution to a neutron velocity of 2200 m/s involve uncertainties that are comparable with the experimental errors. (author)
Key concepts: Radiochemistry, Irradiation, Uranium, Natural uranium, Neutron flux, Analytical Chemistry (journal), Isotopes of uranium, Chemistry