Calculated Neutron Flux Spectra in Samples Irradiated in a Tray Rod Facility of the Nru Reactor

摘要

Neutron flux spectra in the irradiation of milligram samples of plutonium and uranium oxide in a pneumatic facility of the NRU reactor are deduced and effective 235-U and 239-Pu nuclide absorption and fission cross sections in the spectra are calculated. The values derived are compared with values obtained from a g+rs type analysis and with the values obtained by B. R. Leonard, R. C. Liikala and U. P. Jenquin of Battele-Northwest in their independent consideration of the irradiation. Estimates of the uncertainties in the cross sections due to the uncertainties in the specification of the neutron spectrum for the irradiation are also given. (Author)