Measurement of Neutron Capture Cross-Sections of 105Pd with keV-Neutrons Produced by Using a Pulsed Proton Beam

Measurements of keV-neutron capture cross sections and capture gamma-ray spectra of105Pd

“…A small 6 Li-glass detector with a diameter of 5.0 mm and a thickness of 5.0 mm was located at a distance of 30 cm from the neutron source and at an angle of 3.2 • with respect to the proton beam direction in the 15-100 keV measurement. A large 6 Li-glass detector with a diameter of 102 mm and a thickness of 6.4 mm was placed at a distance of 457 cm from the neutron source and at an angle of 1.9 • in the 585 keV measurement. Those angles were determined so as to measure the average energy spectra of neutrons incident on the capture sample.…”

“…The distance was 78.5 cm between the centre of sample and the front surface of the main detector. The spectrometer was set in a heavy shield composed of potassium-free lead, cadmium, borated paraffin, borated polyethylene, and 6 LiH. The signals from the spectrometer were recorded event by event as two-dimensional data of TOF and pulse height (PH).…”

“…They determined the capture cross sections of 105 Pd with errors of about 5%. Ro et al [6] measured the capture cross sections of 105 Pd in the neutron energy region from 15 to 90 keV and at 550 keV with the 3-MV pelletron accelerator at the Research Laboratory for Nuclear Reactors of the Tokyo Institute of Technology. They used the same facility as the present study, but they used a different 105 Pd sample from the present one.…”

“…The incident neutron energy spectra were obtained from the TOF spectra measured with the small or large 6 Li-glass detector for the blank run. Figure 2 shows the normalised incident neutron energy spectra, η(E n ), where E n is the incident neutron energy in the laboratory system.The neutron energy spectra were normalised so Downloaded by [Northeastern University] at 16:20 16 November 2014 that the integration of the spectra with respect to E n was equal to unity.…”

“…Concerning the keV-neutron capture cross sections of 105 Pd, there exist four sets of experimental data [3][4][5][6], and those data were referred to in the evaluations of JENDL-4.0 [7] and ENDF/B-VII.1 [8]. Namely, the calculated results in the evaluations were adjusted so as to reproduce average values of those experimental data.…”