Neutron production data by (α,n) reaction and spontaneous fission

Neutron yield data by (α,n) reaction and spontaneous fission which are very important for analyzing radiation shielding safety of storage and transportation or safe handling of spent fuel, were collected and evaluated to obtain the recommended values and their accuracy. As for thick target neutron yield from (α,n) reactions, experimental data by Bair and Gomez del Campo, West and Sherwood, Jacobs and Liskien, and Stelson and McGowan were compiled in the present evaluation work. The discrepancies between them are discussed referring available evaluation works by Nakasima and Heaton et al. Neutron yield which have not been obtained experimentally were calculated using the experimental data on (α,n) excitation functions and the stopping powers published by Ziegler. As for neutron yield data from spontaneous fission, recommended values by S. Raman were adopted in the present work. Neutron energy spectra were also collected as well as neutron yields data. These data are compiled in this Data Book with theoretical explanation. Neutron generation data of many kind of materials will be obtained by using this Book. (author)