The energy-integrated neutron yields from deuteron interactions with 10 elemental and a SUS 29 B stainless steel target have been measured at 4, 7 and 10 MeV incident energies. The forward peaks in the angular distributions decrease with increasing atomic number. Neutrons from self-target build-up were observed only for U at Ed = 7 MeV. The flux density spectra of neutrons have been determined for different beam stop materials by using the dosimetry reactions and the SULSA unfolding code. An analysis of the neutron yields and spectra shows that W, Ta and Pt can be recommended as construction materials for D-D sources to optimize the signal-to-background ratio.
ASJC Scopus subject areas
- Nuclear and High Energy Physics