Investigation of the Reaction Cross-Section for Production the Radioactive Isotopes Used in Fabricating The Nuclear Batteries

Abstract

Beta-decay radioactive isotopes have been widely used as a high-energy source in nuclear batteries. The aim of this study is to improve the evaluations of nuclear reactions for the production of some radionuclides with possible use in nuclear batteries. In particular, the 38Ar(n,γ)39Ar, 59Co(n,γ)60Co, 112Cd(n,γ)113mCd, 151Eu(n,γ)152Eu, 153Eu(n,γ) 154Eu, 193Os(n,γ) 194Os and 203Tl(n,γ) 204Tl neutron capture reactions have been studied for an incident neutron energy range from 10-6 eV up to 2 MeV. The evaluations of the capture cross sections are based on the nuclear model calculations with the latest release code EMPIRE-3.2.2 (Malta) and compared with the available experimental ones. The TENDL nuclear data library, which provides the output of TALYS nuclear model code system have been also presented along with the extracted data for some interactions with no experimental support. Simulation of the beta particles transportation and the generated bremsstrahlung intensity through silicon carbide semiconductor has been also investigated.