Thermal-neutron flux generation by high-energy protons in thick uranium targets

The transport code, HETC, is used to calculate the transport of medium- and low-energy nucleons and pions through fissionable material. One of the purposes of such calculations is to aid in the design of an intense source of low-energy neutrons from medium-energy protons bombarding uranium targets. The transport code incorporates a revised cross section model so that medium-energy pion and nucleon transport calculations in fissionable material may be carried out. (GHT)