Abstract
We study primary and secondary reactions induced by 600 MeV proton beams in monolithic cylindrical targets made of natural tungsten and uranium by using Monte Carlo simulations with the Geant4 toolkit (1-3). Bertini intranuclear cascade model, Bi- nary cascade model and IntraNuclear Cascade Li` ege (INCL) with ABLA model (4) were used as calculational options to describe nuclear reactions. Fission cross sections, neu- tron multiplicity and mass distributions of fragments for 238 U fission induced by 25.6 and 62.9 MeV protons are calculated and compared to recent experimental data (5). Time distributions of neutron leakage from the targets and heat depositions are calculated.
Highlights
Some neutrons are absorbed by radiative capture (n,γ)
IntraNuclear Cascade Liege (INCL)/ABLA gives much better results on proton induced fission of 238 U compared to other models
It was obtained that three times more neutrons are produced by 600 MeV protons on the fissile target, according to the MCADS results using INCL/ABLA model
Summary
One of the most important applications of high-energy accelerators is to produce neutrons in protoninduced spallation reactions on extended targets made of heavy materials. Neutrons produced by energetic protons can be used to maintain a chain of nuclear fission reactions in a subcritical assembly of an accelerator-driven system (ADS) for nuclear waste incineration [8, 9]. In all such cases the neutron flux around the spallation target has to be thoroughly quantified. Visualization of a history of one proton and all secondary particles is shown on Fig. 1 After that at the last stage of the reaction an excited compound nucleus undergoes deexcitation by evaporating nucleons or by fission
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