Abstract
The project touches upon an issue of U-238 fission reactions and Pu-239 production reactions in subcritical assembly. The experiment took place in November 2014 at the Dzhelepov Laboratory of Nuclear Problems (JINR, Dubna) using PHASOTRON.Data of this experiment were analyzed in Laboratory of Information Technologies (LIT). Four MCNPX models were considered for simulation: Bertini/Dresnen, Bertini/Abla, INCL4/Drensnen, INCL4/Abla. The main goal of the project was to compare the experimental data and simulation results. We obtain a good agreement of experimental data and computation results especially for detectors placed besides the assembly axis. In addition, the U-238 fission reactions are more probable to be observed in the region of a higher particle energy spectrum, located closer to the assembly axis and the particle beam as well and vice versa Pu-239 production reactions were dominant in the peripheral region of geometry.
Highlights
The electronuclear method of neutron generation using a spallation reaction in Accelerator Driven System (ADS) has been studied by many scientist worldwide [1,2,3,4,5,6,7,8,9]
The eciency of the neutron production based on spallation reaction depends on many parameters such as: beam energy, kind of particles and kind and size of target [3, 4, 6]
The calculation results for U-238 ssions reactions are in good accordance to experimental data besides detectors placed on the assembly axis
Summary
The electronuclear method of neutron generation using a spallation reaction in Accelerator Driven System (ADS) has been studied by many scientist worldwide [1,2,3,4,5,6,7,8,9]. The eciency of the neutron production based on spallation reaction depends on many parameters such as: beam energy, kind of particles and kind and size of target [3, 4, 6]. These neutrons can be employed for transmutation of the long-lived isotopes existing in nuclear waste [5, 7, 9] and for nuclear energy production from thorium or spent uranium fuel [1, 2, 8, 9]. This work presents a comparison of experimental data and calculated results predicted by MCNPX code [10]
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