Investigation of the optimal material type and dimension for spallation targets using simulation methods

سال انتشار: 1393
محل انتشار: فصلنامه فیزیک تئوری و کاربردی، دوره: 8، شماره: 1
کد COI اختصاصی: JR_JTAP-8-1_009
زبان مقاله: انگلیسی
تعداد مشاهده: 267

نویسندگان

Department of Physics, Talca University, Talca, Chile

چکیده

Accelerator-driven systems are extensively developed to generate neutron sources for research, industrial, andmedical plans. Different heavy elements are utilized as spallation targets to produce spallation neutrons. Computationalmethods are efficiently utilized to simulate neutronic behavior of a spallation target. MCNPX 2.6.0 is used as a powerfulcode based on Monte Carlo stochastic techniques for spallation process computation. This code has the ability totransport different particles using different physical models.In this paper, MCNPX has been utilized to calculate the leaked neutron yield from Pb, lead-bismuth eutectic (LBE), W,Ta, Hg, U, Th, Sn, and Cu cylindrical heavy targets. The effects of the target thickness and diameter on neutron yieldvalue have been investigated via the thickness and diameter variations between 5 to 30 cm and 5 to 20 cm, respectively.Proton-induced radionuclide production into the targets as well as leaked neutron spectra from the targets has beencalculated for the targets of an optimum determined dimension. The 1-GeV proton particle has been selected to inducespallation process inside the targets. The 2-mm spatial FWHM distribution has been considered for the 1-mA protonbeam.Uranium target produced the highest leaked neutron yield with a 1.32 to 3.7 factor which overweighs the others. Adimension of 15 × 60 cm is suggested for all the cylindrical studied spallation targets. Th target experienced the highestalpha emitter radionuclide production while lighter elements such as Cu and Sn bore the lowest radiotoxicity. LBE liquidspallation target competes with the investigated solid targets in neutronic point of view while has surpass than volatileliquid Hg target.

کلیدواژه ها

Simulation; Spallation neutron yield; Radionuclide production; MCNPX 2.6.0 code

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