A MCNP simulation study of neutronic calculations of spallation targets

Nuclear Technology and Radiation Protection

关键词: MCNPX code;    benchmark;    neutron yield;    spallation target;   

DOI  :  10.2298/NTRP1302128F

来源: DOAJ

【 摘 要 】

The accelerator driven system is an innovative reactor which is beingconsidered as a dedicated high-level waste burner. The function of thespallation target in accelerator driven system is to convert the incidenthigh-energy particle beam to low-energy neutrons. One of the quantities ofmost interest for practical purposes is the number of neutrons produced perproton in a spallation target. However, this vital value depends not only onthe material, but on the size of the target as well, due to the internuclearcascade. The MCNPX 2.4 code can be used for spallation target computation.Some benchmark results have been compared with MCNPX 2.4 simulations toverify the code's potential for calculating various parameters of anaccelerator driven system target. Using the computation method, neutroninteraction processes such as loss, capture and (n, xn) into a spallationtarget have been studied for W, Ta, Pb, Bi, and LBE spallation targets indifferent target dimensions. With relative errors less than 10%, thenumerical simulation provided by the MCNPX code agrees qualitatively withother simulation results previously carried out, qualifying it for spallationcalculations. Among the studied targets, W and Ta targets resulted in ahigher neutron spallation yield using lesser target dimensions. Pb, Bi, andLBE spallation targets behave similarly regarding the accessible leakedneutron yield on the outer surface of the spallation target. By use of athicker target, LBE can compete with both W and Ta targets regarding theneutron yield parameter.

【 授权许可】

Unknown