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Comparison of Calculated Results with Experimental Data for the Tritium Production Rates in a Li2O Assembly

R. T. Santoro, R. G. Alsmiller, Jr., J. M. Barnes, T. A. Gabriel

Nuclear Science and Engineering / Volume 105 / Number 3 / Pages 278-289

July 1990

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The Monte Carlo codes MORSE and MCNP have been used to calculate the tritium production from ≈ 14-MeV neutron reactions in a Li2O assembly. Tritium production from neutron reactions with 6Li and 7Li nuclei were calculated along the central axis of a 0.60-m-diam × 0.60-m-long assembly and four additional assemblies where sheets of Type 304 stainless steel and polyethylene were placed in front of the Li2O to simulate first-wall and coolant materials. The calculated data are compared with measured data obtained at the Fusion Neutron Source at the Japan Atomic Energy Research Institute. The calculated data reproduce the measured data in shape, but differ from the measured data by 10 to 20% in the case of 6Li and as much as 30% at some spatial locations for the 7Li tritium production.

 
 
 
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