Distributions of neutron flux from (p, n) reaction on the liquid lead target for accelerator driven subcritical reactor (ADSR)

Abstract

This paper presents the results of calculating the distributions of neutron flux in an accelerator driven subcritical reactor (ADSR) with thorium fuel. The simulated ADSR consists of 90 fuel rods and 10 graphite reflector rods. All objects are placed in liquid lead. MCNP5 program is used to calculate energy distributions of the neutron flux, axial distributions and radial distributions inside the core of the ADSR. The results show that the neutron fluxes of 250, 450, 600 and 850 angles are similar; axial distributions of neutron flux decrease gradually; the neutron fluxes are the largest between 0.3 and 0.5 MeV. The radial distributions of neutron flux decrease gradually from center, and the largest value is between 30 and 40 cm. The results also show that the neutron fluxes are different with different radii. The results are important for the design and operation of the ADSR.

Analyzing the Neutron Parameters in the Accelerator Driven Subcritical Reactor Using the Mixture of Molten Pb-Bi as Both Target and Coolant

“…There have been many proposals and calculations using liquid lead as an interactive target and coolant [12][13][14][15][16][17].…”