Flux Distribution in a Reactor Consisting of a Spherical Shell of Fuel in a Infinite Moderator.

摘要

This memo gives the general method of computing the critical equation and the flux in the center of the 'flux trap' in an idealized high-flux reactor based on the flux-trap principle. The fuel is concentrated in a spherical infinitely thin shell in an infinite moderator. The shell emits F fission neutrons for each thermal neutron absorbed. Absorption at eithermal energies, both in the fuel and the moderator, are neglected. In this model the fission neutron emitted from the shell slow down according to the age kernel and the diffuse according to diffusion theory, with the boundary condition created by the 'black' shell. Numerical results obtained from the general method described in this memo will be issued in a subsequent momo, 'Fluxes Obtainable in a Flux-Trap Reactor,' CF-58-1-4.