Fast Rigorous Numerical Method for the Solution of the Anisotropic Neutron Transport Problem and the NITRAN System for Fusion Neutronics Application. Pt. 2.

摘要

The I*-method, which is a non-approximative treatment of the neutron balance equations by the use of double-differential cross sections and a generalized angular transfer probability, is realized within the NITRAN system. It is shown, by means of test calculations for assemblies related to fusion reactor neutronics that double-differential cross section data provide substantial progress in transport problems with kinematically complicated reaction channels like (n,2n), (n,n' gamma ), and (n,n' alpha ), because the I*-method is free from kinematic assumptions. The properties of the exponential method to generate the supplementary equations to the SN equations are investigated. (Atomindex citation 11:518005)