Boundary element formulation of fission neutron source problems using only boundary integrals

Author:

Itagaki M.,Brebbia C.A.

Publisher

Elsevier BV

Subject

Applied Mathematics,Computational Mathematics,General Engineering,Analysis

Reference10 articles.

1. Iterative Solution of Elliptic System and Application to the Neutron Diffusion Equation of Reactor Physics;Wachspress,1966

2. Nuclear Reactor Core Analysis Code: CITATION;Fowler;ORNL-TM-2596,1969

3. STEADY-SHIP: A Computer Code for Three-Dimensional Nuclear and Thermal-Hydraulic Analyses of Marine Reactors;Itagaki;JAERI-1309,1988

4. A Timing Comparison Study for Some High Order Finite Element Approximation Procedures and a Low Order Finite Difference Approximation Procedure for the Numerical Solution of the Multigroup Neutron Diffusion Equation

5. Nuclear Reactor Analysis;Henry,1978

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