Iterative and direct approaches to the critical dominant eigenfunction in three-dimensional neutron transport

Journal Article · Sun May 01 04:00:00 EDT 1977 · Nucl. Sci. Eng.; (United States)

OSTI ID:7257454

Premuda, F ^[1]; Spiga, G

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1. Comitato Nazionale per l'Energia Nucleare, Bologna

Two methods, one iterative and the other direct, are presented for the solution of the integral transport equation for monoenergetic neutrons in a three-dimensional finite system, made up of isotropically scattering and multiplying inhomogeneous materials. The methods are suggested by the physical characteristics of criticality, seen in the light of the mathematical concept of the dominance of the fundamental positive flux distribution. Additional results concern the lifecycle point of view for neutron chain reactions, the critical importance function, and the uniform convergence of the Neumann series in all subcritical cases.

• OSTI ID: 7257454
• Journal Information: Nucl. Sci. Eng.; (United States), Journal Name: Nucl. Sci. Eng.; (United States) Vol. 63:1; ISSN NSENA
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
CRITICALITY
EIGENFUNCTIONS
FUNCTIONS
ITERATIVE METHODS
KINETICS
MATHEMATICAL MODELS
NEUTRON FLUX
NEUTRON TRANSPORT THEORY
RADIATION FLUX
REACTOR KINETICS
THREE-DIMENSIONAL CALCULATIONS
TRANSPORT THEORY