Iterative behavior of diffusion theory flux eigenvalue neutronics problems

Technical Report · Tue May 01 00:00:00 EDT 1979

DOI:https://doi.org/10.2172/6266919· OSTI ID:6266919

Vondy, D. R.; Fowler, T. B.

Information is presented about the iterative behavior of selected reactor neutronics problems applying the finite-difference diffusion theory approximation to neutron transport. Several problems were solved different ways to examine the effects of variations in the iteration procedures on the rate of convergence. Estimates of dominant error vector eigenvalues and their dependence on the inner iteration procedures are shown. This information is important because it serves as a guide for code development and application, lacking a thorough theoretical analysis of the iterative behavior.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 6266919
• Report Number(s): ORNL/TM-6843; TRN: 79-017396
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
NEUTRON TRANSPORT THEORY
ITERATIVE METHODS
REACTOR LATTICES
NEUTRON TRANSPORT
FINITE DIFFERENCE METHOD
NEUTRON DIFFUSION EQUATION
NEUTRAL-PARTICLE TRANSPORT
NUMERICAL SOLUTION
RADIATION TRANSPORT
TRANSPORT THEORY
220100* - Nuclear Reactor Technology- Theory & Calculation
654003 - Radiation & Shielding Physics- Neutron Interactions with Matter