Published January 1994
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The numerical analysis of eigenvalue problem solutions in the multigroup diffusion theory
Description
In this paper a general iteration strategy for solving the discrete form of multidimensional neutron diffusion equations is described. Usually the solution method is based on the system of inner and outer iterations. The presented matrix formalism allows us to visualize clearly, how the used matrix splitting influences the structure of the matrix in an eigenvalue problem to be solved as well as the independence between inner and outer iterations within global iterations. To keep the page limit, the present version of the paper consists only with first three of five sections given in the original paper under the same title (which will be published soon). (author). 13 refs
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Additional details
Publishing Information
- Imprint Title
- Reactor Physics and reactor computations
- Imprint Pagination
- 814 p.
- Journal Page Range
- p. 641-653.
- Report number
- INIS-mf--13907
Conference
- Title
- International conference on reactor physics and reactor computations.
- Dates
- 23-26 Jan 1994.
- Place
- Tel Aviv (Israel).
INIS
- Country of Publication
- Israel
- Country of Input or Organization
- Israel
- INIS RN
- 25046125
- Subject category
- S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ITERATIVE METHODS; MANY-DIMENSIONAL CALCULATIONS; NEUTRON DIFFUSION EQUATION; NUMERICAL SOLUTION; RESPONSE MATRIX METHOD
- Descriptors DEC
- CALCULATION METHODS; EQUATIONS; REACTOR KINETICS EQUATIONS