The modified source iteration method for few-group space-time dependent neutron kinetic equations
Description
Time-dependent formulations of the few-group space-dependent neutron kinetic equations are obtained using fully-implicit (backward-difference) approximations to the time derivatives. The fully-implicit equations can be solved at each time step using iterative procedures similar to those applied in static calculations. Usually, it is traditional source iteration method based on the standard combination of outer and inner iterations. However, as the results of numerical experiments and the presented analysis have shown, convergence rate of this algorithm in the transient calculations is not satisfactory. Modified source iteration method with improved characteristics is presented. Results of the executed analysis and numerical experiments show, that presented method is 10-30 times faster than source iteration method. Such essential increase of the proposed method efficiency is due to faster converging iteration process and analytical presentation of the Neumann series sum for the inhomogeneous equation solution. This method is useful for various techniques of space approximation and permits to use acceleration techniques proved for static calculations
Additional details
Publishing Information
- Imprint Title
- Proceedings of the 1992 topical meeting on advances in reactor physics. Volume 2
- Imprint Pagination
- 618 p.
- Journal Page Range
- p. 2.457-2.468.
- Report number
- CONF-920308--Vol.2
Conference
- Title
- American Nuclear Society (ANS) topical meeting on advances in reactor physics.
- Dates
- 8-11 Mar 1992.
- Place
- Charleston, SC (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23067692
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALGORITHMS; CONVERGENCE; CROSS SECTIONS; DIFFERENTIAL EQUATIONS; EFFICIENCY; EIGENVALUES; FINITE DIFFERENCE METHOD; HOMOGENIZATION METHODS; ITERATIVE METHODS; LWGR TYPE REACTORS; MESH GENERATION; MULTIGROUP THEORY; NEUTRON FLUX; POWER DENSITY; REACTIVITY; REACTOR KINETICS; SPACE DEPENDENCE; TIME DEPENDENCE; TRANSIENTS
- Descriptors DEC
- CALCULATION METHODS; EQUATIONS; GRAPHITE MODERATED REACTORS; KINETICS; NUMERICAL SOLUTION; RADIATION FLUX; REACTORS; TRANSPORT THEORY; WATER COOLED REACTORS