Nodal neutron kinetics model based on nonlinear iteration procedure for LWR analysis
Creators
Description
A 3-dimensional neutron kinetics model based on the analytical nodal method and nonlinear iteration procedure is developed for Light Water Reactor (LWR) transient calculations. The solution procedure is decoupled on a local solution of the nodal equations for two-node problems and global iterations of the coarse-mesh finite-difference method. An orthogonality of the basic functions used for the neutron flux expansion results in an efficient algorithm of the solution of the nodal equations for the two-node problem. The initial system of 8G nodal equations is reduced to a set of G and 2G equations, where G is a number of neutron energy groups. A fully implicit scheme with an analytical treatment of the delayed neutron precursors equations is used for time integration. An adaptive time-step size control procedure based on the time-step doubling technique is applied. The described numerical methods are implemented into the computer code SKETCH-N. The 3D LWR Langenbuch-Maures-Werner (LMW) operational transient and 2D and 3D Boiling Water Reactor (BWR) LRA super-prompt-critical benchmark problems are calculated in order to verify the code. A comparison of the computed results with the solutions obtained by the other nodal computer codes demonstrate fidelity and efficiency of the SKETCH-N code
Additional details
Identifiers
- PII
- S0306454997000789;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 25
- Journal Issue
- 8
- Journal Page Range
- p. 507-528
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- Malaysia
- INIS RN
- 34039628
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BENCHMARKS; BWR TYPE REACTORS; DELAYED NEUTRON PRECURSORS; FINITE DIFFERENCE METHOD; NEUTRON FLUX; NEUTRON TRANSPORT; NODAL EXPANSION METHOD; NUMERICAL SOLUTION; REACTOR KINETICS EQUATIONS; S CODES
- Descriptors DEC
- CALCULATION METHODS; COMPUTER CODES; ENRICHED URANIUM REACTORS; EQUATIONS; ISOTOPES; ITERATIVE METHODS; NEUTRAL-PARTICLE TRANSPORT; NUMERICAL SOLUTION; POWER REACTORS; RADIATION FLUX; RADIATION TRANSPORT; RADIOISOTOPES; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 1998 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.