Numerical solution of the neutron transport equation using cellular neural networks
Creators
- 1. Department of Mechanical Engineering, Sharif University of Technology, P.O. Box 11365-9567, Tehran (Iran, Islamic Republic of)
Description
Various methods have been used for solving the neutron transport equation in the past, and a number of computer codes have been developed based on these solution methods. This paper describes a novel method for the solution of the steady-state and time-dependent neutron transport equation using the duality between neutronic parameters in the method of characteristic (MOC) and the electrical parameters in the cellular neural networks (CNN). The relevant electrical circuit can be simulated by professional electrical circuit simulator software, HSPICE. This software is used for numerical solution of the transport equation only by preparation of appropriate inputs. This method does not need inner and outer iterations, which is a necessary step in the other deterministic methods. One of the main applications of the proposed method may be the development of a new hardware by VLSI technology for online spatio-temporal calculations of the transport equation for nuclear reactor core. The accuracy and capability of this method are examined in a 2D steady-state problem for a BWR fuel assembly, and a 2D time-dependent TWIGL seed/blanket problem
Availability note (English)
Available from http://dx.doi.org/10.1016/j.anucene.2008.11.003Additional details
Identifiers
- DOI
- 10.1016/j.anucene.2008.11.003;
- PII
- S0306-4549(08)00284-3;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 36
- Journal Issue
- 1
- Journal Page Range
- p. 15-27
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 40045549
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- ACCURACY; BWR TYPE REACTORS; COMPUTER CODES; DUALITY; FUEL ASSEMBLIES; NEURAL NETWORKS; NEUTRON TRANSPORT THEORY; NUMERICAL SOLUTION; SIMULATORS; STEADY-STATE CONDITIONS; TIME DEPENDENCE
- Descriptors DEC
- ANALOG SYSTEMS; ENRICHED URANIUM REACTORS; FUNCTIONAL MODELS; MATHEMATICAL SOLUTIONS; POWER REACTORS; REACTORS; THERMAL REACTORS; TRANSPORT THEORY; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2008 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.