Reactor physics analysis for the design of nuclear fuel lattices with burnable poisons
Creators
- 1. Área de Ingeniería en Recursos Energéticos, Universidad Autónoma Metropolitana-Iztapalapa, Av. San Rafael Atlixco 186, Col. Vicentina, 09340 México, D.F. (Mexico)
- 2. Departamento de Fisica y Matematicas, Instituto Politecnico Nacional, Adolfo López Mateos, San Pedro Zacatenco, 07738 México, D.F. (Mexico)
Description
Highlights: ► A fuel rod optimization for the coupled bundle-core design in a BWR is developed. ► An algorithm to minimize the rod power peaking factor is used. ► The fissile content is divided in two factors. ► A reactor physics analysis of these factors is performed. ► The algorithm is applied to a typical BWR fuel lattice. - Abstract: The main goals in nuclear fuel lattice design are: (1) minimizing the rod power peaking factor (PPF) in order that the power level distribution is the most uniform; (2) obtaining a prescribed target value for the multiplication factor (k) at the end of the irradiation in order that the fuel lattice reaches the desired reactivity; and (3) obtaining a prescribed target value for the k at the beginning of the irradiation in order that the reactivity excess is neither a high value (to ease the maneuvering of the control systems) nor a low value (to avoid the penalization of the high cost of the burnable poison content). In this work a simple algorithm to design the burnable poison bearing nuclear fuel lattice is presented. This algorithm is based on a reactor physics analysis. The algorithm is focused on finding the radial distribution of the fuel rods having different fissile and burnable poison contents in order to obtain: (1) an adequate minimum PPF; (2) a prescribed target value of the k at the end of the irradiation; and (3) a prescribed target value of the k at the beginning of the irradiation. This algorithm is based on the factorization of the fissile and burnable poison contents of each fuel rod and on the application of the first-order perturbation theory. The performance of the algorithm is demonstrated with the design of a fuel lattice composed of uranium dioxide (UO2) and gadolinium dioxide (Gd2O3) for boiling water reactors (BWR). This algorithm has been accomplished using HELIOS calculation codes. The results show that this simple algorithm is very efficient and precise.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2011.09.026Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2011.09.026;
- PII
- S0029-5493(11)00819-3;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 241
- Journal Issue
- 12
- Journal Page Range
- p. 5039-5054
- ISSN
- 0029-5493
- CODEN
- NEDEAU
Conference
- Title
- 18. international conference on nuclear engineering
- Acronym
- ICONE-18
- Dates
- 17-21 May 2010
- Place
- Xi'an (China)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 43074075
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNABLE POISONS; BWR TYPE REACTORS; CONTROL SYSTEMS; DESIGN; FACTORIZATION; FUEL ELEMENT CLUSTERS; FUEL RODS; GADOLINIUM OXIDES; MULTIPLICATION FACTORS; OPTIMIZATION; PERTURBATION THEORY; POWER DISTRIBUTION; REACTIVITY; REACTOR LATTICES; REACTOR PHYSICS; SPATIAL DISTRIBUTION; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; DIMENSIONLESS NUMBERS; DISTRIBUTION; ENRICHED URANIUM REACTORS; FUEL ASSEMBLIES; FUEL ELEMENTS; GADOLINIUM COMPOUNDS; MATERIALS; NEUTRON ABSORBERS; NUCLEAR POISONS; OXIDES; OXYGEN COMPOUNDS; PHYSICS; POWER REACTORS; RARE EARTH COMPOUNDS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; THERMAL REACTORS; URANIUM COMPOUNDS; URANIUM OXIDES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2011 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.