Published December 2011 | Version v1
Journal article

Reactor physics analysis for the design of nuclear fuel lattices with burnable poisons

  • 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.2011.09.026

Additional 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)

Optional Information

Copyright
Copyright (c) 2011 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.