Published March 2009 | Version v1
Journal article

Power series solution method for solving point kinetics equations with lumped model temperature and feedback

  • 1. Reactor Physics Division, Indira Gandhi Centre for Atomic Research, Kalpakkam, Tamilnadu 603 102 (India)

Description

Point kinetics equations are stiff differential equations, and their solution by the conventional explicit methods will give a stable consistent result only for very small time steps. Since the neutron lifetime in a LMFBR is very short, the point kinetics equations for LMFBRs become even stiffer. In this study the power series solution (PWS) method is applied for solving the point kinetics equations for a typical LMFBR. A Fortran program is developed for accident analysis of LMFBRs with the PWS method for solving the point kinetics and a lumped model for solving the heat transfer equations. A new technique is developed with fixing factor to find out the average temperature at the peak power node (PPN) without performing temperature calculations at all axial nodes in a reactor fuel pin. The temperature at PPN also decides whether the reactor is within the design safety limit (DSL) or it has entered a serious transient that may lead to an accident. The coupled heat transfer and point kinetics models for a peak power node give the average fuel, clad and coolant temperatures. For the transient over power accidents (TOPA), this is the best way for calculating the temperature, with minimum amount of computations. TOPA analyses are carried out with PWS method. It is found that the PWS methodology uses a small number of numerical operations, while the computational time and the accuracy are comparable with the available fast computational tools. This methodology can be used in nuclear reactor simulation studies and accident analysis

Availability note (English)

Available from http://dx.doi.org/10.1016/j.anucene.2008.11.005

Additional details

Identifiers

DOI
10.1016/j.anucene.2008.11.005;
PII
S0306-4549(08)00288-0;

Publishing Information

Journal Title
Annals of Nuclear Energy (Oxford)
Journal Volume
36
Journal Issue
2
Journal Page Range
p. 246-250
ISSN
0306-4549
CODEN
ANENDJ

Optional Information

Copyright
Copyright (c) 2008 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.