RITAC: Reactivity Initiated Transient Analysis Code – An overview
- 1. Research Reactor Services Division, Bhabha Atomic Research Centre, Trombay, Mumbai 400 085 (India)
- 2. Theoretical Physics Division, Bhabha Atomic Research Centre, Trombay, Mumbai 400 085 (India)
Description
Highlights: ► A point reactor kinetics code coupled with thermal hydraulics of plate type fuel is developed. ► The code is applicable to the extent of subcooled boiling of coolant. ► Safety analysis of IAEA benchmark reactor core is carried out. ► Results corroborate well with the results available in the literature. - Abstract: A point reactor kinetics code, coupled with thermal hydraulics of plate type fuel, is developed in order to carry out the reactivity initiated transient analysis of a reactor. Point kinetics equations are solved by matrix algebra, which involves piecewise constant approximation (PCA) i.e. the time dependent functions-reactivity and neutron source terms are assumed to be constant within an interval of time. This code is able to simulate various kinds of reactivity insertion like step, ramp, sinusoidal etc. for transient analysis. Effect of reactivity feedback is included into the code. Solution of kinetics equations gives neutronic power and it is then fed into a thermal hydraulic code where thermal energy conservation equations are solved by finite difference method along with Crank–Nicolson technique to find out the fuel, clad and coolant temperatures during transients. Results of the code corroborate well with the benchmark results.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.anucene.2011.11.013Additional details
Identifiers
- DOI
- 10.1016/j.anucene.2011.11.013;
- PII
- S0306-4549(11)00441-5;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 43
- Journal Page Range
- p. 192-207
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 43124915
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S42: ENGINEERING;
- Descriptors DEI
- BENCHMARKS; ENERGY CONSERVATION; FINITE DIFFERENCE METHOD; IAEA; NEUTRON SOURCES; PLATES; REACTIVITY COEFFICIENTS; REACTIVITY INSERTIONS; REACTOR CORES; REACTOR KINETICS; REACTOR KINETICS EQUATIONS; SAFETY ANALYSIS; SUBCOOLED BOILING; THERMAL HYDRAULICS; TIME DEPENDENCE
- Descriptors DEC
- BOILING; CALCULATION METHODS; EQUATIONS; FLUID MECHANICS; HYDRAULICS; INTERNATIONAL ORGANIZATIONS; ITERATIVE METHODS; KINETICS; MATHEMATICAL SOLUTIONS; MECHANICS; NUMERICAL SOLUTION; PARTICLE SOURCES; PHASE TRANSFORMATIONS; RADIATION SOURCES; REACTOR COMPONENTS
Optional Information
- Copyright
- Copyright (c) 2011 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.