Design a computational program to calculate the composition variations of nuclear materials in the reactor operations
Creators
- 1. Department of Nuclear Engineering, Science and Research Branch, Islamic Azad University, Tehran (Iran, Islamic Republic of)
- 2. OCE, Ofogh Consulting Engineering Company, Tehran (Iran, Islamic Republic of)
- 3. Department of Nuclear Engineering, Science and Research Branch, Islamic Azad University, Fars (Iran, Islamic Republic of)
Description
Highlights: ► The atomic densities of light and heavy materials are calculated. ► The solution is obtained using Runge–Kutta–Fehlberg method. ► The material depletion is calculated for constant flux and constant power condition. - Abstract: The present work investigates an appropriate way to calculate the variations of nuclides composition in the reactor core during operations. Specific Software has been designed for this purpose using C#. The mathematical approach is based on the solution of Bateman differential equations using a Runge–Kutta–Fehlberg method. Material depletion at constant flux and constant power can be calculated with this software. The inputs include reactor power, time step, initial and final times, order of Taylor Series to calculate time dependent flux, time unit, core material composition at initial condition (consists of light and heavy radioactive materials), acceptable error criterion, decay constants library, cross sections database and calculation type (constant flux or constant power). The atomic density of light and heavy fission products during reactor operation is obtained with high accuracy as the program outputs. The results from this method compared with analytical solution show good agreements
Availability note (English)
Available from http://dx.doi.org/10.1016/j.anucene.2013.01.029Additional details
Identifiers
- DOI
- 10.1016/j.anucene.2013.01.029;
- PII
- S0306-4549(13)00046-7;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 57
- Journal Page Range
- p. 111-113
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 45112273
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- ACCURACY; ANALYTICAL SOLUTION; COMPUTER CODES; CROSS SECTIONS; DIFFERENTIAL EQUATIONS; FISSION PRODUCTS; NUCLEAR DATA COLLECTIONS; REACTOR CORES; REACTOR OPERATION; RUNGE-KUTTA METHOD; TIME DEPENDENCE
- Descriptors DEC
- CALCULATION METHODS; EQUATIONS; ISOTOPES; ITERATIVE METHODS; MATERIALS; MATHEMATICAL SOLUTIONS; NUMERICAL SOLUTION; OPERATION; RADIOACTIVE MATERIALS; REACTOR COMPONENTS
Optional Information
- Copyright
- Copyright (c) 2013 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.