Heterogeneous reactor core transport technique using response matrix and collision probability methods
Creators
Description
Highlights: • A computer program HERPAT, Heterogeneous Reactor Particle Transport, is developed. • DP2 Legendre polynomial is used to approximate the surface angular flux. • The integrals are evaluated using macro-band and Carlvik’s method. • The proposed method has a desired performance and guarantees acceptable results. • Efficiency measures the ability to minimize computer execution time and storage requirements. - Abstract: In this paper a whole-core transport technique using response matrix and collision probability (CP) methods is presented for large-scale, highly-heterogeneous reactors. Integral transport method has been used to provide sufficient accuracy for response matrix formation of pin cell sized node with considerably less computational expense. Ray tracing is efficiently applied using macro-bands. For practical application, double P2 (DP2) Legendre polynomial expansion is applied to approximate interface angular flux that is used to couple nodes. The proposed method is based on a sound mathematical foundation and leads to dramatically reduced memory requirements in contrast to the conventional transport method. This method is also applied to several problems such as C5G7, containing mixed oxide (MOX) and UO2 fuel assemblies, to show the effectiveness of the proposed method. The results clearly indicate that the method is quite promising and acceptable
Availability note (English)
Available from http://dx.doi.org/10.1016/j.anucene.2013.06.011Additional details
Identifiers
- DOI
- 10.1016/j.anucene.2013.06.011;
- PII
- S0306-4549(13)00313-7;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 62
- Journal Page Range
- p. 137-143
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 46063375
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Descriptors DEI
- COLLISION PROBABILITY METHOD; FUEL ASSEMBLIES; H CODES; HETEROGENEOUS REACTOR CORES; LEGENDRE POLYNOMIALS; MIXED OXIDE FUELS; NEUTRON TRANSPORT THEORY; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; CALCULATION METHODS; CHALCOGENIDES; COMPUTER CODES; ENERGY SOURCES; FUELS; FUNCTIONS; MATERIALS; MATHEMATICAL SOLUTIONS; NUCLEAR FUELS; NUMERICAL SOLUTION; OXIDES; OXYGEN COMPOUNDS; POLYNOMIALS; REACTOR COMPONENTS; REACTOR CORES; REACTOR MATERIALS; SOLID FUELS; TRANSPORT THEORY; URANIUM COMPOUNDS; URANIUM OXIDES
Optional Information
- Copyright
- Copyright (c) 2013 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.