The VEGA Assembly Spectrum Code
Description
The VEGA is assembly spectrum code, developed as a design tool for producing a few-group averaged cross section data for a wide range of reactor types including both thermal and fast reactors. It belongs to a class of codes, which may be characterized by the separate stages for micro group, spectrum and macro group assembly calculations. The theoretical foundation for the development of the VEGA code was integral transport theory in the first-flight collision probability formulation. Two versions of VEGA are now in use, VEGA-1 established on standard equivalence theory and VEGA-2 based on new subgroup method applicable for any geometry for which a flux solution is possible. This paper describes a features which are unique to the VEGA codes with concentration on the basic principles and algorithms used in the proposed subgroup method. Presented validation of this method, comprise the results for a homogenous uranium-plutonium mixture and a PWR cell containing a recycled uranium-plutonium oxide. Example application for a realistic fuel dissolver benchmark problem , which was extensive analyzed in the international calculations, is also included. (author)
Availability note (English)
Available from INIS in electronic form; Also available from Institute of Nuclear Sciences VINCAFiles
39084549.pdf
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Additional details
Publishing Information
- Publisher
- Institute of Nuclear Sciences VINCA, Belgrade, Yugoslavia
- Imprint Place
- Belgrade (Yugoslavia)
- ISBN
- 86-7306-049-4
- Imprint Pagination
- 12 p.
- Report number
- INIS-RS--1385
Conference
- Title
- Yugoslav Nuclear Society Conference (YUNSC'96), Proceedings
- Original Conference Title
- Konferencija Jugoslovenskog nuklearnog drustva, zbornik radova
- Dates
- 6-9 Oct 1996
- Place
- Belgrade (Yugoslavia)
INIS
- Country of Publication
- Yugoslavia
- Country of Input or Organization
- Yugoslavia
- INIS RN
- 39084549
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENCHMARKS; COLLISION PROBABILITY METHOD; FAST NEUTRONS; FUEL ASSEMBLIES; MIXED OXIDE FUELS; MULTIGROUP THEORY; NEUTRON SPECTRA; NEUTRON TRANSPORT THEORY; THERMAL NEUTRONS; V CODES; VALIDATION
- Descriptors DEC
- BARYONS; CALCULATION METHODS; COMPUTER CODES; ELEMENTARY PARTICLES; ENERGY SOURCES; FERMIONS; FUELS; HADRONS; MATERIALS; MATHEMATICAL SOLUTIONS; NEUTRON TRANSPORT THEORY; NEUTRONS; NUCLEAR FUELS; NUCLEONS; NUMERICAL SOLUTION; REACTOR MATERIALS; SOLID FUELS; SPECTRA; TESTING; TRANSPORT THEORY
Optional Information
- Notes
- 37 refs., 1 figs., 10 tabs, This record replace record 29027935