CGEX reactor calculation geometric module incorporatet in the MMKFK complex
Description
The CGEX geometric module intended for constructing the particle path in a multi-zone reactor with the arbitrarily arranged hexagonal fuel subassemblies is described. The CGEX geometric module has been developed in conformity with the zone classification adopted in the MMKFK program complex and has standard inlets and outlets. The CGEX module is intended for calculating reactors which are represented in a form of a straight multi-zone cylinder subdivided into layers over the height. The zone boundaries are formed by cylindrical surfaces coaxially arranged in arbitrary order. At the geometric module inlet specified are neutron position, flight direction, optical path, inverse value of full interaction cross section in the zone. The module realizes construction of the path up to the point of a next collision or the point of escape from the system. The time, without account of the translation time, spent for calculating the initial coordinates of a particle depends on a particular geometry and varies from 350 to 550 μs and from 450 to 650 μs for the translators FORTRAN -DUBNA and FORTRAN-GDR, respectively. To check the CGEX efficiency, a comparative calculation of the effective multiplication factor of the cell, using the PRS module as a standard one, has been performed. The calculation results permit to draw conclusions on the correctness of the study and CGEX satisfactory response speed
Availability note (English)
MF available from INIS under the Report Number.Files
16006916.pdf
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Additional details
Additional titles
- Original title (Russian)
- Геометрический модул' CGEX для расчета реакторов в составе комплекса MMKFK
Publishing Information
- Imprint Pagination
- 12 p.
- Report number
- NIIAR--41(606)
INIS
- Country of Publication
- USSR
- Country of Input or Organization
- USSR
- INIS RN
- 16006916
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S99: GENERAL AND MISCELLANEOUS;
- Descriptors DEI
- COMPUTER CALCULATIONS; G CODES; M CODES; MULTIPLICATION FACTORS; NEUTRON TRANSPORT; REACTOR CORES; REACTORS; TOTAL CROSS SECTIONS
- Descriptors DEC
- COMPUTER CODES; CROSS SECTIONS; NEUTRAL-PARTICLE TRANSPORT; RADIATION TRANSPORT; REACTOR COMPONENTS
Optional Information
- Notes
- 7 ref.; 3 figs.; 3 tabs.