Published 1968
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Optimal configuration of spatial points in the reactor cell
Description
Optimal configuration of spatial points was chosen in respect to the total number needed for integration of reactions in the reactor cell. Previously developed code VESTERN was used for numerical verification of the method on a standard reactor cell. The code applies the collision probability method for calculating the neutron flux distribution. It is shown that the total number of spatial points is twice smaller than the respective number of spatial zones needed for determination of number of reactions in the cell, with the preset precision. This result shows the direction for further condensing of the procedure for calculating the space-energy distribution of the neutron flux in a reactors cell
Availability note (English)
Available from INIS in electronic form; Also available from the Institute of nuclear sciences VincaAbstract (Serbian)
U radu je odabran raspored prostornih tacaka, optimalan u odnosu na ukupan broj potreban za integraciju reakcija u celiji. Za numericku proveru na jednoj standardnoj celiji reaktora snage koriscen je ranije razijen program VESTERN, koji za racunanje raspodele fluksa koristi metodu verovatnoce sudara. Kako je u radu pokazano, ukupan broj prostornih tacaka dvostruko je manji od odgovarajuceg broj prostornih zona potrebnih za odredjivanje broja reakcija u celiji sa unapred zadatom tacnoscu. Ovakav rezultat pokazuje put ka daljem kondenzovanju postupka za odredjivanje prostorno energetske raspodele fluks u celiji reaktora. (author)Files
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Additional details
Additional titles
- Original title (Serbian)
- optimalni raspored prostornih tacaka u celiji reactora
Publishing Information
- Imprint Place
- Beograd-Vinca (Yugoslavia)
- Imprint Pagination
- 17 p.
- Report number
- INIS-RS--0970
INIS
- Country of Publication
- Yugoslavia
- Country of Input or Organization
- Serbia
- INIS RN
- 38085262
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- COLLISION PROBABILITY METHOD; ENERGY SPECTRA; NEUTRON FLUX; REACTOR CELLS; SPATIAL DISTRIBUTION
- Descriptors DEC
- CALCULATION METHODS; DISTRIBUTION; MATHEMATICAL SOLUTIONS; NUMERICAL SOLUTION; RADIATION FLUX; SPECTRA
Optional Information
- Notes
- 8 figs., 5 refs.
- Secondary number(s)
- IBK--679