Published August 1984
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On the solution of a D2O-benchmark problem using RSYST
Description
Using RSYST a program cycle for corephysics calculations has been compiled and successfully tested in solving the D2O-Benchmarkproblem of IAEA. In Cell calculations ANISN has been used, a reprogrammed version of Origen for burnup and Citation as diffusion code for XY-core calculations. Calculations for multigroup constants including cell calculations have been done in parallel to RSYST with AMPXII too, which showed nearly the same results, small differences certainly due to use of different databases and/or numerical methods. The stepwise proof of data and programs led to numerous parameter calculations the resuslts of which are reported too. (orig.)
Availability note (English)
MF available from INIS under the Report Number.Abstract (German)
Unter Anwendung von RSYST wurde ein Programmzyklus fuer corephysikalische Rechnungen erstellt, seine Anwendung durch Loesung des D2O-Benchmarkproblems der IAEA erfolgreich getestet. Fuer die Zellrechnungen wurde ANISN benutzt, fuer die Abbrandrechnungen Origen, und der Diffusionscode Citation fuer die zweidimensionalen Ganzcore-Rechnungen. Die Bestimmung der Multigruppen-Konstanten einschliesslich der Zellrechnungen erfolgte zu Testzwecken parallel zu RSYST auch mit AMPXII, wobei geringe Ergebnisunterschiede durch unterschiedliche Datenbasen und/oder numerische Methoden verursacht sein duerften. Die schrittweise erfolgende Pruefung von Daten und Programmen fuehrte zu umfangreichen Parameteruntersuchungen, ueber die gleichfalls berichtet wird. (orig.)
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Additional details
Additional titles
- Original title (German)
- Zur Loesung eines D
Publishing Information
- Imprint Pagination
- 74 p.
- Report number
- Juel--1948
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 16014566
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BENCHMARKS; BURNUP; FRJ-1 REACTOR; GROUP CONSTANTS; HEAVY WATER MODERATED REACTORS; MODERATELY ENRICHED URANIUM; MULTIGROUP THEORY; NEUTRON DIFFUSION EQUATION; R CODES; REACTOR CELLS; REACTOR CORES; REACTOR PHYSICS; SLIGHTLY ENRICHED URANIUM
- Descriptors DEC
- ACTINIDES; COMPUTER CODES; CROSS SECTIONS; ELEMENTS; ENRICHED URANIUM; ENRICHED URANIUM REACTORS; ISOTOPE ENRICHED MATERIALS; MATERIALS; METALS; POOL TYPE REACTORS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; TRANSPORT THEORY; URANIUM; WATER COOLED REACTORS; WATER MODERATED REACTORS