Analysis of reactor lattice and core parameters in view of nuclear data modifications
Abstract
A detailed assessment of the JEFF 3.1 and ENDF/B VII.0 nuclear data libraries with the KANEXT code system has been performed on each level of the reactor simulation steps.
This allowed for the sensitivity estimation of the lattice and core parameters to changes in nuclide and specific reaction cross section. The direct calculation of cross section data influence, in particular for specific reaction types, is possible due to the unique substitution feature of the group constant module GRUCAL.
Further on, the different impact of several reaction types on the lattice versus core calculation points out the “engineering uncertainty” using the two major libraries for the identical problem.
MCNP(X) and KANEXT cell models can be mutually adjusted such that differences between stochastic and deterministic data processing can be identified.
The current analysis emphasizes, that the two major nuclear data libraries JEFF 3.1 and ENDF/B VII.0 exhibit to some extent compensation of deviations rather than reliable integral data calculation.
On a special type of a fast reactor application we show that exchange of JEFF 3.1 and ENDF/B VII.0 cross sections introduce large discrepancies. A major part is attributed to the inelastic cross section. Further investigated discrepancies concerning the capture and the fission cross section in the epithermal energy range might be also a concern for LWR which was beyond the scope of the current study.
Kurzfassung
Die Auswirkung von Unterschieden in den zwei großen Wirkungsquerschnittsauswertungen JEFF 3.1 und ENDF/B VII.0 auf integrale Kenngrößen wurde mit dem Programmsystem KANEXT auf Gitter- und Core-Ebene untersucht. Dies erlaubt eine Abschätzung der Sensitivitäten von Gitter- und Corekenngrößen in Bezug auf Änderungen von Nuklid- und einzelnen Wirkungsquerschnitten. Hierfür wurde eine besondere Option des Gruppenkonstantenmoduls GRUCAL benutzt, mit der gezielt Wirkungsquerschnittsdaten ganzer Nuklide oder einzelner Reaktionen ausgetauscht werden können.
Der Einfluss der Unterschiede lässt sich dadurch direkt und auf allen Ebenen der Wirkungsquerschnittserzeugung bestimmen. Bis zu einem gewissen Grad wurde dies auch mit dem Monte Carlo Code MCNPX durchgeführt, um Unterschiede zwischen den deterministischen und stochastischen Verfahren aufzuzeigen.
Die Untersuchung der JEFF 3.1 und ENDF/B VII.0 Bibliotheken für einen schnellen Reaktor zeigt, dass die ähnlichen Ergebnisse auf Core-Ebene eher mit Fehlerkompensation als mit der Qualität der Wirkungsquerschnittsdaten erklärt werden können.
Aus der eingehenden Untersuchung der Reaktionstypen geht der inelastische Wirkungsquerschnitt als Hauptursache hervor. Zudem werden auch Unterschiede für den Einfang- und den Spaltquerschnitt im epithermischen Energiebereich gezeigt, die gegebenenfalls auch für LWR Berechnungen von Bedeutung sind.
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© 2011, Carl Hanser Verlag, München
Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Editorial
- Plant behaviour and coupling with reactor physics
- Technical Contributions/Fachbeiträge
- Multi-scale coupled code systems: from coarse-mesh to high-fidelity LWR core calculations
- Development of multi-physics code systems based on the reactor dynamics code DYN3D
- Development of the coupled 3D neutron kinetics/thermal-hydraulics code DYN3D-HTR for the simulation of transients in block-type HTGR
- Influence of nuclear data uncertainties on reactor core calculations
- Analysis of reactor lattice and core parameters in view of nuclear data modifications
- A complementary Doppler Broadening formalism and its impact on nuclear reactor simulation
- Experiences with the coupled code system S3R/RELAP5-3D in training simulators
- BWR transient analysis with the coupled code system S3K/RELAP5
- The development and assessment of TRACE model for Lungmen ABWR
Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Editorial
- Plant behaviour and coupling with reactor physics
- Technical Contributions/Fachbeiträge
- Multi-scale coupled code systems: from coarse-mesh to high-fidelity LWR core calculations
- Development of multi-physics code systems based on the reactor dynamics code DYN3D
- Development of the coupled 3D neutron kinetics/thermal-hydraulics code DYN3D-HTR for the simulation of transients in block-type HTGR
- Influence of nuclear data uncertainties on reactor core calculations
- Analysis of reactor lattice and core parameters in view of nuclear data modifications
- A complementary Doppler Broadening formalism and its impact on nuclear reactor simulation
- Experiences with the coupled code system S3R/RELAP5-3D in training simulators
- BWR transient analysis with the coupled code system S3K/RELAP5
- The development and assessment of TRACE model for Lungmen ABWR
