Influence of nuclear data uncertainties on reactor core calculations
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M. Klein
Abstract
To investigate the influence of nuclear data uncertainties on reactor core calculations systematically, the sampling based uncertainty and sensitivity software package SUSA developed at GRS was extended for the use with nuclear covariance data. Varied nuclear data are generated randomly corresponding to the uncertainty information from the covariance matrices. After performing a large number of calculations with these data, the results are statistically evaluated; this can be done not only for integral, but also for local output quantities like the assembly power distribution. The method is applied to multi-group Monte Carlo calculations stationary states of the PWR MOX/UO2 core transient benchmark, and to corresponding nodal diffusion calculations. Unexpectedly large uncertainties result for the radial power distribution. The uncertainties in the nodal results agree very well with those in the Monte Carlo reference results; thus, it is possible to apply the random sampling method to determine the influence of nuclear data uncertainties on transient core calculations.
Kurzfassung
Um den Einfluss von Unsicherheiten in den nuklearen Daten auf Reaktorberechnungen systematisch zu untersuchen, wurde das in der GRS entwickelte Sampling-basierte Programm SUSA zur Anwendung mit nuklearen Kovarianzdaten erweitert. Aus diesen werden variierte nukleare Daten zufällig erzeugt. Nach der Durchführung einer großen Anzahl von Berechnungen mit diesen nuklearen Daten werden die Ergebnisse statistisch ausgewertet; dies ist nicht nur für integrale, sondern auch für lokale Ergebnisgrößen möglich. Die Methode wird mit Monte-Carlo-Rechnungen für den stationären Zustand des DWR-MOX/UO2-Kerntransienten-Benchmarks sowie entsprechende nodale Diffusionsrechnungen angewandt. Für die radiale Leistungsverteilung ergeben sich unerwartet große Unsicherheiten. Die Unsicherheiten in den nodalen Ergebnissen stimmen sehr gut mit denen in den Monte-Carlo-Referenzlösungen überein; damit wird es möglich, die Sampling-Methode auch zur Bestimmung des Einflusses nuklearer Datenunsicherheiten auf Transientenberechnungen zu bestimmen.
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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
