On the evaluation of a fuel assembly design by means of uncertainty and sensitivity measures
-
W. Jäger
and V. H. Sánchez Espinoza
Abstract
This paper will provide results of an uncertainty and sensitivity study in order to calculate parameters of safety related importance like the fuel centerline temperature, the cladding temperature and the fuel assembly pressure drop of a lead-alloy cooled fast system. Applying best practice guidelines, a list of uncertain parameters has been identified. The considered parameter variations are based on the experience gained during fabrication and operation of former and existing liquid metal cooled fast systems as well as on experimental results and on engineering judgment.
Kurzfassung
Dieser Beitrag stellt Ergebnisse einer Unsicherheits- und Sensitivitätsanalyse hinsichtlich der Berechnung sicherheitsrelevanter Parameter wie Brennstoff- und Hüllrohrtemperatur und Druckverlust über das Brennelement, dar. Mit Hilfe von bewährten Methoden wurde eine Liste mit möglichen Unsicherheitsparametern erstellt. Die berücksichtigten Parametervariationen basieren auf Erfahrungsberichten aus Herstellung, Betrieb und auf experimentellen Untersuchungen.
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© 2012, Carl Hanser Verlag, München
Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Simulation of HALDEN IFA-650 loss-of-coolant accidents tests with TRACE
- On the evaluation of a fuel assembly design by means of uncertainty and sensitivity measures
- Best estimate plus uncertainty analysis of LBLOCA for Indian PHWR
- Remarks on boiling water reactor stability analysis – part 1: theory and application of bifurcation analysis
- Upgrading (V)HTR fuel elements for generationIV goals by SiC encapsulation
- Investigation of the Ru-43LV fuel behaviour under LOCA conditions in a CANDU reactor
- PCA-based ANN approach to leak classification in the main pipes of VVER-1000
- Analytical investigation of the properties of the neutron noise induced by vibrating absorber and fuel rods
- Diffusion approximation for certain scattering parameters of the Anli-Güngör phase function
- Calculation of beta induced Bremsstrahlung exposure from therapeutic radionuclide 198Au in tissues, DNA and RNA
- Dosimetric aspects of 103Pd radioactive stent source
- Radiological significance of coal, slag and fly ash samples from the Eastern Black Sea region
Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Simulation of HALDEN IFA-650 loss-of-coolant accidents tests with TRACE
- On the evaluation of a fuel assembly design by means of uncertainty and sensitivity measures
- Best estimate plus uncertainty analysis of LBLOCA for Indian PHWR
- Remarks on boiling water reactor stability analysis – part 1: theory and application of bifurcation analysis
- Upgrading (V)HTR fuel elements for generationIV goals by SiC encapsulation
- Investigation of the Ru-43LV fuel behaviour under LOCA conditions in a CANDU reactor
- PCA-based ANN approach to leak classification in the main pipes of VVER-1000
- Analytical investigation of the properties of the neutron noise induced by vibrating absorber and fuel rods
- Diffusion approximation for certain scattering parameters of the Anli-Güngör phase function
- Calculation of beta induced Bremsstrahlung exposure from therapeutic radionuclide 198Au in tissues, DNA and RNA
- Dosimetric aspects of 103Pd radioactive stent source
- Radiological significance of coal, slag and fly ash samples from the Eastern Black Sea region