Sensitivity analysis of parameters important to nuclear criticality safety of Castor X/28F spent nuclear fuel cask
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M.J. Leotlela
Abstract
In nuclear criticality safety analysis it is essential to ascertain how various components of the nuclear system will perform under certain conditions they may be subjected to, particularly if the components of the system are likely to be affected by environmental factors such as temperature, radiation or material composition. It is therefore prudent that a sensitivity analysis is performed to determine and quantify the response of the output to variation in any of the input parameters. In a fissile system, the output parameter of importance is the keff. Therefore, in attempting to prevent reactivity-induced accidents, it is important for the criticality safety analyst to have a quantified degree of response for the neutron multiplication factor to perturbation in a given input parameter. This article will present the results of the perturbation of the parameters that are important to nuclear criticality safety analysis and their respective correlation equations for deriving the sensitivity coefficients.
Kurzfassung
Bei der Kritikalitätssicherheitsanalyse wird festgestellt, wie sich verschiedene Komponenten des nuklearen Systems unter gewissen Bedingungen verhalten, insbesondere wenn die Systemkomponenten durch Umweltfaktoren beeinflusst werden können, wie z.B. Temperatur, Strahlung oder Materialzusammensetzung. Mit Hilfe einer Sensitivitätsanalyse sollten deshalb Rückmeldungen auf Schwankungen der Eingangsparameter quantifiziert werden können. In einer spaltfähigen Anordnung ist der Ausgangsparameter keff von besonderer Bedeutung. Zur Vermeidung reaktivitätsinduzierter Unfälle muss das Verhalten des Neutronenmultiplikationsfaktors gegenüber einer Störung in einem gegebenen Eingangsparameter quantitativ bekannt sein. Dieser Beitrag präsentiert die Ergebnisse von Störungen der Parameter, die für die Kritikalitätsanalyse wichtig sind und ihre entsprechenden Korrelationsgleichungen zur Ableitung der Sensitivitätskoeffizienten.
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© 2015, Carl Hanser Verlag, München
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Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Theoretical study of steam condensation induced water hammer phenomena in horizontal pipelines
- Estimation of experimental uncertainty for physical measurements based on the start-up data of the latest VVER-1000 units
- Analysis of SBO ATWS for Maanshan PWR
- Subchannel analysis of Al2O3 nanofluid as a coolant in VMHWR
- The neutronic calculations for some fluids, libraries and structural materials in a hybrid reactor system
- Design and implementation progress of multi-purpose simulator for nuclear research reactor using LabVIEW
- International assessment of application of the Code of Conduct on the Safety of Research Reactors
- 15 MeV proton irradiation effects on Bi-based high temperature superconductors
- Estimation of radiation damage of iron by a reactor gamma spectrum
- Measuring U concentration in solution product of UF6 hydrolysis using a gamma ray densitometer
- Sensitivity analysis of parameters important to nuclear criticality safety of Castor X/28F spent nuclear fuel cask
- Application of UN method to neutron transport equation in slab geometry using HG phase function
- Preparation of human resources for future nuclear energy using FBNR as the instrument of learning
- Technical Note
- Interface network groups
