Estimation of experimental uncertainty for physical measurements based on the start-up data of the latest VVER-1000 units
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S. Tsyganov
Abstract
During the last decades several new VVER-1000 units of different projects have been commissioned. At some of them similar initial fuel loadings were implemented. To determine experimentally neutron-physics characteristics of those units almost similar physical start-up test programs were performed and measurement equipment were also similar. The paper presents the analysis of some result of neutron-physics characteristics that were carried out during physics start-up of VVER-1000 units with similar initial fuel loading. The subject of analysis is an estimation of experimental uncertainties. An effort is made to consider individual test result as a single random realization of universal set. It is assumed the analysis of individual results spread helps to estimate general inherent uncertainty of experiment.
Kurzfassung
Bei vielen der in den letzten Jahren in Betrieb genommenen WWER-1000 Reaktoren wurden ähnliche Erstbeladungen, Inbetriebnahme-Programme und Messtechniken verwendet. Die Ergebnisse der messtechnischen Aufnahme von neutronenphysikalischen Kennzahlen in der Inbetriebnahme-Phase werden verglichen. Dabei wird das Hauptaugenmerk auf die Unsicherheit der experimentellen Messungen gelegt und einzelne Messungen als zufällige Einzelwerte einer Grundmenge betrachtet. Des Weiteren wird angenommen, dass die Untersuchung der Streubreite der Einzelergebnisse hilft, die allgemeine Genauigkeit der Versuchsreihe abzuschätzen.
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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
