Account for uncertainties of control measurements in the assessment of design margin factors
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V. Dementiev
Abstract
This paper considers two interrelated issues and – proceeding from the conditional probability concept and Bayes’ statistical theorem – suggests a universal method to process measured data with account of prior information available. To assure reliable reactor operation, at the design stage it is suggested to account for errors of subsequent control measurements while assessing the engineering margin factors for reactor parameters to be measured.
Kurzfassung
Um einen zuverlässigen Reaktorbetrieb zu gewährleisten, ist es notwendig schon in der Designphase bei der Festlegung der Fehlerspanne für im Betrieb zu messende Reaktorparameter die Fehler dieser Messung zu berücksichtigen. Hierzu wird ein Verfahren vorgestellt.
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© 2013, Carl Hanser Verlag, München
Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Editorial
- Selected contributions to the XXIInd symposium of the Atomic Energy Research organization
- Technical Contributions/Fachbeiträge
- Fuel cycles of WWER-440: results of basic design modification
- Use of erbium as burnable poison for VVER reactors
- The estimation of the control rods absorber burn-up during the VVER-1000 operation
- The main characteristic of the evolution project SuperVVER with spectrum shift regulation
- Automatic loading pattern optimization tool for Loviisa VVER-440 reactors
- Uncertainties of the neutronic calculations at core level determined by the KARATE code system and the KIKO3D code
- The reactor dynamics code DYN3D and its trigonal-geometry nodal diffusion model
- Comparison of sensitivity and uncertainty in Gd and Er containing fuels for VVER-1000 using TSUNAMI-2D
- Contribution of the number of measured data to calculation uncertainty in the worth of VVER control rods
- A comparison of the FA's models with the detailed and simplified description in the MCU code calculations
- Account for uncertainties of control measurements in the assessment of design margin factors
- Results of precision calculations of three-dimensional power density in VVER-1000 core with feedbacks using MCU code
- CFD analysis of temperature deviations in Gd assembly heads
- Application of statistical uncertainty and sensitivity evaluations to a PWR LBLOCA analysis calculated with the code ATHLET. Part 1: uncertainty analysis
- Post test calculations of a severe accident experiment for VVER-440 reactors by the ATHLET code
- The impact on the competence on severe accidents following the Fukushima event
Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Editorial
- Selected contributions to the XXIInd symposium of the Atomic Energy Research organization
- Technical Contributions/Fachbeiträge
- Fuel cycles of WWER-440: results of basic design modification
- Use of erbium as burnable poison for VVER reactors
- The estimation of the control rods absorber burn-up during the VVER-1000 operation
- The main characteristic of the evolution project SuperVVER with spectrum shift regulation
- Automatic loading pattern optimization tool for Loviisa VVER-440 reactors
- Uncertainties of the neutronic calculations at core level determined by the KARATE code system and the KIKO3D code
- The reactor dynamics code DYN3D and its trigonal-geometry nodal diffusion model
- Comparison of sensitivity and uncertainty in Gd and Er containing fuels for VVER-1000 using TSUNAMI-2D
- Contribution of the number of measured data to calculation uncertainty in the worth of VVER control rods
- A comparison of the FA's models with the detailed and simplified description in the MCU code calculations
- Account for uncertainties of control measurements in the assessment of design margin factors
- Results of precision calculations of three-dimensional power density in VVER-1000 core with feedbacks using MCU code
- CFD analysis of temperature deviations in Gd assembly heads
- Application of statistical uncertainty and sensitivity evaluations to a PWR LBLOCA analysis calculated with the code ATHLET. Part 1: uncertainty analysis
- Post test calculations of a severe accident experiment for VVER-440 reactors by the ATHLET code
- The impact on the competence on severe accidents following the Fukushima event
