Data collection assessment for the human performance analysis in nuclear installations
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M. Farcasiu
Abstract
The purpose of this paper is to provide a good knowledge and understanding on the main factors influencing human performance in complex systems operation. Identification and establishment of the necessary data for human factor performance analysis in a socio-technical context based on the analysis of HRA methods are performed. An evaluation of the techniques used for collecting and characterization of necessary data for HRA (observation, questionnaire, interview, task analysis, change analysis, simulator, expert judgement) is achieved also. The necessary data to perform HRA for the TRIGA reactor operation, for activities of the post-irradiation examination laboratory and activities of the radioactive waste plant treatment from RATEN ICN Pitesti were obtained. Recommendations on how to obtain data and knowledge related to development of methodical framework of HRA data collection, characterization and evaluation are also presented in this paper.
Kurzfassung
Dieser Beitrag stellt die wichtigsten Faktoren zusammen, die das menschliche Verhalten im Betrieb komplexer Systeme beeinflussen. Dazu werden die für eine Human-Factor-Analyse notwendigen Daten identifiziert und in einen sozio-technischen Kontext basierend auf der Anwendung von HRA-Methoden zusammengestellt. Dabei werden auch die Techniken zur Erfassung und Charakterisierung der für die HRA notwendigen Daten (Beobachtung, Fragebogen, Interview, Aufgabenanalyse, Änderungsanalyse, Simulator, Expertenurteil) bewertet. Die Analyse wird am Beispiel des Betriebs des TRIGA-Reaktors, der Tätigkeiten des Laboratoriums für Nachbestrahlungsuntersuchungen und der Tätigkeiten in der Anlage für radioaktive Abfälle von RATEN ICN Pitesti durchgeführt. Empfehlungen zur Erhebung der notwendigen Daten und des notwendigen Wissens werden ebenso wie der methodische Rahmen zur Erhebung, Charakterisierung und Auswertung von HRA-Daten vorgestellt.
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© 2018, Carl Hanser Verlag, München
Articles in the same Issue
- Contents/Inhalt
- Contents
- Technical Contributions/Fachbeiträge
- Porosity evolution study in irradiated UO2 fuel based on fuel matrix swelling
- Data collection assessment for the human performance analysis in nuclear installations
- Abnormal control rod withdrawal analysis for innovative research reactor using PARET-ANL codes
- Improving CANDU performance by using uranium – thorium mixed oxide fuel
- Computation of gamma radioactivity of natural rocks in the vicinity of Antalya province and its effect on health
- Calculation of liquid waste discharge limits for routine discharge of Tehran research reactor
- Thermal hydraulic assessment of a new design of PWR fuel assembly
- Simulation of error in suppression of Xenon oscillations in a WWER-1000 nuclear reactor
- A novel dual-molality densitometer for gauging in annular two phase flows using radial basis function
- Design and construction of toroidal field coil for Taban device
Articles in the same Issue
- Contents/Inhalt
- Contents
- Technical Contributions/Fachbeiträge
- Porosity evolution study in irradiated UO2 fuel based on fuel matrix swelling
- Data collection assessment for the human performance analysis in nuclear installations
- Abnormal control rod withdrawal analysis for innovative research reactor using PARET-ANL codes
- Improving CANDU performance by using uranium – thorium mixed oxide fuel
- Computation of gamma radioactivity of natural rocks in the vicinity of Antalya province and its effect on health
- Calculation of liquid waste discharge limits for routine discharge of Tehran research reactor
- Thermal hydraulic assessment of a new design of PWR fuel assembly
- Simulation of error in suppression of Xenon oscillations in a WWER-1000 nuclear reactor
- A novel dual-molality densitometer for gauging in annular two phase flows using radial basis function
- Design and construction of toroidal field coil for Taban device
