Operating experience feedback from safety significant events at research reactors
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A. M. Shokr
Abstract
Operating experience feedback is an effective mechanism to provide lessons learned from the events and the associated corrective actions to prevent recurrence of events, resulting in improving safety in the nuclear installations. This paper analyzes the events of safety significance that have been occurred at research reactors and discusses the root causes and lessons learned from these events. Insights from literature on events at research reactors and feedback from events at nuclear power plants that are relevant to research reactors are also presented along with discussions. The results of the analysis showed the importance of communication of safety information and exchange of operating experience are vital to prevent reoccurrences of events. The analysis showed also the need for continued attention to human factors and training of operating personnel, and the need for establishing systematic ageing management programmes of reactor facilities, and programmes for safety management of handling of nuclear fuel, core components, and experimental devices.
Kurzfassung
Betriebliche Erfahrungswerte sind ein effektiver Mechanismus um aus sicherheitsrelevanten Ereignissen Lehren zu ziehen und geeignete Korrekturmaßnahmen durchzuführen, die zu einer verbesserten Sicherheit einer kerntechnischen Anlage führen. Dieser Beitrag analysiert sicherheitsrelevante Ereignisse bei Forschungsreaktoren und analysiert Ursachen und aus den Ereignissen gezogene Lehren. Einblicke zu Ereignissen bei Forschungsreaktoren aus der Literatur und Feedback aus Ereignissen bei Kernkraftwerken, die für Forschungsreaktoren relevant sind werden ebenfalls diskutiert. Die Ergebnisse der Analyse zeigen die Bedeutung der Kommunikation sicherheitsrelevanter Informationen und des Austauschs von betrieblichen Erfahrungswerten. Die Analyse zeigt auch die Notwendigkeit der Weiterbildung des Betriebspersonals und der Einführung systematischer Altersmanagementprogramme für Reaktoranlagen, sowie Programme für das Sicherheitsmanagement beim Umgang mit Brennelementen, Kernkomponenten und experimentellen Vorrichtungen.
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© 2015, Carl Hanser Verlag, München
Articles in the same Issue
- Contents/Inhalt
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- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Evaluation of A-dependence of cross-sections for light charged particle production in proton induced reactions at intermediate energies
- Sensitivity study with respect to direction of ADI method during re-flooding in AHWR
- Experimental investigation of thermal mixing phenomena in a tee pipe
- Flow impinging effect of critical heat flux and nucleation boiling heat transfer on a downward facing heating surface
- Operating experience feedback from safety significant events at research reactors
- Review of regulatory requirements relevant to calibration of monitoring instruments in research reactors
- The dust characteristics in the collisional plasma sheath at the presence of external magnetic field
- Shamir Secret Sharing Scheme with Dynamic Access Structure (SSSDAS): case study on nuclear power plant
- Criticality calculations with PN approximation for certain scattering parameters of Anlı-Güngör and Henyey-Greenstein phase functions in spherical geometry
- An analytical approach for a nodal formulation of a two-dimensional fixed-source neutron transport problem in heterogeneous medium
- Evaluation of gross radioactivity in foodstuffs
- Development of gamma spectroscopy employing NaI(Tl) detector 3 inch × 3 inch and readout electronic of flash-ADC/FPGA-based technology
Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Evaluation of A-dependence of cross-sections for light charged particle production in proton induced reactions at intermediate energies
- Sensitivity study with respect to direction of ADI method during re-flooding in AHWR
- Experimental investigation of thermal mixing phenomena in a tee pipe
- Flow impinging effect of critical heat flux and nucleation boiling heat transfer on a downward facing heating surface
- Operating experience feedback from safety significant events at research reactors
- Review of regulatory requirements relevant to calibration of monitoring instruments in research reactors
- The dust characteristics in the collisional plasma sheath at the presence of external magnetic field
- Shamir Secret Sharing Scheme with Dynamic Access Structure (SSSDAS): case study on nuclear power plant
- Criticality calculations with PN approximation for certain scattering parameters of Anlı-Güngör and Henyey-Greenstein phase functions in spherical geometry
- An analytical approach for a nodal formulation of a two-dimensional fixed-source neutron transport problem in heterogeneous medium
- Evaluation of gross radioactivity in foodstuffs
- Development of gamma spectroscopy employing NaI(Tl) detector 3 inch × 3 inch and readout electronic of flash-ADC/FPGA-based technology
