International assessment of application of the Code of Conduct on the Safety of Research Reactors
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A. M. Shokr
Abstract
The self-assessments performed by thirty-eight countries on application of the Code of Conduct on the Safety of Research Reactors were analyzed and discussed. The results of this analysis were used to identify areas of satisfactory application of the Code and area needing improvements, and therefore require more attention worldwide. The results showed improvement in application of the Code provisions; ntformat otably in aging management, regulatory supervision, and consideration of human factors. However, there is a continuing need for further improvement in these areas, as well as in operational radiation protection, emergency preparedness and decommissioning planning. Additionally, increased attention needs to be given to periodic safety reviews, evaluation of site-specific hazards, and assessment of extreme external events. The results showed consistency with the feedback from other sources of information on generic safety issues for research reactors.
Kurzfassung
Die von 38 Ländern durchgeführte Selbstbewertung der Anwendung des Code of Conduct über die Sicherheit von Forschungsreaktoren wird analysiert und diskutiert. Die Analyseergebnisse wurden verwendet um Bereiche zu identifizieren, in denen die Anwendung des Code befriedigend ist und Bereiche, in denen Verbesserungen nötig sind. Die Ergebnisse zeigen Verbesserungen bei der Anwendung der im Code festgelegten Bestimmungen, insbesondere beim Alterungsmanagement, bei der behördlichen Überwachung und bei der Berücksichtigung der menschlichen Faktoren. Dennoch gibt es Raum für weitere Verbesserungen in diesen Bereichen, ebenso wie beim betrieblichen Strahlenschutz, beim Notfallmanagement und bei der Planung des Rückbaus. Zusätzlich dazu müssen periodische Sicherheitsüberprüfungen, die Bewertung standortbezogener Gefahren und extremer externer Ereignisse verstärkt berücksichtigt werden. Die Ergebnisse zeigen Übereinstimmung mit anderen Informationsquellen über generische Sicherheitsaspekte bei Forschungsreaktoren.
References
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© 2015, Carl Hanser Verlag, München
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Artikel in diesem Heft
- 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
