Minimizing radiation exposure for the reactor staff during the dismantling of a TRIGA research reactor
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M. Lesar
Abstract
An experimental method for the determination of the long-term activation of concrete shielding has been performed for two TRIGA research reactors in Ljubljana, Slovenia and in Vienna, Austria. The activity of concrete was studied on concrete samples taken directly from the external shielding of the reactor body with consecutive activation under specified parameters. The present work intends to help minimize radiation exposure for the reactor staff engaged in dismantling the concrete shield of a typical TRIGA Mark II research reactor.
Kurzfassung
Eine experimentelle Methode zur Bestimmung der Langzeitaktivierung wurde betrachtet für zwei TRIGA Forschungsreaktoren in Ljubljana, Slovenien und in Wien, Österreich. Die Aktivität von Beton wurde anhand von Betonproben untersucht, die direkt von der externen Abschirmung des Reaktors entnomen wurden mit nachfolgender Aktivierung unter bestimmten Parametern. Ziel der vorliegenden Arbeit ist die Minimierung der Strahlenexposition des Reaktorpersonals, das mit dem Rückbau der Betonabschirmung eines typischen TRIGA Mark II Forschungsreaktor befasst ist.
References
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© 2006, Carl Hanser Verlag, München
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Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Minor actinide burning in a CANDU thorium reactor
- Modeling of the TOSQAN test facility with the lumped parameter code COCOSYS
- Thermal-hydraulic modeling of the onset of flow instability in MTR reactors
- 10.3139/124.100302
- 10.3139/124.100304
- Radiation transfer in inhomogeneous exponential media
- Neutron transport problems for extremely anisotropic scattering
- Milne problem for isotropic and linearly anisotropic scattering for specular and diffuse reflecting boundary conditions solved with the HN method
- ICDE-results on complete common cause failures in the light of results obtained with the POS model
- Modelling of the cumulative behaviour of Caesium and Strontium activities in nuclear fuel
- Analytical study of the closure flow inside the ETRR-2 core chimney
- Minimizing radiation exposure for the reactor staff during the dismantling of a TRIGA research reactor
