An interpretation procedure for the purpose of incorporation monitoring during decommissioning of nuclear reactors
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R. Schupfner
Abstract
The incorporation monitoring during decommissioning of nuclear reactors is faced with a complex situation arising from a mixture of radionuclides. The development of an interpretation procedure to enable the application of an optimised incorporation monitoring on conditions of decommissioning of nuclear reactors has been carried out combining results from radionuclide analyses of contaminated or activated materials and the proven methods of incorporation monitoring in the case of the intake of single radionuclides. In this study the radiological requirements, the mathematical elements of the interpretation procedure are presented as well as the application to an activated concrete of biological shielding.
Kurzfassung
Die Inkorporationskontrolle während des Rückbaus von Kernreaktoren muss sich aufgrund der auftretenden Radionuklidgemische mit einer unübersichtlichen Situation auseinandersetzen. Daher wurde ein Interpretationsverfahren entwickelt, das die optimierte Anwendung der Inkorporationskontrolle unter den Bedingungen des Rückbaus von Kernreaktoren ermöglicht. Dabei wurden die Ergebnisse von Radionuklidanalysen kontaminierten oder aktivierten Materials verknüpft mit den bewährten Methoden zur Inkorporationskontrolle bei Einzelradionukliden. In dieser Arbeit werden die radiologischen Voraussetzungen und die mathematischen Elemente des Interpretationsverfahrens ebenso präsentiert wie die Anwendung auf aktivierten Beton eines biologischen Schildes.
References
1 ICRP Pub. 60, International Commission on Radiological Protection, Publication 60, Pergamon Press, 1990Suche in Google Scholar
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© 2006, Carl Hanser Verlag, München
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Current use of probabilistic safety evaluations for advanced reactor concepts
- Experiments and comparing calculations on thermohydraulic pressure surges in pipes
- Experimental investigation and CFD simulation of horizontal air/water slug flow
- Uncertainty and sensitivity analysis of the CPS-CC voiding in the RBMK reactor Ignalina-2
- Irradiation damages in tantalum spallation target
- Multigroup neutron reflection and leakage conditions for axial core models with anisotropic scattering
- Performance analyses of the pool-top radiation level reduction systems at the ETRR-2 research reactor
- An interpretation procedure for the purpose of incorporation monitoring during decommissioning of nuclear reactors
- Thermal hydraulics of the fixed bed nuclear reactor concept
- Technical Note
- The critical slab problem for linearly anisotropic scattering and reflecting boundary conditions with the HN method
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Current use of probabilistic safety evaluations for advanced reactor concepts
- Experiments and comparing calculations on thermohydraulic pressure surges in pipes
- Experimental investigation and CFD simulation of horizontal air/water slug flow
- Uncertainty and sensitivity analysis of the CPS-CC voiding in the RBMK reactor Ignalina-2
- Irradiation damages in tantalum spallation target
- Multigroup neutron reflection and leakage conditions for axial core models with anisotropic scattering
- Performance analyses of the pool-top radiation level reduction systems at the ETRR-2 research reactor
- An interpretation procedure for the purpose of incorporation monitoring during decommissioning of nuclear reactors
- Thermal hydraulics of the fixed bed nuclear reactor concept
- Technical Note
- The critical slab problem for linearly anisotropic scattering and reflecting boundary conditions with the HN method
