Current use of probabilistic safety evaluations for advanced reactor concepts
-
C. Kirchsteiger
and R. Bolado-Lavin
Abstract
There is international consensus that for the various nuclear Advanced Reactor Concepts (ARCs), which are currently under development, design and operational safety goals as well as modern review frameworks for risk assessment required for licensing related decision-making shall be developed. The objective of this paper is to screen information available from different countries and international organisations on such efforts as far as they consider the use of Probabilistic Safety Assessment (PSA) or specific probabilistic evaluations. The screening of available information is done for many different types of ARCs (so-called Generation III, III+ and IV), including either active, passive or both types of systems. Main conclusion is that very little information is available for full probabilistic assessments, only recently some activities started on partial probabilistic evaluations, such as on the reliability of certain types of passive systems. Therefore, published statements on significantly lower risk levels achieved by certain ARCs are at least not verifiable.
Kurzfassung
Es gibt einen allgemeinen Konsens, dass für die zur Zeit entwickelten zahlreichen fortgeschrittenen Reaktorkonzepte design- und betriebliche Sicherheitsziele sowie Risikoanalyserahmenbedingungen geschaffen werden müssen. Zielsetzung dieses Artikels ist es, die in verschiedenen Ländern und durch internationale Organisationen vorangetriebenen Maßnahmen in diesem Bereich zu untersuchen. Die Auswertung öffentlich zugänglicher Information in diesem Bereich wird für fortgeschrittenen Reaktorkonzepte der sogenannten Generation III, III+ und IV durchgeführt. Die Hauptschlussfolgerung ist, dass es trotz sehr umfangreicher auch öffentlich zugänglicher Information zu technischen Sicherheitsaspekten derartiger Reaktorkonzepte kaum Informationen über den geforderten probabilistischen Sicherheitsnachweis gibt. Die so oft publizierten Meldungen über signifikante Risikominderungen entsprechender Reaktorkonzepte sind daher zumindest im Rahmen des selbst geforderten Sicherheitsregelwerks nicht nachvollziehbar.
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© 2006, Carl Hanser Verlag, München
Articles in the same Issue
- 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
Articles in the same Issue
- 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