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Reaktor-Sicherheitstechnik pp 188–227Cite as

Verlust des Reaktorkühlmittels

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Zusammenfassung

Der Kühlmittelverluststörfall (am. LOCA, loss of coolant accident) der Leichtwasserreaktoren ist besonders ausführlich untersucht worden. Das liegt vor allem daran, daß er schon frühzeitig als „größter anzunehmender Unfall“ (GAU), später etwas präziser als „Auslegungsstörfall“definiert wurde, aus dem die Spezifikation für die begrenzende sicherheitstechnische Auslegung der Anlage hergeleitet wurde. Heute sind eine ganze Anzahl anderer Störfälle, wie sie in den vorangehenden Kapiteln beschrieben wurden, ebenso wie einige Einwirkungen von außen zusätzlich auslegungsbestimmend.

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  1. Institut für Reaktortechnik, Universität Karlsruhe, Deutschland

    Professor Dr. Dieter Smidt

  2. Institut für Reaktortechniklung, Kernforschungszentrums Karlsruhe, Deutschland

    Professor Dr. Dieter Smidt

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Smidt, D. (1979). Verlust des Reaktorkühlmittels. In: Reaktor-Sicherheitstechnik. Springer, Berlin, Heidelberg. https://doi.org/10.1007/978-3-642-50225-5_8

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