Presentation of an analysis of decay heat removal from the reactor pressure vessel of a nuclear ship in case of sinking. For this incident possible heat transport mechanisms are analysed which assure a sufficient decay heat removal after the controlled flooding of the safety containment. A special research was made for the heat conductivity of the wetted pressure vessel insulation and first experimental results of the thermal conductivity coefficient of wetted insulations are presented. (Se)
Heat removal from the reactor pressure vessel to the surrounding seawater in case of sinking
Waermeableitung vom Reaktordruckbehaelter an das Seewasser beim Sinken eines Schiffes
1978
10 Seiten, 9 Bilder
Aufsatz (Konferenz)
Englisch
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