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AbstractAbstract
[en] Equipment is described for leak testing of the steam-water system, designed for nuclear power plants with fast sodium reactors. In the event of a water vapour leak, the vapour condenses in a cooler and a conducting electrolyte is formed from solid sodium chloride. The electrical circuit is closed and an outer leak of the steam-water space of the steam generator is indicated. (J.C.)
Original Title
Zarizeni k signalizaci vnejsi netesnosti parovodniho prostoru clankoveho parniho generatoru umisteneho v krabici
Source
15 Oct 1985; 31 Jul 1981; 3 p; CS PATENT DOCUMENT 220075/B/; CS PATENT APPLICATION PV 5849-81; Application date: 31 Jul 1981
Record Type
Patent
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