A number of safety studies are under way concerning the reactor plant of N.S. Mutsu. One such study relates to Loss of Coolant Accidents (LOCA), which has been conducted to cover mainly the two subjects of (i) experiments to ascertain the integrity of stainless stell fuel cladding under the action of the Emergency Core Cooling System (ECCS), and (ii) analysis of containment integrity following a LOCA. The stainles steel cladding tests were conducted to test swelling, rupture, oxidation and compression characteristics. Few reports are known to have been published in this domain, so that the present results should prove useful for future studies related to ECCS evaluation analyses on stainless steel fuel cladding. The containment integrity analysis covered variations of containment pressure and temperature following a LOCA, performed separately for short-and long-term perods. Estimates were also made on the changes in the hydrogen concentration present inside the containment after a LOCA. The results obtained should serve in determining the characteristic response to LOCA of marine reactor plants. (Se)
Safety studies on lOKA for N.S. Mutsu
Sicherheitsstudium fuer den Fall von Kuehlmittelverlusten beim Nuklearschiff Mutsu
1978
8 Seiten, 13 Bilder, 2 Tabellen, 5 Quellen
Aufsatz (Konferenz)
Englisch
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