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Core melt spreading on a reactor containment floor
KTH, Tidigare Institutioner                               , Fysik.
2000 (Engelska)Ingår i: Progress in nuclear energy (New series), ISSN 0149-1970, E-ISSN 1878-4224, Vol. 36, nr 4, s. 405-468Artikel i tidskrift (Refereegranskat) Published
Abstract [en]

The ex-vessel core melt spreading, cooling and stabilization is proposed for a nuclear power plant containment design. Clearly, the retention and coolability of the decay-heated core debris is very much the focal point in the proposed new and advanced designs so that, in the postulated event of a severe accident, the containment integrity is maintained and the risk of radioactivity releases is eliminated. The work reported here includes three tasks (i) to review related methodology and data base, (ii) to develop the scaling methodology and (iii) to validate the assessment methodology developed by the authors. The study is based on state-of-the-art knowledge of the melt spreading phenomenology, in particular, and, of severe accident phenomenology in general.

Ort, förlag, år, upplaga, sidor
2000. Vol. 36, nr 4, s. 405-468
Nyckelord [en]
viscous gravity currents, surface, domes
Identifikatorer
URN: urn:nbn:se:kth:diva-20074ISI: 000089697500004OAI: oai:DiVA.org:kth-20074DiVA, id: diva2:338767
Anmärkning
QC 20100525Tillgänglig från: 2010-08-10 Skapad: 2010-08-10 Senast uppdaterad: 2017-12-12Bibliografiskt granskad

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