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Heat Transfer Research
Fator do impacto: 0.404 FI de cinco anos: 0.8 SJR: 0.264 SNIP: 0.504 CiteScore™: 0.88

ISSN Imprimir: 1064-2285
ISSN On-line: 2162-6561

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Heat Transfer Research

DOI: 10.1615/HeatTransRes.v30.i7-8.160
pages 549-558

Boiling Crisis at the Outer Surface of Reactor Vessel

A. A. Sulatski
Alexandrov Rtsearch Institute of Technology (NITI), 188540 Sosnovy Bor, Leningrad region, Russia
O. D. Cherny
Alexandrov Rtsearch Institute of Technology (NITI), 188540 Sosnovy Bor, Leningrad region, Russia
V. K. Efimov
The Research Institute of Technology, Sosnovy Bor, Leningrad Region, Russia
V. S. Granovski
The Research Institute of Technology, Sosnovy Bor, Leningrad Region, Russia

RESUMO

An experimental investigation of the departure from nucleate boiling (DNB) on the vessel bottom model of VVER-640 has been carried out to address the problem of VVER (PWR or BWR) reactor vessel external cooling in the case of a severe accident with core melting. Based on the devised DNB model and the obtained and reported experimental data, a correlation is proposed for calculation of critical heat fluxes (CHF) on curved surfaces, including the outer surface of the reactor vessel bottom, in relation to surface orientation and coolant parameters.


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