%0 Journal Article %A Sulatski, A. A. %A Cherny, O. D. %A Efimov, V. K. %A Granovski, V. S. %D 1999 %I Begell House %N 7-8 %P 549-558 %R 10.1615/HeatTransRes.v30.i7-8.160 %T Boiling Crisis at the Outer Surface of Reactor Vessel %U https://www.dl.begellhouse.com/journals/46784ef93dddff27,2eb14e5e7e9995d3,4e3f6b2b2fe99347.html %V 30 %X 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. %8 1999-11-30