RT Journal Article ID 4e3f6b2b2fe99347 A1 Sulatski, A. A. A1 Cherny, O. D. A1 Efimov, V. K. A1 Granovski, V. S. T1 Boiling Crisis at the Outer Surface of Reactor Vessel JF Heat Transfer Research JO HTR YR 1999 FD 1999-11-30 VO 30 IS 7-8 SP 549 OP 558 AB 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. PB Begell House LK https://www.dl.begellhouse.com/journals/46784ef93dddff27,2eb14e5e7e9995d3,4e3f6b2b2fe99347.html