HEAT TRANSFER IN BOILING OF WATER
IN A FILL OF SPHERICAL ELEMENTS

V. V. Lozovetskii

UDC 621.039.5.46.001

An experimental study has been made of heat exchange in bubble and 
transient regimes of boiling in spherical-element fills as applied 
to the cores of nuclear reactors with spherical fuel microelements 
based on uranium dioxide with multilayer ceramic coatings. Critical 
dependences describing experimental data and making it possible to 
calculate the heat-transfer coefficient in such regimes of boiling 
have been obtained.

Moscow State University of Forest, 1ya Institutskaya Str., 
Mytishchi, Moscow Region, 141005, Russia; email: lozovetsky@mail.ru. 
Translated from Inzhenerno-Fizicheskii Zhurnal, Vol. 80, No. 4, pp. 
35-39, July-August, 2007. Original article submitted December 
19, 2005; revision submitted April 6, 2006.