Authors & Affiliations
Boltenko E.A.
Electrogorsk Research Center for Safety of Nuclear Power Plants, Electrogorsk, Russia
Boltenko E.A. - Senior Researcher, Dr. Sci. (Tech.), Electrogorsk Research Center for Safety of Nuclear Power Plants. Contacts: 6, Saint Constantine st., Electrogorsk, Moscow region, Russia, 142530. Tel.: (496)433-21-17, (916)233-12-11; e-mail:
Abstract
More efficient operation of reactor plant fuel assemblies can be achieved through the use of new technical solution aimed obtaining more intense heat removal on conves heat-transfer surfaces, and higher values of departure from nucleater boiling ratio (DNBR). Technical solutions using which it is possible to obtain more intense heat removal on convex heat-transfer surfaces and higher DNBR values in reactor plant fuel assemblies are considered. One possible way in which more intense heat removal from a convex heat transfer surface can be obtained is to use interacting swirl flows. Enhancement of heat transfer on the convex heat-transfer surfaceis achieved owing to interaction between the swirled and transit flows.
The use of interacting swirled flows (swirl flow and transit flow) for enhancing heat transfer on a convex heat-transfer surface of fuel rods makes it possible to achieve significantly better heat removal in the convective region (by a factor of 2-3 as compared with a smooth surface. The CHF values in the entire region of two-phase flow are higher than the CHF values for a smooth surface (from 30% in the surface boiling region to 250% in the region of dispersed annular flow mode). By implementing an alternative heat removal arrangement in FAS in which heat is removed from both convex and concave heat heat-transfer surfaces of fuel rods, it is possible to obtain a significally lower maximal fuel rod temperature (by more than 1000 C with the reactor plant power output increased to 150%), significally higher power density in the reacto r plant, and much higher DNBR values on the concave and convex heat–transfer surfaces of fuel.
Keywords
fuel assembly, heat removal intensity, heat removal enhancement methods, convex surface, burn-out, critical heat flux
Article Text (PDF, in Russian)
UDC 536.24
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2016, issue 3, 3:3