Fast Reactors and Accelerator Driven Systems Knowledge Base

Conference Article: The problems of thermohydraulics of prospective fast reactor concepts

Sedov, A.A. (RRC Kurchatov Institute, Moscow (Russian Federation))

Abstract

In this report the main requirements to fast reactors in system of future multicomponent Nuclear Power with closed U-Pu fuel cycle are regarded. The peculiarities of different liquid-metal (sodium and lead-alloyed) coolants as well as the thermohydraulics problems of prospective FR concepts are discussed.

view the full text of this article (9 pages, format: PDF, size= 695kB)

key words: fast reactors; fuel cycle; hydrodynamics; liquid metals; plutonium; thermal analysis; uranium
Reference:
Technical committee meeting on methods and codes for calculations of thermohydraulic parameters for fuel, absorber pins and assemblies of LMFR's with traditional and burner cores. Obninsk (Russian Federation) 27-31 Jul 1998
International Atomic Energy Agency, Vienna (Austria)
IAEA-TECDOC--1157, pp:256-264