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.
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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
- International Atomic Energy Agency, Vienna (Austria)