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Mokhova, O.V.; Churkin, A.N.; Yagov, P.V.; Gorodkov, D.S.
Technical meeting on heat transfer, thermal-hydraulics and system design for supercritical pressure water cooled reactors. Book of abstracts2010
Technical meeting on heat transfer, thermal-hydraulics and system design for supercritical pressure water cooled reactors. Book of abstracts2010
AbstractAbstract
[en] At present OKB 'GIDROPRESS' (Podolsk) and IPPE (Obninsk) are engaged in performing the conceptual design and computational studies of the single-loop reactor plant VVER-SCP cooled by supercritical water. Two variants of coolant flow arrangement in the core are considered: single-pass and double-pass. The paper emphasizes the thermohydraulic features of VVER-SCP single-pass core. The computational studies performed for VVER-SCP core have revealed the necessity of the following: - throttling of the fuel assembly inlet for the coolant flow thermohydraulic stability; - hydro-profiling of the core for equalizing the coolant temperatures at the outlets of fuel assembles with different power; - limitation of power peaking in fuel rods in the fuel assembly. The paper gives a brief description of VVER-SCP design and the results of the computational studies and principal engineering solutions, aimed at assurance of coolant flow stability and equalization of coolant heating in different fuel assemblies, are presented. A brief description of the applied methods and codes is given. (author)
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International Atomic Energy Agency, Vienna (Austria); 46 p; Jul 2010; p. 32; Technical meeting on heat transfer, thermal-hydraulics and system design for supercritical pressure water cooled reactors; Pisa (Italy); 5-8 Jul 2010; IAEA-TM--38683-24; Also available on-line: http://www-pub.iaea.org/MTCD/Meetings/PDFplus/2010/38683/38683_BookOfAbstracts.pdf
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