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Hydrodynamics and heat transfer in reactor components cooled by liquid metal coolants in single/two phase. 11. meeting of the International Association for Hydraulic Research (IAHR) Working Group. Working material

Abstract

This Working Material includes the papers presented at the International Meeting 'Hydrodynamics and heat transfer in reactor components cooled by liquid metal coolants in single/two-phase', which was held 5-9 July 2004 at the State Scientific Center of Russian Federation - Institute for Physics and Power Engineering named after A.I. Leypunsky, in Obninsk near Moscow. The objectives of the meeting were to discuss new results obtained in the field of liquid metal coolant and to recommend the lines of further general physics and applied investigations, with the purpose of validating existing and codes under development for liquid metal cooled advanced and new generation nuclear reactors. Most of the contributions present results of experimental and numerical investigations into velocity, temperature and heat transfer in fuel subassemblies of fast reactors cooled by sodium or lead. In the frame of the meeting a benchmark problem devoted to heat transfer in the model subassembly of the fast reactor BREST-OD-300 was proposed. Experts from 5 countries (Japan, Netherlands, Spain, Republic of Korea, and Russia) took part in this benchmark exercise. The results of the benchmark calculations are summarized in the Working Material. The results of hydrodynamic studies of pressure head chambers and collector systems of liquid  More>>
Authors:
"NONE"
Publication Date:
Jul 01, 2005
Product Type:
Technical Report
Report Number:
TWG-FR-125
Resource Relation:
Conference: 11. meeting of the International Association for Hydraulic Research (IAHR) Working Group, Obninsk (Russian Federation), 5-9 Jul 2004; Other Information: Refs, figs, tabs
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BISMUTH ALLOYS; COOLING; FAST REACTORS; FUEL ASSEMBLIES; HYDRODYNAMICS; LEAD; LIQUID METAL COOLED REACTORS; LIQUID METALS; LITHIUM; MEETINGS; NATURAL CONVECTION; REACTOR COMPONENTS; RUSSIAN FEDERATION; SODIUM; SODIUM ALLOYS; SUPERCONDUCTING SUPER COLLIDER; TEST FACILITIES; THERMAL HYDRAULICS
OSTI ID:
20719981
Research Organizations:
International Atomic Energy Agency, Technical Working Group on Fast Reactors, Vienna (Austria)
Country of Origin:
IAEA
Language:
English
Other Identifying Numbers:
TRN: XA0600385032246
Availability:
Available from INIS in electronic form
Submitting Site:
INIS
Size:
499 pages
Announcement Date:
May 13, 2006

Citation Formats

Hydrodynamics and heat transfer in reactor components cooled by liquid metal coolants in single/two phase. 11. meeting of the International Association for Hydraulic Research (IAHR) Working Group. Working material. IAEA: N. p., 2005. Web.
Hydrodynamics and heat transfer in reactor components cooled by liquid metal coolants in single/two phase. 11. meeting of the International Association for Hydraulic Research (IAHR) Working Group. Working material. IAEA.
2005. "Hydrodynamics and heat transfer in reactor components cooled by liquid metal coolants in single/two phase. 11. meeting of the International Association for Hydraulic Research (IAHR) Working Group. Working material." IAEA.
@misc{etde_20719981,
title = {Hydrodynamics and heat transfer in reactor components cooled by liquid metal coolants in single/two phase. 11. meeting of the International Association for Hydraulic Research (IAHR) Working Group. Working material}
abstractNote = {This Working Material includes the papers presented at the International Meeting 'Hydrodynamics and heat transfer in reactor components cooled by liquid metal coolants in single/two-phase', which was held 5-9 July 2004 at the State Scientific Center of Russian Federation - Institute for Physics and Power Engineering named after A.I. Leypunsky, in Obninsk near Moscow. The objectives of the meeting were to discuss new results obtained in the field of liquid metal coolant and to recommend the lines of further general physics and applied investigations, with the purpose of validating existing and codes under development for liquid metal cooled advanced and new generation nuclear reactors. Most of the contributions present results of experimental and numerical investigations into velocity, temperature and heat transfer in fuel subassemblies of fast reactors cooled by sodium or lead. In the frame of the meeting a benchmark problem devoted to heat transfer in the model subassembly of the fast reactor BREST-OD-300 was proposed. Experts from 5 countries (Japan, Netherlands, Spain, Republic of Korea, and Russia) took part in this benchmark exercise. The results of the benchmark calculations are summarized in the Working Material. The results of hydrodynamic studies of pressure head chambers and collector systems of liquid metal cooled reactors are presented in a number of papers. Also attention was given to the generalization of experimental data on hydraulic losses in the pipelines in case of mutual influence of local pressure drops, and to the modeling of natural convection in the fuel subassemblies and circuits with liquid metal cooling. Special emphasis at the meeting was placed on thermal hydraulics issues related to the development and design of target systems, such as heat removal in the target unit of the cascade subcritical reactor cooled by liquid salt; the target complex MK-1 for accelerator driven systems cooled by eutectic lead-bismuth alloy; and the test facility IFMIF with lithium target. Also, the results of research work performed with the purpose of supporting innovative technologies aimed at the use of liquid metals, e.g., heat pipe applied to nuclear power facilities, lyophobic-capillary porous systems, and others are presented here. As part of the technical program, meeting participants visited test facilities for thermal hydraulics research with liquid metal coolants (sodium, NaK, lead-bismuth, lithium) in the SSC RF IPPE.}
place = {IAEA}
year = {2005}
month = {Jul}
}