A coolant flow simulation in fast reactor wire-wrapped assembly-Reference-Cited by-同舟云学术

A coolant flow simulation in fast reactor wire-wrapped assembly

Published:2013-05-16 Issue:6 Volume:60 Page:429-433
ISSN:0040-6015
Container-title:Thermal Engineering
language:en
Short-container-title:Therm. Eng.

Author:

Volkov V. Yu.,Belova O. V.,Krutikov A. A.,Skibin A. P.

Publisher

Pleiades Publishing Ltd

Subject

Energy Engineering and Power Technology,Nuclear Energy and Engineering

Link

http://link.springer.com/content/pdf/10.1134/S0040601513060116.pdf

Reference8 articles.

1. Federal Target Program “New-Generation Nuclear Power Technologies for the Period 2010-2015 and Up to 2020” adopted on January 21, 2010, http://www.atomic-energy.ru/node9368 .

2. K. D. Hamman and R. A. Barry, A CFD M&S Process for Fast Reactor Fuel Assemblies (U.S. Department of Energy National Laboratory, Idaho, 2008).

3. U. Bieder, V. Barthel, F. Ducros, et al., CFD Calculations of Wire Wrapped Fuel Bundles: Modeling and Validation Strategies (Argonne National Laboratory, Chicago, Illinois, 2010), http://www.oecd-nea.org/nsd/csni/cfd/workshops/CFD4NRS-3/technical-papers/1/1.4%20-Advanced%20Reactors.pdf .

4. W. D. Pointer, P. Fischer, J. Smith, et al., Simulations of Turbulent Diffusion in Wire-Wrapped Sodium Fast Reactor Fuel Assemblies (Argonne National Laboratory, Chicago, Illinois, 2010), http://www-pub.iaea.org/MTCD/meetings/PDFplus/2009/cn176/cn176-Presentations/parallel-session-6.3/06-18.Pointer.pdf .

5. J. K. Fink and L. Leibowitz, Thermodynamic and Transport Properties of Sodium Liquid and Vapor (Argonne National Laboratory, Chicago, Illinois, 1995).

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