Characterization of velocity and temperature fields in a 217 pin wire wrapped fuel bundle of sodium cooled fast reactor

Author:

Naveen Raj M.,Velusamy K.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference41 articles.

1. Flow and convective heat transfer analysis using RANS for a wire – wrapped fuel assembly;Ahmad;J. Mech. Sci. Technol.,2006

2. Thermal hydraulics of rod bundles: the effect of eccentricity;Amit;Nucl. Eng. Des.,2013

3. SUPERENERGY-2: A Multiassembly Steady-State Computer Code for LMFBR Core Thermal–Hydraulic Analysis, PNL-3379;Basehore,1980

4. Heat Transfer and Fluid Flow in Nuclear Systems;Baxi,1981

5. Bogoslovskaya, G.P., Zhukov, A.V., Sorokin, A.P., 2000. Models and characteristics of interchannel exchange in pin bundles cooled by liquid metal, XA0055052. In: IAEA-TECDOC-1157, LMFR Core Thermohydraulics: Status and Prospects, pp. 191-206.

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