Evaluation of existing correlations for the prediction of pressure drop in wire-wrapped hexagonal array pin bundles

Author:

Chen S.K.,Todreas N.E.,Nguyen N.T.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference47 articles.

1. Heat transfer, momentum losses and flow mixing in a 61-tube bundle with wire-wrap;Arwikar;Nuclear Engineering and Design,1979

2. Baumann, W., Cosal, V., Hoffmann, H., Moller, R., Rust, K., 1968. Brennelemente mit Wendelformigen Abstandshalter für Schnelle Brutreaktoren. KfK-768. Also EURFNR-571.

3. Helium cooled systems, the gas cooled fast breeder reactor;Baxi,1981

4. The thermal hydraulics in a rod bundle representative of the start-up core of the ALLEGRO Gas cooled Fast Reactor—experimental and numerical approaches;Berthoux;Nuclear Engineering and Design,2010

5. Thermal and hydraulic design of the CVTR-fuel assemblies. CVNA-115;Bishop,1962

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1. Thermal-hydraulic investigation of the lead-bismuth alloy-cooled wire-wrapped fuel assembly with different pitch to diameter ratios and wire shapes;Nuclear Engineering and Design;2024-11

2. A review of CFD studies on thermal hydraulic analysis of coolant flow through fuel rod bundles in nuclear reactor;Progress in Nuclear Energy;2024-06

3. Experimental study on flow and heat transfer of medium-Prandtl-number fluid along a hexagonal helical cruciform seven-rods;International Journal of Heat and Mass Transfer;2024-06

4. References;Handbook on Thermal Hydraulics in Water-Cooled Nuclear Reactors;2024

5. References;Handbook on Thermal Hydraulics in Water-Cooled Nuclear Reactors;2024

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