Experimental studies on the pressure drop across the various components of a PHWR fuel channel

Experiments were carried out to measure the pressure drop across various components of a pressurised heavy water reactor (PHWR) fuel channel under single-phase flow conditions. Empirical correlations developed to predict the pressure drop for the various components of the fuel channel like rod bundl...

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Bibliographic Details
Published in:Experimental thermal and fluid science 1999-09, Vol.20 (1), p.34-44
Main Authors: Vijayan, P.K, Pilkhwal, D.S, Saha, D, Venkat Raj, V
Format: Article
Language:English
Subjects:
Applied sciences
Bundle misalignment
CANDU fuel bundle
End fittings
Energy
Energy. Thermal use of fuels
Exact sciences and technology
Fission nuclear power plants
Fuel channel components
Fuel channel creep
Fuel locators
Heavy water reactors
Installations for energy generation and conversion: thermal and electrical energy
Junction pressure drop
Pipe fittings
Pipe flow
Pressure drop
Pressure tube reactors
Refuelling tools
Split-wart spaced bundles
Wire-wrap bundles
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Summary:Experiments were carried out to measure the pressure drop across various components of a pressurised heavy water reactor (PHWR) fuel channel under single-phase flow conditions. Empirical correlations developed to predict the pressure drop for the various components of the fuel channel like rod bundles, end fittings, fuel locator and refuelling tools are presented. In addition, the effects of bundle alignment at the junction and creep of fuel channels (both radial and axial) on pressure drop have been studied.
ISSN:0894-1777
1879-2286
DOI:10.1016/S0894-1777(99)00024-2