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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Veröffentlicht in:	Experimental thermal and fluid science 1999-09, Vol.20 (1), p.34-44
Hauptverfasser:	Vijayan, P.K, Pilkhwal, D.S, Saha, D, Venkat Raj, V
Format:	Artikel
Sprache:	eng
Schlagworte:	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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Beschreibung
Zusammenfassung:	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