Published May 2001 | Version v1
Miscellaneous

Pressure drop correlation for a PWR fuel assembly with mixing vane

  • 1. KAERI, Taejon (Korea, Republic of)

Description

A pressure drop correlation is developed to estimate the pressure drop across a PWR fuel grid spacer with the mixing vane using a simplified computational fluid dynamics (CFD) analysis. The pressure loss at the mixing-vane spacer was assessed to largely depend on the relative plugging of the flow cross section by the fuel support elements and the mixing vane and the flow acceleration. The correlation coefficients were detemined from the experimental data and the increase of fluid velocity from the CFD analysis. The CFD analysis simulated the spacer and mixing vanes as infinite thin surfaces, and neglected the fuel support elements. The measured loss coefficient for the split-vane spacer was reproduced by new correlation well and showed good agreement with the estimated one from the CFD calculation. the correlation loss coefficients for other mixing-vane spacers are also in good agreement with those that are directly estimated from the predicted pressure drops

Part of:
Proceedings of the Korean Nuclear Society spring meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Taejon (Korea, Republic of)
Imprint Title
Proceedings of the Korean Nuclear Society spring meeting
Imprint Pagination
[ONE CDROM]
Journal Page Range
[9 p.]

Conference

Title
2001 spring meeting of the Korean Nuclear Society
Dates
24-25 May 2001
Place
Cheju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
33040367
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CORRELATIONS; CRITICAL HEAT FLUX; FUEL ASSEMBLIES; FUEL RODS; PRESSURE DROP; PWR TYPE REACTORS; SPACERS; VANES
Descriptors DEC
ENRICHED URANIUM REACTORS; FUEL ELEMENTS; HEAT FLUX; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
6 refs, 8 figs