Published 1980 | Version v1
Report

Thermal diffusivity measurements of recirculating flows to validate model tests for liquid metal reactors

  • 1. Central Electricity Generating Board, Berkeley, England

Description

Before data from water model tests can be applied to sodium-cooled reactors, a lower limit for Reynolds number to give thermal similarity must be established. A route for determining this is to infer the turbulent diffusivity of heat for water and sodium in the relevant geometry by comparing measured temperature profiles to those predicted by a numerical code. Such a code has been developed, based on the finite element method, and its predictions of velocity and temperature fields compared with measurements made in a simple axisymmetric pipe expansion. Initial results are encouraging, but show the need for further refinement of the turbulence model

Additional details

Additional titles

Augmented title (English)
LMFBR

Publishing Information

Imprint Title
Proceedings of the ANS/ASME/NRC international topical meeting on nuclear reactor thermal-hydraulics: LMFBR and HTGR advanced reactor concepts and analysis methods
Journal Page Range
p. 1818-1835.
Report number
NUREG/CP--0014(Vol.3)

Conference

Title
ANS/ASME topical meeting on reactor thermal-hydraulics.
Dates
9 - 12 Oct 1980.
Place
Saratoga, NY, USA.