Published 1980 | Version v1
Report

Theoretical investigations on thermal-hydraulics of fast reactor fuel rod bundles

  • 1. Netherlands Energy Research Foundation, Petten

Description

Velocity and temperature predictions have been made in a bundle of bare rods with liquid metal cooling by means of the finite element method. A variational principle is applied to develop the finite element relationships. The resulting set of nonlinear algebraic equations for the nodal velocities are solved iteratively using the Newton-Raphson method. The mixing length model of turbulence is applied to predict local velocities and temperatures right up to the wall including anisotropic effects of eddy diffusivities. The numerical results deal with the heat transfer both from the fuel rod surface into subchannels and between subchannels itself, formed by bare rods and arranged in triangular array. A comparison between predictions and measurements in a 19-rod bundle is presented and the agreement is fair

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. 2126-2146.
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.

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
12642333
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
FINITE ELEMENT METHOD; FUEL ASSEMBLIES; FUEL RODS; HEAT TRANSFER; HYDRAULICS; LMFBR TYPE REACTORS; MATHEMATICAL MODELS
Descriptors DEC
BREEDER REACTORS; ENERGY TRANSFER; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FUEL ELEMENTS; LIQUID METAL COOLED REACTORS; NUMERICAL SOLUTION; REACTOR COMPONENTS; REACTORS