Published January 1985 | Version v1
Report Restricted

An application of mixing length theory to two-phase flow thermohydraulics in ATR

Creators

  • 1. Australian Atomic Energy Commission. Div. of Nuclear Technology

Description

Steam-water thermohydraulic data obtained for ATR conditions in PNC's Heat Transfer Laboratory are analysed in terms of concepts previously developed from mixing length theory. Data analysed cover pressure loss for pipes, fuel bundles, spacers and other obstructions; average steam volume fraction; heat transfer behaviour in the approach to the boiling crisis; and the influence of wall roughness in pipes. The analysis has led to predictive equations for many of the conditions covered in the experimental program, and has provided insight into detailed two-phase mechanisms occuring under ATR conditions. (author)

Availability note (English)

MF available from INIS under the Report Number.

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Additional details

Publishing Information

Imprint Pagination
106 p.
Report number
PNC-N--941-85-10

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
17065583
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
ANALYTICAL SOLUTION; BOILING; FUEL ELEMENT CLUSTERS; HEAT TRANSFER; HYDRAULICS; JATR REACTOR; PIPES; PRESSURE DROP; STEAM; STEAM QUALITY; THERMODYNAMICS; TWO-PHASE FLOW; VOID FRACTION; WATER
Descriptors DEC
ENERGY TRANSFER; FLUID FLOW; FUEL ASSEMBLIES; HEAVY WATER MODERATED REACTORS; HWLWR TYPE REACTORS; HYDROGEN COMPOUNDS; NATURAL URANIUM REACTORS; OXYGEN COMPOUNDS; PHASE TRANSFORMATIONS; PLUTONIUM REACTORS; POLAR SOLVENTS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; SOLVENTS; THERMAL REACTORS; WATER COOLED REACTORS