Published 1977 | Version v1
Book Metadata-only

A review of dryout data in SGHWR fuel bundle simulations

Creators

  • 1. UKAEA Reactor Group, Winfrith. Atomic Energy Establishment

Description

Experiments are reviewed that have been carried out at AEE Winfrith investigating dryout in electrically heated simulations of SGHWR fuel clusters. The effect of flow conditions is examined in the context of a set of reference experiments and the effect of varying geometrical factors is discussed in detail, the large number of experiments allowing the effect of single parameter variation to be explored. (author)

Additional details

Publishing Information

Publisher
Mechanical Engineering Pub. for the Institution of Mechanical Engineers.
Imprint Place
London
ISBN
0 85298 379 4
Imprint Title
Heat and fluid flow in water reactor safety. Conference sponsored by the Thermodynamics and Fluid Mechanics Group of the Institution of Mechanical Engineers, Manchester, 13-15 September 1977
Journal Issue
no. 8
Series
IMechE Conference Publications 1977.
Journal Page Range
p. 203-207.

Conference

Title
Conference on heat and fluid flow in water reactor safety.
Dates
13 - 15 Sep 1977.
Place
Manchester, UK.

INIS

Country of Publication
United Kingdom
Country of Input or Organization
United Kingdom
INIS RN
9376548
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COOLANT LOOPS; DRYOUT; FUEL ELEMENT CLUSTERS; HEAT FLUX; SGHWR REACTOR; SIMULATION
Descriptors DEC
ENRICHED URANIUM REACTORS; FUEL ASSEMBLIES; HEAVY WATER MODERATED REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS