Published 2011 | Version v1
Miscellaneous

Experimental investigation of quench phenomena and two-phase flow behavior for hot horizontal tubes well above the limiting temperature for solid-liquid contact

  • 1. McMaster Univ., Hamilton, Ontario (Canada)

Description

Quench cooling of a hot dry surface involves the rapid decrease in surface temperature by a sudden contact with a coolant. Situations involving quenching are encountered in a number of postulated accidents in Canada Deuterium Uranium (CANDU) reactors, such as quenching of a hot calandria tube in certain Loss of Coolant Accidents (LOCA). In this study, an experimental setup has been built and a series of experiments were conducted to investigate quenching of hot horizontal tubes by a water multi-jet system. The effects of key role parameters on the re-wetting delay time, the re-wetting front velocity and the quench and re-wetting temperatures were investigated. These variables were found to be strongly dependent on water subcooling. The effects of initial surface temperature, jet velocity and surface curvature were also investigated. (author)

Part of:
The 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-14)

Additional details

Publishing Information

Publisher
Canadian Nuclear Society
Imprint Place
Toronto, Ontario (Canada)
ISBN
978-1-926773-05-6
Imprint Title
The 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-14)
Imprint Pagination
766 Megabytes
Journal Page Range
[15 p.]

Conference

Title
14. International Topical Meeting on Nuclear Reactor Thermalhydraulics
Acronym
NURETH-14
Dates
25-30 Sep 2011
Place
Toronto, Ontario (Canada)

INIS

Country of Publication
Canada
Country of Input or Organization
Canada
INIS RN
47071066
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CANDU TYPE REACTORS; COOLANTS; LOSS OF COOLANT; REACTOR COOLING SYSTEMS; TUBES
Descriptors DEC
ACCIDENTS; COOLING SYSTEMS; ENERGY SYSTEMS; HEAVY WATER MODERATED REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS

Optional Information

Notes
Paper NURETH14-554, 19 refs., 1 tab., 16 figs.