Published 2011 | Version v1
Miscellaneous Metadata-only

Updated heat-transfer correlations for supercritical water-cooled reactor applications

Creators

  • 1. Univ. of Ontario Inst. of Tech., Faculty of Energy Systems and Nuclear Science, Oshawa, ON (Canada)

Description

It is expected that the next generation of water-cooled nuclear reactors will operate at supercritical pressures (~25 MPa) and high coolant temperatures (350-625oC). In support of the development of SuperCritical Water-cooled Reactors (SCWRs), research is currently being conducted for heat-transfer at supercritical conditions. Currently, there are no experimental datasets for heat transfer from power reactor fuel bundles to the fuel coolant (water) available in open literature. Therefore, for preliminary calculations, heat-transfer correlations obtained with bare-tube data can be used as a conservative approach. This paper presents an analysis of experimental supercritical-water data and new supercritical heat- transfer correlations, for water and carbon dioxide, developed as part of a larger project assessing the feasibility of Generation IV SCWR concepts. (author)

Part of:
ISSCWR-5. The 5th International Symposium on Supercritical-Water-Cooled Reactors

Additional details

Publishing Information

Publisher
Canadian Nuclear Society
Imprint Place
Toronto, Ontario (Canada)
ISBN
978-1-926773-02-5
Imprint Title
ISSCWR-5. The 5th International Symposium on Supercritical-Water-Cooled Reactors
Imprint Pagination
90.1 Megabytes
Journal Page Range
[15 p.]

Conference

Title
5. International Symposium on Supercritical-Water-Cooled Reactors
Dates
13-16 Mar 2011
Place
Vancouver, BC (Canada)

INIS

Country of Publication
Canada
Country of Input or Organization
Canada
INIS RN
48068403
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature, Numerical Data
Descriptors DEI
COOLANTS; EVALUATED DATA; FUEL ELEMENT CLUSTERS; HEAT TRANSFER; PIPES; PWR TYPE REACTORS; TURBULENT FLOW; WATER COOLED REACTORS
Descriptors DEC
DATA; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID FLOW; FUEL ASSEMBLIES; INFORMATION; NUMERICAL DATA; POWER REACTORS; REACTORS; THERMAL REACTORS; TUBES; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
27 refs., 4 tabs., 12 figs.