Published 2014 | Version v1
Miscellaneous

Thermalhydraulics and safety research in support of Phase-II of the Canadian Generation-IV national program

Creators

  • 1. Atomic Energy of Canada Limited, Chalk River, ON (Canada)

Description

The thermalhydraulics and safety projects in the Phase-II of the Canadian National Program for Gen-IV Energy Technologies have been established to (i) provide relevant experimental data for verification and validation of prediction methods and analytical toolsets developed in Phase-I, and (ii) improve the accuracy of prediction methods in support of fuel assembly optimization and safety analyses. Several experimental projects are currently being carried out to obtain heat-transfer data with annuli, 3-rod assembly, and 4-rod assembly in refrigerant- 134a flow, carbon dioxide flow, and water flow, and blow-down and natural-circulation data with tubes in water and carbon dioxide flow, respectively. These experimental data have led to improved understanding of the thermalhydraulics phenomena and enhanced the prediction accuracy of parameters. Prediction methods for thermalhydraulics parameters have been derived to support the fuel optimization and safety analyses. This has led to improved confidence in the development of the Canadian SCWR concept. (author)

Part of:
PBNC 2014 : 19th Pacific Basin Nuclear Conference; 38th Annual Student Conference of the Canadian Nuclear Society and Canadian Nuclear Association

Additional details

Publishing Information

Publisher
Canadian Nuclear Society
Imprint Place
Toronto, Ontario (Canada)
ISBN
978-1-926773-16-2
Imprint Title
PBNC 2014 : 19th Pacific Basin Nuclear Conference; 38th Annual Student Conference of the Canadian Nuclear Society and Canadian Nuclear Association
Imprint Pagination
270 Megabytes
Journal Page Range
[16 p.]

Conference

Title
19. Pacific Basin Nuclear Conference; 38. Annual Student Conference of the Canadian Nuclear Society and Canadian Nuclear Association
Dates
24-28 Aug 2014
Place
Vancouver, British Columbia (Canada)

INIS

Country of Publication
Canada
Country of Input or Organization
Canada
INIS RN
49016158
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature, Numerical Data
Descriptors DEI
EXPERIMENTAL DATA; HEAT TRANSFER; NATURAL CONVECTION; REACTOR SAFETY; SUPERCRITICAL STATE; THERMAL HYDRAULICS; TURBULENT FLOW; WATER COOLED REACTORS
Descriptors DEC
CONVECTION; DATA; ENERGY TRANSFER; FLUID FLOW; FLUID MECHANICS; HEAT TRANSFER; HYDRAULICS; INFORMATION; MASS TRANSFER; MECHANICS; NUMERICAL DATA; REACTORS; SAFETY

Optional Information

Notes
Paper PBNC2014-056. 20 refs., 1 tab., 12 figs.