Published 2009 | Version v1
Miscellaneous

Using a thermalhydraulics system code to estimate heat transfer coefficients for a critical heat flux experiment

Creators

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

Description

RELAP5/SCDAPSIM MOD 3.4 is used to predict wall temperature before and after critical heat flux (CHF) is reached in a vertical, uniformly heated tube using light water as the working fluid. The heated test section is modeled as a 1 m long Inconel 600 tube having an OD of 6.35 mm and ID of 4.57 mm with a 0.5 m long unheated development length at the inlet. Simulations are performed at pressures of 0.5 to 2.0 MPa with mass fluxes from 500 to 2000 kg m-2 s-1 and inlet qualities ranging from -0.2 to 0. Loss of flow simulations are performed with flow reduction rates of 10, 20, 50, and 100 kg m-2 s-2. Inlet mass flux at CHF was nominally independent of rate in the model; this may or may not be realistic. (author)

Part of:
New nuclear frontiers. 30th annual Canadian Nuclear Society conference and 33rd CNS/CNA student conference

Additional details

Publishing Information

Publisher
Canadian Nuclear Society
Imprint Place
Toronto, Ontario (Canada)
ISBN
0-919784-95-X
Imprint Title
New nuclear frontiers. 30th annual Canadian Nuclear Society conference and 33rd CNS/CNA student conference
Imprint Pagination
275 Megabytes
Journal Page Range
[11 p.]

Conference

Title
30. annual canadian nuclear society conference; 33. CNS/CNA student conference
Dates
31 May - 3 Jun 2009
Place
Calgary, Alberta (Canada)

INIS

Country of Publication
Canada
Country of Input or Organization
Canada
INIS RN
41007197
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COMPUTER CODES; CRITICAL HEAT FLUX; HEAT TRANSFER; THERMAL HYDRAULICS; WATER
Descriptors DEC
ENERGY TRANSFER; FLUID MECHANICS; HEAT FLUX; HYDRAULICS; HYDROGEN COMPOUNDS; MECHANICS; OXYGEN COMPOUNDS

Optional Information

Notes
14 refs., 1 tab., 7 figs.