Published 2009
| Version v1
Miscellaneous
Using a thermalhydraulics system code to estimate heat transfer coefficients for a critical heat flux experiment
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)
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.