Published 2011
| Version v1
Miscellaneous
Scaling of a PWR steam generator simulator with the help of CFD
Description
A project is planned at PSI to experimentally simulate natural circulation mixing in a PWR steam generator during a severe accident whereby superheated steam is generated and secondary water cooling is lost. To assist in the scaling of the mock-up, CFD with the Reynolds Stress Model is used. The methodology is first validated against the Westinghouse 1/7th scale experiments. Thereafter, the flow field is simulated in the PSI mock-up which consists of 270 U-tubes with 0.005 m diameter and 4.9 m length. We show that the scaling assumptions (recirculation ratio, fraction of tubes seeing the hot plume, etc) are globally confirmed by the CFD simulations. (author)
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
- [12 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
- 47071422
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- COMPUTERIZED SIMULATION; FLUID MECHANICS; NATURAL CONVECTION; PWR TYPE REACTORS; REACTOR ACCIDENTS; STEAM GENERATORS
- Descriptors DEC
- ACCIDENTS; BOILERS; CONVECTION; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; HEAT TRANSFER; MASS TRANSFER; MECHANICS; POWER REACTORS; REACTORS; SIMULATION; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Paper NURETH14-306, 5 refs., 3 tabs., 7 figs.