TRIOU analysis of natural convection in the upper plenum of the MONJU reactor
Creators
- 1. 1CEA, DEN, DER/SSTH, Grenoble (France)
- 2. JAEA, Tsuruga (Japan)
Description
The IAEA is coordinating a benchmark project on natural convection phenomena in the Upper Plenum of the MONJU reactor. The JAEA has provided both detailed geometrical data of the plant and complete thermalhydraulic boundary conditions describing a pump trip transient, accomplished during the start-up experiments. For the initial conditions of the pump trip transient, extensive sensitivity analyses have been made with the CFD code TrioU. These calculations show a high sensitivity of the global flow pattern in the MONJU Upper Plenum depending on the order of the numerical scheme and the modeling of the geometrically complex Upper Core Structure. During the pump trip, the formation of a thermal stratification within the plenum has been observed which persists for more than one hour. All calculations with TrioU have shown a homogenization of the temperature in the plenum after about 15 minutes. A slight reduction of the mixing in the Upper Plenum could have been achieved by modifying the form of the flow holes in the Inner Barrel (fillets instead of sharp edges) in order to reduce their axial pressure loss. (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
- [13 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
- 47071430
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- COMPUTERIZED SIMULATION; FLUID MECHANICS; IAEA; JAEA; MONJU REACTOR; NATURAL CONVECTION; NUCLEAR POWER PLANTS; THERMAL HYDRAULICS; TRANSIENTS
- Descriptors DEC
- BREEDER REACTORS; CONVECTION; ENERGY TRANSFER; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FLUID MECHANICS; HEAT TRANSFER; HYDRAULICS; INTERNATIONAL ORGANIZATIONS; JAPANESE ORGANIZATIONS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; MASS TRANSFER; MECHANICS; NATIONAL ORGANIZATIONS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; REACTORS; SIMULATION; SODIUM COOLED REACTORS; THERMAL POWER PLANTS
Optional Information
- Notes
- Paper NURETH14-562, 10 refs., 6 tabs., 6 figs.