Published 2011 | Version v1
Miscellaneous

TRIOU analysis of natural convection in the upper plenum of the MONJU reactor

  • 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)

Part of:
The 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-14)

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)

Optional Information

Notes
Paper NURETH14-562, 10 refs., 6 tabs., 6 figs.