Thermohydraulic Investigations of Decay Heat Removal Systems by Natural Convection for Liquid-Metal Fast Breeder Reactors

Hoffmann, H.; Weinberg, D.; Ieda, Y.; Marten, K.; Tschöke, H.; Frey, H.H.; Dres, Kurt

doi:10.13182/nt89-a34338

Cited by 8 publications

(1 citation statement)

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“…Within the European Fast Breeder Reactor project, an experimental approach in the RAMONA facility has been largely used to study decay heat removal situations [1]. RAMONA was a 1/20 scale water model of the upper plenum with boundary conditions imposed at the core outlet and with active immersed coolers.…”

Section: Introductionmentioning

confidence: 99%

Analysis of the Natural Convection Flow in the Upper Plenum of the MONJU Reactor with Trio_U

Bieder

Fauchet

2013

Science and Technology of Nuclear Installations

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The IAEA has coordinated a benchmark project on natural convection phenomena in the upper plenum of the MONJU reactor. 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 of the reactor. For the initial conditions of the pump trip transient, extensive sensitivity analyses have been made with the CFD code Trio U. These calculations show a high sensitivity of the global flow pattern in the MONJU upper plenum depending on the initial order of the numerical scheme and the modelling 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 almost two hours. All calculations 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.

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Section: Introductionmentioning

confidence: 99%