Validation of trace one-dimensional model using Phenix end of life natural circulation experiments

Conference paper (2017)

Authors

S. Silva Pinto Wahnon RST/Reactor Physics and Nuclear Materials - AS , European Commission Joint Research Centre, Institute for Energy and Transport
L Ammirabile European Commission Joint Research Centre, Institute for Energy and Transport
J.L. Kloosterman RST/Radiation, Science and Technology
D. Lathouwers RST/Reactor Physics and Nuclear Materials - AS
Research Group
RST/Reactor Physics and Nuclear Materials (AS) (TU Delft)
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Published Date

2017

Language

English

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Faculty

Applied Sciences

Department

RST/Radiation, Science and Technology

Research Group

RST/Reactor Physics and Nuclear Materials

Abstract

The demonstrated technological feasibility of sodium-cooled fast reactors (SFRs) makes them stand out among the other fast reactor concepts proposed by Generation-IV International Forum (GIF) for short-term deployment. Therefore, it is necessary to develop computational tools capable of performing reliable safety analyses and plant behavior simulations under complex transient scenarios to assure SFR’s compliance with the highest safety goals. To satisfy this need, a multi-physics 3-dimensional core and system model is being developed. This will allow a more detailed representation of the physics of the plant and to anticipate more accurately plant behavior, even under wider three dimensional scenarios, such as asymmetric transients. As a first step of the tool development, a 1-dimensional thermal-hydraulic model of the French SFR Phenix was created and the Phenix end-of-life natural circulation test was simulated. The 1-dimensional model transient calculations are in good agreement, both in trend and absolute values, with the experimental data proving the value of the developed model to assess if natural convection is sufficient to cool the Phenix core after a scram. Nevertheless, some phenomena observed experimentally cannot be completely caught due to the 1-dimensional nature of the model. Thus, in view to improve the representation of plant behavior and as next step in the development of the multi-physics computational tool, the developed 1-dimensional model is being extended into a 3-dimensional thermal-hydraulics model. The coupling will be performed using the system codes TRACE-PARCS, modified to simulate more accurately sodium-cooled fast reactors.