Published May 2016 | Version v1
Journal article

Phenomenological investigation of sodium boiling in a SFR core during a postulated ULOF transient with CATHARE 2 system code. A stabilized boiling case

  • 1. Departement d'Etudes des Reacteurs (DER), Commissariat a l'Energie Atomique et aux Energies Alternatives (CEA), Saint-Paul-Lez-Durance (France)
  • 2. Departement de Modelisation des Systemes et Structures (DM2S), Commissariat a l'Energie Atomique et aux Energies Alternatives (CEA), Gif-sur-Yvette (France)

Description

In the framework of the research and development on GEN IV sodium fast reactors (SFRs), the phenomenology of sodium boiling during a postulated unprotected loss of flow (ULOF) transient has been investigated with the CATHARE 2 system code. This study focuses on a stabilized boiling case: in such a regime, no flow redistribution occurs from the subassemblies which have reached the saturation temperature to those that are still single-phase. In this paper, for a subassembly design featuring no restrictive structures above the fuel bundle, a quasi-static approach is first developed to get an upper bound of the reactor core power at boiling onset that would be compatible with the well-known Ledinegg criteria for diphasic flow static equilibrium. Then, dynamics results achieved through simulation with the CATHARE 2 code for a postulated ULOF are presented: boiling is shown to remain stable during the transient for such a core power at boiling onset. Another important outcome of the simulation is the calculation of a dynamic instability, in the form of a two-phase hydrodynamic chugging phenomenon. The predicted phenomenology of this stabilized boiling case should be studied further in order to consider its dependency on the underlying closure laws and to eliminate the possibility of a numerical instability. (author)

Availability note (English)

Available from http://dx.doi.org/10.1080/00223131.2015.1111778

Additional details

Publishing Information

Journal Title
Journal of Nuclear Science and Technology (Tokyo)
Journal Volume
53
Journal Issue
5
Journal Page Range
p. 692-697
ISSN
0022-3131

Conference

Title
10. international topical meeting on nuclear thermal hydraulics, operation and safety
Acronym
NUTHOS-10
Dates
14-18 Dec 2014
Place
Okinawa (Japan)

Optional Information

Notes
15 refs., 8 figs., 1 tab.