Phenomenological investigation of sodium boiling in a SFR core during a postulated ULOF transient with CATHARE 2 system code. A stabilized boiling case
Creators
- 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/10.1080/00223131.2015.1111778Additional details
Identifiers
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)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 47114151
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BOILING; COMPUTER CODES; COMPUTERIZED SIMULATION; DROPLETS; FLOW RATE; FUEL ELEMENT CLUSTERS; HELMHOLTZ INSTABILITY; LOSS OF FLOW; MONTE CARLO METHOD; REACTOR CORES; SUPERPHENIX REACTOR; THERMAL HYDRAULICS
- Descriptors DEC
- ACCIDENTS; BREEDER REACTORS; CALCULATION METHODS; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FLUID MECHANICS; FUEL ASSEMBLIES; HYDRAULICS; INSTABILITY; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; MECHANICS; PARTICLES; PHASE TRANSFORMATIONS; PLASMA INSTABILITY; PLASMA MACROINSTABILITIES; PLUTONIUM REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SIMULATION; SODIUM COOLED REACTORS
Optional Information
- Notes
- 15 refs., 8 figs., 1 tab.