The aim in this paper is to validate the PLTEMP/ANL V3.6 code for thermal hydraulics analysis of the BR2 reactor at steady-state operation under forced flow cooling conditions. Hot channel factors and operation limiting conditions based on selected safety system settings (SSS) with uncertainties were reviewed and included into PLTEMP. Safety margins to ONB (Onset-of-Nucleate-Boiling) and to FI (Flow Instability) are calculated for the BR2 HEU fuelled core and compared with the existing safety limits for the heat fluxes in SAR-BR2. A preliminary thermal-hydraulics analysis is performed for the LEU (UMo) fuel preserving the geometrical parameters of the standard BR2 fuel assembly. Power peaking factors evaluated by MCNP for both HEU and LEU fuel assemblies are included in PLTEMP. Thermal-hydraulics studies are extended to include conditions of natural circulation cooling. The margins to ONB and to FI are estimated for both HEU and LEU cores.
|Title of host publication||13th International Topical Meeting on Research Reactor Fuel Management (RRFM)|
|Place of Publication||Brussels, Belgium|
|State||Published - 24 Mar 2009|
|Event||2009 - RRFM - 13th Annual Topical Meeting on Research Reactor Fuel Management - ENS, Vienna|
Duration: 22 Mar 2009 → 25 Mar 2009
|Conference||2009 - RRFM - 13th Annual Topical Meeting on Research Reactor Fuel Management|
|Period||2009-03-22 → 2009-03-25|