This paper presents the first part of the transient analysis for the BR2 reactor, performed with the ANL – transient thermal-hydraulics code PARET/V7.5. Considered are reactivity insertion transients with automatic power reduction by the control rods. The code qualification for application at BR2 is performed against existing transient analysis data for standard HEU fuel (93% U5) and assuming zero reactivity coefficients, as it is done in the SAR-BR2. Calculations at reactor manipulation conditions and during nominal power operation are performed for variable initial flow. Time variations of power, energy, coolant and clad/fuel temperature are evaluated and analyzed. The admissible reactivity insertion rate is determined in each specific case. The sensitivity of the results to variation of the delay time for the response of the control system to a power trip is considered. After comparison of the results obtained for the HEU core with the safety limits in the SAR-BR2, the PARET/V7.5 code is used for simulation of the described transients in the LEU core, loaded with dispersed U-9Mo fuel (20% U5, 7.5-8.0 gUtot/cc).
|Title of host publication||2009 International Meeting on Reduced Enrichment for Research and Test Reactors|
|Place of Publication||Illinois, United States|
|State||Published - 4 Nov 2009|
|Event||RERTR 2009 - Beijing|
Duration: 1 Nov 2009 → 5 Nov 2009
|Period||2009-11-01 → 2009-11-05|