The DRACCAR code, under development by IRSN, simulates in a 3D geometry the thermo-mechanical and thermo¬hydraulic behaviour of a fuel rods bundle (a fuel assembly or a portion of it), during a Loss of Coolant Accident (LOCA) in a Light Water Reactor (LWR). The objective of the study, realized in cooperation with IRSN, is to perform a preliminary test of the thermo-hydraulic module of the DRACCAR code, based at the present on the system code CESAR. The code models dealing with the thermo-mechanical behaviour of fuel rods were previously assessed. The accidental transient, used as test case, consists of a LOCA initiated by a break (15 inches of size) in the cold leg of a French PWR, 1300 MW of power. The IRSN has simulated, with CATHARE2 code, the whole reactor system and the obtained results, concerning the thermo-hydraulic behaviour of the fuel rods, ha ve been used as a benchmark for DRACCAR code, used by ENEA to simulate the same accidental transient. The DRACCAR simulation of the considered accident, as well as the comparison with CATHARE2 results, are detailed in the report, trying to explain the observed discrepancies and to address the future developments of the DRACCAR code. The performed work is within the Specific Topic of Cooperation N°2 - DRACCAR CODE between ENEA and IRSN.
Preliminary assessment of the DRACCAR thermo-hydraulic module. Comparison with CATHARE2 results on the simulation of a LOCA in a French PWR
Ederli, Stefano
2012-08-28
Abstract
The DRACCAR code, under development by IRSN, simulates in a 3D geometry the thermo-mechanical and thermo¬hydraulic behaviour of a fuel rods bundle (a fuel assembly or a portion of it), during a Loss of Coolant Accident (LOCA) in a Light Water Reactor (LWR). The objective of the study, realized in cooperation with IRSN, is to perform a preliminary test of the thermo-hydraulic module of the DRACCAR code, based at the present on the system code CESAR. The code models dealing with the thermo-mechanical behaviour of fuel rods were previously assessed. The accidental transient, used as test case, consists of a LOCA initiated by a break (15 inches of size) in the cold leg of a French PWR, 1300 MW of power. The IRSN has simulated, with CATHARE2 code, the whole reactor system and the obtained results, concerning the thermo-hydraulic behaviour of the fuel rods, ha ve been used as a benchmark for DRACCAR code, used by ENEA to simulate the same accidental transient. The DRACCAR simulation of the considered accident, as well as the comparison with CATHARE2 results, are detailed in the report, trying to explain the observed discrepancies and to address the future developments of the DRACCAR code. The performed work is within the Specific Topic of Cooperation N°2 - DRACCAR CODE between ENEA and IRSN.I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.
