In the frame of the Generic Site Safety Report GSSR for the ITER experimental plant, several accident analyses have been carried out to quantify in detail the radiological risk linked with the possible releases. In this context a hypothetical double-ended pipe rupture of the largest pipe was analysed to bound all possible leaks in the ex-vessel section of a divertor primary heat transfer system during pulse operation. That analysis was performed using a thermal-hydraulic system code, a containment code and an aerosol transportation code. The present paper shows the results obtained by using, for the same accident, only the nuclear source term ECART code. A comparison with the results given in GSSR is also presented and discussed.
Analysis of an Ex-Vessel Break in the ITER Divertor Cooling Loop with the ECART Code
PACI, SANDRO;
2002-01-01
Abstract
In the frame of the Generic Site Safety Report GSSR for the ITER experimental plant, several accident analyses have been carried out to quantify in detail the radiological risk linked with the possible releases. In this context a hypothetical double-ended pipe rupture of the largest pipe was analysed to bound all possible leaks in the ex-vessel section of a divertor primary heat transfer system during pulse operation. That analysis was performed using a thermal-hydraulic system code, a containment code and an aerosol transportation code. The present paper shows the results obtained by using, for the same accident, only the nuclear source term ECART code. A comparison with the results given in GSSR is also presented and discussed.I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.
