The closure of the Nuclear Power Plant(NPP) in Italy following the Chernobyl event in 1986, did not imply the termination of researches in nuclear technology. Actually in Italy, UNIPI immediately after the Chernobyl event started to analyze the new reactor concept, primarily Simplified Boiling Water Reactor (SBWR) and Advanced PWR (AP-600). The document deals with the identification and the characterization of thermal-hydraulic phenomena expected in SBWR and AP-600. It was found, in particular, that the tight interaction between primary system and containment and the performance of passive systems put new challenges to the predictive capabilities of codes and that new experiments in the area were needed.
"Thermal-hydraulic Analysis of intrinsically safe reactors - Final Report" (in Italian)
D'Auria Francesco Saverio
Primo
Investigation
1990-01-01
Abstract
The closure of the Nuclear Power Plant(NPP) in Italy following the Chernobyl event in 1986, did not imply the termination of researches in nuclear technology. Actually in Italy, UNIPI immediately after the Chernobyl event started to analyze the new reactor concept, primarily Simplified Boiling Water Reactor (SBWR) and Advanced PWR (AP-600). The document deals with the identification and the characterization of thermal-hydraulic phenomena expected in SBWR and AP-600. It was found, in particular, that the tight interaction between primary system and containment and the performance of passive systems put new challenges to the predictive capabilities of codes and that new experiments in the area were needed.I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.
