The document deals with the analysis of an experiment to be performed in LOBI ITF in the configuration Mode2. LOBI was a Pressurized Water Reactor (PWR) simulator installed in the EC center of Ispra Italy financially supported by EURATOM. The configuration Mod2 of LOBI was designed as a consequence of the Three Mile accident in US and is the follow-up of the configuration Mod1. Mod2 was designed to simulate stratification phenomena and natural circulation which are important during Small Break Loss of Coolant Accidents (SBLOCA); as a difference Mod1 was designed to simulate phenomena expected during Large Break Loss of Coolant (LBLOCA) scenarios. Namely downcomer size in Mod2 was much smaller than in the case of Mod1 and a large number of Emergency Core Cooling Systems (ECCS) were installed in Mod2. The concerned A2-77 Natural Circulation (NC) experiment was performed to model as far as possible the PWR performance. Various phase of NC were identified and brought to important findings in Nuclear Reactor Safety, including the characterization of instabilities and the reflux condensing mode. The work was discussed in a specific meeting in Ispra of the so-called LPTF research group where University of Pisa represented Italy.
"Analysis of natural circulation test A2-77 performed in LOBI facility, by RELAP5/MOD2 code"
D'Auria F.
Primo
Investigation
;
1987-01-01
Abstract
The document deals with the analysis of an experiment to be performed in LOBI ITF in the configuration Mode2. LOBI was a Pressurized Water Reactor (PWR) simulator installed in the EC center of Ispra Italy financially supported by EURATOM. The configuration Mod2 of LOBI was designed as a consequence of the Three Mile accident in US and is the follow-up of the configuration Mod1. Mod2 was designed to simulate stratification phenomena and natural circulation which are important during Small Break Loss of Coolant Accidents (SBLOCA); as a difference Mod1 was designed to simulate phenomena expected during Large Break Loss of Coolant (LBLOCA) scenarios. Namely downcomer size in Mod2 was much smaller than in the case of Mod1 and a large number of Emergency Core Cooling Systems (ECCS) were installed in Mod2. The concerned A2-77 Natural Circulation (NC) experiment was performed to model as far as possible the PWR performance. Various phase of NC were identified and brought to important findings in Nuclear Reactor Safety, including the characterization of instabilities and the reflux condensing mode. The work was discussed in a specific meeting in Ispra of the so-called LPTF research group where University of Pisa represented Italy.I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.
