Themalhydraulic system codes are complex tools developed to simulate the power plants behavior during off-normal conditions. Among the objectives of the code calculations the evaluation of safety margins, the operator training, the optimization of the plant design and of the emergency operating procedures, are mostly considered in the field of the nuclear safety. The first generation of codes was developed in the United States at the end of `60s. Since that time, different research groups all over the world started the development of their own codes. At the beginning of the `80s, the second generation codes were proposed; these differ from the first generation codes owing to the number of balance equations solved (six instead of three), the sophistication of the constitutive models and of the adopted numerics. The capabilities of available computers have been fully exploited during the years. The authors then summarize some of the major steps in the process of developing, modifying, and advancing the capabilities of the codes. They touch on the fact that Italian, and for that matter non-American, researchers have not been intimately involved in much of this work. They then describe the application of these codes in Italy, even though there are no operating or under construction nuclear power plants at this time. Much of this effort is directed at the general question of plant safety in the face of transient type events.

The Italian experience on T/H best estimate codes: achievements and perspectives / Alemberti, A.; Caruso, Gianfranco; D'Auria, F.; Fiorino, E.; Galassi, G. M.; Marlla, G.; Marsili, P.; Meloni, P.; Naviglio, Antonio. - STAMPA. - 1:(1996), pp. 249-261. (Intervento presentato al convegno OECD/CSNI Workshop on Transient thermalhydraulics and Neutronic codes requirements tenutosi a Annapolis (USA) nel 5-8/11/1996).

The Italian experience on T/H best estimate codes: achievements and perspectives

CARUSO, Gianfranco;NAVIGLIO, Antonio
1996

Abstract

Themalhydraulic system codes are complex tools developed to simulate the power plants behavior during off-normal conditions. Among the objectives of the code calculations the evaluation of safety margins, the operator training, the optimization of the plant design and of the emergency operating procedures, are mostly considered in the field of the nuclear safety. The first generation of codes was developed in the United States at the end of `60s. Since that time, different research groups all over the world started the development of their own codes. At the beginning of the `80s, the second generation codes were proposed; these differ from the first generation codes owing to the number of balance equations solved (six instead of three), the sophistication of the constitutive models and of the adopted numerics. The capabilities of available computers have been fully exploited during the years. The authors then summarize some of the major steps in the process of developing, modifying, and advancing the capabilities of the codes. They touch on the fact that Italian, and for that matter non-American, researchers have not been intimately involved in much of this work. They then describe the application of these codes in Italy, even though there are no operating or under construction nuclear power plants at this time. Much of this effort is directed at the general question of plant safety in the face of transient type events.
1996
OECD/CSNI Workshop on Transient thermalhydraulics and Neutronic codes requirements
THERMAL-HYDRAULIC TRANSIENT; NUCLEAR REACTOR SAFETY; ACCIDENT SIMULATION
04 Pubblicazione in atti di convegno::04b Atto di convegno in volume
The Italian experience on T/H best estimate codes: achievements and perspectives / Alemberti, A.; Caruso, Gianfranco; D'Auria, F.; Fiorino, E.; Galassi, G. M.; Marlla, G.; Marsili, P.; Meloni, P.; Naviglio, Antonio. - STAMPA. - 1:(1996), pp. 249-261. (Intervento presentato al convegno OECD/CSNI Workshop on Transient thermalhydraulics and Neutronic codes requirements tenutosi a Annapolis (USA) nel 5-8/11/1996).
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/11573/385748
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