So far, Research Reactor safety analysis has been performed using conservative computer tools commonly called channel codes. These codes such as PARET, EUREKA and others are generally based on simple physical models that are combined between them to reflect neutronic and thermal hydraulic behaviour of nuclear core under static and dynamic conditions. Nowadays, with the great exploitation of research reactors for different purposes, the revisiting of their safety features seems to be very important and the application of Best Estimate system codes seems to be more adequate in order to reach great confidence in the safety assessment of these research reactors. However, we should keep in mind that the available BE codes were developed for nuclear power industry and their application to research reactors is not strait full. Thus, in this paper, a comparative study of channel codes such PARET and RETRAC-PC with a more complex Thermal Hydraulic code system, such as RELAP5/Mod 3.2 is presented. This comparison concerns the simulation of Reactivity insertion accidents (RIA) and loss of flow transient with and without scram in the IAEA 10MW Highly enriched uranium (HEU) and Low enriched Uranium (LEU) cores.
Comparative Study between Relap5/3.2 system code and channel codes for the safety analysis of research reactors
D'AURIA, FRANCESCO SAVERIO
2005-01-01
Abstract
So far, Research Reactor safety analysis has been performed using conservative computer tools commonly called channel codes. These codes such as PARET, EUREKA and others are generally based on simple physical models that are combined between them to reflect neutronic and thermal hydraulic behaviour of nuclear core under static and dynamic conditions. Nowadays, with the great exploitation of research reactors for different purposes, the revisiting of their safety features seems to be very important and the application of Best Estimate system codes seems to be more adequate in order to reach great confidence in the safety assessment of these research reactors. However, we should keep in mind that the available BE codes were developed for nuclear power industry and their application to research reactors is not strait full. Thus, in this paper, a comparative study of channel codes such PARET and RETRAC-PC with a more complex Thermal Hydraulic code system, such as RELAP5/Mod 3.2 is presented. This comparison concerns the simulation of Reactivity insertion accidents (RIA) and loss of flow transient with and without scram in the IAEA 10MW Highly enriched uranium (HEU) and Low enriched Uranium (LEU) cores.I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.
