The application of RELAP5 at GRNSPG & NINE (Nuclear Research Group of San Piero a Grado–Nuclear and Industrial Engineering) started more than 30 years ago during which several versions of the code have been applied for the analysis of a very large variety of scenarios occurring in facilities and nuclear installations. The present paper has two goals: (1) to summarize the results and main outcomes achieved through the application of RELAP5 to international projects and benchmarks in which GRNSPG & NINE was involved and (2) to qualify the system’s thermal-hydraulic code calculations through the systematic application of a set of developed procedures. Among the analyses performed, this paper will provide insights into the code results and, wh...
The independent code assessment constitutes an important part in the qualification of an analytical...
So far, Research Reactor safety analysis has been performed using conservative computer tools comm...
Removing the residual heat from a nuclear reactor is an important safety aspect of thermal hydraulic...
The assessment of the tools used for deterministic safety analysis and the compliance with the accep...
A pioneering activity was completed dealing with the application of the well-established code Relap5...
A pioneering activity was completed dealing with the application of the well-established code Relap5...
The results obtained in a more-than-a-decade application of thermal-hydraulic system codes to the an...
The idea of accuracy extrapolation was launched in this paper. The concerned area is nuclear thermal...
Over the past year, the focus of RELAP5 use at the Savannah River Site has been on code applications...
The main object of interest was a typical fuel assembly, which constitutes a core of the nuclear rea...
This paper describes a computer model that has been developed for a VVER-1000 nuclear power plant fo...
The independent code assessment constitutes an important part in the qualification of an analytical ...
The document (in Italian) constituted the first of a series dealing with the application of RELAP c...
The results obtained in a more-than-a-decade application of thermal-hydraulic system codes to the an...
This paper presents results of application of system thermal hydraulic code RELAP5/Mod3.2 in predict...
The independent code assessment constitutes an important part in the qualification of an analytical...
So far, Research Reactor safety analysis has been performed using conservative computer tools comm...
Removing the residual heat from a nuclear reactor is an important safety aspect of thermal hydraulic...
The assessment of the tools used for deterministic safety analysis and the compliance with the accep...
A pioneering activity was completed dealing with the application of the well-established code Relap5...
A pioneering activity was completed dealing with the application of the well-established code Relap5...
The results obtained in a more-than-a-decade application of thermal-hydraulic system codes to the an...
The idea of accuracy extrapolation was launched in this paper. The concerned area is nuclear thermal...
Over the past year, the focus of RELAP5 use at the Savannah River Site has been on code applications...
The main object of interest was a typical fuel assembly, which constitutes a core of the nuclear rea...
This paper describes a computer model that has been developed for a VVER-1000 nuclear power plant fo...
The independent code assessment constitutes an important part in the qualification of an analytical ...
The document (in Italian) constituted the first of a series dealing with the application of RELAP c...
The results obtained in a more-than-a-decade application of thermal-hydraulic system codes to the an...
This paper presents results of application of system thermal hydraulic code RELAP5/Mod3.2 in predict...
The independent code assessment constitutes an important part in the qualification of an analytical...
So far, Research Reactor safety analysis has been performed using conservative computer tools comm...
Removing the residual heat from a nuclear reactor is an important safety aspect of thermal hydraulic...