The Best Estimate approach in nuclear thermal-hydraulics has been developed within the framework of system codes application to large Nuclear Power Plants for electricity production. To this aim a wide range code validation program has been undertaken by the international scientific community. More recently the validation range and the applicability of those codes has been extended to cover the conditions, namely geometry, operating pressure and other fluid related parameters of Research Reactors (RR). This paper deals with an overview of needs in research reactor technology and with the description of results from selected applications of the codes to identified RR.
Application of best-estimate thermal-hydraulic codes for the safety evaluation of research reactors
D’Auria F.
Penultimo
Supervision
;
2006-01-01
Abstract
The Best Estimate approach in nuclear thermal-hydraulics has been developed within the framework of system codes application to large Nuclear Power Plants for electricity production. To this aim a wide range code validation program has been undertaken by the international scientific community. More recently the validation range and the applicability of those codes has been extended to cover the conditions, namely geometry, operating pressure and other fluid related parameters of Research Reactors (RR). This paper deals with an overview of needs in research reactor technology and with the description of results from selected applications of the codes to identified RR.I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.
