In the development and safety evaluation process of nuclear reactors, the thermal hydraulic analysis reactor coolant system , the containment system and their coupling is essential in understanding operational/transient phenomena of the reactors. Experimental assessment data base characterizes the prototype system physical behaviors Since it is expensive to construct a full scale test facility , reduced scaled test facilities are used Geometrical characteristics of the facility and the initial/boundary conditions of the experiments have to be correctly scaled to ensure the dynamic similarity with the prototype. Objective of the paper is to provide some insight about the scaling methods used in scaling experimental test facility
Scaling rationale design and extrapolation problem for ITF and SETF
D'AURIA, FRANCESCO SAVERIO
2014-01-01
Abstract
In the development and safety evaluation process of nuclear reactors, the thermal hydraulic analysis reactor coolant system , the containment system and their coupling is essential in understanding operational/transient phenomena of the reactors. Experimental assessment data base characterizes the prototype system physical behaviors Since it is expensive to construct a full scale test facility , reduced scaled test facilities are used Geometrical characteristics of the facility and the initial/boundary conditions of the experiments have to be correctly scaled to ensure the dynamic similarity with the prototype. Objective of the paper is to provide some insight about the scaling methods used in scaling experimental test facilityI documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.