Uncertainty and Sensitivity Studies with TRACE-SUSA and TRACE-DAKOTA by Means of Transient BFBT Data

• Published in: Science and technology of nuclear installations Vol. 2013; no. 2013; pp. 1 - 9
• Main Authors: Jaeger, Wadim, Sánchez Espinoza, Victor Hugo, Montero Mayorga, Francisco Javier, Queral, Cesar
• Format: Journal Article
• Language: English
• Published: Cairo, Egypt Hindawi Puplishing Corporation 01-01-2013; Hindawi Publishing Corporation; Hindawi Limited
• Subjects: Boundary conditions; Codes; Computational fluid dynamics; Fluid flow; Hydraulics; Inlet temperature; Mathematical models; Nuclear power plants; Nuclear reactors; Pressure drop; Sensitivity analysis; Studies; Uncertainty; Void fraction
• DOI: 10.1155/2013/565246
• EISSN: 1687-6083
• ISSN: 1687-6075

In the present paper, an uncertainty and sensitivity study is performed for transient void fraction and pressure drop measurements. Two transients have been selected from the NUPEC BFBT database. The first one is a turbine trip without bypass and the second one is a trip of a recirculation pump. TRACE (version 5.0 patch 2) is used for the thermohydraulic study and SUSA and DAKOTA are used for the quantification of the model uncertainties and the evaluation of the sensitivities. As uncertain parameters geometrical values, hydraulic diameter, and wall roughness are considered while mass flow rate, power, pressure, and inlet subcooling (inlet temperature) are chosen as boundary and input conditions. Since these parameters change with time, it is expected that the importance of them on pressure drop and void fraction will change, too. The results show that the pressure drop is mostly sensitive to geometrical variations like the hydraulic diameter and the form loss coefficient of the spacer grid. For low void fractions, the parameter of the highest importance is the inlet temperature/subcooling while at higher void fraction the power is also of importance.