The Development and Benchmarking of Integral Thermal-hydraulics Codes

Abstract

Nuclear power plants are complex and highly interrelated systems. To assess the response of such plants to anticipated transients, design basis events, and beyond design basis conditions requires integral analysis codes. Since the various processes controlling the reactor response are themselves complex and interdependent, it is extremely important that both individual models and their integrated response be compared to pertinent experimental results. Only through such benchmarking and documentation of the results can the user be given the necessary confidence level in the analytical model as well as an appreciation of the uncertainties associated with the individual models. Severe accident analysis codes are used as an example of how development and benchmarking should be carried out and recorded to provide the needed information for the user.