The Reactor Excursion and Leak Analysis Program (RELAP5) is a light water reactor transient analysis code developed for the United States Nuclear Regulatory Commission (US NRC) for simulation of a wide variety of hydraulic and thermal transients in both nuclear and nonnuclear systems involving mixtures of steam, water, non condensable gases and solutes under single phase and two phase conditions. Thermal hydraulic analysis is currently one of the most searched terms in nuclear engineering.
The RELAP5 code has received extensive validation and international participation in the development and testing of the code over the years. It is available for UNIX and PC platforms, with excellent post-processing software (APTPLOT). Its versatility enables the analyst to build models of system behaviors.
Fauske & Associates, LLC (FAI) engineers regularly utilize RELAP5 for thermal hydraulic safety analysis, including pre test prediction and post test evaluation, as illustrated in the figure above. Major experience includes extensive piping dynamic loads evaluations for AP1000® systems as well as system evaluations on operating nuclear plants in the U.S. and overseas.