VIPRE (Versatile Internals and Component Program for Reactors) is used for nuclear reactor thermal-hydraulic analysis applications. It was designed to help evaluate nuclear reactor core safety limits including minimum departure from nucleate boiling ratio (MDNBR), critical power ratio (CPR), fuel and clad temperatures, and coolant state in normal operation and assumed accident conditions. The VIPRE code was developed for the United States Electric Power Industry under the sponsorship of EPRI.

NAS operates the VIPRE User Group (VUG) for member organizations and EPRI. VUG members fund ongoing code maintenance and development activities to ensure the long-term code viability.