relap7.inl.govRELAP-7 - Overview

You may be trying to access this site from a secured browser on the server. Please enable scripts and reload this page. Turn on more accessible mode Turn off more accessible mode Skip Ribbon Commands Skip to main content Turn off Animations Turn on Animations To navigate through the Ribbon, use standard browser navigation keys. To skip between groups, use Ctrl+LEFT or Ctrl+RIGHT. To jump to the first Ribbon tab use Ctrl+[. To jump to the last selected command use Ctrl+]. To activate a command, use Enter. Browse Tab 1 of 3. Page Tab 2 of 3. Publish Tab 3 of 3. RELAP-7 Currently selected Documents Contact RELAP-7 It looks like your browser does not have JavaScript enabled. Please turn on JavaScript and try again. Overview Currently selected Documents Overview The RELAP-7 (Reactor Excursion and Leak Analysis Program) is the next generation nuclear power plant (NPP) systems safety analysis software application being developed at the Idaho National Laboratory (INL). RELAP-7 is currently funded by the Department of Energy’s Office (DOE) of Nuclear Energy Advance Modeling and Simulation (NEAMS) program. RELAP-7 is designed to take advantage of the previous thirty-five years of advancements in computer architecture, software design, numerical methods and physical models. RELAP-7 retains the traditional NPP systems analysis capability, but with a wider range of time scales (advanced implicit algorithms) and flow regimes (higher-order accurate spatial integration of advanced single and two-phase flow models), and integrated multiphysics (tightly coupled multi-dimensional core analysis with balance of plant). The final product is an improvement in NPP systems analysis capability that can be applied to a much wider range of systems physical phenomena with reduced uncertainties. Developed upon INL's modern scientific software development and runtime HPC framework, MOOSE (Multi-Physics Object-Oriented Simulation Environment), RELAP-7 makes extensive use of MOOSE’s advanced implicit algorithms and simplified multi-physics multi-dimensional algorithmic coupling. Multi-dimensional physics components, such as radiation transport, thermal fluids, and multi-scale fuels performance designed for both Light Water Reactors (LWRS) and Advanced Reactor Technologies (ART) are implemented in RELAP-7. As a result, RELAP-7 maintains the traditional NPP systems analysis capability while extending to include an advanced multiphysics capability for multiscale, multi-dimensional nuclear core analysis tightly coupled to the balance of plant for a wide range of reactor applications. RELAP-7 NPP simulation capability will include traditional design basis accident scenarios, advanced reactor core design, detailed end of life fuel cycle analysis and operational strategies and evaluating performance-based requirements for Advanced Technology Fuels (ATF), including High-Assay Low-Enriched Uranium (HALEU) nuclear fuel. false,false,1...