INL's Nuclear Computational Resource Center
This software is available free of charge for all users via GitHub.
MOOSE, the Multiphysics Object Oriented Simulation Environment, is a finite-element multiphysics framework largely developed by Idaho National Laboratory. It offers a high level interface to sophisticated nonlinear solver technology, such as BISON for nuclear fuel, Griffin for radiation transport and reactor multiphysics, and more. MOOSE has a straightforward API well suited to how scientists and engineers tackle real-world problems. It is a fully coupled and fully implicit multiphysics solver that is automatically parallel, making it possible to run large simulations and tackle complicated models.
BlackBear is a MOOSE-based application that models the degradation in concrete, steel, and other structural materials over time and under specified environmental conditions. It also models the response of those materials to loading conditions that they are safely expected to withstand, with these simulations done accounting for the modeled degradation.
Data Integration Aggregated Model and Ontology for Nuclear Deployment – DIAMOND for short – is a data model. It interfaces with various data sources and functionalities associated with nuclear power plants and facilities to ensure a seamless flow of data and of the related data handling methods. DIAMOND can be used to standardize data storage and exchange formats, automating data searches. It also can allow the sharing and comparing of data in a single or between multiple nuclear power plants, as well as revealing cost-saving opportunities.
Deep Lynx is a megaproject manager, an integrated platform for the design and operation of large projects. Such projects are prone to cost and schedule overruns, in part, because engineering teams in design, procurement and construction often exchange data manually. This practice increases the risk of error. Deep Lynx is a data warehouse that stores information in a graph like format following a structure of concept and category properties and relationships that users define. As such, Deep Lynx makes it easier to avoid communication errors and improve performance with regard to meeting megaproject cost and schedule targets.
FALCON is a MOOSE-based application that models fluid flow, heat transfer, rock mechanics, and chemical reactions in geological porous media. It is primarily used for the study of geothermal reservoirs, thermal energy storage, carbon sequestration, and groundwater flow and transport. The code is also built with the Stochastic MOOSE module, allowing for examining probabilistic distributions of model parameters.
Heron is a modeling toolset and plugin for RAVEN that aids in the evaluation of the economic viability of electrical grids, integrated energy systems, and other grid-energy system configurations. It does this by assessing the impact of random events occurring within a probability distribution envelope that is specific to a particular project, such as a light-water reactor operating in a deregulated market. Heron can also be used to construct workflows that solve complex resource allocation problems to meet target economic goals.
Magpie is a MOOSE-based application that links various atomistic codes that analyze distinct, separable, and independent elementary components to applications based on the MOOSE framework. Magpie currently provides coupling modules for SPPARKS (a kinetic Monte Carlo solver from Sandia National Laboratory that simulates particle motion) and MyTRIM(a binary collision Monte Carlo solver for ion transport in materials).
Mastodon is a MOOSE-based application for seismic analysis and risk assessment. It is finite-element code that can easily run in parallel to do soil structure analysis in one, two, or three dimensions. Mastodon can simulate source-to-site wave propagation and analyze risk over time during a simulated event. This risk assessment is probabilistic. Hence, Mastodon can estimate the likelihood of an outcome as well as provide a deterministic analysis of risk.
Risk Analysis Virtual ENvironment, or RAVEN, is a flexible, multi-purpose framework for risk analysis, calculating uncertainty, optimizing parameters and more of complex system codes. RAVEN can investigate the response of such codes and their input space using Monte Carlo, Grid or Latin Hyper Cube sampling schemes. It is particularly strong at finding input space regions that lead to system failure, finding limit surfaces, and other aspects of system feature discovery. RAVEN runs on MAC, Linux and Windows operating systems with multi-core and multi-thread parallel computing.
These INL-licensed software tools require a license in order to be used by researchers. Additional codes may be available. To license a code, click the Request Licenses Software button.
BISON is a finite element-based nuclear fuel performance code. It is applicable to light water reactor fuel rods, TRISO particle fuel, metallic rod and plate fuel, and other fuel forms. BISON solves thermomechanics and species diffusion equations for 1D, 2D and 3D geometries, with fuel models that describe temperature properties, fission product swelling and other material aspects. Because it is based on the MOOSE framework, Bison can solve problems efficiently using standard workstations or very large high-performance computers.
Griffin is a finite element-based reactor multiphysics application. It is suitable for steady state and time-dependent coupled neutronics calculations leveraging the various MOOSE-based thermal-fluids applications (Pronghorn, Relap-7, SAM, Sockeye, etc.) and fuel performance application (BISON). Griffin solves the linearized Boltzmann transport equation in 1D, 2D, and 3D heterogeneous and homogeneous geometries. It has been used in the analysis of pebble bed reactors (PBRs, PB-FHR), prismatic reactors (PMRs), molten-salt reactors (MSR), fast sodium-cooled reactors (FSR), microreactors, nuclear thermal propulsion (NTP), and several experimental facilities.
Grizzly models the degradation due to normal operating conditions of nuclear power plant systems, structures, and components. The code also simulates the ability of degraded components to safely perform under a variety of conditions. Grizzly can be applied to a variety of components. However, its development focused initially on the embrittlement of reactor pressure vessels and concrete structures. Vessels can degrade and facture due to irradiation and high temperatures, while concrete can degrade due to expansive alkali-silica reactions. Grizzly has capability to model the performance effect of these and other mechanisms.
The MOOSE Application Library for Advanced Manufacturing UTilitiEs, or MALAMUTE, is a simulation code for a variety of advanced manufacturing processes designed to connect the microscale characteristics and evolution of materials with their engineering scale, post-manufacture performance. MALAMUTE currently models electric field assisted sintering (EFAS, also known as spark plasma sintering) and laser surface heating (deformation, melting, and welding). Additive manufacturing capabilities are also under development. MALAMUTE leverages and builds on the MOOSE modules to provide a wide range of multiphysics capability up to three dimensions utilizing the finite element and finite volume methods.
MARMOT is a mesoscale fuel performance code. As such, it can predict the evolution of the microstructure and material properties of fuels and claddings due to stress, temperature, and irradiation damage. MARMOT can, therefore, supply microstructure-based materials models to other code that works on engineering scale, which is larger than mesoscale, with an example being BISON. MARMOT solves equations involving solid mechanics and heat conduction using the finite element method.
RELAP5-3D is the latest released code in the RELAP5 series. Developed at Idaho National Laboratory, the RELAP5 family aids the analysis of transients and accidents in water-cooled nuclear power plants and related systems. The software can also analyze advanced reactor designs. RELAP5-3D differs from earlier code in the series because it offers fully integrated and multi-dimensional thermal-hydraulic and kinetic modeling. It runs on both Linux and Windows operating systems, with training and users group available.
A next generation nuclear systems safety code, RELAP-7 takes advantage of advances in computer architecture, software design, numerical methods, and physical models for use in the Risk Informed Safety Margin Characterization (RISMC) methodology and in nuclear power plant (NPP) safety analysis. RELAP-7 is a more capable than its predecessors in the RELAP family due to better flow models, improved numerical approximations, the ability to handle long duration events like full life cycle fuel evaluations, and easy coupling to other simulation code.
Sockeye is a MOOSE-based heat pipe simulator and analysis tool. It, therefore, provides the ability to accurately predict heat transfer for heat-pipe-cooled microreactors and other heat pipe applications. Importantly, Sockeye models heat conduction transients in 1D and 2D as well as offering tools to analyze the operating envelope of heat pipes. So, it provides insight into operational limits in transient conditions, something not readily possible with steady-state analysis. Using Sockeye, users can spot operational limits and adjust designs accordingly.
Pronghorn is a multi-dimensional, coarse-mesh, thermal-hydraulics code for advanced reactors and is particularly well-suited to model gas-cooled pebble bed and prismatic reactors. It serves the intermediate fidelity realm situated between detailed computational fluid dynamics analysis and lumped system models.
INL maintains a large number of commercial analysis codes, open-source packages, and codes owned/licensed by other entities. Below is a small sampling of some available codes. In order to use codes licensed by others, you will need to contact the code developers for a license.
MCNP® is a software created and maintained by Los Alamos National laboratory. It is a general purpose Monte Carlo n-particle code that can be used for neutron, photon, electron, or coupled neutron/photon/electron transport. This tool can be used in a variety of applications including radiation protection and dosimetry, radiation shielding, radiography, medical physics, and nuclear criticality safety.
SCALE is a software created and maintained by Oak Ridge National Laboratory used for analysis of nuclear safety and design. It is a comprehensive tool for criticality safety, reactor physics, radiation shielding, radioactive source term characterization and sensitivity and uncertainty analysis.
System Analysis Module (SAM) is a fast-running, whole-plant transient analysis code with improved-fidelity capability for fast turnaround design scoping and safety analyses of advanced non-light-water reactors.
SERPENT is a three-dimensional continuous-energy Monte Carlo reactor physics burnup calculation code, specifically designed for lattice physics applications. The code uses built-in calculation outlines for generating homogenized multi-group constants for deterministic reactor simulator calculations. The standard output includes effective and infinite multiplication factors, homogenized reaction cross sections, scattering matrices, diffusion coefficients, assembly discontinuity factors, point-kinetic parameters, effective delayed neutron fractions and precursor group decay constants. User-defined tallies can be set up for calculating various integral reaction rates and spectral quantities.
Cubit is a flexible and powerful toolkit for generation of 2D and 3D meshes and geometries for finite element analysis. The main goal of the tool is to reduce the time required to generate meshes, particularly large hex meshes of complicated, interlocking assemblies.