NCRC Applications

NCRC distributes a number of NEAMS-developed applications. The following sections highlight some of the codes available through the NCRC.

NCRC applications may be obtained by outside institutions and individuals for execution and/or development. Currently, the following access methods are available for certain applications:

  • HPC Binary Access (Level 1)
    Users in the category will be provided an INL-HPC account that includes a binary version of the desired application ready for use on INL-HPC resources.

  • Binary Access (Level 2)
    Users in this category will be provided with access to a binary version of the desired application that is executable on non-INL systems, such as a personal workstation or institution cluster.

  • Source Code Access (Level 4)
    Users in this category will be provided with complete source code access to an application. This level of access is reserved for individuals that will be developing new capabilities for the application and contributing directly to the project.

Requesting Access

To request access to an NEAMS-developed code, please follow the instructions on INL's Nuclear Computational Resource Center website.

schooltip:Existing HPC GitLab Users

For existing users who access codes via hpcgitlab.hpc.inl.gov, please see the Transition Guide for help on accessing the new home for NCRC source code (level 4): github.inl.gov. New users can safely ignore this notice.

BISON

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. Bison is available within our NCRC Conda channel.

Blue Crab

Blue Crab is a combination (coupling) of other NCRC Applications: Bison, Griffin, Pronghorn and SAM.

Dire Wolf

Dire Wolf is a combination (coupling) of other NCRC Applications: Bison, Griffin and Sockeye.

Griffin

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 the 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-FHRs), prismatic reactors (PMRs), molten-salt reactors (MSRs), fast sodium-cooled reactors (FSRs), microreactors, nuclear thermal propulsion (NTPs), and several experimental facilities.

Grizzly

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 fracture 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.

MARMOT

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 applications that work at a larger scale, such as BISON which works at an engineering scale. MARMOT solves equations involving solid mechanics and heat conduction using the finite element method.

Pronghorn

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.

RELAP5-3D

RELAP5-3D is the latest released code in the RELAP5 series. Developed at Idaho National Laboratory, the RELAP5 family aids in 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.

RELAP-7

RELAP-7 is a two-phase thermal systems code based on the MOOSE thermal hydraulics module. RELAP-7 provides two-phase components suitable for LWRs provides closures for two-phase water from TRACE.

SAM

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.

Sockeye

Sockeye is a heat pipe analysis application geared towards heat pipes of interest in heat-pipe-cooled microreactors. Sockeye provides various transient heat pipe modeling capabilities, including a 1D, two-phase flow model and a 2D effective thermal conductivity model based on heat conduction, which leverages analytic expressions of operational limits.