Oak Ridge National Laboratory (ORNL) is a federally funded research and development center in Oak Ridge, Tennessee, United States. Founded in 1943, the laboratory is now sponsored by the United States Department of Energy and administered by UT–Battelle, LLC.
The National Technical Information Service (NTIS) is an agency within the U.S. Department of Commerce. The primary mission of NTIS is to collect and organize scientific, technical, engineering, and business information generated by U.S. government-sponsored research and development, for private industry, government, academia, and the public. The systems, equipment, financial structure, and specialized staff skills that NTIS maintains to undertake its primary mission allow it to provide assistance to other agencies requiring such specialized resources.
Dry cask storage is a method of storing high-level radioactive waste, such as spent nuclear fuel that has already been cooled in a spent fuel pool for at least one year and often as much as ten years. Casks are typically steel cylinders that are either welded or bolted closed. The fuel rods inside are surrounded by inert gas. Ideally, the steel cylinder provides leak-tight containment of the spent fuel. Each cylinder is surrounded by additional steel, concrete, or other material to provide radiation shielding to workers and members of the public.
Neutron transport is the study of the motions and interactions of neutrons with materials. Nuclear scientists and engineers often need to know where neutrons are in an apparatus, in what direction they are going, and how quickly they are moving. It is commonly used to determine the behavior of nuclear reactor cores and experimental or industrial neutron beams. Neutron transport is a type of radiative transport.
The Advanced Simulation and Computing Program (ASC) is a super-computing program run by the National Nuclear Security Administration, in order to simulate, test, and maintain the United States nuclear stockpile. The program was created in 1995 in order to support the Stockpile Stewardship Program. The goal of the initiative is to extend the lifetime of the current aging stockpile.
The Waterford Steam Electric Station, Unit 3, also known as Waterford 3, is a nuclear power plant located on a 3,000-acre (1,200 ha) plot in Killona, Louisiana, in St. Charles Parish, about 25 miles (40 km) west of New Orleans.
The base load is the minimum level of demand on an electrical grid over a span of time, for example, one week. This demand can be met by unvarying power plants, dispatchable generation, or by a collection of smaller intermittent energy sources, depending on which approach has the best mix of cost, availability and reliability in any particular market. The remainder of demand, varying throughout a day, is met by dispatchable generation which can be turned up or down quickly, such as load following power plants, peaking power plants, or energy storage.
Monte Carlo N-Particle Transport (MCNP) is a general-purpose, continuous-energy, generalized-geometry, time-dependent, Monte Carlo radiation transport code designed to track many particle types over broad ranges of energies and is developed by Los Alamos National Laboratory. Specific areas of application include, but are not limited to, radiation protection and dosimetry, radiation shielding, radiography, medical physics, nuclear criticality safety, detector design and analysis, nuclear oil well logging, accelerator target design, fission and fusion reactor design, decontamination and decommissioning. The code treats an arbitrary three-dimensional configuration of materials in geometric cells bounded by first- and second-degree surfaces and fourth-degree elliptical tori.
MELCOR is a fully integrated, engineering-level computer code developed by Sandia National Laboratories for the U.S. Nuclear Regulatory Commission to model the progression of severe accidents in nuclear power plants. A broad spectrum of severe accident phenomena in both boiling and pressurized water reactors is treated in MELCOR in a unified framework. MELCOR applications include estimation of severe accident source terms, and their sensitivities and uncertainties in a variety of applications.
Nuclear criticality safety is a field of nuclear engineering dedicated to the prevention of nuclear and radiation accidents resulting from an inadvertent, self-sustaining nuclear chain reaction.
Open Design Alliance is a nonprofit organization creating software development kits (SDKs) for engineering applications. ODA offers interoperability tools for CAD, BIM, and Mechanical industries including .dwg, .dxf, .dgn, Autodesk Revit, Autodesk Navisworks, and .ifc files and additional tools for visualization, web development, 3D PDF publishing and modeling.
NEi Nastran was an engineering analysis and simulation software product of NEi Software. Based on NASA's Structural Analysis program NASTRAN, the software is a finite element analysis (FEA) solver used to generate solutions for linear and nonlinear stress, dynamics, and heat transfer characteristics of structures and mechanical components. NEi Nastran software is used with all major industry pre- and post-processors, including Femap, a product of Siemens PLM Software, and the in-house brands NEi Nastran in-CAD, NEi Fusion, and NEi Works for SolidWorks. This software was acquired by Autodesk in May 2014.
The National Center for Computational Sciences (NCCS) is a United States Department of Energy (DOE) Leadership Computing Facility that houses the Oak Ridge Leadership Computing Facility (OLCF), a DOE Office of Science User Facility charged with helping researchers solve challenging scientific problems of global interest with a combination of leading high-performance computing (HPC) resources and international expertise in scientific computing.
FLiBe is the name of a molten salt made from a mixture of lithium fluoride (LiF) and beryllium fluoride. It is both a nuclear reactor coolant and solvent for fertile or fissile material. It served both purposes in the Molten-Salt Reactor Experiment (MSRE) at the Oak Ridge National Laboratory.
Small modular reactors (SMRs) are a class of small nuclear fission reactors, designed to be built in a factory, shipped to operational sites for installation and then used to power buildings or other commercial operations. The first commercial SMR was invented by a team of nuclear scientists at Oregon State University (OSU) in 2007. Working with OSU's prototype, NuScale Power developed the first working model, available to the US market, in 2022. The term SMR refers to the size, capacity and modular construction. Reactor type and the nuclear processes may vary. Of the many SMR designs, the pressurized water reactor (PWR) is the most common. However, recently proposed SMR designs include: generation IV, thermal-neutron reactors, fast-neutron reactors, molten salt, and gas-cooled reactor models.
MALPAS is a software toolset that provides a means of investigating and proving the correctness of software by applying a rigorous form of static program analysis. The tool uses directed graphs and regular algebra to represent the program under analysis. Using the automated tools in MALPAS an analyst can describe the structure of a program, classify the use made of data and provide the information relationships between input and output data. It also supports a formal proof that the code meets its specification.
The Office of Nuclear Energy (NE) is an agency of the United States Department of Energy which promotes nuclear power as a resource capable of meeting the energy, environmental, and national security needs of the United States by resolving technical and regulatory barriers through research, development, and demonstration.
RELAP5-3D is a simulation tool that allows users to model the coupled behavior of the reactor coolant system and the core for various operational transients and postulated accidents that might occur in a nuclear reactor. RELAP5-3D can be used for reactor safety analysis, reactor design, simulator training of operators, and as an educational tool by universities. RELAP5-3D was developed at Idaho National Laboratory to address the pressing need for reactor safety analysis and continues to be developed through the United States Department of Energy and the International RELAP5 Users Group (IRUG) with over $3 million invested annually. The code is distributed through INL's Technology Deployment Office and is licensed to numerous universities, governments, and corporations worldwide.
MOOSE is an object-oriented C++ finite element framework for the development of tightly coupled multiphysics solvers from Idaho National Laboratory. MOOSE makes use of the PETSc non-linear solver package and libmesh to provide the finite element discretization.
The Radiation Safety Information Computational Center (RSICC) is a U.S. Department of Energy Specialized Information Analysis Center (SIAC) authorized to collect, analyze, maintain, and distribute computer software and data sets in the areas of radiation transport and safety. The RSICC is operated by Oak Ridge National Laboratory in Oak Ridge, Tennessee. The primary sponsors of the RSICC are the U.S. Department of Energy, the U.S. Department of Homeland Security, and the U.S. Nuclear Regulatory Commission.
