List of software for nuclear engineering

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With the decreased cost and increased capabilities of computers, Nuclear Engineering has implemented computer software (Computer code to Mathematical model) into all facets of this field. There are a wide variety of fields associated with nuclear engineering, but computers and associated software are used most often in design and analysis. Neutron kinetics, thermal-hydraulics, and structural mechanics are all important in this effort. Each software needs to be tested and verified before use. [1] The codes can be separated by use and function. Most of the software are written in C and Fortran. [2]

Contents

Monte Carlo Radiation Transport

Transmutation, fuel depletion

Reactor Systems Analysis

psr-0315AMPX-77, Modular System for Coupled Neutron-Gamma MultiGroup Cross-Sections from ENDF/B-5
ccc-0459BOLD/VENTURE-4, Reactor Analysis System with Sensitivity and Burnup
nesc0387CITATION, 3-D MultiGroup Diffusion with 1st Order Perturbation and Criticality Search
ccc-0643CITATION-LDI2, 2-D MultiGroup Diffusion, Perturbation, Criticality Search, for PC
ccc-0650DOORS3.2A, 1-,2-,3-dimensional discrete-ordinates system for deep-penetration neutron and photon transport
uscd1234DRAGON 3.05D, Reactor Cell Calculation System with Burnup
nesc0784DSNP, Program and Data Library System for Dynamic Simulation of Nuclear Power Plant
nea-1683ERANOS 2.3N, Modular code and data system for fast reactor neutronics analyses
nea-1916FINPSA TRAINING 2.2.0.1 -R-, a PSA model in consisting of event trees, fault trees, and cut sets
nea-0624JOSHUA, Neutronics, Hydraulics, Burnup, Refuelling of LWR
psr-0608SAPHIRE 8.0.9, Systems Analysis Programs for Hands-On Integrated Reliability Evaluations
iaea1439STACY, Very High Temp. Reactor V/HTR Safety Analyses for the Quantification of Fission Product Release from the Fuel
iaea1437SUPERMC 3.3.0, Super Monte Carlo simulation program for nuclear and radiation process
iaea1370TRIGLAV, Research Reactor Calculations
uscd1239VENTEASY, Criticality Search for a Desired Keffective by Adjusting Dimensions, Nuclide Concentrations, or Buckling
ccc-0654VENTURE-PC 1.1, Reactor Analysis System with Sensitivity and Burnup
iaea0871VPI-NECM, Nuclear Engineering Program Collection for College Training
nea-0655VSOP, Neutron Spectra, 2-D Flux Synthesis, Fuel Management, Thermohydraulics Calculation
iaea1440VSOP99-11, Neutron Spectra, 2-D Flux Synthesis, Fuel Management, Thermohydraulics Calculation

Particle Accelerators and High Voltage Machines

nesc0983EGUN, Charged Particle Trajectories in Electromagnetic Focusing System
ests0428POISSON SUPERFISH, Poisson Equation Solver for Radio Frequency Cavity
ccc-0228SPAR, High-Energy Muon, Pion, Heavy Ion Stopping-Powers and Ranges

Magnetic Fusion Research

nea-1839ACAB-2008, ACtivation ABacus Code
nea-1638ANITA-IEAF, Isotope Inventories from Intermediate Energy Neutron Irradiation for Fusion Applications
nesc0873COAST-4, Design and Cost of Tokamak Fusion Reactors
nea-1200ELEORBIT, 3-D Simulation of Electron Orbits in Magnetic Multipole Plasma Source
nea-0490HEDO-2, Magnetic Field Calculation and Plot of Air Core Coils
nea-0583MEDUSA-PIJ, 1-D Thermohydraulic Analysis of Laser Driven Plasma
ccc-0858TMAP7, Tritium Migration Analysis Program

Toolkit

Deterministic Radiation Transport

Steady-state Reactor Analysis

Spatial Kinetics

Thermal-Hydraulics

Computational Fluid Dynamics

Severe Accident

Many codes are supported by the U.S. Nuclear Regulatory Commission (NRC). These include SCALE, PARCS, TRACE (Formerly RELAP5 and TRAC-B), MELCOR, and many others.

http://www.nrc.gov/about-nrc/regulatory/research/safetycodes.html

See also

Related Research Articles

<span class="mw-page-title-main">Oak Ridge National Laboratory</span> Laboratory in Tennessee, United States

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.

<span class="mw-page-title-main">Torness nuclear power station</span> Nuclear power plant in East Lothian, Scotland

Torness nuclear power station is a nuclear power station located approximately 30 miles (50 km) east of Edinburgh at Torness Point near Dunbar in East Lothian, Scotland. It was the last of the United Kingdom's Advanced Gas-cooled Reactors to be fully commissioned. Construction of this facility began in 1980 for the then South of Scotland Electricity Board (SSEB) and it was commissioned in 1988. It is a local landmark, highly visible from the A1 trunk road and East Coast Main Line railway.

<span class="mw-page-title-main">Neutron transport</span> Study of motions and interactions of neutrons

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.

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.

CRAC-II is both a computer code and the 1982 report of the simulation results performed by Sandia National Laboratories for the Nuclear Regulatory Commission. The report is sometimes referred to as the CRAC-II report because it is the computer program used in the calculations, but the report is also known as the 1982 Sandia Siting Study or as NUREG/CR-2239. The computer program MACCS2 has since replaced CRAC-II for the consequences of radioactive release.

SALOME is a multi-platform open source (LGPL-2.1-or-later) scientific computing environment, allowing the realization of industrial studies of physics simulations.

MERCURE is an atmospheric dispersion modeling CFD code developed by Électricité de France (EDF) and distributed by ARIA Technologies, a French company.

<span class="mw-page-title-main">Carolinas–Virginia Tube Reactor</span> Decommissioned experimental pressurized water reactor in South Carolina, US

Carolinas–Virginia Tube Reactor (CVTR), also known as Parr Nuclear Station, was an experimental pressurized tube heavy water nuclear power reactor at Parr, South Carolina in Fairfield County. It was built and operated by the Carolinas Virginia Nuclear Power Associates. CVTR was a small test reactor, capable of generating 17 megawatts of electricity. It was officially commissioned in December 1963 and left service in January 1967.

FLUKA is a fully integrated Monte Carlo simulation package for the interaction and transport of particles and nuclei in matter. FLUKA has many applications in particle physics, high energy experimental physics and engineering, shielding, detector and telescope design, cosmic ray studies, dosimetry, medical physics, radiobiology. A recent line of development concerns hadron therapy.

<span class="mw-page-title-main">OpenFOAM</span> Open-source software package for numerical processes

OpenFOAM is a C++ toolbox for the development of customized numerical solvers, and pre-/post-processing utilities for the solution of continuum mechanics problems, most prominently including computational fluid dynamics (CFD).

<span class="mw-page-title-main">ESI Group</span>

ESI Group provides virtual prototyping software that simulates a product's behavior during testing, manufacturing and real-life use. Engineers in a variety of industries use its software to evaluate the performance of proposed designs in the early phases of the project with the goal of identifying and eliminating potential design flaws.

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.

<span class="mw-page-title-main">RELAP5-3D</span>

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.

Xie George Xu was the Edward E. Hood Chair Professor of Engineering at Rensselaer Polytechnic Institute (RPI), Troy, New York, United States, before he relocated in 2020 to China and joined the faculty of the University of Science and Technology of China.

Consortium for the Advanced Simulation of Light Water Reactors (CASL) is an Energy Innovation Hub sponsored by United States Department of Energy (DOE) and based at Oak Ridge National Laboratory (ORNL). CASL combines fundamental research and technology development through an integrated partnership of government, academia, and industry that extends across the nuclear energy enterprise. The goal of CASL is to develop advanced computational models of light water reactors (LWRs) that can be used by utilities, fuel vendors, universities, and national laboratories to help improve the performance of existing and future nuclear reactors. CASL was created in May 2010, and was the first energy innovation hub to be awarded.

Corys is a manufacturer of training and engineering simulators for the rail transport, energy and hydrocarbon industries. The company is based in Grenoble, France, and was founded in 1997. Corys is the acronym for COmpagnie de Réalisation Industrielle de Simulateurs - Company of industrial simulators production.

Robert Dautray was a French engineer, scientific director of the French Commissariat à l'Energie Atomique (CEA) and High Commissioner for Atomic Energy. He was a member of the French Academy of Sciences, section mechanical and computer sciences, and of the French Academy of Technology.

<span class="mw-page-title-main">Simcenter STAR-CCM+</span> Engineering software by Siemens

Simcenter STAR-CCM+ is a commercial Computational Fluid Dynamics (CFD) based simulation software developed by Siemens Digital Industries Software. Simcenter STAR-CCM+ allows the modeling and analysis of a range of engineering problems involving fluid flow, heat transfer, stress, particulate flow, electromagnetics and related phenomena.

References

  1. IAEA (1999). "Verification and Validation of Software Related to Nuclear Power Plant Instrumentation and Control".{{cite journal}}: Cite journal requires |journal= (help)
  2. "Nuclear Engineering Division".
  3. Shim, Hyung Jin; Park, Ho Jin; Kwon, Soonwoo; Seo, Geon Ho; Kim, Chang Hyo (2015-08-01). "McCARD for neutronics design and analysis of research reactor cores". Annals of Nuclear Energy. Joint International Conference on Supercomputing in Nuclear Applications and Monte Carlo 2013, SNA + MC 2013. Pluri- and Trans-disciplinarity, Towards New Modeling and Numerical Simulation Paradigms. 82: 48–53. doi:10.1016/j.anucene.2014.08.030. ISSN   0306-4549.
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  5. Ha, Sang-Jun; Park, Chan-Eok; Kim, Kyung-Doo; Ban, Chang-Hwan (2011-02-25). "DEVELOPMENT OF THE SPACE CODE FOR NUCLEAR POWER PLANTS". Nuclear Engineering and Technology. 43 (1): 45–62. doi:10.5516/NET.2011.43.1.045. ISSN   1738-5733.
  6. Préa, Raphaël; Fillion, Philippe; Matteo, Laura; Mauger, Gédéon; Mekkas, Anouar (2020-10-20). "CATHARE-3 V2.1: The new industrial version of the CATHARE code". ATH'20 - Advances in Thermal Hydraulics 2020: https://www.ans.org/pubs/proceedings/article.
  7. Mimouni, S.; Boucker, M.; Laviéville, J.; Guelfi, A.; Bestion, D. (2008-03-01). "Modelling and computation of cavitation and boiling bubbly flows with the NEPTUNE_CFD code". Nuclear Engineering and Design. Benchmarking of CFD Codes for Application to Nuclear Reactor Safety. 238 (3): 680–692. doi:10.1016/j.nucengdes.2007.02.052. ISSN   0029-5493.
  8. Angeli, P.-E.; Bieder, U.; Fauchet, G. (2015-08-30). "Overview of the TrioCFD code: Main features, VetV procedures and typical applications to nuclear engineering". NURETH 16 - 16th International Topical Meeting on Nuclear Reactor Thermalhydraulics.
  9. van Dorsselaere, J. P.; Seropian, C.; Chatelard, P.; Jacq, F.; Fleurot, J.; Giordano, P.; Reinke, N.; Schwinges, B.; Allelein, H. J.; Luther, W. (2009-03-01). "The ASTEC Integral Code for Severe Accident Simulation". Nuclear Technology. 165 (3): 293–307. doi:10.13182/nt09-a4102. ISSN   0029-5450 via Taylor & Francis.