List of software for nuclear engineering

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]

Monte Carlo Radiation Transport

Geant4 (CERN)
McCARD (KAIST)^[3]
MCNP (LANL)
MCU (MCU) (Kurchatov Institute)
OpenMC
PHITS (JAEA)
SCALE (KENO V and KENO VI) (ORNL)
Serpent (VTT)
TRIPOLI-4 (CEA)^[4]

Transmutation, fuel depletion

ACAB code Activation and transmutation calculations for nuclear applications
ORIP_XXI code Isotope transmutation simulations
ORILL Code 1D transmutation, fuel depletion (burn-up) and radiological protection code
FISPACT-II Multiphysics, inventory and source-term code
MURE Serpent-MCNP utility for Reactor Evolution
VESTA Monte Carlo depletion interface code

Reactor Systems Analysis

psr-0315	AMPX-77, Modular System for Coupled Neutron-Gamma MultiGroup Cross-Sections from ENDF/B-5
ccc-0459	BOLD/VENTURE-4, Reactor Analysis System with Sensitivity and Burnup
nesc0387	CITATION, 3-D MultiGroup Diffusion with 1st Order Perturbation and Criticality Search
ccc-0643	CITATION-LDI2, 2-D MultiGroup Diffusion, Perturbation, Criticality Search, for PC
ccc-0650	DOORS3.2A, 1-,2-,3-dimensional discrete-ordinates system for deep-penetration neutron and photon transport
uscd1234	DRAGON 3.05D, Reactor Cell Calculation System with Burnup
nesc0784	DSNP, Program and Data Library System for Dynamic Simulation of Nuclear Power Plant
nea-1683	ERANOS 2.3N, Modular code and data system for fast reactor neutronics analyses
nea-1916	FINPSA TRAINING 2.2.0.1 -R-, a PSA model in consisting of event trees, fault trees, and cut sets
nea-0624	JOSHUA, Neutronics, Hydraulics, Burnup, Refuelling of LWR
psr-0608	SAPHIRE 8.0.9, Systems Analysis Programs for Hands-On Integrated Reliability Evaluations
iaea1439	STACY, Very High Temp. Reactor V/HTR Safety Analyses for the Quantification of Fission Product Release from the Fuel
iaea1437	SUPERMC 3.3.0, Super Monte Carlo simulation program for nuclear and radiation process
iaea1370	TRIGLAV, Research Reactor Calculations
uscd1239	VENTEASY, Criticality Search for a Desired Keffective by Adjusting Dimensions, Nuclide Concentrations, or Buckling
ccc-0654	VENTURE-PC 1.1, Reactor Analysis System with Sensitivity and Burnup
iaea0871	VPI-NECM, Nuclear Engineering Program Collection for College Training
nea-0655	VSOP, Neutron Spectra, 2-D Flux Synthesis, Fuel Management, Thermohydraulics Calculation
iaea1440	VSOP99-11, Neutron Spectra, 2-D Flux Synthesis, Fuel Management, Thermohydraulics Calculation

Particle Accelerators and High Voltage Machines

nesc0983	EGUN, Charged Particle Trajectories in Electromagnetic Focusing System
ests0428	POISSON SUPERFISH, Poisson Equation Solver for Radio Frequency Cavity
ccc-0228	SPAR, High-Energy Muon, Pion, Heavy Ion Stopping-Powers and Ranges

Magnetic Fusion Research

nea-1839	ACAB-2008, ACtivation ABacus Code
nea-1638	ANITA-IEAF, Isotope Inventories from Intermediate Energy Neutron Irradiation for Fusion Applications
nesc0873	COAST-4, Design and Cost of Tokamak Fusion Reactors
nea-1200	ELEORBIT, 3-D Simulation of Electron Orbits in Magnetic Multipole Plasma Source
nea-0490	HEDO-2, Magnetic Field Calculation and Plot of Air Core Coils
nea-0583	MEDUSA-PIJ, 1-D Thermohydraulic Analysis of Laser Driven Plasma
ccc-0858	TMAP7, Tritium Migration Analysis Program

Toolkit

PyNE The Nuclear Engineering Toolkit

Nuclear Fuel Cycle

Cyclus An agent-based framework for modeling the flow of material through nuclear fuel cycles.

Deterministic Radiation Transport

Steady-state Reactor Analysis

SIMULATE5

Spatial Kinetics

Thermal-Hydraulics

ATHLET (GRS, Gesellschaft für Anlagen- und Reaktorsicherheit)
TRACE (NRC)
SPACE (KEPCO) ^[5]
RELAP5-3D (Idaho National Laboratory)
GOTHIC (Numerical Advisory Solutions)
CATHARE (CEA)^[6]
FLICA-4 (CEA)
RETRAN (RETRAN-02 and RETRAN-3D)
VIPRE-01
PROTO-FLO
PROTO-HX
PROTO-HVAC
PROTO-Sprinkler

Computational Fluid Dynamics

CFX (ANSYS)
FLUENT (ANSYS)
StarCD (Siemens)
STAR-CCM+ (Siemens)
LOGOS
COBRA-TF
TransAT
code_saturne (EDF)
neptune_cfd (EDF)^[7]
Trio_CFD (CEA)^[8]

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

References

^ IAEA (1999). "Verification and Validation of Software Related to Nuclear Power Plant Instrumentation and Control". {{cite journal}}: Cite journal requires |journal= (help)
^ "Nuclear Engineering Division".
^ 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.
^ Brun, E.; Damian, F.; Diop, C. M.; Dumonteil, E.; Hugot, F. X.; Jouanne, C.; Lee, Y. K.; Malvagi, F.; Mazzolo, A.; Petit, O.; Trama, J. C.; Visonneau, T.; Zoia, A. (2015-08-01). "TRIPOLI-4®, CEA, EDF and AREVA reference Monte Carlo code". 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: 151–160. doi:10.1016/j.anucene.2014.07.053. ISSN 0306-4549.
^ 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.
^ 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.
^ 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.
^ 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.
^ 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.

External links

[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.

[4] Brun, E.; Damian, F.; Diop, C. M.; Dumonteil, E.; Hugot, F. X.; Jouanne, C.; Lee, Y. K.; Malvagi, F.; Mazzolo, A.; Petit, O.; Trama, J. C.; Visonneau, T.; Zoia, A. (2015-08-01). "TRIPOLI-4®, CEA, EDF and AREVA reference Monte Carlo code". 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: 151–160. doi:10.1016/j.anucene.2014.07.053. ISSN 0306-4549.

[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.

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