Misplaced Pages

List of software for nuclear engineering

Article snapshot taken from[REDACTED] with creative commons attribution-sharealike license. Give it a read and then ask your questions in the chat. We can research this topic together.

This article has multiple issues. Please help improve it or discuss these issues on the talk page. (Learn how and when to remove these messages)
This article needs additional citations for verification. Please help improve this article by adding citations to reliable sources. Unsourced material may be challenged and removed.
Find sources: "List of software for nuclear engineering" – news · newspapers · books · scholar · JSTOR (August 2017) (Learn how and when to remove this message)
This article may have confusing or ambiguous abbreviations. Please review the Manual of Style, help improve this article, and discuss this issue on the talk page. (August 2017) (Learn how and when to remove this message)
(Learn how and when to remove this message)

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. The codes can be separated by use and function. Most of the software are written in C and Fortran.

Monte Carlo Radiation Transport

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

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

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.
  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. 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.
  7. 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

Categories:
List of software for nuclear engineering Add topic