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 need to test and verify before use.[1] The codes can be separated by use and function. most of software's written in C and Fortran.[2]

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

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".
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