• DocumentCode
    2850910
  • Title

    3D Graphical Simulation of Nuclear Reactor in Open GL & C# Using Probability Density Functions

  • Author

    Khowaja, Hussain Hyder Ali ; Saeed, M. Noman

  • Author_Institution
    Sir Syed University of Engineering & Technology, Karachi, Pakistan. hhalik@gmail.com
  • fYear
    2004
  • fDate
    30-31 Dec. 2004
  • Firstpage
    25
  • Lastpage
    28
  • Abstract
    The experimentation of nuclear reactor is perhaps one of the most expensive and may produce hazardous effects if not controlled properly but with the advancements of 3D graphics and high speed processing; the computational simulation gives almost same result that could be performed on physical experimentation. Once the software is written, countless experiments to examine the factors affecting a reactors performance can be carried out at little cost and with no dangerous side effects. Our simulation software is developed using C# & CsGL (An Open GL wrapper for C#). It provides a 3D environment of a Nuclear Reactor controlled by input parameters interacted with output result simulations. Its purpose is to helps students & engineers in education for understanding energy generation process. The implementation of Monte Carlo method for this simulation involves following lives of a large group of neutrons in the reactor, with each neutron taking it’s own random walk from release; either absorption, exiting reactor, or causing further fission. From this it is possible to work out how enrichment level and fuel:moderator ratio affect the reactors performance. It also allows to vary control rods, f:m ratios, pump speed, along with its inner & outer components views.
  • Keywords
    Computational modeling; Costs; Fission reactors; Graphics; High performance computing; Inductors; Neutrons; Physics computing; Probability density function; Software performance;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Engineering, Sciences and Technology, Student Conference On
  • Print_ISBN
    0-7803-8871-2
  • Type

    conf

  • DOI
    10.1109/SCONES.2004.1564763
  • Filename
    1564763