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13D061NMAN - Numerical Methods for Nuclear Reactor Analysis

Course specification
Course title Numerical Methods for Nuclear Reactor Analysis
Acronym 13D061NMAN
Study programme Electrical Engineering and Computing
Module Nuclear, Medical and Ecological Engineering
Type of study doctoral studies
Lecturer (for classes)
Lecturer/Associate (for practice)
    Lecturer/Associate (for OTC)
      ESPB 9.0 Status elective
      Condition none
      The goal Students will be enabled to be engaged in a numerical methods for nuclear reactor analysis
      The outcome To possess active knowledge in the filed of numerical methods used for nuclear reactor analysis
      Contents
      Contents of lectures Boltzmann transport equation. Integral-differential and integral kind of equation. Approximate methods of solutions of transport equation for neutrons and photons. Difference method, finite element method and discrete ordinate method. Heat and mas transport equations. Monte Carlo method. Well known computer codes and application in nuclear analysis.
      Contents of exercises Study research work
      Literature
      1. E.E. Lewis, W.F.Miller, Computational Methods of Neutron Transport, ANS, 1993.
      2. Lamarsh, J. R. and Baratta, A.: Introduction to Nuclear Engineering, (2001).
      Number of hours per week during the semester/trimester/year
      Lectures Exercises OTC Study and Research Other classes
      6
      Methods of teaching Lectures/menthorship/study research work
      Knowledge score (maximum points 100)
      Pre obligations Points Final exam Points
      Activites during lectures 0 Test paper 0
      Practical lessons 0 Oral examination 30
      Projects
      Colloquia 0
      Seminars 70