February 19(Mon) ~ 22(Thu), 2001

 

A Short Course on

Neutron & Radiation Transport Simulation :

Theory and Applications

 


Purpose of Short Course

  The short course on Neutron and Radiation Transport Simulation: Theory and Applications takes place in the Department of Nuclear Engineering at the Korea Advanced Institute of Science and Technology (KAIST), Taejon, Korea during February 19 - 22, 2001.

  The subject of neutron and radiation transport theory is the most fundamental discipline in nuclear science and technology. It deals with predicting the behavior of neutrons in nuclear reactors and related systems. Traditionally, the methods for neutral particle (neutrons and gammas) transport have been the backbone of the particle transport methods. However, it turned out that the transport of charged particles (such as electrons, positrons, protons, plasma ions, and so on) that are gaining more importance in recent years can be treated with the same basic methods for the neutral particle transport, perhaps with some minor modifications.

  This short course addresses the latest development on the radiation particle transport theory, numerical methods, and applications. The course provides key basic theory of the particle transport as well as a selection of advanced numerical methods of modern attention. The subjects covered are an overview of deterministic methods, finite element method with applications to optical tomography and down-well logging problem, discrete ordinates methods, Monte Carlo method, perturbation and variational method with an application to spatial homogenization of heterogeneous fuel assemblies, multiband method for resonance cross section and fast reactor design, method of characteristics, and the Boltzmann-Fokker-Planck equation for charged particle transport. The course also includes several computer demonstration sessions using production codes. The lecturer in each subject is an internationally well recognized individual and a prominent authority in his respective field.

  The course is designed to provide continuing education to graduate students and practitioners at research institutes and industry working in the fields of nuclear reactor design, radiation protection and shielding, radiation dosimetry, nuclear medicine, and related areas. It is hoped that the course arouses strong interests from the newcomers to the subject and delivers maximum benefits to the participants already practicing in the subject fields.


 

Korea Advanced Institute of Science and Technology

Department of Nuclear and Quantum Engineering

Nuclear Reactor Analysis and Particle Transport Lab

 

Last update : February 26, 2001

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