一、課程說明(Course Desc<x>ription) 
<br>This is an advanced course under the topic of reactor physics and analysis. Basic concepts 
<br>associated with the fission chain reactions will be reviewed. As a major ob<x>jective of this 
<br>course, 
<br>students have to understand the developments of the neutron transport equations and the one-
<br>speed diffusion theory of a nuclear reactor. The established knowledge will be applied to derive 
<br>the multigroup diffusion model and to investigate the heterogeneous effects that are 
<br>considered in practical reactor design.    
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<br>二、指定用書(Textbooks) 
<br>James J. Duderstadt and Louis J. Hamilton, "Nuclear Reactor Analysis", 1st Edition, John Wiley 
<br>& Sons, 1976.
<br>
<br>三、參考書籍(References) 
<br>1. John R. Lamarsh and Anthony J. Baratta, “Introduction to Nuclear Engineering”, 3rd Edition, 
<br>Prentice Hall, 2001.
<br>2. Elmer E. Lewis, "Fundamentals of Nuclear Reactor Physics", Academic Press, 1st Edition, 
<br>Academic Press, 2008.  
<br>3. Elmer E. Lewis, "Computational Methods of Neutron Transport", 1st Edition, American 
<br>Nuclear Society, 1993.  
<br>
<br>四、教學方式(Teaching Method) 
<br>3 hours lecture per week。 
<br>
<br>五、教學進度(Syllabus) 
<br>Chapter 2： The Nuclear Physics of Fission Chain Reactions  (5 hours)
<br>Chapter 3： Fission Chain Reactions and Nuclear Reactors - an Introduction (1 hours)
<br>Chapter 4： Neutron Transport  (12 hours)
<br>Chapter 5： The One-Speed Diffusion Theory Model  (15 hours)
<br>Chapter 7： Multigroup Diffusion Theory  (6 hours)
<br>Chapter 8： Fast Spectrum Calculations and Fast Group Constants  (3 hours)
<br>Chapter 9： Thermal Spectrum Calculations and Thermal Group Constants  (3 hours)
<br>Chapter 10： Cell Calculations for Heterogeneous Core Lattice  (3 hours)
<br>
<br>六、成績考核(Evaluation) 
<br>Midterm        35%
<br>Final              35%
<br>Homework    30%
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