● 課程說明(Course Desc<x>ription)
<br>This course is designed to function both as a text for first-year graduate 
<br>courses in nuclear materials and as a reference for workers involved in the 
<br>materials design and performance aspects of nuclear power plants. Besides, 
<br>contents introduced in this course can be applied in other field such as in 
<br>semiconductor process and the aerospace applications.
<br>
<br>The contents are arranged as follows: point defects in solids, diffusion in 
<br>solids, dislocations and grain boundaries, equation of state of UO2, fuel 
<br>element thermal performance, fuel chemistry, behavior of solid fission 
<br>products in oxide fuel elements, swelling due to fission gases, pore migration 
<br>and fuel restructuring kinetics, fission gas release, mechanical properties of 
<br>UO2, radiation damage, radiation effects in me<x>tals, interaction of sodium 
<br>and 
<br>stainless steel, modeling of the structural behavior of fuel elements and 
<br>assemblies. 
<br>
<br>● 指定用書(Text Books)
<br>D.R. Olander, "Fundamental Aspects of Nuclear Reactor Fuel Elements," Chapter 
<br>17-19, TID-26711-P1, U.S. ERDA, 1976.
<br>
<br>● 參考書籍(References)
<br>M.W. Tompson, "Defects and Radiation Damage in Materials," Cambridge 
<br>University Press, 1969.
<br>G.S. Was, "Fundamentals of Radiation Matereials Science," Springer, 2007.
<br>
<br>● 教學方式(Teaching Method)
<br>任課老師以投影片授課
<br>修課學生上台做讀書報告
<br>
<br>● 教學進度(Syllabus)
<br>Chapter 1 Radiation Damage Events
<br>Chapter 2 The Displacement of Atoms
<br>Chapter 3 The Damage Cascade
<br>Chapter 4 Point Defect Formation and Diffusion
<br>Chapter 5 Radiation-Enhanced Diffusion and Rate Theory
<br>Chapter 6 Radiation-Induced Segregation
<br>Chapter 7 Dislocation Microstructure
<br>Chapter 8 Irradiation-Induced Voids and Bubbles
<br>Chapter 9 Radiation Hardening and Embrittlement
<br>
<br>● 成績考核(Evaluation)
<br>Homework (20%)
<br>Midterm Examination (30%)
<br>Final Examination (30%)
<br>Presentation (10%)
<br>Final Report (10%)