● 課程說明(Course Desc<x>ription)
<br>This course is designed to function both as a text for first-year graduate courses in nuclear materials and as a reference for workers involved in the materials design and performance aspects of nuclear power plants. The contents are arranged as follows: point defects in solids, diffusion in solids, dislocations and grain boundaries, equation of state of UO/sub 2/, fuel element thermal performance, fuel chemistry, behavior of solid fission products in oxide fuel elements, swelling due to fission gases, pore migration and fuel restructuring kinetics, fission gas release, mechanical properties of UO/sub 2/, radiation damage, radiation effects in me<x>tals, interaction of sodium and stainless steel, modeling of the structural behavior of fuel elements and assemblies.
<br>
<br>● 指定用書(Text Books)
<br>D.R. Olander, "Fundamental Aspects of Nuclear Reactor Fuel Elements," Chapter 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 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	Raiation-Induced Segregation
<br>Chapter 7	Dislocation Microstrucure
<br>Chapter 8	Irradiation-Induced Voids and Bubbles
<br>Chapter 9	Radiation Hardening and Embrittlement
<br>
<br>● 成績考核(Evaluation)
<br>Homework (15%)
<br>Midterm Examination (30%)
<br>Final Examination (35%)
<br>Presentation (10%)
<br>Final Report (10%)
<br>