Course Title : Nuclear Materials

Code 10C013
Course Year Master and Doctor Course
Term 1st term
Class day & Period Tue 1st
Location C3-Lecture Room 5
Credits 2
Restriction No Restriction
Lecture Form(s) Lecture
Language Japanese
Instructor Takagi Ikuji

Course Description


Course Goals

Course Topics

Theme Class number of times Description
Fission Reactor Materials 5 Overview of nuclear reactors (nuclear fission and its control), Nuclear fuel (abundance of U-235, isotope enrichment, fission cross section), Cladding materials (Zr-based alloys, hydrogen embrittlement), Control materials, Moderating materials, Cooling materials, Structural materials
Fusion Reactor Materials 4 Brief history of nuclear fusion, Structural materials (radioactivation, irradiation damage), Coil materials, Blanket materials (tritium breeding, fuel cycle), Plasma-facing materials (divertor, hydrogen recycling, tritium inventory)
Recent Topics 5
Feedback 1




Independent Study Outside of Class

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