We elucidate the present status and prospects of fusion reactors which are considered to be ultimate energy source. Issues and engineering approaches to plasma confinement schemes for fusion reaction control, first walls, blanket, materials, and engineering concerning fusion reactor design are lectured.
To understand the engineering issues to realize fusion reactors by obtaining knowledge about nuclear fusion reactions, plasmas, cooling, fusion materials, etc.
nuclear fusion, plasma, magnetic confinement, tokamak, helical devices, blanket, neutron irradiation, cooling, fusion materials, super conducting magnet, plasma heating, plasma diagnostics
|Intercultural skills||Communication skills||Specialist skills||Critical thinking skills||Practical and/or problem-solving skills|
Lectured are given by four professors.
|Course schedule||Required learning|
|Class 1||Fusion reactions and inertial confinement||Students shall understand and explain nuclear fusion reactions and inertial confinement. fusion.|
|Class 2||Fundamental prpperties of plasmas||Students shall understand and explain fundamental characteristics of plasma.|
|Class 3||MHD equations and MHD equilibrium||Students shall understand and explain MHD equation and its equilibria.|
|Class 4||MHD instabiliites||Students shall understand and explain MHD instabilities.|
|Class 5||Compatibility of structure materials with candidate coolants in fusion blanket||Students shall understand and explain compatibility of structure materials with candidate coolants in fusion blanket.|
|Class 6||History of research for magnetic confinement and tokamak devices||Students can explain histories of research for magnetic confinement and tokamak devices.|
|Class 7||Plasma heating and current drive, plasma diagnostics and superconducting magnets||Students can explain roles of plasma heating and current drive, plasma diagnostics and superconducting magnets in fusion devices.|
|Class 8||Experimental fusion reactor ITER||Students can explain an experimental fusion reactor ITER.|
|Class 9||High thermal load in first wall and diverter, and ITER test blanket modules||Students shall understand and explain high thermal load in first wall and diverter, and ITER test blanket modules.|
|Class 10||Liquid metal MHD in fusion blanket||Students shall understand and explain liquid metal MHD in fusion blanket.|
|Class 11||Current status and issues of fusion materials under severe condition (1)||Students can explain current status and issues of fusion materials under severe conditions.|
|Class 12||Current status and issues of fusion materials under severe condition (2)||Students can explain current status and issues of fusion materials under severe conditions.|
|Class 13||Design of fusion reactors||Students shall understand and explain design of fusion reactors.|
|Class 14||Tokamak prototype fusion reactors||Students can explain tokamak prototype fusion reactors.|
|Class 15||Helical type fusion devices||Students can explain helical type fusion devices.|
Nothing in particular, but some handouts and/or slide prints are distributed.
Wston M. Stacey,""Fusion"", Wiley Interscience
K. Miyamoto, "Fundamentals of Plasma Physics and Controlled Fusion", NIFS-PROC-48, 2000
Reports the themes of which are given during lectures.