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2019　Nuclear Fusion Reactor Engineering

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Academic unit or major
Graduate major in Nuclear Engineering
Instructor(s)
Iio Shunji  Tsutsui Hiroaki  Yoshida Katsumi  Kondo Masatoshi 
Class Format
Lecture     
Media-enhanced courses
Day/Period(Room No.)
Tue5-6(原講571, North No.2, 5F-571)  Fri5-6(原講571, North No.2, 5F-571)  
Group
-
Course number
NCL.A402
Credits
2
Academic year
2019
Offered quarter
2Q
Syllabus updated
2019/3/18
Lecture notes updated
-
Language used
English
Access Index

Course description and aims

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.

Student learning outcomes

To understand the engineering issues to realize fusion reactors by obtaining knowledge about nuclear fusion reactions, plasmas, cooling, fusion materials, etc.

Keywords

nuclear fusion, plasma, magnetic confinement, tokamak, helical devices, blanket, neutron irradiation, cooling, fusion materials, super conducting magnet, plasma heating, plasma diagnostics

Competencies that will be developed

✔ Specialist skills Intercultural skills Communication skills Critical thinking skills Practical and/or problem-solving skills

Class flow

Lectured are given by four professors.

Course schedule/Required learning

  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 History of research for magnetic confinement and tokamak devices Students can explain histories of research for magnetic confinement and tokamak devices. candidate coolants in fusion blanket.
Class 6 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 7 Experimental fusion reactor ITER Students can explain an experimental fusion reactor, ITER.
Class 8 Tritium fuel cycle in fusion reactors Students can explain tritium fuel cycle in fusion reactors
Class 9 Tritium behaviors in various materials of fusion reactors Students can explain tritium behaviors in various materials of fusion reactors.
Class 10 Safety issuses on fusion reacors Students canexplain 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.

Textbook(s)

Nothing in particular, but some handouts and/or slides are uploaded to OCW-i.

Reference books, course materials, etc.

Wston M. Stacey,""Fusion"", Wiley Interscience
K. Miyamoto, "Fundamentals of Plasma Physics and Controlled Fusion", NIFS-PROC-48, 2000

Assessment criteria and methods

Reports the themes of which are given during lectures.

Related courses

  • NCL.N401 ： Basic Nuclear Physics
  • NCL.N403 ： Nuclear Materials and Structures

Prerequisites (i.e., required knowledge, skills, courses, etc.)

None required.

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