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2019　Nuclear Materials and Structures

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Academic unit or major
Graduate major in Nuclear Engineering
Instructor(s)
Kobayashi Yoshinao  Yoshida Katsumi 
Class Format
Lecture     
Media-enhanced courses
Day/Period(Room No.)
Tue3-4(原講571, North No.2, 5F-571)  Fri3-4(原講571, North No.2, 5F-571)  
Group
-
Course number
NCL.N403
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

This course focuses on materials issue related to fission nuclear reactors, and covers the fundamentals of nuclear materials and structural mechanics.
The contents are as follows:
a) Introduction of reactor types and major components of each reactor.
b) Materials science of nuclear fuel materials.
c) Coolants and control materials.
d) Cladding materials.
e) Neutron radiation damage and introduction of crystalline defects into crystals.
f) Property changes due to neutron irradiation.
g) Thermal stability of defects.
h) Structural mechanics of fuel assembly and reactor systems
i) Decommissioning engineering.
Aim of this course includes getting knowledge of nuclear materials and irradiation damage, structure of nuclear reactor components and required strength for them. The knowledge is the base for nuclear safety consideration.

Student learning outcomes

Students will be able to explain and discuss
1) Major components of fission nuclear reactors,
(a) such as nuclear fuels, structural materials, (b) control materials, coolants, (c) shielding materials,
from the view of materials science
2) Radiation damage of structural materials
3) Structural mechanics of nuclear reactors

Keywords

Fission nuclear reactor, Nuclear material, Fuel and structural materials, Neutron radiation damage, Defects in crystals, Structural mechanics, Structural design, Decommissioning engineering

Competencies that will be developed

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

Class flow

The instructor explains with handouts.

Course schedule/Required learning

  Course schedule Required learning
Class 1 Nuclear fission reaction and variety of nuclear fission reactors. Main components of nuclear reactors. Explain nuclear fission reaction and variety of nuclear fission reactors. Main components of nuclear reactors.
Class 2 Fabrication process of metals and relation to their properties. Explain fabrication process of metals and their properties.
Class 3 Requirements of materials properties for nuclear applications. Explain requirements of materials properties for nuclear applications.
Class 4 Interaction between neutrons and materials Explain interaction between neutrons and materials.
Class 5 Structural defects in crystal Explain structural defects in crystal.
Class 6 Introduction of crystalline defects into materials and their recovery. Structural materials and their irradiation response. Explain introduction of crystalline defects into materials and their recovery, and structural materials and their irradiation response.
Class 7 Properties of metallic and oxide fuel materials and their irradiation response. Explain properties of metallic and oxide fuel materials and their irradiation response.
Class 8 Control materials, coolants and shielding materials Explain control materials, coolants and shielding materials. Midterm examination of No.1-8
Class 9 Midterm examination of No.1-8 Midterm examination of No.1-8
Class 10 Fundamentals on structural integrity of components in nuclear power plant Explain fundamentals on structural integrity of components in nuclear power plant.
Class 11 Fundamentals on structural design of nuclear reactor: Material mechanics Explain fundamentals on structural design of nuclear reactor: Material mechanics.
Class 12 Structural design of fast reactor compared with light water reactor Explain structural design of fast reactor compared with light water reactor.
Class 13 Severe accident progression of FDNPP Comprehend severe accident progression of FDNPP
Class 14 Decommissioning of FDNPP Comprehend decommissioning of FDNPP
Class 15 Materials development of advanced reactors Comprehend materials development of advanced reactors

Textbook(s)

None required.

Reference books, course materials, etc.

Benjamin Ma, Nuclear reactor materials and applications, Van Norstrand reinhold company
K. Linga Murty and Indrajit Charit, An Introduction to Nuclear Materials: Fundamentals and Applications, Wiley-VCH
Henri Bailly, D. Menessier, C. Prunier, The Nuclear Fuel of Pressurized Water Reactors and Fast Neutron Reactors: Design and Behaviour, Intercept Ltd
Karl Whittle, Nuclear Materials Science, IOP

Assessment criteria and methods

Students’ course scores are based on midterm and final exams.

Related courses

  • NCL.C401 ： Nuclear Fuel Cycle Engineering
  • NCL.D401 ： Experiments for Materials related to Decommissioning A
  • TSE.A202 ： Solid Mechanics and Structure Engineering

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

No prerequisites.

Contact information (e-mail and phone)    Notice : Please replace from "[at]" to "@"(half-width character).

Yoshinao Kobayashi　(kobayashi.y.at[at]m.titech.ac.jp, 3075)
Katsumi Yoshida (k-yoshida[at]lane.iir.titech.ac.jp, 2960)

Office hours

Contact by e-mail in advance to schedule an appointment.

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