2017 | Nuclear Materials and Structures

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2017　Nuclear Materials and Structures

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Academic unit or major: Graduate major in Nuclear Engineering

Instructor(s): Yano Toyohiko Takahashi Minoru

Class Format: Lecture

Media-enhanced courses

Day/Period(Room No.): Tue3-4(North No.2, 5F-571) Fri3-4(North No.2, 5F-571)

Group: -

Course number: NCL.N403

Credits: 2

Academic year: 2017

Offered quarter: 2Q

Syllabus updated: 2017/4/26

Lecture notes updated: -

Language used: English

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Syllabus

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
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

Competencies that will be developed

✔ Specialist skills

Intercultural skills

Communication skills

Critical thinking skills

Practical and/or problem-solving skills

Class flow

1) The instructor explains with writing on the board. Students should take notes.
2) Attendance is taken in every class.

Course schedule/Required learning

Textbook(s)

None required.

Reference books, course materials, etc.

Benjamin Ma, Nuclear reactor materials and applications, Van Norstrand reinhold company, ISBN:0-442-22559-8
Murray and Holbert, Nuclear Energy, 7th edition, Elsevier ISBN:978-0-12-416654-7

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).

Toyohiko Yano　(tyano[at]nr.titech.ac.jp, 3380)
Minoru Takahashi (mtakahas[at]lane.iir.titech.ac.jp, 2957)

Office hours

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

	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 mechanical properties.	Explain fabrication process of metals and relation to their mechanical 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.	Explain introduction of crystalline defects into materials and their recovery.
Class 7	Properties of metallic fuel materials and their irradiation response.	Explain properties of metallic fuel materials and their irradiation response.
Class 8	Properties of oxide fuels and their irradiation response.	Explain properties of oxide fuels and their irradiation response.
Class 9	Structural materials and their irradiation response.	Explain structural materials and their irradiation response.
Class 10	Control materials, coolants and shielding materials	Explain control materials, coolants and shielding materials. Midterm examination of No.1-10 lectures.
Class 11	Fundamentals on structural integrity of components in nuclear power plant	Explain fundamentals on structural integrity of components in nuclear power plant.
Class 12	Fundamentals on structural design of nuclear reactor: (1) Material mechanics	Explain fundamentals on structural design of nuclear reactor: (1) Material mechanics.
Class 13	Fundamentals on structural design of nuclear reactor: (1) Material mechanics (Cont'd)	Explain fundamentals on structural design of nuclear reactor: (1) Material mechanics (Cont'd).
Class 14	Fundamentals on structural design of nuclear reactor: (2) Strength design of nuclear reactor components	Explain fundamentals on structural design of nuclear reactor: (2) Strength design of nuclear reactor components.
Class 15	Structural design of fast reactor compared with light water reactor	Explain structural design of fast reactor compared with light water reactor. Midterm examination of No.11-15 lectures.

TOKYO INSTITUTE OF TECHNOLOGY