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2019　Radioactive Waste Management and Disposal Engineering

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Academic unit or major
Graduate major in Nuclear Engineering
Instructor(s)
Tsukahara Takehiko  Takeshita Kenji  Takao Koichiro   
Class Format
Lecture     
Media-enhanced courses
Day/Period(Room No.)
Tue3-4(原講571, North №2, 5F-571)  
Group
-
Course number
NCL.C402
Credits
1
Academic year
2019
Offered quarter
3Q
Syllabus updated
2019/10/1
Lecture notes updated
-
Language used
English
Access Index

Course description and aims

A deep geological disposal is one of the most important ways for the safe treatment of various kinds of radioactive wastes generated by nuclear power and reprocessing plants. This course focuses on the relation between the disposal engineering and natural environments, and explains basic science and technologies in the waste disposal, e.g., vitrified glass, bentonite buffer material, canister, overpack, and rock.
Moreover, the course aims to cultivate students' skills to evaluate the safety and feasibility of the radioactive waste management scientifically.

Student learning outcomes

The goals of this course are as follows.
1. Students can understand the qualities, the safety, and the performances of engineered barrier systems consisting of vitrified glass, bentonite buffer material, canister, overpack, and rock.
2. Students can obtain the scientific knowledge of waste management and the problem solving abilities.

Keywords

Nuclear fuel cycle, waste management, deep geological disposal, vitrified glass, artificial barrier

Competencies that will be developed

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

Class flow

In order to enhance students' learning, the practice will be provided.

Course schedule/Required learning

  Course schedule Required learning
Class 1 Concept of nuclear waste disposal Studies on the characteristics of radioactive wastes and disposal methods
Class 2 Vitrified glass Studies on the fabrication methods of vitrified glass and their properties
Class 3 Designing, manufacturing, and welding methods of overpack Studies on the designing, manufacturing, and welding methods of overpack and their properties
Class 4 Corrosion, fracture, destruction, life span of overpack Studies on the evaluation of corrosion, fracture, destruction, life span of overpack
Class 5 Properties, design, and degeneration of bentonite buffer materials Studies on the properties, design, and degeneration of bentonite buffer materials
Class 6 Migraition behavior of water and radionuclides in the bentonite buffer materials Studies on the migration behavior of water and radionuclides in the bentonite buffer materials
Class 7 The natural environments for deep geological disposal Studies on the natural environments (geology, rock, hydraulic, geochemistry) and the quarantine function
Class 8 Evaluation of the safety and the feasibility of deep geological disposal Studies on a scenario and a solution for evaluating the safety and the feasibility of deep geological disposal

Textbook(s)

none

Reference books, course materials, etc.

Handouts will be distributed at the beginning of class when necessary.
Principles and Standards for the Disposal of Long-Lived Radioactive Waste, N. Chapman and C. McCombie, Pergamon(2003)

Assessment criteria and methods

Exercise and report

Related courses

  • NCL.C401 ： Nuclear Fuel Cycle Engineering
  • NCL.D405 ： Experiments for Nuclear Fuel Debris and Back‐end Fuel Cycle Ａ
  • NCL.D406 ： Experiments for Nuclear Fuel Debris and Back‐end Fuel Cycle B
  • CAP.E361 ： Radiation Chemistry
  • CAP.E362 ： Nuclear Chemical Engineering
  • NCL.C604 ： Nuclear Fuel Cycle Engineering Sepcial Laboratory

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

none

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

ptsuka[at]lane.iir.titech.ac.jp / 3067

Office hours

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