EU Nuclear Reactor Technology 2 GEN - 5PUGTRN2

Goal(s)

Nuclear fuel
The course provides an up-to-date overview of the different technological aspects associated to the design, fabrication and operation of the PWR (Pressurized Water Reactor) nuclear fuel. The introduction is devoted to present the major existing reactor designs and fuel technologies. The course then focalizes on the fuel assemblies of PWR and on a lesser degree SFR (sodium Fast Reactor). The final objective is to provide a global vision of fuel design with particular emphasis on the relationships between the various physical phenomena that affect the fuel assemblies. This course is taught in English.

Reactor Kit
In this course, each chapter is followed by a group project. With some technical help and communication advice from the teacher, each group has to understand (fully or half of) a scientific article (from a journal or a conference) dealing with some design studies or issues of an existing or paper nuclear reactor.
Since articles which complete each other are chosen, all different aspects about this (often innovative) nuclear reactor type are thus finally studied by the entire class and a consistent "student conference" can be given on the subject at the end by all groups, as an evaluation.

Nuclear safety
Know the main principle of nuclear safety. See applications of this principles on industrial cases

Content(s)

Nuclear fuel
Chapter 1 - Overview of reactors and fuel designs
Chapter 2 -PWR fuel assembly design
Chapter 3- Nuclear fuel materials (PWR and SFR)
Chapter 4 - Fuel rod design (PWR)
Chapter 5 - Fuel assembly mechanical design (PWR)
Chapter 6 - Fuel assembly thermal-hydraulics design (PWR)
Chapter 7 - Neutronics design (PWR)

Reactor Kit
Chapter 1 : design principles, attempt of classification
Chapter 2 : water-moderated reactors (PWR, CANDU, ...)
Chapter 3 : graphite-moderated reactors (RBMK, GTR, HTR, ...)
Chapter 4 : fast systems (GFR, SFR) and even more exotic/innovative ones

Nuclear safety
Introduction to safety principles : in-depth defense, safety functions, safety barriers, redundancy and diversification

• Nuclear Reactor Physics 1, 2 and 3
• Thermal-hydraulics 1 and 2
• Nuclear Reactor Technology 1

Test

Nuclear Fuel : The students are evaluated on a 2-hour written exam. All documents are forbidden at the written exam. The exams will have two parts: multiple choice questions and questions to be developed. One of the questions to be developed will be based on the conclusions of the student from the lecture of research papers provided during the course.

Additional Information

Bibliography

Nuclear Fuel:
[1] « Le Combustible Nucléaire des Réacteurs a Eau sous Pression et des Réacteurs a Neutron Rapides: Conception et Comportement », H Bailly, D. Ménessier, C. Prunier, Eyrolles, 1996.
[2] « RCC-C: Règles de conception et de construction applicables aux assemblages de combustible des centrales nucléaires REP », Association Française pour les règles de conception et de construction des matériel des chaudières électro-nucléaires (AFCEN), 1995.
[3] « Examen des critères techniques de sûreté du combustible nucléaire », OECD 2001.
[4] « Thermal analysis of Pressurized Water Reactors », L.S. Tong, J Weisman, American Nuclear Society, 1996.
[5] « Thermal Analysis of Liquid Metal Fast Breeder Reactors », Y.S. Tang, R.D. Coffield, Jr. R.A. Markley, American Nuclear Society, 1978.
[6] « Nuclear Reactor Engineering », S. Glasstone and A. Sesonske, 1994.
[7] « Nuclear Heat Transport », M.M. El-Wakil, 1971.