NucE
497A: Introduction to Nuclear
Engineering
Textbook: J. R. Lamarsh and A. Baratta, Introduction to Nuclear Engineering (3rd ed.), Prentice Hall, 2001.
Reference: W.M. Stacey, “Nuclear Reactor Physics”, John Willey & Sons, 2001
J. J. Duderstadt and L. J. Hamilton, Nuclear Reactor Analysis, John Wiley & Sons, 1976.
Instructor: Kostadin N. Ivanov, 206 Reber Building, 865-0040, kni1@psu.edu.
Goals: This course is designed as an intensive summer semester course providing introduction to nuclear engineering (Nuc E) to the undergraduate co-op students, and to graduate students with non-NucE background, and to returning students. After successfully completing this course, undergraduate students will be able to effectively follow the regular NucE curriculum.
Office Hours: By Appointment
Classes: Distance Education
Topics:
1. Introduction: Role of Nuclear Engineering (1 class)
2. Atomic and Nuclear Physics (3 classes)
3. Interaction of Radiation with Matter (3 classes)
4. Nuclear Reactors and Nuclear Power (2 classes)
5. Neutron Diffusion and Moderation (3 classes)
6. Nuclear Reactor Theory (4 classes)
7. Reactor Kinetics (4 classes)
Computer Usage: Students are required to use PCs on several homework assignments.
Lab Projects: None
ABET Category Content: Engineering science: 3 credits
Engineering design: 0 credits
Grading: 15% Homework
20% 1st Exam
30% 2nd Exam
35% 3rd Exam
Introduction to the course - Course objectives, Grading, homework, exams,
Attendance
Chapter
1 of Lamarsh
Lecture 1 The scope of nuclear engineering
Chapter
2 of Lamarsh
Lecture 2 Fundamental particles
Lecture 3 Radiation, radioactive decay and calculations
Lecture 4 Nuclear Reactions
` Chapter 3 of Lamarsh
Lecture 5 Neutron interactions and cross-sections
Lecture 6 Polyenergetic neutrons and fission
Lecture 7 Gamma-ray interactions and charged particles
Exam 1
Chapter
4 of Lamarsh
Lecture 8 Types of nuclear reactors
Lecture 9 Nuclear fuel cycles
Chapter
5 of Lamarsh
Lecture 10 Neutron flux and current, and diffusion equation
Lecture 11 Solutions of the diffusion equation
Lecture 12 The group diffusion method, thermal neutron diffusion, and two-group calculation of neutron moderation
Chapter
6 of Lamarsh
Lecture 13 One-group reactor equation, the slab reactor, and other reactor shapes
Lecture 14 The one group critical equation, and thermal reactors
Exam 2
Lecture 15 Reflected reactors, and multi-group calculations
Lecture 16 Heterogeneous reactors
Chapter
7 of Lamarsh
Lecture 17 Reactor kinetics
Lecture 18 Control rods and chemical shim
Lecture 19 Temperature effects on reactivity
Lecture 20 Fission product poisoning, and core properties during the lifetime
Exam 3