Servizi per la didattica
PORTALE DELLA DIDATTICA
Set-Cookie: language=it; path=/; domain=.polito.it;

Nuclear fission reactor physics and transport theory

01TWMND

A.A. 2019/20

Course Language

Inglese

Course degree

Master of science-level of the Bologna process in Energy And Nuclear Engineering - Torino

Course structure
Teaching Hours
Lezioni 65
Esercitazioni in aula 15
Teachers
Teacher Status SSD h.Les h.Ex h.Lab h.Tut Years teaching
Dulla Sandra Professore Ordinario ING-IND/18 35 15 0 0 2
Teaching assistant
Espandi

Context
SSD CFU Activities Area context
ING-IND/18 8 B - Caratterizzanti Ingegneria energetica e nucleare
2019/20
The course provides the specific physical and mathematical bases to be used in the study of the physics of fission and fusion reactors. The course is made of two parts. In the first, the kinetic theory is treated. The classic Boltzmann equation is deduced and the relationship between kinetic theory and fluid models is studied. In the second part the neutron transport equation and the physical principles of nuclear fission reactors are illustrated. Some simplified models and approximations for the description of the neutronics of multiplying systems are then presented, together with the fundamentals of criticality theory, reactor dynamics and perturbation theory.
The course provides the specific physical and mathematical bases to be used in the study of the physics of fission and fusion reactors. The course is made of two parts. In the first, the kinetic theory is treated. The classic Boltzmann equation is deduced and the relationship between kinetic theory and fluid models is studied. In the second part the neutron transport equation and the physical principles of nuclear fission reactors are illustrated. Some simplified models and approximations for the description of the neutronics of multiplying systems are then presented, together with the fundamentals of criticality theory, reactor dynamics and perturbation theory.
The part of the course on transport theory should enable the students to understand the fundamentals of kinetic theory and the link to neutronics and fluid-dynamics. The student should also acquire the basic knowledge on some of the mathematical physical models for the design of the cores of nuclear reactors. He should be able to carry out calculations and simulations of the neutronics of multiplying systems, criticality calculations and evaluations on the dynamics of nuclear reactors, and he should acquire the capability to physically interpret the results.
The part of the course on transport theory should enable the students to understand the fundamentals of kinetic theory and the link to neutronics and fluid-dynamics. The student should also acquire the basic knowledge on some of the mathematical physical models for the design of the cores of nuclear reactors. He should be able to carry out calculations and simulations of the neutronics of multiplying systems, criticality calculations and evaluations on the dynamics of nuclear reactors, and he should acquire the capability to physically interpret the results.
The student should have the basic knowledge of mathematics and physics, as can be acquired in the courses of a bachelor’s program in industrial engineering.
The student should have the basic knowledge of mathematics and physics, as can be acquired in the courses of a bachelor’s program in industrial engineering.
1 Kinetic theory of gases 1.1 Rarefied gases 1.2 Binary collisions 1.3 Boltzmann equation 1.4 H theorem 1.5 Equations of fluid-dynamics 2 Design calculation of multiplying structures 2.1 Generation of nuclear data; 2.2 Criticality calculation; multiplication eigenvalue and physical meaning; 2.3 Integration of the neutronic calculation in the design of a nuclear reactor. 3 Neutronic models 3.1 Multigroup diffusion theory; 3.2 Homogeneous and heterogeneous reactors; reflected reactors; 3.3 Neutron transport theory. 3.4 Slowing-down of neutrons in matter 4 Perturbation theory 4.1 Perturbation methods for eigenvalues; 4.2 Generalized perturbation techniques. 5 Nuclear reactor dynamics 5.1 Factorization methods for the solution of the neutronic equations; point kinetics and quasi-static method; 5.2 Non-linear feed-back effects; 5.3 Transmutation phenomena. 6 Mathematical and computational techniques 6.1 Spherical harmonics method 6.2 Discrete ordinate method 6.3 Analytical solution of the linear transport equation
1 Kinetic theory of gases 1.1 Rarefied gases 1.2 Binary collisions 1.3 Boltzmann equation 1.4 H theorem 1.5 Equations of fluid-dynamics 2 Design calculation of multiplying structures 2.1 Generation of nuclear data; 2.2 Criticality calculation; multiplication eigenvalue and physical meaning; 2.3 Integration of the neutronic calculation in the design of a nuclear reactor. 3 Neutronic models 3.1 Multigroup diffusion theory; 3.2 Homogeneous and heterogeneous reactors; reflected reactors; 3.3 Neutron transport theory. 3.4 Slowing-down of neutrons in matter 4 Perturbation theory 4.1 Perturbation methods for eigenvalues; 4.2 Generalized perturbation techniques. 5 Nuclear reactor dynamics 5.1 Factorization methods for the solution of the neutronic equations; point kinetics and quasi-static method; 5.2 Non-linear feed-back effects; 5.3 Transmutation phenomena. 6 Mathematical and computational techniques 6.1 Spherical harmonics method 6.2 Discrete ordinate method 6.3 Analytical solution of the linear transport equation
In the sessions applications of the theory presented in the lectures are proposed, such as: - Simulation of the collisional process in a gas - analytical solution of a 0D kinetic model - Analitycal solution of the neutron transport equation in the infinite medium
In the sessions applications of the theory presented in the lectures are proposed, such as: - Simulation of the collisional process in a gas - analytical solution of a 0D kinetic model - Analitycal solution of the neutron transport equation in the infinite medium
- Bell, G. I., and Glasstone, S. Nuclear Reactor Theory, Van Nostrand Reinhold Inc.,U.S., 1970 - A. F. Henry, Nuclear-reactor Analysis, MIT Press, 1975 - K. M. Case, P. F. Zweifel, Linear transport theory, Addison-Wesley, 1967 - R. V. Meghreblian, D. K. Holmes, Reactor Analysis, McGraw-Hill, 1960
- Bell, G. I., and Glasstone, S. Nuclear Reactor Theory, Van Nostrand Reinhold Inc.,U.S., 1970 - A. F. Henry, Nuclear-reactor Analysis, MIT Press, 1975 - K. M. Case, P. F. Zweifel, Linear transport theory, Addison-Wesley, 1967 - R. V. Meghreblian, D. K. Holmes, Reactor Analysis, McGraw-Hill, 1960
Modalità di esame: Prova orale obbligatoria;
The evaluation is carried out by an oral examination, to verify that the student knows the basic principles of particle transport, the fundamentals of nuclear reactor physics and the methods to solve neutron transport problems in steady state and in transient regimes. In the first part of the exam the student can present an argument of his choice. In the second part the student is asked to answer questions on both general transport theory and nuclear reactor physics.
Exam: Compulsory oral exam;
The evaluation is carried out by an oral examination, to verify that the student knows the basic principles of particle transport, the fundamentals of nuclear reactor physics and the methods to solve neutron transport problems in steady state and in transient regimes. In the first part of the exam the student can present an argument of his choice. In the second part the student is asked to answer questions on both general transport theory and nuclear reactor physics.


© Politecnico di Torino
Corso Duca degli Abruzzi, 24 - 10129 Torino, ITALY
m@il