(PHYSICS AND NUMERICAL MODELS OF NUCLEAR REACTORS)
CdSINGEGNERIA NUCLEARE
Codice518II
CFU12
PeriodoAnnuale
LinguaInglese
The student who successfully completes the course will have the ability to understand the neutron transport phenomena typical of a nuclear reactor core, with reference both to the static and dynamic effects important for the reactor core design. He will be able to demonstrate a solid knowledge of the neutron diffusion and transport theories, particularly as it concerns their application to engineering problems like the determination of the multiplication constant of a reactor core or the calculation of a reactor fuel cell. He will be also aware of the mathematical and numerical tools that are at the basis of the typical reactor core calculations.
The student who successfully completes the course will have the ability to understand the neutron transport phenomena typical of a nuclear reactor core, with reference both to the static and dynamic effects important for the reactor core design. He will be able to demonstrate a solid knowledge of the neutron diffusion and transport theories, particularly as it concerns their application to engineering problems like the determination of the multiplication constant of a reactor core or the calculation of a reactor fuel cell. He will be also aware of the mathematical and numerical tools that are at the basis of the typical reactor core calculations.
During the oral examination the student will be assessed on his/her demonstrated ability to discuss with rigor the main course contents using the appropriate terminology. It is also expected that he/she will show a good ability in making connection between the different topics of the course.
Methods:
- Final oral exam
During the oral examination the student will be assessed on his/her demonstrated ability to discuss with rigor the main course contents using the appropriate terminology. It is also expected that he/she will show a good ability in making connection between the different topics of the course.
Methods:
- Final oral exam
The student will master the main analytical and numerical tools for the prediction of the behaviour of neutrons in nuclear reactors.
The student will master the main analytical and numerical tools for the prediction of the behaviour of neutrons in nuclear reactors.
Oral Examination with proposal of problems.
Oral Examination with proposal of problems.
The student will become acquainted with the behaviour of neutrons as the fundamental aspect of any nuclear plant, in terms of power production and energy. The inherent feedbacks, the dynamic and static behaviour should enter into the the DNA of any nuclear engineer as the focus of his / her study.
The matter proposes a fascinating series of topics, strictly linked to the history of nuclear energy (from Fermi and coworkers to the most up to date computational techniques). The student should feel this link to the historical and present developments of this fascinating matter.
The student will become acquainted with the behaviour of neutrons as the fundamental aspect of any nuclear plant, in terms of power production and energy. The inherent feedbacks, the dynamic and static behaviour should enter into the the DNA of any nuclear engineer as the focus of his / her study.
The matter proposes a fascinating series of topics, strictly linked to the history of nuclear energy (from Fermi and coworkers to the most up to date computational techniques). The student should feel this link to the historical and present developments of this fascinating matter.
The oral examination will provide sufficient easy to the teacher to assess the mstery that the student has reached in handling the fascinating mathematical and physical concepts and tools offered by the course.
The oral examination will provide sufficient easy to the teacher to assess the mstery that the student has reached in handling the fascinating mathematical and physical concepts and tools offered by the course.
Physical Principles of Nuclear Engineering. However, the course is conceived for staring from scratch in nuclear matters.
Physical Principles of Nuclear Engineering. However, the course is conceived for staring from scratch in nuclear matters.
None.
None.
Delivery: face to face
Learning activities:
- attending lectures
- participation in seminar
- participation in discussions
- Laboratory work
Attendance: Advised
Delivery: face to face
Learning activities:
- attending lectures
- participation in seminar
- participation in discussions
- Laboratory work
Attendance: Advised
Teaching methods:
- Lectures
- Seminar
- laboratory
The course covers the following aspects: the continuity equation, the Fick’s law and the diffusion equation of the neutrons; steady-state neutron diffusion problems with fixed source; the Green function of the diffusion equation; the neutron slowing down and the resonance absorption; the multiplication constant of a critical reactor with one or more energy groups; the delayed neutrons and the kinetic of a homogeneous reactor core; typical strategies to solve the criticality problems with one or more energy groups; solution of linear algebraic equation systems with direct or iterative methods (Jacobi, Gauss-Seidel, SOR, ADI,...); numerical solution of multigroup neutron kinetics problems with delayed neutrons; the integro-differential transport equation and its spherical harmonics approximation; the integral transport equation and its derivation from the integro-differential form; the collision probability method; the discrete ordinate method; the ray effect.
The course covers the following aspects: the continuity equation, the Fick’s law and the diffusion equation of the neutrons; steady-state neutron diffusion problems with fixed source; the Green function of the diffusion equation; the neutron slowing down and the resonance absorption; the multiplication constant of a critical reactor with one or more energy groups; the delayed neutrons and the kinetic of a homogeneous reactor core; typical strategies to solve the criticality problems with one or more energy groups; solution of linear algebraic equation systems with direct or iterative methods (Jacobi, Gauss-Seidel, SOR, ADI,...); numerical solution of multigroup neutron kinetics problems with delayed neutrons; the integro-differential transport equation and its spherical harmonics approximation; the integral transport equation and its derivation from the integro-differential form; the collision probability method; the discrete ordinate method; the ray effect.
Teaching materials provided by the teacher.
Recommended readings include:
- J.R. Lamarsh, Nuclear Reactor Theory, Addison Wesley Publishing;
- E.E. Lewis, W.F. Miller, Computational Methods of Neutron Transport, Wiley-Interscience Publication;
- G.I. Bell, S. Glasstone, Nuclear Reactor Theory, Van Nostrand Reinhold Company;
- A. Hebert; Applied Reactor Physics, Presses Internationales Polytechnique.
Teaching materials provided by the teacher.
Recommended readings include:
- J.R. Lamarsh, Nuclear Reactor Theory, Addison Wesley Publishing;
- E.E. Lewis, W.F. Miller, Computational Methods of Neutron Transport, Wiley-Interscience Publication;
- G.I. Bell, S. Glasstone, Nuclear Reactor Theory, Van Nostrand Reinhold Company;
- A. Hebert; Applied Reactor Physics, Presses Internationales Polytechnique.
Contact Prof. Valerio Giusti at v.giusti@ing.unipi.it for any direction.
Contact Prof. Valerio Giusti at v.giusti@ing.unipi.it for any direction.
Oral examination. It is possible to split the final examination into two parts, the first related to the Reactor Physics module, the second to the module of Numerical models. The two colloquia will be considered tests "in itinere".
The oral test consists of an interview between the candidate the lecturer and, generally, a lecturer's colleague or collaborator. The duration of the oral interview is ranging between one and two hours depending on the quality of it.
To pass the test the candidate has to show the ability of express him/herself in a clear manner using the correct terminology answering the posed questions. If the candidate will show a complete lack of knowledge of one of the different argument discussed during the course, the test will fail.
Oral examination. It is possible to split the final examination into two parts, the first related to the Reactor Physics module, the second to the module of Numerical models. The two colloquia will be considered tests "in itinere".
The oral test consists of an interview between the candidate the lecturer and, generally, a lecturer's colleague or collaborator. The duration of the oral interview is ranging between one and two hours depending on the quality of it.
To pass the test the candidate has to show the ability of express him/herself in a clear manner using the correct terminology answering the posed questions. If the candidate will show a complete lack of knowledge of one of the different argument discussed during the course, the test will fail.
At the end of the MSc Course, a thesis work in this matter will constitute a great opportunity, also for stages abroad.
At the end of the MSc Course, a theis work in this matter will constitute a great opportunity, also for stages abroad.
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