Nuclear Reactor Kinetics and Plant Control (An Advanced Course in Nuclear Engineering)

Nuclear Reactor Kinetics and Plant Control
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Theory of slow neutrons 4. Critical Theory of the Fermi 5. Kinetics of the nuclear reactor at "zero power" 6. Effects of temperature and power on the kinetics of the reactor 7. Study of perturbations of reactivity 8. Introduction to nuclear power and research The course is addressed to students from the Nuclear Physics Degree at University of Pavia for duration of 16 hours. The course consists of a theoretical part during which basic principles of nuclear reactor physics and kinetics are overviewed and experimental experiences are illustrated and analysed and a practical part during which experimental experiences are performed at LENA reactor facility and the results of the measurements are discussed.

The basic topics of the course are: 1. Evaluation of the reactor effective multiplication factor Keff in subcritical condition and approximate calibration of reactor control rods; 2.

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Measurement of the moderator Void Coefficient; 5. Measurement of reactor power and shut-down transients and delayed neutrons kinetics analysis; 6. Analysis of the kinetics of saturable poisons in specific Xe ; 8. Fuel burn-up calculation and measurement of reactor control reactivity margin and shutdown reactivity margin; 9.

Evaluation of the reactor critical mass loading by means of the Inverse Multiplication Factor method. The course is addressed to students from the Nuclear Engineering Degree at Politecnico di Milano: the scheduled program of 40 hours is divided in 24 hours of lectures and 16 hours of practical training at the reactor. In this latter part, students can gain experience on the plant, assisting the reactor operators during the tasks necessary for the execution of the tests, measurements and activities mentioned above.

An Advanced Course In Nuclear Engineering Series

This is a 24 hour course and the main topics covered rise from global energy demand and consumption past, present and future to the Energetic Source Comparison fossil, renewable and nuclear ; from the Nuclear Fission and Fusion to the Principles of Operation of Nuclear Reactors Physics of the core and the kinetics of control ; from the Nuclear Power Plants of the second GEN II , third GEN III and fourth generation Gen IV to the Nuclear Research Reactors, the advanced nuclear research and Nuclear technologies applied to industry, medicine, agro-food industry and forensics investigation.

The overall course has the duration of one year h of theoretical lectures and laboratories and months of training stages in Italian or in foreign partner institutions. In particular, training objectives are: radiation protection, industrial applications of ionizing radiation, the production of radioisotopes and radiopharmaceuticals for nuclear medicine, methods of measurement and control of environmental radioactivity, nuclear analytical techniques applied to the science of materials and cultural heritage, the decommissioning of nuclear facilities, the techniques of reprocessing of irradiated nuclear fuel and radioactive waste management.

Furthermore LENA usually hosts trainees for stage period as part of their educational path, this is the case of the 6 months stages inside the international Master's Degree in Nuclear and Ionizing Radiation Technology. Professionals Training Nowadays, the need for specifically trained personnel, with particular regard to the aspects of operational safety, plays an increasingly prominent role in the industrial market. This aspect has particular importance in the nuclear field, where aspects such as high competence and ability to operate safely play a key role.

Therefore, in addition to the academic level education, thanks to the expertise achieved in the operation and management of the reactor, LENA offers also basic and advanced training courses for professionals from private Companies, Utilities and Governmental Institutions, both in national and international framework. The following Chart 2 shows a typical course organization process: starting from the detail analysis carried out together with the requester to the development and the final verification of effectiveness.

Nuclear Reactor Design An Advanced Course in Nuclear Engineering

Rent the eBook. FAQ Policy. About this book Understanding time-dependent behaviors of nuclear reactors and the methods of their control is essential to the operation and safety of nuclear power plants. Show all. Show next xx. Read this book on SpringerLink.

Recommended for you. The recent experimental and computational techniques to investiage the influence of irradiation on mechanical properties will also be introduced. Also it deals with the design methods of radiation counting, spectroscopy, timing and imaging system. It also covers the 2-dimensional x-ray radiography and advanced gamma-ray imagers together with emission and transmission tomographies and laminography, which can be extended into 3-dimensional imaging techniques.

Although focus of the lectures will be upon mastering fundamentals of the imaging physics, cutting-edge issues will also be discussed to stimulate graduate research in the related areas.

In addition to the basic principles of NMR techniques, some examples of NMR applications in biomedical research, nanoporous materials and NMR quantum computations are discussed and some basic NMR experiments related to lectures are performed. In this class, we will discuss the basic concepts of neutron scattering and various neutron scattering techniques such as small-angle neutron scattering, reflectometry, triple-axis spectroscopy, and neutron spin-echo spectroscopy. Based on these, representative examples of neutron scattering in nano-materials will be introduced.

This important alternative energy technology is evaluated comparatively in terms of technoeconomic, sociolpolitical and environmental aspects of nuclear energy uses. The nuclear energy utilization programs of major countries, regional or global basis are assessed for the characterization of different nuclear energy policy. In view of the established international nonproliferation regime and International Atomic Energy Agency IAEA , the prospect of Nuclear Energy Policy Alternatives should be analysed in conformity with changing policy issues. It contains the basics of nuclear fusion, fusion reactor analysis, experiments for inertial capture and magnetics, plasma heating, economic and environmental problems, and so on.

It also covers the case study of nuclear plasma fusion system designs. For this, it contains the basic principles of low-temperature plasmas and etc. And it studies several cases of industrial applications of plasma.

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The topics of the course include principles of particle acceleration, application of accelerators, characteristics of several kinds of accelerators. The fundamental characteristics of the charged particle beams passing through RF cavity and beam optical components are also discussed. Every lecture focuses on the regulatory experience, international regulatory information and trends, and up-to-date technologies of safety regulations. Every lecture includes the regulatory experience for the NPPs, international regulatory and trends, and up-to-date technologies of nuclear safety regulations.

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Every lecuture focuses on the regulatory experience, international regulatory information and trends, and up-to-date technologies of safety regulations. At the beginning of the semester, projects is given to the students and the results are evaluated at the end of the semester.

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Object systems are nuclear energy systems and radiation applaication systems for medical, science, etc. The course presents the requirements for publishing in a professional journal in nuclear and quantum engineering. Each student will write preliminary documents and a final paper for real or imaginary publication. Class-work time will be directed among pair and group work, peer evaluation and teacher interaction. The final paper will be orally presented to the class in a format similar to a professional meeting.

The content can be variable and will be chosen by the instructor. Methods of risk model development and their quantification with software tools are included. The topics of the course cover plant risk model, its uncertainty analysis, and recently emerging technical issues such as passive system risk assessment, human reliability, digitalized plant risk assessment, software reliability assessment, and automatic diagnostic features.

The irradiation and temperature effects are treated in view of theory and experiment, Nuclear fuel design, fabrication, performance assessment models, reliability analysis, and recent trends of nuclear core materials are explained. The properties and strengthening mechanisms of ferritic martensitic steels and nickel-base superalloys are explained in view of those high temperature nuclear environments.

The materials degradation in various environments such as, liquid-metal, super-critical water, super-critical CO2, high temperature helium, and so on, are described. Finally, the impact of the surface damage to high temperature properties are discussed. To encourage the participation of students, students seminar on selected topics are included as well as lectures. Also the cost-benefit, risk-benefit, Del-Phi, and the socio-political factor analysis will be discussed in order to be used as the input of the decision making for the new nuclear policy.

Emphasis on development of mathematical and numerical models, and solution techniques, of two-phase flow. Treatment of physical models of separated flow such as flow-regime map, wall friction and heat transfer, interfacial friction and heat transfer, bifurcation phenomena. Development of a simple two-phase code and performance of class practice for various events. All rights reserved. Principles and Applications of Nuclear Engineering. This course is designed to provide the key knowledge of the nuclear engineering to the graduate students with non-nuclear background interested in nuclear engineering.

Radiation Science, Technology, and Applications. Nuclear Reactor Kinetics.

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This course is designed to cover the dynamics of nuclear systems. Nuclear Reactor Analysis and Design. This course is designed to cover the nuclear reactor analysis and design, introduction of neutron transport equation, approximation of diffusion theory, solution of few-group and multi-group neutron diffusion equation, calculation of energy distribution of fast and thermal neutrons, and homogenization to heterogeneous reactors.

Fast Reactor Design and Analysis. This course deals with the essential principles, characteristics, and applications of the fast reactors utilizing fast neutrons. Reactor Thermal-Hydraulics.