240NU211 - Fusion Technology

Transcription

1 Coordinating unit: Teaching unit: Academic year: Degree: ECTS credits: ETSEIB - Barcelona School of Industrial Engineering FIS - Department of Physics MASTER'S DEGREE IN INDUSTRIAL ENGINEERING (Syllabus 2014). (Teaching unit Optional) MASTER'S DEGREE IN NUCLEAR ENGINEERING (Syllabus 2012). (Teaching unit Optional) 4,5 Teaching languages: English Teaching staff Coordinator: Others: De Blas Del Hoyo, Alfredo Futatani, Shimpei Degree competences to which the subject contributes Specific: 1. Ability to write the main systems of a nuclear power plant and identify the main features of such systems. 2. Knowledge of different reactor designs and nuclear plants, including proposals for future reactors, and will be able to assess their strengths and weaknesses. 1 / 9

2 Teaching methodology 1. LECTURES AND CASE EXAMPLES. Lectures are devoted to form the content of the subject, and some case examples enable to retain and quantify the presented concepts. These lecture sessions are supported by slides that graphically complement the main ideas of the presentations. Previous nesses to that, the slides are distributed to the students, making easy to follow the explanations. The "Digital Campus" will be used throughout the course. 2. MULTIMEDIA RESOURCES. Some technological aspects of the subject are complemented by multimedia projections: - Magnetic confinement Fusion. - Tore Supra. (Superconducting materials used in this experimental fusion device). - JET, Joint European Torus. 3. LAB WORK. The following lab work has been prepared with the aim of motivating the student: Use of a Nuclear Fusion Reactor Simulator type Tokamak for educational purposes. The students individually will simulate the following cases: P1. Reproduction of actual experiences of fusion devices (JET, Tore Supra). P2. ITER fusion reactor operation simulation. P3. Plasma confinement improvement in a fusion reactor. Safety factor profile inversion, magnetic shear. (10 hours) Methodology for the development of the lab work: - Presentation of the software: content, models included, and data base required. - Running of the simulation program: definition of input parameters and data, output data and storage. - Analysis of the results. - Guidance for the answers of the stated questions, and report elaboration. 4. TECHNICAL VISIT. Technical visit to the reactor Tore Supra and the ITER site in CEA, France: -Tore Supra is a thermonuclear fusion reactor type Tokamak, builded in The toroidal magnetic fields are created by using superconducting coils. The reactor is operated by the "Departament de Recherches sur la Fusion Contrôlée", of the "Commissariat d'energie Atomique", "Association EURATOM-CEA sur la fusion", Cadarache France. -Visit the ITER site in Cadarache. France. This is a thermonuclear reactor of 500 MW of nominal power, is a tokamak reactor. The coils are superconducting. The budget is more than M. This is the second biggest international project in the world. With the participation of: EEUU, Japón, Europa, China, Rusia, Corea, and India. (7 hours + travel) A special relevance is given to technological aspects related to the different heating and cooling methods as the Neutral Beam Injection (NBI), Radio Frequency (RF) heating systems, cryogenic systems, electrical systems for the generation of magnetic fields, and plasma diagnostics. Learning objectives of the subject At the end of the course the student will be able: a) To know the basic physics necessary in order to understand the development of nuclear fusion energy. b) To provide the state of art of the different technological ways towards the achievement of a commercial fusion reactor. 2 / 9

3 c) To understand the technological aspects required for the fusion energy production d) To applied the elemental background and tools for performance evaluations and calculations. e) To know the ITER project, the technological aspects, the objectives, and the construction schedule (CE8). Study load Total learning time: 112h 30m Hours large group: 0h 0.00% Hours medium group: 0h 0.00% Hours small group: 40h 30m 36.00% Guided activities: 0h 0.00% Self study: 72h 64.00% 3 / 9

4 Content 1. Introduction Learning time: 6h Theory classes: 3h Self study : 3h 1.1. Energy Resources Fusion Reactions Fuels Fusion products Thermonuclear fusion history. 2. Fusion reactions rate Learning time: 6h Theory classes: 3h Self study : 3h 2.1. Plasma kinetics 2.2. Thermonuclear plasma evolution 2.3. Cross sections 2.4. Two Maxwellian distributions 2.5. A monoenergetic beam and a Maxwelliam distribution 2.6. Fusion reaction rate 2.7. Fusion reaction rate in plasmas with only one kind of particles Power density. Fluency. 3. Energy losses 3.1. Radiative Power losses, Bremsstrahlung 3.2. Cyclotron radiation power loss Recombination 3.4. Charge exchange 4 / 9

5 4. Thermonuclear plasma balance Learning time: 4h Theory classes: 2h Self study : 2h 4.1. Lawson's criteria Conservation equations Thermal equilibrium and ignition temperature. 5. Plasma confinement systems Learning time: 8h Theory classes: 4h Self study : 4h 5.1 Introduction. Classification Open systems. Magnetic mirrors: confinement system; simple mirror, lowest B mirror; baseball mirror, Yingyang mirror Closed systems: Introduction, Stability, Magnetic fields (toroidal, pooidal) Tokamaks: JET. Tore-Supra, DIII-D. ITER Stellarators: TJ-II, LHD, Wendeistain 7-AS, Wendeistain 7-X. 6. Heating systems Learning time: 4h Theory classes: 2h Self study : 2h 6.1. Ohmic heating Neutral Beam Infection (NBI) Adiabatic compression Radio Frequency (RF) heating Relativistic electrons heating. 5 / 9

6 7. Plasma impurity. Fuel breeding 7.1. Impurities: effects, concentrations Helium accumulation Divertors Fuel breeding: gas blanking, NBI's. 8. Energy extractor systems 8.1. Fusion reactor's thermohydraulics Blanket design Energy Direct Conversion. 9. Diagnostic systems Learning time: 4h Theory classes: 2h Self study : 2h 9.1. Density measurements Temperature measurements Measurements of fusion products. 10. Neutronics. Tritium production Neutronic flux distribution Tritium production rate Neutron effects on reactor materials Shielding design. 6 / 9

7 11. Inertial fusion Introduction Lawson's criteria in ICS Inertial confinement steps Laser fusion: laser. Energy exchange with plasma Particles beams fusion: relativistic electrons, ions. 12. ITER project Learning time: 16h Theory classes: 8h Self study : 8h Main characteristics Design Construction schedule and planning Operation planning Safety and Environmental Impact. 7 / 9

8 Planning of activities USE OF A NUCLEAR FUSION REACTOR SIMULATOR TYPE TOKAMAK FOR EDUCATIONAL PURPOSES. Hours: 17h Laboratory classes: 5h Self study: 12h P1. Reproduction of actual experiences of fusion devices (JET, Tore Supra). P2. ITER fusion reactor operation simulation. P3. Plasma confinement improvement in a fusion reactor. Safety factor profile inversion, magnetic shear. Support materials: Experimental manual: Use of a Nuclear Fusion Reactor Simulator type Tokamak for educational purposes. Specific objectives: The objectives 1, 3 and 5 are achieved. Contribution to competences CE 7 and CE8. TECHNICAL VISIT TO THE REACTOR TORE SUPRA AND THE ITER SITE IN CEA, FRANCE: Hours: 6h Laboratory classes: 6h -Technical visit to the fusion reactor Tore Supra, tokamak, superconducter -Technical visit to the ITER site. Specific objectives: The objectives 1, 3 and 5 are achieved. Contribution to competences CE 7 and CE8. 8 / 9

9 Qualification system The student performances are assessed both by the continuous learning exams (50%), named NAC, and by the continuous work participation (50%), named NAEP. On the one hand, the qualification of the theoretical knowledge is determined by two exams. The first one will be done after the lecture of about 4 topics (NACET), and the second one will involve all the contents (NE). On the other hand, the qualification of the continuous work participation will be determined by the lab work reports (MP), the presence to the different lab works (AP), the participation to the technical visit (V), the attendance to the invited conferences (IC). Finally, the final qualification (NF) will be the maximum of the following qualifications: NF = Maximum (NF1, NF2 ) NF1 = NE NF2 = r * NE + (1- r) * NAC NAC = q * NAEP + (1- q) * NACET NAEP=1/4. MP + 1/4. AP + 1/4.V + 1/4 IC r = 0,5 q = 0,5 NF =Final qualification NE =Second exam result NAC =Qualification of the continuous learning exams NAEP = Qualification of the continuous work participation NACET = First exam result Bibliography Basic: Raeder, J. Controlled nuclear fusion : fundamentals of its utilization for energy supply. New York: Wiley & Sons, cop ISBN Wesson, John; Campbell, D. J. Tokamaks. 4th ed. Oxford : New York: Clarendon Press ; Oxford University Press, cop ISBN Dolan, Thomas James. Fusion Research : principles, experiments and technology. New York: Pergamon Press, ISBN Dies, J.; Albajar, F.; Fontanet, J. Simulator of nuclear fusion reactor,tipus tokamak, for educational proposals. Barcelona: UPC. Imatge, Dies, J. Slides of Nuclear Fusion: ITER. Barcelona: UPC. Imatge, Complementary: Hutchinson, I. H. Principles of plasma diagnostics. 2nd ed. Cambridge: Cambridge University Press, ISBN Wakatani, Masahiro. Stellarator and Heliotron Devices. Oxford: Oxford University Press, ISBN Adam, M.M.J. La Fusion thermonucléaire contrôlée par confinement magnétique. Paris: Masson, ISBN Kammash, Terry. Fusion reactor physics : principles and technology. Michigan: Ann Arbor Science, Freidberg, Jeffrey P. Plasma physics and fusion energy. Cambridge: Cambridge University Press, ISBN Others resources: 9 / 9