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| Version 2013-2014 |
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| GENU2002-1 | Advanced nuclear materials
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| Duration : | 28,5h Th, 3h Pr |
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| Number of credits : |
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| Lecturer : | N... |
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Language(s) of instruction :
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| English language |
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Course contents :
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| The ex cathedra part of the course covers the following main topics:
- Corrosion phenomena: description and occurrence
- Electrochemical and chemical study of corrosion problems: basic equations, user diagrams and practical examples
- Detailed study of frequently occurring corrosion types (e.g. pitting, IGA, SCC, ...): setting
and context, explanation, influences of the environment and material properties
- Methods of corrosion prevention and protection (design aspects, coatings, water treatment and inhibitors, electrochemical methods)
- Effects of radiation on corrosion (e.g., irradiation assisted corrosion)
- Corrosion problems in nuclear reactors: material behaviour and material requirements, technological aspects and environment-sensitive damage, with emphasis on light water reactors, in general, and steam generators, in particular
- Reactor pressure vessel life management: material degradation issues, legal context, advanced analysis and mitigation
- Fuel cladding and stainless steel degradation under irradiation
- Advanced treatment of irradiation effects in materials: radiation damage mechanisms at microscopic level
Some of these topics are further elaborated during seminars and visits to the SCK*CEN laboratories (incl. hot cells).
- Basic measurements: source strength, neutron flux (activation analysis, neutron counting), neutron spectrum (time of flight methods, unfolding methods), reaction rates
- Activity, dose and cross-section measurement
- Measurement of neutron transport parameters: stationary methods, pulsed neutron experiments
- Measurement of reactivities (and reactivity coefficients): survey, static methods, dynamic measurements, inverse kineticsStatistical fluctuation method: reactor noise, mathematical
analysis, applications (Rossi-alpha, sign correlations, zero crossings)
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Learning outcomes of the course :
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| To provide the students with a comprehensive treatment of the corrosion and embrittlement degradation mechanisms of materials in nuclear environment. |
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Prerequisites and co-requisites/ Recommended optional programme components :
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| Basic knowledge of materials science, chemistry and electrochemistry.
REFERENCE BOOKS ON PREREQUISITE
- See website www.sckcen.be/bnen, Brochures and Info, Background books W. D'haeseleer (mathematics)
- See introductory chapters in references above
- See also: Roberge, P.R., Handbook of Corrosion Engineering, McGraw-Hill, 1999.
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Planned learning activities and teaching methods :
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Mode of delivery (face-to-face ; distance-learning) :
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- 1 t.m.
- Visits to SCK*CEN laboratories (especially hot cells)
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Recommended or required readings :
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- Fontana, M.G., Corrosion Engineering, 3rd Ed., McGraw-Hill, 1986.
- Bogaerts, W.F., Active Library on Corrosion (CD-ROM), 2nd Ed., Elsevier, 1998.
- Benjamin, M., Nuclear Reactor Materials and Applications, Van Nostrand Reinhold, 1983.
- Glasstone, S. & A. Sesonske, Nuclear Reactor Engineering, 4-th Ed, Vol 1, Chapman & Hall, New York, 1994 (Chapter 7: Reactor Materials, pp 406-462).
- Cahn, R.W., Haasen, P., Kramer, E.J., Materials Science and Technology, Volume 10 B,
Volume editor Frost B.R.T. , Chapters 7-9
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Assessment methods and criteria :
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| Oral exam, written preparation. |
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Work placement(s) :
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Organizational remarks :
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Contacts :
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| Eric van Walle: eric.van.walle@sckcen.be |
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