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| META0030-2 | Nuclear Materials I
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| Duration : | 18h Th, 10h Pr, 10h Vis. |
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| Credits/ECTS : |
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| Holder(s) : | Jacqueline Lecomte‑Beckers |
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| Language : | English language |
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| Course contents : |
- Brief review of most important mechanical properties of materials
- stress-strain relationship
- ductile and brittle fracture; ductile-brittle transition
- fatigue failure
- creep
- Stress analysis: stress intensity, thermal stresses
- Functional requirements of materials in a nuclear environment
- "nuclear" materials: fuel, fuel cladding, moderator/reflector, coolant
- structural materials: reactor internals and vessel, piping, valves
- Degradation mechanisms of materials in a nuclear environment
- radiation effects: general principles, atomic displacements, embrittlement, swelling fatigue: due to thermal stresses and stratification
- corrosion: p.m. (to be developed in course "Nuclear Materials II"
- Detailed treatment of important materials in a nuclear environment (especially nuclear-
mechanical interactions and relationships)
- fuel and cladding
- moderator/reflector
- structural materials (incl reactor internals, reactor vessel).
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| Course objective : |
- To familarise students with the basic aspects of material science as they apply to nuclear systems
- To learn the basic processes of material degradation and ageing due to the nuclear environment (esp. radiation effects and fatigue).
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| Prerequisites : | Basic chemistry, material behaviour.
REFERENCE BOOKS ON PREREQUISITE
See website www.sckcen.be/bnen (http://www.sckcen.be/bnen,)
Brochures and Info, Background books W. D'haeseleer |
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| Organization : |
- 1 t.m.
- Visits to SCK*CEN laboratories
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| Written notes : |
- 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).
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| Assessment : | Oral examination; written preparation. |
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| Contacts : | Eric van Walle: eric.van.walle@sckcen.be |
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