LEcture 6 Radiation Effects in Materials - ocw.mit.edu · •Intuitively understand a few radiation...
Transcript of LEcture 6 Radiation Effects in Materials - ocw.mit.edu · •Intuitively understand a few radiation...
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Qualitative Radiation Effects in Structural
Materials
22.14 – Nuclear Materials Slide 1
Figures taken from G. S. Was, “Fundamentals of Radiation Materials Science” unless otherwise noted
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Learning Objectives
• Intuitively understand a few radiation effects in structural materials
• Phase instability• Radiation induced segregation• Void swelling• Dislocation loops• Hardening & embrittlement
• Understand material selection choices in nuclear systems with radiation present
22.14 – Nuclear Materials Slide 2
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Phase Instability
• Precipitation and dissolution• Related to point defect movement towards sinks
22.14 – Nuclear Materials Slide 3
Movement of vacancies (V), interstitials (I), and atoms A & B towards a defect sink in a binary A-B alloy
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Directions of Movement
22.14 – Nuclear Materials Slide 4
Atomic size helps determine whether an atom will move preferentially via vacancies or interstitials
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Precipitation
22.14 – Nuclear Materials Slide 5
[Fig. 9.2 from Gary S. Was. Fundamentals of Radiation Materials Science.ISBN: 9783540494713] removed due to copyright restrictions.
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Precipitation
22.14 – Nuclear Materials Slide 6
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Dissolution
22.14 – Nuclear Materials Slide 7
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Effects of Temperature
22.14 – Nuclear Materials Slide 8
T (C)
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Remember This?
22.14 – Nuclear Materials Slide 9
Why do you think Cr moves away from the grain boundary?
[Fig. 6.1 from Gary S. Was. Fundamentals of Radiation Materials Science.ISBN: 9783540494713] removed due to copyright restrictions.
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Irradiation Creep
22.14 – Nuclear Materials Slide 10
Irradiated at 45 Mpa and nominal temperature of 605°C
Top of tube ~30°C higher in temperature
0 MPa 146 MPa
D9 steel at 40 dpa, 520°C HT9
Average diametral strain of ~8%
Maximum strain ~25%
~6% uniform strain
Courtesy of Garner, F. A. et al. Used with permission.
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Void Swelling
22.14 – Nuclear Materials Slide 11
© Garner, F. A. et al. All rights reserved. This content is excluded from our CreativeCommons license. For more information, see http://ocw.mit.edu/help/faq-fair-use/.
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Macroscale Void Swelling
22.14 – Nuclear Materials Slide 12
Swelling of spiral wrapped 316SS fuel cladding from the fast flux test reactor (FFTF)
© Makenas, B. J., S. A. Chastain, and B. C. Gneiting.All rights reserved. This content is excluded from ourCreative Commons license. For more information,see http://ocw.mit.edu/help/faq-fair-use/.
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Void Swelling Behavior
22.14 – Nuclear Materials Slide 13
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Void Swelling vs. Temperature
22.14 – Nuclear Materials Slide 14
© Garner, F. A. and D. S. Gelles. All rights reserved. This content is excluded from our CreativeCommons license. For more information, see http://ocw.mit.edu/help/faq-fair-use/.
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Void Swelling vs. Temperature
22.14 – Nuclear Materials Slide 15
[Fig. 8.19 from Gary S. Was. Fundamentals of Radiation Materials Science.ISBN: 9783540494713] removed due to copyright restrictions.
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Void Swelling vs. Gas Pressure
22.14 – Nuclear Materials Slide 16
G. R. Odette, T. Yamamoto and P. Wells. Michigan Ion Beam Workshop (2014)
This graph is in the public domain. This graph is in the public domain.
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Void Swelling vs. Precipitates
• Why would tempered martensite resist void swelling better?
• Think about density of defect sinks
22.14 – Nuclear Materials Slide 17
Voyevodin, Bryk, Borodin, Melnichenko, Kalchenko, Garner, 2012
Courtesy of Garner, F. A. et al. Used with permission.
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Void Swelling vs. Crystal Structure
22.14 – Nuclear Materials Slide 18
Surface of Uranus 50 duplex alloy irradiated at 625°C to 140 dpa
Ferrite grains swell less than austenite grains due to different swelling rate and different temperature regime of swelling
EP-450 at 480oC and 300 dpa without gas, showing swelling is strongest in ferrite grains
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When Does Void Swelling Happen?• Vacancy clustering can either form:
• Vacancy clusters (mini-voids)
• Dislocation loops
22.14 – Nuclear Materials Slide 19
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Energy Balance Determines
22.14 – Nuclear Materials Slide 20
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Which One Is Stable?
22.14 – Nuclear Materials Slide 21
What can stabilize voids for small size (m)?
• Gas pressure
• High stacking fault energy (harder to form loop)
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What Are These Loops?
22.14 – Nuclear Materials Slide 22
V. Gavini, K. Bhattacharya, M. Ortiz. Phys. Rev. B, 76, 180101(R)
© The American Physical Society. All rights reserved. This contentis excluded from our Creative Commons license. For moreinformation, see http://ocw.mit.edu/help/faq-fair-use/.
© The American Physical Society. All rights reserved. This contentis excluded from our Creative Commons license. For moreinformation, see http://ocw.mit.edu/help/faq-fair-use/.
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Visualizing Interstitial Loops
22.14 – Nuclear Materials Slide 23
doi:10.1038/srep00190
Reprinted by permission from Macmillan Publishers Ltd: Scientific Reports.Source: Yang, Z. et al, "Dislocation Loop Formation and Growth under InSitu Laser and / or Electron Irradiation." Scientific Reports 1, Articlenumber: 190 (2011). © 2011.
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Hardening, Embrittlement
22.14 – Nuclear Materials Slide 24
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Radiation Embrittlement
1. Defects are produced
2. Defects cluster, forming dislocation loops, precipitates, amorphous regions…
3. Dislocations can’t move as easily
4. Balance between slip & fracture is shifted
22.14 – Nuclear Materials Slide 25
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Embrittlement: Discuss
• Fuel unloading
• Pressurized thermal shock (PTS)
• Foreign Material Exclusion (FME)• Currently the largest source of LWR shutdowns
22.14 – Nuclear Materials Slide 26
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AP-1000 Material Selection
22.14 – Nuclear Materials Slide 27
Why are there only Alloy 718 grids on the top & bottom of the core?This table is in the public domain.
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Revisit Material Selection
Slide 28© source unknown. All rights reserved. This content is excluded from our CreativeCommons license. For more information, see http://ocw.mit.edu/help/faq-fair-use/.
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Material Selection: Core
22.14 – Nuclear Materials Slide 29
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22.14 Materials in Nuclear EngineeringSpring 2015
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