Thermal diffusivity of proton and spallation neutron ...€¦ · W and W-Re alloys (up to 25 mass %...
Transcript of Thermal diffusivity of proton and spallation neutron ...€¦ · W and W-Re alloys (up to 25 mass %...
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Tungsten R&D at ESS
Thermal diffusivity of proton and spallation neutron irradiated tungsten
Jemila Habainy1,2
Yongjoong Lee1, Yong Dai3, Srinivasan Iyengar1,2
European Spallation Source1, Lund University2 , Paul Scherrer Institut3
7th High Power Targetry Workshop, East Lansing, Michigan, June 2018
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ESS Tungsten Target
dpa/year in Tungsten
• 2.5 m diameter, rotating, helium-cooled, 7000 pure tungsten bricks, 8x3x1 cm3
• 5 MW, 2.0 GeV, 14 Hz pulsed proton beam
• 357 kJ/pulse deposited in target, 100 C/pulse, max. temp 450 C, max. stress 100 MPa
• Accumulated damage max. 2 dpa/year (5-year lifetime)
• Potential issues:
Degradation of thermal and mechanical properties, severe irradiation-induced embrittlement, fatigue, oxidation,
36 sectors
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Image by ESS-Bilbao
Jemila Habainy 7th High Power Targetry Workshop East Lansing, Michigan June 2018
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Unirr. tungsten – Fatigue studies
• Ramp up and normal beam pulses will cause thermal fatigue
• Fatigue and tensile tests were conducted at 25°, 280° and 480°C
• Comparing fatigue limits of rolled, forged and HIPed tungsten, from 4 different suppliers
– J. Habainy et al. Fatigue behaviour of rolled and forged tungsten at 25°, 280° and 480 °C, J. Nucl. Mater., vol. 465, pp. 438-447, 2015
– J. Habainy et al. Fatigue properties of tungsten from two different processing routes, J. Nucl. Mater., vol. 506, pp. 83-91, 2018
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Unirr. tungsten – Fatigue studies
Ductile to brittle transition temperature is high, some specimens are still completely brittle at 500°C
HIPed
Rolled
25 °C
480 °C 480 °C
280 °C
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PSI: SINQ Target Irradiation Program – STIP V
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560 MeV/ 1.3 mA Proton beam
• STIP-V Irradiated between 2007-2008
• 560 MeV/ 1.3 mA proton beam
• 2x hot-rolled W bars, size: 60x8x1mm
• 5-28 dpa, 100°-800 °C
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STIP-V irradiated tungsten
Rod 3 Rod 5
Jemila Habainy 7th High Power Targetry Workshop East Lansing, Michigan June 2018
Two low dose samples:
3.9 dpa, 158 appm He, Tirr 115 °C
5.8 dpa, 245 appm He, Tirr 140 °C
with approx. 2% Rhenium
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Jemila Habainy
LFA at PSI
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LFA – Light Flash Apparatus
9Jemila Habainy 7th High Power Targetry Workshop East Lansing, Michigan June 2018
Thermal conductivity = Thermal diffusivity Specific heat Density
Thermal diffusivity = 0.1388 d2
t1/2
https://www.netzsch-thermal-analysis.com/en/landing-pages/principle-of-the-lfa-method/
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Thermal diffusivity – unirradiated
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Effect of surface preparation
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Akiyoshi, M., Fusion Engineering and Design (2018), https://doi.org/10.1016/j.fusengdes.2018.03.008
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Thermal diffusivity – irradiated
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Effect of rhenium content on thermal diffusivity of unirradiated tungsten
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T. Tanabe et al. / Materials Letters 57 (2003) 2950–2953
Unirradiated
F. Hofmann et al. / Scientific Reports volume 5, Article number: 16042
(2015)
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W and W-Re alloys (up to 25 mass % Re) were
irradiated in the Japan materials test reactor
(JMTR) reactor at 330 K to thermal and fast
neutron fluences of 1.031020and 3.371019 (E> 1
MeV), respectively.
Effect of rhenium content on thermal diffusivity of neutron irradiated tungsten
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Effect of rhenium content on thermal diffusivity of neutron irradiated tungsten
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0.88
0.92
0.96
1
1E+11 1E+12 1E+13 1E+14
Ther
mal
dif
fusi
vit
y
Fluence [ions/cm2]
Normalised thermal diffusivity of gold
ion irradiated tungsten
Heavy ion irradiated tungsten foil
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Thermal diffusivity of annealed irradiated tungsten
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Annealed at 1000 C, 1 h
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Simulating temperature in ESS tungsten using LFA results
18Standard material data LFA material data (irr W)
Simulation model
Temperature [C] in ESS tungsten immediately after a
pulse
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Simulating stress in ESS tungsten using LFA results
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Standard material data
LFA material data LFA material data + 20 % increase in
stiffness
Equivalent stress in ESS tungsten immediately after a pulse
83 MPa 117 MPa
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20 mm
Unirr. tested at 450°C 1.4 dpa, tested at 450°C
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Summary
Studies of thermal and mechanical properties of irradiated tungsten:
Thermal diffusivity – decreased by 28-51% lower, depending on temperature. Annealing of 3.9 dpa W, at 1000 °C for 1 h, resulted in a slight recovery of thermal diffusivity.
Fatigue – lowest runout at 135 MPa. Rolled tungsten has higher fatigue limit but shows more scatter.
Hardness – increased by almost 75 % at 3.5 dpa
Ductility – tungsten shows zero ductility at ESS relevant temp., already at 1.3 dpa
Oxidation – even 5 ppm impurity in He will oxidize tungsten
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