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IAEAInternational Atomic Energy Agency
ASTM-Zr-2016
Is Spent Nuclear Fuel Immune from Delayed Hydride Cracking (DHC) during Dry Storage? –
An IAEA Coordinated Research Project
C. Coleman, V. Markelov, M. Roth, V. Makarevicius, Z. He, J.K. Chakravartty, A.M. Alvarez-Holston, Ali Kanwar Liaquat,,
L. Ramanathan, V. Inozemtsev.
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IAEA 2
Contribute information on DHC for Zircaloy-4
fuel cladding
The objective:
to evaluate the temperature dependence of the
loading threshold for DHC in Zircaloy-4 cladding and
apply the results to the conditions for dry storage.
The results are based on an international,
interlaboratory experimental programme.
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IAEA
Outline
• Limits of DHC
• Conditions during dry storage of spent
nuclear fuel
• Measurement of limits of DHC leading to
immunity
• Application to dry storage
3
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IAEA
Limits of DHC
• Hydrogen concentration
• Heating
• Stress intensity factor – KIH
• Temperature
4
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IAEA
Temperature dependence of DHC
5
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IAEA
Limits of DHC
• Hydrogen concentration
• Heating
• Stress intensity factor – KIH
• Temperature
6
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IAEA
History of DHC - definition of KIH
7
KI =ƒ(σ√a)
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IAEA
Limits of DHC
• Hydrogen concentration
• Heating
• Stress intensity factor – KIH
• Temperature
8
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IAEA
Conditions during dry storage
• High temperature from radioactive decay
that declines with time:
USNRC requires ≤ 400 °C
• Hoop stress from internal gas pressure that
declines with temperature through Gas Law:
USNRC requires ≤90 MPa
9
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IAEA
Potential failure mechanisms
• Oxidation: inert atmosphere
• I-SCC: no stress ramp and temperatures too
low for I migration
• Creep rupture: predicted strains < 1%
• DHC: subject of this paper
10
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IAEA 11
Cladding materials – Zircaloy-4
• LWR
• PWR Stress-relieved, 480 oC, 3.5 h (CWSR)
• CANDU
• Stress-relieved, 500 oC, 8 h
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IAEA 12
Cladding materials - dimensions
Outside diameter
mm
Wall thickness
mm
PWR 9.5 0.57
CANDU 13.1 0.39
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IAEA 13
Microstructure
Grain
width
(µm)
Grain
shape
Texture
FR
Strength
at 250°C
(MPa)
PWR <1 Elongated 0.58 419
CANDU 4 Elongated/
Equiaxed
0.66 256
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IAEA
Pin-Loading Tension Specimen, Fixture and
Assembly (Studsvik Nuclear)
14
KI = [P/(2t√W)] f (a/W)
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IAEA 15
Specimen preparation & testing
• 120 to180 ppm hydrogen added
• Circumferential hydrides
• 13 mm long section
• Two notches extended 1.5 mm by fatigue
• Crack detection by potential drop, crack
opening or microscopy
• Testing in temperature range 227 to 315 oC
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IAEA 16
Test temperature history
Tem
pe
ratu
re
Time
5 oC/min
1,5 oC/min
Peak temperature, 60 min
Test temperature30 min
Loading
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IAEA
Methods to test for KIH
• Multiple specimen method
• Based on ASTM E1681
• Constant displacement
• Based on ASTM E1681
• Stepped uploading
• Stepped downloading
17
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IAEA
Multiple separate specimens
18
1.E-11
1.E-10
1.E-09
1.E-08
1.E-07
0 10 20 30
Cra
ck
gro
wth
ra
te (
m/s
)
KI (MPa√m)
CANDU
250°C
7 MPa√m
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IAEA
Constant displacement
19
PWR
267°C
7.6 MPa√m
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IAEA
Stepped downloading
20
PWR
250°C
5.2 MPa√m
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IAEA
Crack surfaces after test on PWR
cladding at 267°C
21
Notch
Notch
DHC
DHCFatigue
Fatigue
Crack growth direction
Top: 6.16 mm, bottom: 6.55 mm;
difference 6.1%
KIH 7.6 MPa√m
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IAEA
Temperature dependence of KIH
22
KIH =√C/(1/(1-2ν)-σf/σy))
where
C = E2εT t/8π(1-ν2)2
0
5
10
15
20
25
220 240 260 280 300 320
KIH
(MPa√m
)
Test Temperature ( C)
PWR
PHWR
PWR calc
PHWR calc
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IAEA
High temperature limit for DHC in
PWR cladding, T0
23
0.01
0.1
1
10
100
0
5
10
15
20
25
200 220 240 260 280 300 320
Cra
ck g
row
th r
ate
(m
/sx1
0-8
)
KIH(M
Pa√
m)
Test Temperature (°C)
PWR KIH
V Ref [28]
PWR V
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IAEA
Immunity from DHC during dry
storage of spent nuclear fuel
24
0
10
20
30
40
50
60
70
80
90
0
100
200
300
400
500
0 10 20 30 40
Ho
op
str
es
s (
MP
a)
Te
mp
era
ture
(°C
)
Time (Years)
Immune at 360C
Immune at 320C
hoop stress
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IAEA
Critical flaw depth at US NRC limit
• a = (KIH/σ)2. Q/1.2 π
• Q, shape factor varies between 1.0 and 1.5
• Limiting stress, σ, is 90 MPa
• KIH = 5.2 MPa√m
• Flaw depth, a, 1.5 to 2.3 times cladding
thickness: through-wall
• No cracks observed up to 20 years storage
25
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IAEA
Summary
• KIH in Zircaloy fuel cladding measured by
four techniques.
• At 250°C value was 5.2 MPa√m for PWR
cladding.
• KIH increased with temperature to a high
value with corresponding drop in crack
growth rate.
• Represents immunity from DHC.
26
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IAEA
Summary (continued)
• For DHC, flaws have to be very large to
grow.
• The temperature immunity and large critical
flaw size imply DHC unlikely during dry
storage of spent fuel; conclusion supported
by surveillance.
• Recommend more surveillance and testing
of irradiated material to increase confidence
in this conclusion.
27