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Science and Technology of Nuclear Installations
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Science and Technology of Nuclear Installations
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2014
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Article
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Tab 3
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Research Article
Thermomechanical Model and Bursting Tests to Evaluate the Risk of Swelling and Bursting of Modified 9Cr-1Mo Steel Steam Generator Tubes during a Sodium-Water Reaction Accident
Table 3
Experimental results of SQUAT tests.
SQUAT test
Pressure (bar)
Target temperature (°C)
Bursting time measured (s)
Breaking elongation (%)
Strain rate (%/s)
9
70
1050
390
23
0.06
10
70
1050
401
15
0.04
7
70
1100
187
18
0.10
8
70
1200
42
20
0.48
1
70
1280
10.2
3
0.29
2
170
850
>2150
—
—
3
170
900
460
35
0.08
4
170
950
111
26
0.23
5
170
1000
39
20
0.51
6
170
1050
19.5
12
0.62