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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 1
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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 1
Values of Young’s modulus.
(°C)
(MPa)
600
151000
700
89944
800
28889
900
16297
1000
8148
1100
8148
1200
2963