Nuclear power plant accident simulations of gasket materials under simultaneous radiation plus thermal plus mechanical stress conditions Page: 33 of 46
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1
0.8
0.6
0
0.4
0.2
0PREDICTED FOR MCC
-1810C + 6 kGy/h
- 2340C
101
100
AGING TIME, HR
Figure 23. Comparison of the transformed CSR result for 2340C with the combined
environment result predicted to simulate SA-1.0.8
0.6
0
0.4
0.2
01
10
at, AGING TIME AT 2300C, HR100
Figure 24. Time-temperature superposition of combined environment normalized tensile
elongation data (the elongation e divided by its unaged value, eo) for the MCC material
using the same 10 kcal/mol activation energy found to apply to CSR and CS results.26
o MCC- 2300C + 5.94 kGy/h
x MCC- 2000C + 5.88 kGy/h
x
0
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Gillen, K. T. & Malone, G. M. Nuclear power plant accident simulations of gasket materials under simultaneous radiation plus thermal plus mechanical stress conditions, report, July 1, 1997; Albuquerque, New Mexico. (https://digital.library.unt.edu/ark:/67531/metadc690316/m1/33/: accessed April 25, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.