Nuclear power plant accident simulations of gasket materials under simultaneous radiation plus thermal plus mechanical stress conditions Page: 11 of 46
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The first sample, which was never removed from its CS fixture, was also allowed to sit at
room temperature for a minimum of 12 h, after which it was quickly removed from its CS
fixture and transferred to another of the CSR jigs and compressed to the identical
thickness utilized in the CS fixture. After waiting at least another hour, the room
temperature force was obtained for both samples. Both samples were then quickly
transferred back to the CS fixtures for further aging in the LICA facility. By repeating
this procedure at several time intervals, it was possible to obtain compression stress
relaxation and compression set values versus aging time. Although the data sampling
procedures were somewhat different, the scatter in the compression stress relaxation
results from the two samples was similar to that found for identical samples run using the
standard CSR procedure.
Tensile tests
Tensile samples (-150 mm long by 6 mm wide) were cut from the compression-molded
sheets before aging. Tensile testing (5.1-cm initial jaw separation, 12.7 cm/min strain
rate) was performed on an Instron 1000 tensile testing machine equipped with pneumatic
grips and an extensometer clamped on the sample.
Density measurements
Density measurements were made using the Archimedes approach, in which the sample
(typically 20 mg) is weighed in air and then in ethanol. A minimum of 3 samples of each
material were measured and the average density recorded.
Modulus profiles
Modulus measurements were made using a computer-controlled, automated version of
our modulus profiling apparatus, which has been described in detail previously [8-10].
RESULTS AND DISCUSSION
Compression stress relaxation and compression set experimental results
Table 2 lists the experimental conditions (radiation dose rate, temperature, and
mechanical strain) for the 11 CSR and CS experiments. The five experiments on the
C65MCC sample are designated C65MCC-1, C65MCC-2, etc., with similar designations
for the five experiments on the C65M material. The experimental procedure was to
initially strain each sample in the special CSR jigs under room temperature (-23*C).
This was followed by a measurement of the sealing force as quickly as possible (typically
within 30 s of straining the sample), followed by a second measurement after -10 min.
The CSR jigs were then kept at room temperature (no radiation) for -20 h, at which time
a third force measurement was made. The initial decay in force over the first -20 h
represented purely physical relaxation processes (completely reversible); this decay was4
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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/m1/11/: accessed April 18, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.