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U.S. Department of Energy
Office of Scientific and Technical Information

Review of waste package verification tests. Semiannual report, April-September 1983. Volume 3

Technical Report ·
OSTI ID:5261894

The current study is part of an ongoing task to specify tests that may be used to verify that engineered waste package/repository systems comply with NRC radionuclide containment and controlled release performance objectives. Work covered in this report analyzes verification tests for carbon steel container corrosion and the testing methodologies that are appropriate for evaluating interaction effects between adjacent components in waste packages. Three testing programs were initiated this year to quantify anticipated conditions in salt and basaltic repository systems. In the first effort, natural rock salt was gamma irradiated in the dry (as-received) condition and also in the presence of saturated brine. The aim was to determine pH and total base concentration changes in brine arising from the interaction of the irradiated salt and migrating brine inclusions. The second effort was designed to evaluate the aqueous corrosion conditions around a carbon steel container in the presence of a bentonite/crushed basalt packing and gamma irradiation. The last testing program was designed to estimate the speed at which water could penetrate this packing and reach the container. Data from these tests are described. 40 references, 18 figures, 9 tables.

Research Organization:
Brookhaven National Lab., Upton, NY (USA)
DOE Contract Number:
AC02-76CH00016
OSTI ID:
5261894
Report Number(s):
NUREG/CR-3091-Vol.3; BNL-NUREG-51630-Vol.3; ON: DE84007883
Country of Publication:
United States
Language:
English