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Release rates from waste packages in a salt repository

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:7150962
The authors previously predicted very low thermally induced brine migration velocity in a salt repository after the salt has consolidated against the waste package - so low that radionuclide release into the consolidated salt is expected to occur largely by molecular diffusion of species in brine in the salt grain boundaries. In this paper they present estimates of radionuclide release rates from waste packages into salt. This analysis shows that for the parameter values selected here, and for containment times of > 300 yr, release rates from individual waste packages in salt can meet the US Nuclear Regulatory Commission's (NRC's) performance objective for the engineered barrier system. If the container fails shortly after emplacement, the release rate for /sup 137/Cs is exceeded for up to 300 yr.
Research Organization:
Univ. of California, Berkeley (USA)
OSTI ID:
7150962
Report Number(s):
CONF-8711195-
Conference Information:
Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 55
Country of Publication:
United States
Language:
English