Estimates of radionuclide release from glass waste forms in a tuff repository and the effects on regulatory compliance
This paper discusses preliminary estimates of the release of radionuclides from waste packages containing glass-based waste forms under the expected conditions at Yucca Mountain. These estimates can be used to evaluate the contribution of waste package performance toward meeting repository regulatory restrictions on radionuclide release. Glass waste will be held in double stainless steel canisters. After failure of the container sometime after the 300 to 1000 year containment period, the open headspace in these cans will provide the only area where standing water can accumulate and react with the glass. A maximum release rate of 0.177 g/m{sup 2} x year or 1.3 grams per year was obtained. Normalized loss of 1.3 grams per year corresponds to 0.08 parts in 100,000 per year of the 1660 kg reference weight of DWPF glass.
- Research Organization:
- Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
- DOE Contract Number:
- W-7405-ENG-48
- OSTI ID:
- 59909
- Report Number(s):
- UCRL-93735; CONF-860418-10; ON: DE86012191
- Resource Relation:
- Conference: 88. annual meeting of the American Ceramic Society, Chicago, IL (United States), 27 Apr - 1 May 1986; Other Information: PBD: Apr 1986
- Country of Publication:
- United States
- Language:
- English
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