23.04.2013 Views

Management of Commercially Generated Radioactive Waste - U.S. ...

Management of Commercially Generated Radioactive Waste - U.S. ...

Management of Commercially Generated Radioactive Waste - U.S. ...

SHOW MORE
SHOW LESS

Create successful ePaper yourself

Turn your PDF publications into a flip-book with our unique Google optimized e-Paper software.

REFERENCES FOR APPENDIX K<br />

K.30<br />

Acres Consulting Services, Ltd. 1977. "<strong>Radioactive</strong> <strong>Waste</strong> Repository Study." In Hydrogeology<br />

and <strong>Waste</strong> Containment. Atomic Energy <strong>of</strong> Canada Topical Report 08, Ottawa, Canada.<br />

Allard, B. H., H. Kipatsi and J. Rydberg. Sorption <strong>of</strong> Long-Lived Radionuclides on Clay and<br />

Rock--Determination <strong>of</strong> Distribution Coefficients; 2--Review <strong>of</strong> Literature, KBS Technical<br />

Report 55, KBS Scientific, Stockholm, Sweden.<br />

Ames, L. L. and D. Rai. 1978. Radionuclide Interactions with Soil and Rock Media.<br />

EPA 520/6-78-007, Environmental Protection Agency, Research Triangle Park, North Carolina.<br />

Ames, L. L. and B. Sand. 1958. "Factors Affecting the Maximum Hydrothermal Stability in<br />

Montmorillonites." Am. Mineral, 43: pp. 641-648.<br />

Blackburn, L. D., et al. 1978. Maximum Allowable Temperature for Storage <strong>of</strong> Spent Nuclear<br />

Reactor Fuel, HEDL-TME 78-37, Hanford Engineering Development Laboratory, Richland,<br />

Washington.<br />

Bradshaw, R. L. and W. C. McClain, eds. 1971. Project Salt Vault: A Demonstration <strong>of</strong> the<br />

Disposal <strong>of</strong> High-Activity Solidified <strong>Waste</strong>s in Underground Salt Mines. ORNL-4555, Oak<br />

Ridge National Laboratory, Oak Ridge, Tennessee.<br />

Breck, D. W. 1974 Zeolite Molecular Sieves. p. 537, John Wiley and Sons, New York.<br />

Dames and Moore. 1978. Thermomechanical Stress Analysis and Development <strong>of</strong> Thermal Loading<br />

Guidlines. Vol. 20 <strong>of</strong> Technical Support GEIS: <strong>Radioactive</strong> <strong>Waste</strong> Isolation in Geologic<br />

Formations. Y/OWI/TM-36. Prepared for the Office <strong>of</strong> <strong>Waste</strong> Isolation by the Union Carbide<br />

Corp., Oak Ridge, Tennessee.<br />

Eberl, D., G. Whitney and H. Khoury. 1978. "Hydrothermal Reactivity <strong>of</strong> Smectite," Am.<br />

Mineral, 63: 401-409.<br />

Grim, R. E. 1968. Clay Mineralogy. McGraw-Hill, New York.<br />

Haggblom, H. 1977. Calculations <strong>of</strong> Nuclide Migration in Rock and Porus Media Penetrated<br />

by Water, KBS Technical Report 52, KBS Scientific, Stockholm, Sweden.<br />

Hay, R. L. 1966. "Zeolites and Zeolithic Reactions in Sedimentary Rocks. Geol. Soc. Am.<br />

Special Paper 85, pp. 15-68, Geologic Society <strong>of</strong> America, New York.<br />

International Nuclear Fuel Cycle Evaluation, Working Group Seven. August, 1979. "Technical<br />

Details.<strong>of</strong> a Geologic Repository in Salt--Disposal <strong>of</strong> <strong>Radioactive</strong> <strong>Waste</strong>s". INFCE/WG.7/26.<br />

Appendix A. INFCE, Vienna.<br />

Jacobsson, A. 1977. A Short Review <strong>of</strong> the Formation, Stability and Cementing Properties<br />

<strong>of</strong> Natural Zeolites, KBS Technical Report 27, pp. 14-15, KBS Scientific, Stockholm,<br />

Sweden.<br />

Jenks, G. H. 1977. Maximum Acceptable Temperatures <strong>of</strong> <strong>Waste</strong>s and Containers During<br />

Retrievable Geologic Storage, Y/OWI/TM-42. Office <strong>of</strong> <strong>Waste</strong> Isolation,<br />

Union Cascade Corp., Oak Ridge, Tennessee.<br />

Karn-Bransle-Sakerhet. 1978. Handling <strong>of</strong> Spent Nuclear Fuel and Final Storage <strong>of</strong> Vitrified<br />

High-Level Reprocessing <strong>Waste</strong>, Volume 11, Geology, KBS Technical Report 011, pp. 47-48,<br />

KBS Scientific, Stockholm, Sweden.<br />

Latimer, W. M. 1952. The Oxidation States <strong>of</strong> the Elements and Their Potentials in Aqueous<br />

Solutions, pp. 220-228, 241, Prentice Hall, New Jersey.<br />

Mendel, J. E. et al. 1977. Annual Report on the Characteristics <strong>of</strong> High-Level <strong>Waste</strong><br />

Glasses. BNWL-2252 1977. Pacific Northwest Laboratory, Richland, Washington.

Hooray! Your file is uploaded and ready to be published.

Saved successfully!

Ooh no, something went wrong!