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DEMONSTRATION DISPOSAL OF HIGH-LEVEL RADIOACTIVE SOLIDS IN LYONS, KANSAS, SALT MINE: BACKGROUND AND PRELIMINARY DESIGN OF EXPERIMENTAL ASPECTS

Description: A demonstration of the disposal of high-level radioactive waste solids to be carried out in a salt mine at Lyons, Kansas, will have as its objectives: (1) the demonstration of required waste-handling equipment and techniques, (2) the determination of the stability of salt under the influence of heat and radiation, and (3) the collection of information on creep and plastic flow of salt which is needed for the design of an actual disposal facility. As presently conceived, 14 irradiated fuel assem… more
Date: January 10, 1964
Creator: Bradshaw, R. L.; Perona, J. J. & Blomeke, J. O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Actinide Partitioning and Transmutation Program. Progress report, April 1--June 30, 1977

Description: Experimental work on the 16 tasks comprising the Actinide Partitioning and Transmutation Program was continued. Summaries of work are given on Purex Process modifications, actinide recovery, Am-Cm recovery, radiation effects on ion exchangers, LMFBR transmutation studies, thermal reactor transmutation studies, fuel cycle studies, and partitioning-transmutation evaluation. (JRD)
Date: October 1, 1977
Creator: Tedder, D. W. & Blomeke, J. O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Review and Analysis of European Industrial Experience in Handling LWR Spent Fuel and Vitrified High-Level Waste

Description: The industrial facilities that have been built or are under construction in France, the United Kingdom, Sweden, and West Germany to handle light-water reactor (LWR) spent fuel and canisters of vitrified high-level waste before ultimate disposal are described and illustrated with drawings and photographs. Published information on the operating performance of these facilities is also given. This information was assembled for consideration in planning and design of similar equipment and facilities… more
Date: July 10, 2001
Creator: Blomeke, J.O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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EVALUATION OF ULTIMATE DISPOSAL METHOD FOR LIQUID AND SOLID RADIOACTIVE WASTES. PART I. INTERIM LIQUID STORAGE

Description: As the first part of a study to evaluate the economics of the various steps leading to and including the permanent disposal of high-activity liquid and solid radioactive waste, costs of interim liquid storage of acid and alkaline Purex and Thorex wastes were estimated for storage times of 0.5 to 30 years. A 6- ton/day plant was assumed, processing 1500 tons/year of uranium converter fuel at a burnup of 10,000 Mwd/ton and 270 tons/year of thorium converter fuel at a burnup of 20,000 Mwd/ton. Tan… more
Date: August 22, 1961
Creator: Bradshaw, R.L.; Perona, J.J.; Roberts, J.T. & Blomeke, J.O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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EVALUATION OF ULTIMATE DISPOSAL METHODS FOR LIQUID AND SOLID RADIOACTIVE WASTES. PART II. CONVERSION TO SOLID BY POT CALCINATION

Description: The costs of pot calcination of Purex and Thorex wastes were calculated. The wastes were assumed produced by a plant processing 1500 ton/year of U converter fuel at a burnup of 10,000 Mwd/ton and 270 ton/year of Th converter fuel at 20,000 Mwd/ton. Costs were calculated for processing Purex waste in acidic and reacidified forms and for processing Thorex wastes in acidic and reacidified forms and with constituents added for producing an acidic Thorex glass. Calcination vessel designs were right … more
Date: October 16, 1961
Creator: Perona, J.J.; Bradshaw, R.L.; Roberts, J.T. & Blomeke, J.O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Actinide partitioning and transmutation program progress report, October 1, 1976--March 31, 1977

Description: Experimental work on the 16 tasks comprising the Actinide Partitioning and Transmutation Program was initiated at the various sites. This work included the development of conceptual material balance flowsheets which define integrated waste systems supporting an LWR fuel reprocessing plant and a mixed (U-Pu) oxide fuel refabrication plant. In addition, waste subsystems were defined for experimental evaluation. Computer analysis of partitioning-transmutation, utilizing an LMFBR for transmutation,… more
Date: January 1, 1977
Creator: Blomeke, J. O. & Tedder, D. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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EVALUATION OF ULTIMATE DISPOSAL METHODS FOR LIQUID AND SOLID RADIOACTIVE WASTES. PART III. INTERIM STORAGE OF SOLIDIFIED WASTES

Description: The costs of interim storage of solidified Purex and Thorex wastes in water-filled canals were estimated as the third part of a study to evaluate, from the standpoint of econoNonemics and hazards, the various steps leading to and including the permanent disposal of highly radioactive liquid and solid wastes. The wastes were assumed to have been solidified following their production in a plant proccessed 1500 metric tons per year of uranium converter fuel it a burnup of 10,000 Mwd/ton and 270 to… more
Date: October 21, 1963
Creator: Blomeke, J O; Perona, J J; Weeren, H O & Bradshaw, T L
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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EVALUATION OF ULTIMATE DISPOSAL METHODS FOR LIQUID AND SOLID RADIOACTIVE WASTES. IV. SHIPMENT OF CALCINED SOLIDS

Description: The costs of shipping caleined Purex and Thorex wastes were calculated assuming the wastes were produced by a plant processing 1500 metric tons/year of U converter fuel at a burnup of 10,000 Mwd ton, 270 metric tons/year of Th converter fuel at 20,000 Mwd/ton. Calculations were made for Purex waste calcined in acidic and reacidified (after alkaline storage) forms and for Thorex waste calcined in acidic and reacidified forms and with constituents added for producing an acidic Thorex glass. Shipp… more
Date: October 18, 1962
Creator: Perona, J.J.; Bradshaw, R.L.; Blomeke, J.O. & Roberts, J.T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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EVALUATION OF ULTIMATE DISPOSAL METHODS FOR LIQUID AND SOLID RADIOACTIVE WASTES. V. EFFECTS OF FISSION PRODUCT REMOVAL ON COSTS OF WASTE MANAGEMENT

Description: In a study based on optimistic expectations of waste composition from future fission product separations processes, estimated costs for management of wastes from which 90 and 99% of all fission products were removed were from 70 to 80% of those for management of waste from which no fission products were removed. This cost difference is not believed to be sufficient to pay for the separation and final disposal of the fission products, which was not included in the waste management costs; hence, … more
Date: June 26, 1963
Creator: Perona, J.J.; Blomeke, J.O.; Bradshaw, R.L. & Roberts, J.T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Projections of spent fuel to be discharged by the U. S. nuclear power industry

Description: Calculated properties of spent fuel projected to be discharged and accumulated by the U.S. nuclear power industry through the year 2031 A.D. are presented. The projections are based on installed nuclear capacities of 380 and 543 GW(e) in the year 2000 and 2030, respectively. They include compilations of the grams of the elements, curies of radioactivity, thermal decay power, photon and neutron emission rates, and radiotoxicities of the assemblies that are accumulated at a Spent Unreprocessed Fu… more
Date: October 1, 1977
Creator: Alexander, C. W.; Kee, C. W.; Croff, A. G. & Blomeke, J. O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Overall Assessment of Actinide Partitioning and Transmutation for Waste Management Purposes

Description: A program to establish the technical feasibility and incentives for partitioning (i.e., recovering) actinides from fuel cycle wastes and then transmuting them in power reactors to shorter-lived or stable nuclides has recently been concluded at the Oak Ridge National Laboratory. The feasibility was established by experimentally investigating the reduction that can be practicably achieved in the actinide content of the wastes sent to a geologic repository, and the incentives for implementing this… more
Date: January 1, 1980
Creator: Blomeke, J. O.; Croff, A. G.; Finney, B. C. & Tedder, D. W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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An Investigation of ThF4 - Fused Salt Solutions for Homogeneous Breeder Reactors

Description: Technical report presenting a consideration of the characteristics of fused salt-ThF4 solutions suitable for use in homogeneous reactors. Presented in tandem with a brief survey of the literature pertaining to such solutions and a summary of the experimental work accomplished. [From Abstract]
Date: June 19, 1951
Creator: Blomeke, J. O. & Johnston, C. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Preliminary assessment of partitioning and transmutation as a radioactive waste management concept

Description: Partitioning (separating) the actinide elements from nuclear fuel cycle wastes and transmuting (burning) them to fission products in power reactors represents a potentially advanced concept of radioactive waste management which could reduce the long-term (greater than 1000 years) risk associated with geologic isolation of wastes. The greatest uncertainties lie in the chemical separations technology needed to recover greater than 99 percent of the actinides during the reprocessing of spent fuels… more
Date: September 1, 1977
Creator: Croff, A. G.; Tedder, D. W.; Drago, J. P.; Blomeke, J. O. & Perona, J. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Aqueous Uranium Slurry Studies

Description: A summary of the laboratory development program on aqueous uranium slurry fuels for the Homogenous Reactor Project during the period April 1951 through March 1953 is presented. These investigations were devoted primarily to a study of the uranium oxides in aqueous suspensions. It was concluded that U(VI) was most likely to be the stable valence state in such slurry fuels and it was shown that β-UO3·H2O platelet crystals were the stable modification at 250°C. Very pure slurries of β-UO3·H2O pla… more
Date: October 20, 1955
Creator: Blomeke, J. O.; Bamberg, J. L.; Blomeke, J. O.; Bruce, F. R.; Fulmer, J. M.; McBride, J. P. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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