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Ceramic and glass radioactive waste forms

Description: This report contains 14 individual presentations and 6 group reports on the subject of glass and polycrystalline ceramic radioactive waste forms. It was the general consensus that the information available on glass as a waste form provided a good basis for planning on the use of glass as an initial waste form, that crystalline ceramic forms could also be good waste forms if much more development work were completed, and that prediction of the chemical and physical stability of the waste form fa… more
Date: January 1, 1977
Creator: Readey, D.W. & Cooley, C.R. (comps.)
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Standby status report Hot Semiworks facility

Description: This report is written to provide information concerning the status of the Hot Semiworks facility as it is placed in stand-by on July 1, 1957. The plant was constructed in 1951 and early 1952. It vas operated on Redox type investigations until the last of 1953. The plant was then converted to the Purex flowsheet under Project CA 513 D. Operations on the Purex type investigations were started in early 1955 and continued until early in 1956. At that time a maintenance program for plant improvemen… more
Date: September 1, 1957
Creator: Cooley, C. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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WSEP 30-ton liquid transfer cask: Design criteria and performance tests

Description: Shipment of radioactive wastes in shielded transfer casks is a continuing practice between the 300 Area and the 200 Areas. However, the Waste Solidification Engineering Prototypes (WSEP) located in 324 Building, 300 Area, require the transfer of significant quantities of radioactive wastes. Two new 30-ton casks are being placed in service to accommodate the increased number of shipments. The purpose of this report is to document the design criteria, tests and calculations performed on the casks… more
Date: March 30, 1966
Creator: Cooley, C. R. & Spaeth, M. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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WSEP 30-Ton Liquid Transfer Cask: Design Criteria and Performance Tests

Description: Shipment of radioactive wastes in shielded transfer casks is a continuing practice between the 300 Area and the 200 Areas. However, the Waste Solidification Engineering Prototypes (WSEP) located in 324 Building, 300 Area, require the transfer of significant quantities of radioactive wastes. Two new 30-ton casks are being placed in service to accommodate the increased number of shipments. The purpose of this report is to document the design criteria, tests and calculations performed on the casks… more
Date: March 30, 1966
Creator: Cooley, C. R. & Spaeth, M. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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THE ZIRFLEX PROCESS INTERIM DEVELOPMENT SUMMARY

Description: The Zircaloy-clad fuels and the application of the Zirflex Process for dissolution are discussed. Zirflex chemical flowsheets are presented as developed by pilot plant operatlons. The Zirflex Process is applicable to the reprocessing of fuels from the Dresden Reactor and the PWR Reactor. Other applications of the process are the Plutonium Recycle Test Reactor fuels and the New Production Reactor fuels, possible fuels from the Experimental Breeder Reactor; NPD-2 fuels; and fuels from Carolina-Vi… more
Date: June 24, 1959
Creator: Platt, A.M. & Cooley, C.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hastelloy F Dissolver Installation in 321 Building

Description: Hastelloy F is a prime contender as a material of construction for plant dissolvers in the power fuel reprocessing program. Consequently, the fabrication and installation of dissolver was undertaken to delineate any unknown problems associated with the use of Hastelloy F; and, at the same time, to provide a vessel for development studies on the Niflex or the Sulfex processes. The purpose of this report is to describe the actual basis for design as well as to present the problems encountered dur… more
Date: May 25, 1959
Creator: Cooley, C. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Dissolution of Stainless Steel Clad Power Reactor Fuels with Nitric Acid and Hydrofluoric Acid

Description: The processing of irradiated fuels from power and propulsion reactors is planned by Hanford Atomic Products Operation as part of the Atomic Energy Commission's interim reprocessing scheme. The several chemical processes proposed for the reprocessing of these fuels may be divided into two categories: first, total dissolution processes which dissolve both fuel element cladding and core material and, second, selective dissolution processes which dissolve either cladding or core material. The Nifle… more
Date: October 12, 1959
Creator: Cooley, C. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Zirflex- Interim Development Summary

Description: The processing of spent fuels from nuclear power and propulsion reactors is planned by Hanford Atomic Products Operation as part of the Atomic Energy Commission's interim processing scheme. The spent nuclear fuels have cores of UO2, U, or alloys of U-Mb, U-Al, or U-Zr clad in either stainless steel, aluminum, or Zircaloy. This report discusses only the Zircaloy-clad fuels and the applications of the Zirflex Process for dissolution. Zirflex chemical flow sheets are presented as developed by pilo… more
Date: June 24, 1959
Creator: Platt, A. M. & Cooley, C. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Costs of mixed low-level waste stabilization options

Description: Selection of final waste forms to be used for disposal of DOE`s mixed low-level waste (MLLW) depends on the waste form characteristics and total life cycle cost. In this paper the various cost factors associated with production and disposal of the final waste form are discussed and combined to develop life-cycle costs associated with several waste stabilization options. Cost factors used in this paper are based on a series of treatment system studies in which cost and mass balance analyses were… more
Date: March 1, 1998
Creator: Schwinkendorf, W.E. & Cooley, C.R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Integrated process analysis of treatment systems for mixed low level waste

Description: Selection of technologies to be developed for treatment of DOE`s mixed low level waste (MLLW) requires knowledge and understanding of the expected costs, schedules, risks, performance, and reliability of the total engineered systems that use these technologies. Thus, an integrated process analysis program was undertaken to identify the characteristics and needs of several thermal and nonthermal systems. For purposes of comparison, all systems were conceptually designed for a single facility pro… more
Date: October 1, 1997
Creator: Cooley, C.R.; Schwinkendorf, W.E. & Bechtold, T.E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Comparison of costs for alternative mixed low-level waste treatment systems

Description: Total life cycle costs (TLCCs), including disposal costs, of thermal, nonthermal and enhanced nonthermal systems were evaluated to guide future research and development programs for the treatment of mixed low-level waste (MLLW) consisting of RCRA hazardous and low-level radioactive wastes. In these studies, nonthermal systems are defined as those systems that process waste at temperatures less than 350 C. Preconceptual designs and costs were developed for thirty systems with a capacity (2,927 l… more
Date: December 31, 1996
Creator: Schwinkendorf, W.E.; Harvego, L.; Cooley, C.R. & Biagi, C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Overview of DOE's field screening technology development activities

Description: The Department of Energy (DOE) has recently created the Office of Environmental Restoration and Waste Management, into which it consolidated those activities. Within this new organization, the Office of Technology Development (OTD) is responsible for research, development, demonstration, testing, and evaluation (RDDT E) activities aimed at meeting DOE cleanup goals, while minimizing cost and risk. Site characterization using traditional drilling, sampling, and analytical methods comprises a sig… more
Date: January 1, 1991
Creator: Frank, C.W.; Anderson, T.D.; Cooley, C.R.; Hain, K.E.; Lien, S.C.T. (USDOE Office of Environmental Restoration and Waste Management, Washington, DC (USA). Office of Technology Development); Snipes, R.L. (Martin Marietta Energy Systems, Inc., Oak Ridge, TN (USA)) et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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