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Merriman, J.R.; Pashley, J.H.
Oak Ridge Gaseous Diffusion Plant, Tenn. (USA)1970
Oak Ridge Gaseous Diffusion Plant, Tenn. (USA)1970
AbstractAbstract
No abstract available
Source
1 Apr 1970; 16 p
Record Type
Report
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Country of publication
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INIS VolumeINIS Volume
INIS IssueINIS Issue
Stephenson, M.J.; Pashley, J.H.
Oak Ridge Gaseous Diffusion Plant, Tenn. (USA)1973
Oak Ridge Gaseous Diffusion Plant, Tenn. (USA)1973
AbstractAbstract
No abstract available
Primary Subject
Source
29 Aug 1973; 45 p
Record Type
Report
Literature Type
Progress Report
Report Number
Country of publication
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INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Original Title
Patent
Primary Subject
Source
2 Oct 1973; 22 p; US PATENT DOCUMENT 3,762,133
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Stephenson, M.J.; Eby, R.S.; Pashley, J.H.
Oak Ridge Gaseous Diffusion Plant, Tenn. (USA)1976
Oak Ridge Gaseous Diffusion Plant, Tenn. (USA)1976
AbstractAbstract
[en] Recent progress in the development of a fluorocarbon adsorption process for the recovery of krypton from the off-gas of fuel reprocessing plants is reported. Three packed columns comprise the main working sections of the process. Each column is designed to exploit certain gas-liquid solubility differences that exist between the solvent and the various gas constituents that might be present. The main separation of noble gas is accomplished in the absorber. The other two columns, each fitted with a reboiler and an overhead condenser, comprise the intermediate and final stripper sections of the plant
Primary Subject
Secondary Subject
Source
28 Jan 1976; 13 p; Available from NTIS; Available from NTIS. $4.50.
Record Type
Report
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Pashley, J.H.; Thomas, J.H.; Smith, R.L.
Oak Ridge Gaseous Diffusion Plant, TN (USA); Paducah Gaseous Diffusion Plant, KY (USA); Nuclear Assurance Corp., Washington, DC (USA)1982
Oak Ridge Gaseous Diffusion Plant, TN (USA); Paducah Gaseous Diffusion Plant, KY (USA); Nuclear Assurance Corp., Washington, DC (USA)1982
AbstractAbstract
[en] Since the Manhattan project days of World War II, the feed material for uranium isotope enrichment plants has been uranium hexafluoride (UF6). The deployment of a uranium metal-based enrichment process would, of course, lead to different conversion requirements and possibly to cost impacts as well. We discuss some of the technical feature changes which may be employed in both the provision of feed metal and the conversion of product to fuel-grade uranium dioxide and then describe some of the business/economic issues as they appear to us now
Original Title
Uranium-metal-based enrichment process
Primary Subject
Source
24 Feb 1982; 13 p; AICHE 1982 national winter meeting; Orlando, FL (USA); 28 Feb - 3 Mar 1982; CONF-820202--20; Available from NTIS, PC A02/MF A01; 1 as DE85015601; Portions of this document are illegible in microfiche products. Paper No. 16c.
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Merriman, J.R.; Stephenson, M.J.; Pashley, J.H.; Dunthorn, D.I.
Oak Ridge Gaseous Diffusion Plant, Tenn. (USA)1970
Oak Ridge Gaseous Diffusion Plant, Tenn. (USA)1970
AbstractAbstract
No abstract available
Source
1970; 29 p; 11. AEC air cleaning conference; Richland, Wash; 31 Aug 1970; CONF-700816--4
Record Type
Report
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Stephenson, M.J.; Merriman, J.R.; Dunthorn, D.I.; Pashley, J.H.
Oak Ridge Gaseous Diffusion Plant, Tenn. (USA)1972
Oak Ridge Gaseous Diffusion Plant, Tenn. (USA)1972
AbstractAbstract
No abstract available
Primary Subject
Source
1972; 15 p; 12. air cleaning conference; Oak Ridge, TN; 28 Aug 1972; CONF-720823--16
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Stephenson, M.J.; Dunthorn, D.I.; Reed, W.D.; Pashley, J.H.
Oak Ridge Gaseous Diffusion Plant, Tenn. (USA)1974
Oak Ridge Gaseous Diffusion Plant, Tenn. (USA)1974
AbstractAbstract
No abstract available
Primary Subject
Source
1974; 12 p; 13. air cleaning conference; San Francisco, California, USA; 12 Aug 1974; CONF-740807--13
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
BREEDER REACTORS, ELEMENTS, ENERGY SOURCES, EPITHERMAL REACTORS, FAST REACTORS, FBR TYPE REACTORS, FUELS, FUNCTIONAL MODELS, LIQUID METAL COOLED REACTORS, MANAGEMENT, NONMETALS, NUCLEAR FACILITIES, NUCLEAR FUELS, RARE GASES, REACTOR MATERIALS, REACTORS, SEPARATION PROCESSES, WASTE MANAGEMENT, WASTE PROCESSING, WASTES
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Hargrove, R.S.; Knighton, J.B.; Eby, R.S.; Pashley, J.H.; Norman, R.E.
Oak Ridge Gaseous Diffusion Plant, TN (USA); Lawrence Livermore National Lab., CA (USA)1986
Oak Ridge Gaseous Diffusion Plant, TN (USA); Lawrence Livermore National Lab., CA (USA)1986
AbstractAbstract
[en] AVLIS RD and D efforts are currently proceeding toward full-scale integrated enrichment demonstrations in the late 1980's and potential plant deployment in the mid 1990's. Since AVLIS requires a uranium metal feed and produces an enriched uranium metal product, some change in current uranium processing practices are necessitated. AVLIS could operate with a UF6-in UF6-out interface with little effect to the remainder of the fuel cycle. This path, however, does not allow electric utility customers to realize the full potential of low cost AVLIS enrichment. Several alternative processing methods have been identified and evaluated which appear to provide opportunities to make substantial cost savings in the overall fuel cycle. These alternatives involve varying levels of RD and D resources, calendar time, and technical risk to implement and provide these cost reduction opportunities. Both feed conversion contracts and fuel fabricator contracts are long-term entities. Because of these factors, it is not too early to start planning and making decisions on the most advantageous options so that AVLIS can be integrated cost effectively into the fuel cycle. This should offer economic opportunity to all parties involved including DOE, utilities, feed converters, and fuel fabricators. 10 refs., 11 figs., 2 tabs
Original Title
Effect of AVLIS feed requirements on overall fuel cycle
Primary Subject
Secondary Subject
Source
Aug 1986; 57 p; National meeting of the American Institute of Chemical Engineers; Boston, MA (USA); 24-27 Aug 1986; CONF-860826--13; Available from NTIS, PC A04/MF A01; 1 as DE87010275; Portions of this document are illegible in microfiche products.
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Leone, S.M.; Richardson, E.W.; Knight, R.G.; McGinnis, C.P.; Pashley, J.H.
Paducah Gaseous Diffusion Plant, KY (USA); Oak Ridge Gaseous Diffusion Plant, TN (USA)1978
Paducah Gaseous Diffusion Plant, KY (USA); Oak Ridge Gaseous Diffusion Plant, TN (USA)1978
AbstractAbstract
[en] It was assumed that a water insoluble uranium compound essentially free of fluorides would be the desired form for the final storage of cascade tails. UO2 produced in a two-step process in which the UF6 is reduced to UF4 with hydrogen in a tower reactor, followed by pyrohydrolysis to UO2 with steam in a screw reactor, has been selected as a suitable compound for storage. The UO2 would be stored in 55-gallon steel drums holding approximately 900 kg, and the drums would be warehoused until a permanent storage facility could be developed. Approximately one-third of the fluoride content of the UF6 will be recovered as anhydrous HF with potential for industrial sale, while the remaining fluoride content will be reacted with limestone and disposed of in landfills. The magnitude of the conversion process is illustrated by considering a typical electrical generation rate of 50 GW(e) per year. At this level, two plants nominally sized at 10 metric tons of uranium per day will be required
Primary Subject
Secondary Subject
Source
18 Dec 1978; 37 p; Available from NTIS., PC A03/MF A01
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Report
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Country of publication
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