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GENI Program
16
The 1992 Pacific Northwest Residential Energy Survey
8
Fiscal Year 2001
7
ADEPT Program
6
Hanford Laboratories Operation Monthly Activities Report
6
LWBR Development Program
6
Small Wind Electric Systems Consumers' Guides
6
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Project Chariot
5
Chemical Processing Department Monthly Report
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Production of DsSub 2$O for Use in the Fission of Uranium
Brief discussions of experimental methods, kinetics, and the catalysts used in the production of D{sub 2}O are presented (J.E.D.)
Date:
June 23, 1941
Creator:
Urey, H. C.; Grosse, A. V. & Walden, G.
Object Type:
Report
System:
The UNT Digital Library
Chemical Properties of Uranium Hexafluoride, UF6
Uranium hexafluoride has the distinction of being the only stable gaseous compound of uranium known up to the present moment. Because of this property it is the only compound that can be used for processes of isotope separation, such as diffusion, thermal diffusion, centrifuge separation, distillation, and other of a similar nature. Here is a short description of the properties of UF{sub 6} and is intended for a reader interested only casually in this compound. UF{sub 6} is a very reactive compound and a very strong fluorinating agent. It is immediately hydrolized by water. In fluorinating reactions it is reduced to the green highly stable UF{sub 4}. It reacts instantaneously with hydrogen at room temperature. It fluorinates many metals; sodium and mercury are attacked in the cold, lead, zinc, tin and iron on heating; platinum and gold react only above 400 C. With organic compounds like alcohol, ether, benzene or toluene, immediate fluorination takes place with formation of HF and carbon or carbonaceous material. The compound forms colorless, very volatile, beautiful transparent crystals of high refractive index. Melting point = 69.5{sup o}; boiling point at 760 mm = 56.2{sup o}; D20{sup o} = 4.68. The crystals melt water pressure to …
Date:
June 25, 1941
Creator:
Grosse, Aristid V.
Object Type:
Report
System:
The UNT Digital Library
Formation of the 50-Year Element 94 from Deuteron Bombardment of U$sup 23$$sup 8$
None
Date:
June 1, 1942
Creator:
Kennedy, J.W.; Perlman, M.L.; Segre, E. & Wahl, A.C.
Object Type:
Report
System:
The UNT Digital Library
Summarizing Report of Investigations Relating to Uranium Covering the Period September 1, 1942 to April 15, 1943
None
Date:
June 1, 1943
Creator:
Kraus, C. A.
Object Type:
Report
System:
The UNT Digital Library
Technical Division weekly progress report for period ending May 29, 1943
This report details Technical Division activities for the week ending May 29, 1943.
Date:
June 1, 1943
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Technical Division weekly progress report for period ending June 5, 1943
This report details Technical Division activities for the week ending June 5, 1943.
Date:
June 8, 1943
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
PROGRESS REPORT ON METALLURGY OF TUBALLOY TO UNIVERSITY OF CHICAGO
None
Date:
June 10, 1943
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Weekly progress report -- Technical Section for period ending June 12, 1943
Progress was reported from the 300, 100, and 200 Areas. It covered the X pile, aluminium corrosion, graphite purity, fuel element fabrication, bismuth phosphate extraction and decontamination processes, waste disposal from bismuth phosphate processing, control rod systems for Site W, shielding problems at the Site W separation plant, fuel element failure detection, power distribution in the Clinton pile, reactor instrumentation for Site W.
Date:
June 15, 1943
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Investigation of the use of a recycle stream to mediate hydrogen transfer to improve the conversion of eastern oil shale to liquid products
The processing of eastern oil shale has long been known to require the addition of hydrogen to increase the oil yield. Several researchers, have investigated the use of both high pressure hydrogen and hydrogen donor solvents. Much of the donor solvent work has used pure,compounds such as tetralin and has not addressed the use of-a more realistic solvent such as one derived from the production process itself. The work reported herein is for the research Task 1.2.2, Process Studies, in the Annual Project Plan, October l, 1990--September 30, 1991, of the Cooperative Agreement. In the study, a shale oil-derived, recycle oil was used to mediate the transfer of hydrogen to eastern oil shale. The work was divided into two main parts which correspond to the two main portions of the Hydrogen-Extraction (H-E{trademark}) process: (1) the shale oil extraction which involves the use of a donor solvent to aid in the extraction of the shale oil and (2) the regeneration of the donor solvent to a hydrogen-rich state ready for recycle. The results of the investigation to evaluate shale oil extraction using a shale oil-derived donor solvent suggest that temperature had the, greatest effort on organic conversion. At a temperature of …
Date:
June 1, 1944
Creator:
Barbour, F. A.; Guffey, F. D.; Thomas, K. P. & Blake, R. F.
Object Type:
Report
System:
The UNT Digital Library
Canning procedure study drop out temperature
None
Date:
June 9, 1944
Creator:
Jones, K.G.
Object Type:
Report
System:
The UNT Digital Library
Canning procedure study barium chloride base flux for bronze bath
None
Date:
June 19, 1944
Creator:
Grills, R. C.; Lewis, E. V. & Jones, K. G.
Object Type:
Report
System:
The UNT Digital Library
100-B Unit purge June 14, 1945
None
Date:
June 1, 1945
Creator:
Dahlen, P. A.
Object Type:
Report
System:
The UNT Digital Library
Alloys of Uranium and Silicon. [Part] 2. The Epsilon Phase
None
Date:
June 1945
Creator:
Bitsianes, Gust
Object Type:
Report
System:
The UNT Digital Library
Autoclave Tests of Tuballoy Uranium Slugs and Alloys
None
Date:
June 1, 1945
Creator:
Bensen, N.; Straetz, R. P. & Draley, J. E.
Object Type:
Report
System:
The UNT Digital Library
Manual of Operations for the S-50 Plant
It is recognized that the S-50 plant operations are far from standardized and therefore any manual will require continual revision to keep it up to date. Even during the period of writing this first edition, many changes occurred and were incorporated in the manual. Such revisions could delay indefinitely the issuance of the manual and it was felt that in its present form it could be useful in the training of new plant personnel. The specific purpose of the process employed by the Ferclave Corporation in the plant at Oak Ridge, Tennessee, is one of secret information and cannot be released here. It can be stated, however, that the plant operation involves the processing of a chemical substance. This substance is not identified in the plant or in the process but is referred to only as 'material'. Its code designation is C-616. The process in general involves the separation of the raw material into constituents with more desirable properties. It is not necessary to know the name of the material nor the exact nature of the process in order to carry out the operations so this information will not be given in this Manual. The problem involved is to transport …
Date:
June 1, 1945
Creator:
R.T., Overman
Object Type:
Report
System:
The UNT Digital Library
The Melting and Casting of Uranium From Powder
None
Date:
June 1, 1945
Creator:
Chipman, J.
Object Type:
Report
System:
The UNT Digital Library
PERFORMANCE OF CHIPPED MAGNESIUM VERSUS HAMMERMILLED MAGNESIUM IN THE BOMB REDUCTION OF TETRAFLUORIDE. PART I
The O. Hommel Company, of Carnegie, Penna., supplied Mallinckrodt Chemical Works with three types of Mg chips or powder (Type 84, 85B, and 87B) formed by machining Mg ingots. This material was tested and compared with standard New England Lime Mg in a series of reduction runs. A new type of powder (Type 93) developed by the O. Hommel Company during the course of the first experiment was also sert to Mallinckrodt Chemical Works foi preliminary testing. As this was superior to the other tynes tested, a large batch was made up and sent to both Electro Metallurgical Company and Mallinckrodt Chemical Works in order to confirm the preliminary results obtained by Mallinckrodt Chemical Works alone. (auth)
Date:
June 1, 1945
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
The Production of Uranium Powder Compacts
None
Date:
June 1, 1945
Creator:
Cammann, O.
Object Type:
Report
System:
The UNT Digital Library
Summary Report for Month of June 1943 - Metallurgy Division
None
Date:
June 1, 1945
Creator:
Foote, F.
Object Type:
Report
System:
The UNT Digital Library
100-D unit purge
None
Date:
June 4, 1945
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Separations process batch size
A maximum batch size of 400 g Pu-239 is favored. The upper safe limit of product batch size is over 1 kg.
Date:
June 9, 1945
Creator:
Mackey, B. H.
Object Type:
Report
System:
The UNT Digital Library
100-F unit purge
None
Date:
June 16, 1945
Creator:
Dahlen, P. A.
Object Type:
Report
System:
The UNT Digital Library
The corrosion of aluminum in dilute solutions: laboratory studies
After it had been decided that aluminum was to be used as a corrosion-resistant material with good heat transfer properties, it was desired to determine the operating conditions to be used in the water-cooled Handford plant in order to avoid danger of corrosion penetration of thin aluminum parts. The studies here reported were undertaken with the object of determining these conditions by investigating the effects of all the known variables which might influence the corrosion behavior of aluminum in a water-coolded plant at HEW. The addition of hydrogen peroxide to the testing solutions was the only effort made to simulate special conditions at the plant.
Date:
June 19, 1945
Creator:
Draley, J. E.; Arendt, J. W.; English, G. C.; Story, E. F.; Wainscott, M. M. & Berger, R. W.
Object Type:
Report
System:
The UNT Digital Library
CORROSION TESTING OF TUBALLOY URANIUM -COLUMBIUM ALLOYS
None
Date:
June 19, 1945
Creator:
Nelson, F.; Binger, W.W. & Hopkins, J.M.
Object Type:
Report
System:
The UNT Digital Library