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Oxygen-hydrogen meter assembly for use in remote sodium sampling systems

Description: An assembly of an electrolytic oxygen meter and a diffusion type hydrogen meter was designed to fit into the Multipurpose Sampler hardware already installed and operating on the four FFTF sodium systems. One of the key elements in this assembly is a ceramic-metal sealed oxygen sensor which allows use of a metal tube to extend the 51 cm (20 in.) between the sampler top and the flowing sodium region.
Date: February 1, 1980
Creator: Barton, G.B.; Bohringer, A.P. & Yount, J.A.
Partner: UNT Libraries Government Documents Department
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Development of a modified diffusion type carbon activity meter for liquid sodium

Description: A high sensitivity automated carbon activity meter has been developed by combining elements of technology used in other instruments. The basic principle is the diffusion of carbon through an iron membrane driven by the concentration gradient between the sodium being measured and the sweep gas. The membrane used is similar to that used by Harwell workers, i.e., a coil of small diameter iron tubing with an oxide coating on the inner surface. A sweep gas of helium is used to pick up the carbon oxi… more
Date: January 1, 1980
Creator: Barton, G. B.; Cook, W. V. & McCauley, D. L.
Partner: UNT Libraries Government Documents Department
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Reactions of sodium with various concretes and concrete materials

Description: This paper presents a summary of the work performed to date on the investigation of sodium-concrete reactions. Principal results to date have been achieved in laboratory-scale investigations using differential thermal analysis (DTA), thermo-magnetic analysis (TMA), and other techniques. The results of these tests are described. Comparisons with the laboratory-scale tests and available bench- and large-scale tests are made. In view of these data, future work requirements and plans are discussed.
Date: January 1, 1976
Creator: Hassberger, J. A.; Barton, G. B.; Witkowski, R. E. & Charles, R. G.
Partner: UNT Libraries Government Documents Department
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GAS CHROMATOGRAPHIC SYSTEM FOR FFTF FAILED FUEL DETECTION AND LOCATION - STATE-OF-THE-ART REPORT

Description: A review of the present state-of-the-art in the areas of gas chromatography, radiochemical counting and inert cover gas sampling reveals that : 1, The chromatographic approach to fuel failure detection and locatlon is technically feasible and holds promise of having distinct advantages over existing methods. 2, Considerable knowledge which is directly applicable to the problem exists and therefore the research and development costs required will be modest, 3. Existfng knowledge indicates that t… more
Date: April 26, 1969
Creator: Barton, G. B.
Partner: UNT Libraries Government Documents Department
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Report on Carbon-14 generation and release at some of the Hanford reactors

Description: The Hanford graphite-moderated reactors have an enclosed gas circulation system to maintain control of the composition of gas atmosphere in the graphite stack. This investigation was undertaken to answer several questions concerning the generation and release of Carbon-14 in the operation of these graphite moderated reactors. The principle question was: Will an increase in the nitrogen content of the reactor atmosphere increase the release of Carbon-14 sufficiently to create a health hazard. Ot… more
Date: December 14, 1964
Creator: Barton, G.B.
Partner: UNT Libraries Government Documents Department
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Status report: Carbon-14 in the condensate from the silica gel dryers of the production reactors

Description: Volatile compounds containing C{sup 14} produced in the cooling gas systems of Hanford reactors can be lost from the cooling gas by two routes. These are (a) escape via the reactor stacks through leaks in the cooling gas system and (b), adsorption with water vapor on the silica gel of the dryers for the cooling gas with subsequent regeneration of the silica gel and condensation of the water for disposal. Information relative to the release rates by the stack gas route was reported in HW-75618. … more
Date: March 14, 1963
Creator: Barton, G. B.
Partner: UNT Libraries Government Documents Department
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Solidification of high level wastes Part 1, Evaporation and calcination of Purex IWW--volatility and leachability of fission products

Description: The basic objective of the storage of radioactive wastes is to protect humanity from: (1) direct radiation, (2) contamination of food and water supplies, and (3) contamination of mineral resources. There have been many proposals for the disposal of high level liquid wastes from chemical plants processing nuclear fuels. These include our present Hanford system of tank storage; disposal to deep wells, such as the oil industry uses for discard of brines they pump; storage in salt caverns; disposal… more
Date: August 4, 1959
Creator: Barton, G. B.
Partner: UNT Libraries Government Documents Department
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Chemistry of the "Silver Reactor"

Description: The use of a reactor charged with silver nitrate coated packing for removal of radio-iodine from the waste gases of Hanford chemical processing plants has been successful in removing approximately 99.5 percent of this activity. Studies by the Radiological Sciences Department indicated the desirability of further reducing the amount of radio-iodine released to the atmosphere. Therefore, this study was undertaken with the objectives of better understanding the inherent limitations to iodine remov… more
Date: March 5, 1956
Creator: Barton, G. B. & McClanahan, Jr., E. D.
Partner: UNT Libraries Government Documents Department
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Analytical results on leachings from Nutsche Filters

Description: This report describes results of an investigation to determine whether plutonium nitrates and lanthanum compounds were being entrained on the filter aid and filter block of the Nutsche Filters in Cell 2 of Bldg. 231. Leach samples were analyzed for La, Pu, phosphate, fluoride, Pu{sup 240}, and Am. From the data the authors concluded that the holdup on the Nutsche Filter is due to insoluble plutonium compounds either filtered from solution, or more likely, formed on the filter. These compounds w… more
Date: July 2, 1951
Creator: Barton, G.B.
Partner: UNT Libraries Government Documents Department
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Analysis of a standard Pu solution by the control laboratories in 231 and 234-5 Buildings

Description: A solution of Pu was prepared for use in a re-investigation of the present 49 titration method. Three 500 microliter portions of the sample were dried and ignited to PuO{sub 2}. From the weight of the residue and the impurity analysis, the concentration, in g/l, of the solution was found to be 222.2, 221.5, and 222.5; average of 222.0. The six samples submitted to the control laboratory in Bldg. 231 were reported as: 219.3, 223.6, 221.5, 220.9, 222.3, and 228.2 (re-run 229.3); average of 222.6 … more
Date: July 14, 1950
Creator: Barton, G.B.
Partner: UNT Libraries Government Documents Department
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The Determination of Total Plutonium in the Presence of Aluminum

Description: Introduction: "The adoption of aluminum nitrate as salting agent in the Redox process made it imperative that a method be available for determining plutonium in the presence of aluminum. However, large amounts of aluminum have been found to interfere with the determination of plutonium by the lanthanum fluoride procedure. Previous attempts to increase the accuracy of the lanthanum fluoride method, by precipitating LaF3 from 4 M HF (rather than 2 M), have been successful only when the initial pl… more
Date: February 10, 1950
Creator: Burns, R. E. & Barton, G. B.
Partner: UNT Libraries Government Documents Department
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