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Interim report No.1, PT-105-403-P, installation and initial operation

Description: The effect of temperature on the properties of graphite is being determined by exposing samples to pile neutrons at controlled temperatures in the range 75 C to 225 C. The first series of samples were charged into the newly installed dry, water-cooled test channel at B pile on January 23, 1951. This report presents details of the charging operation and observations noted during the initial operation of the test.
Date: February 7, 1951
Creator: Haussler, W. M. & Purcell, R. H.
Partner: UNT Libraries Government Documents Department
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PT IP-205-A: Irradiation of Zircaloy-2 jacketed rod-and-tube elements in the KER Loops

Description: The objective of the production test is detailed in this report is to obtain information about the behavior of Zircaloy-2 jacketed rod-and-tube fuel elements during irradiation at high coolant temperatures specifically, this test should provide information about fuel element dimensional stability, suitability of the rod and tube support system, and behavior of the uranium--Zircaloy-2 bond. Four co-extended Zircaloy-2 jacketed rod-and-tube elements, two with welded tube end closure and two with … more
Date: October 9, 1958
Creator: Kratzer, W. K.
Partner: UNT Libraries Government Documents Department
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Effect of saturation of water with dissolved corrosion product on the in-reactor corrosion rate of aluminum in deionized water: Proposal for test in 1706 KER

Description: This report discusses a proposal to measure the corrosion rate of aluminum-clad DOE elements in deionized water in one of the KER Loops at the highest obtainable surface temperatures under conditions where the bulk water adjacent to the elements is saturated with aluminum corrosion product. This will determine whether in-reactor corrosion may be reduced by controlling the aluminum concentration in the water and also provide corrosion data in deionized water at higher temperatures than is now av… more
Date: January 27, 1959
Creator: Dickinson, D. R.
Partner: UNT Libraries Government Documents Department
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Production test IP-245-A dual area trip-out of B & C Reactor process pumps

Description: The objectives of the test described in this report are to obtain current knowledge of the flow characteristics of the B and C Reactor flow systems under various transient conditions that have a reasonable probability of occurrence. These tests will be used to revaluate the B and C Reactor bulk temperature limits, the Ball 3X low pressure trip settings, and quantitative adequacy of emergency flow from the combined high tanks - export system.
Date: March 26, 1959
Creator: Long, J. T. & Jones, S. S.
Partner: UNT Libraries Government Documents Department
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Presentation on extrusion cladding at Sheath Meeting, Chalk River, September 25--26, 1956

Description: Included is a summary of the material presented at the Sheath meeting at Chalk River on Sept. 25--26, 1956. Information is included on cladding plates, end plugs for plates, electroplating techniques, equipment to extrusion clad full length plates at SRL, progress on extrusion cladding the inside of tubes, and a program for future work on extrusion cladding.
Date: October 17, 1956
Creator: O`Leary, W. J.
Partner: UNT Libraries Government Documents Department
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PT-105-600-A: First measurement of graphite temperature reactivity coefficient at KE (compilation of data)

Description: This test consisted of a series of helium purges of the pile gas atmosphere to bring the helium content up to about 70 to 80% helium followed by a series of CO{sub 2} purges to restore the pile atmosphere to its initial composition. The purges where spaced roughly four hours apart to enable the reactor to reach a steady temperature before purge was undertaken. The test results are presented in this report.
Date: May 13, 1955
Creator: Gumprecht, R. O.
Partner: UNT Libraries Government Documents Department
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Slug temperature after H{sub 2}O stoppage

Description: On the basis of numerous rough calculations it has generally been assumed that if the water flow to a tube were to stops while pile operation continued. The tube central temperature would increase in a matter of seconds to dangerously high values. In several seconds the water around the central slugs would flash to steam, shortly thereafter the aluminum cans would melt and this would give good contact between the slug and the tube which would quickly melt. The bare uranium would react with the … more
Date: June 10, 1958
Creator: Jones, S. S. & Ekern, W. F.
Partner: UNT Libraries Government Documents Department
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Proposal for irradiation of uranium swelling behavior capsules

Description: The swelling behavior of unalloyed clad uranium operating with a cladding surface temperature of 250--350 C and fuel temperatures from 450--750 C is of importance for Hanford`s fuel element development work. To obtain information on the effect of cladding restraint, exposure, and the above temperatures, on uranium swelling rates, a series of experiments is proposed for irradiation in Hanford reactors. The experimental assemblies consist of uranium fuel rods supported concentrically in an alumin… more
Date: September 23, 1958
Creator: Weber, J. W.
Partner: UNT Libraries Government Documents Department
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Delayed Light Emission in Green Plant Meterials:Temperature-Dependence and Quantum Yield

Description: The discovery of the delayed light emission of plant materials by Strahler and Arnold in 1951 has stimulated a good deal of interest in this rather remarkable property. The emitted light has been shown to be due to an electronic transition between the first excited singlet state of chlorophyll and the ground state. At room temperature, a luminescence is observable from about 0.01 seconds to several minutes after excitation. Thus, the electronic transition cannot be rate-determining and the proc… more
Date: July 1, 1958
Creator: Tollin, G.; Fujimori, E. & Calvin, M.
Partner: UNT Libraries Government Documents Department
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Absorption Spectra of Aromatic Disulfides

Description: The effect of solvents and temperature on the optical absorption spectrum of a number of substituted aromatic disulfides is reported. The problems offered by the disulfide link and the exchange reactions between disulfides, and between disulfides and thiols, are receiving increasing attention. Recently the base-catalyzed exchange between various alkyl disulfides and the corresponding thiols was studied by means of a radioactive-tracer technique. Our initial purpose was to extend these investiga… more
Date: October 31, 1956
Creator: Fava, Antonio & Calvin, Melvin
Partner: UNT Libraries Government Documents Department
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Vertical rod temperatures

Description: An important factor affecting the decision on the use of a seal around the VSR on ``C`` is the temperature at which the rod can be expected to reach. Also the temperature of the rod-tip affects the choice of tip moderating material. These temperatures are calculated for a given set of conditions for ``C`` pile. The results of the calculations are best seen by referring to the attached figures. The affects of emissivity and weight of rod can be estimated by comparing the proper curves. The assum… more
Date: August 14, 1951
Creator: Roy, G. M.
Partner: UNT Libraries Government Documents Department
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DR Pile lattice conductance study

Description: The start-up of the DR Pile at a time when every effort was being made to increase the power levels of the older piles, suggested the possibility of studying, during the early damage period, some of the conditions which were limiting the operating levels of the old piles. Of the operational limitations restricting the power level of the old piles, the maximum graphite temperature is the most severe and actually determines the operating level of the B, D, and F Piles and, to some extent, the H P… more
Date: March 31, 1951
Creator: Wheelock, C. W.
Partner: UNT Libraries Government Documents Department
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An analysis of the suitability of various coring patterns for inclusion in ``C`` Reactor

Description: Preliminary meetings on coring of the graphite have been held with interested parties of the Technical and Production Divisions at which time the advantages and problems of coring were discussed. The advantages and the problems which must be surmounted in order to core have been presented to the working committee. A study of the means of accomplishing coring has been made considering only the central and maximum fringe coring. It is important that the minimum and maximum coring be established a… more
Date: April 13, 1951
Creator: Roy, G. M. & Andersen, R. K.
Partner: UNT Libraries Government Documents Department
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234-5 Development Group - summary report, use of {open_quotes}AT{close_quotes} solution without evaporation

Description: A summary of work is presented from the 234-5 Development Group, September 1, 1950, with regard to the feasibility of transferring the plutonium processing solution, without evaporation, to the Purification Building. Critical factors identified were the concentration of the nitric acid and temperature.
Date: September 1, 1950
Creator: Lyon, W.L. & Facer, J.F.
Partner: UNT Libraries Government Documents Department
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