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Study of Requirements and Suitability of Available Reactors for Fast Fuel Tests

Description: Report issued by the APDA over studies conducted on the requirements of reactors for fuel testing. As stated in the summary, "the purpose of this study is to determine the requirements for radiation space for fast reactor fuel testing and to determine the capability of existing Commission and private test and power reactors to meet these requirements" (p. 7). This report includes tables, and illustrations.
Date: February 23, 1963
Creator: Doyle, T. A.; Duffy, J. G.; Jens, W. H.; McHugh, W. E.; Page, E. M. & Warberg, H. S.
Partner: UNT Libraries Government Documents Department
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Southwest Retort, Volume 15, Number 6, February 1963

Description: This publication of the Dallas-Fort Worth Section of the American Chemical Society includes information about research, prominent scientist, organizational business, and various other stories of interest to the community. Published monthly during long academic semesters.
Date: February 1963
Creator: American Chemical Society. Dallas/Fort Worth Section.
Partner: UNT Libraries
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Niobium-Tin-Aluminum Alloy Studies

Description: From Abstract : "A proposed constitutional diagram was developed from equilibrium data obtained for the niobium-tin binary alloy system. ... Alloying Nb3Sn with Nb3Al appears to raise the zero field superconducting transformation temperature of Nb3Sn slightly."
Date: February 1963
Creator: Ellis, Thomas Gordon & Wilhelm, Harley A.
Partner: UNT Libraries Government Documents Department
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Gamma Ray Efficiencies for Well Type Scintillation Crystals

Description: From Abstract : "Gamma ray efficiencies for various sized well type NaI(Ti) crystals have been calculated using an IBM 704 digital computer. The adjustable parameters in the program are the gamma ray energy, the heights and diameters of the crystal and the well, the thickness of the well lining, and the positions of the (point) source inside the well. Some typical results are presented in graphical form."
Date: February 8, 1963
Creator: Dingus, Ronald S. & Stewart, M. G.
Partner: UNT Libraries Government Documents Department
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The Strontium-Strontium Hydride Phase System

Description: Technical report. From Abstract : "The Sr-SrH2 phase diagram was studied by thermal analysis, chemical analysis of equilibrated phases and X-ray diffraction. The maximum solubility of SrH2 in strontium metal is 38 mole % at the peritectic temperature of 880°C. Strontium metal undergoes an allotropic transformation at 555°C and melts at 768°C. A second transformation was found, at about 240°C, in samples containing hydrogen. Strontium hydride was found to have an allotropic transformation at 855°C."
Date: February 20, 1963
Creator: Peterson, D. T. & Colburn, R. P.
Partner: UNT Libraries Government Documents Department
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Complex Systems of the Rare Earth Metals With Glycolate, Lactate, and α-Hydroxyisobutyrate Ligands

Description: From Abstract : "The solubilities of the individual rare earth lactates and α-hysroxyisobutyrates in water at 20 and 60° were determined for comparison with the rare earth glycolate solubilities determined earlier."
Date: February 21, 1963
Creator: Powell, J. E.; Karraker, R. H.; Kolat, R. S. & Farrell, J. L.
Partner: UNT Libraries Government Documents Department
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High Pressure Research at Low Temperatures

Description: Two principle reasons exist for the extension of high pressure research to temperatures near absolute zero. First, the comparison of certain data with theory (such as the pressure-volume relationship) is more meaningful if the effects of thermal vibrations can be ignored. Second, there are phenomena which can be studied only at low temperatures. These include superconductivity, the properties of solid helium and other inert gases, some electronic phenomena, etc.
Date: February 24, 1963
Creator: Swenson, C. A.
Partner: UNT Libraries Government Documents Department
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Control rod studies

Description: This study was undertaken to answer questions asked regarding the required rod stroke for control of modified Tory II-C reactors. All problems described were solved with the Angie code and based on Tory-II-C design problems, RZ 501 and RZ 502, representing hot and cold reactors respectively.
Date: February 28, 1963
Creator: Cole, A.
Partner: UNT Libraries Government Documents Department
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Porosity gain from increase in core radius and fuel mass in Tory II-C

Description: A set of calculations has been done to determine the amount by which the volume of solid material in a Tory II-C core can be reduced with respect to the total core volume. Three separate problems were studied. In each case, some change was made which by itself would increase the K[sub eff] of the reactor. Then, in order to keep K[sub eff] unchanged, a certain amount of core material was removed. The calculations were done by means of the one-dimensional neutronic diffusion code ZOOM. The base problem ZR 1008 on which the variations were made is a cross section of Tory II-C as represented in two dimensions by ANGIE problem RZ 501. The cross section is taken at a distance of 0.3 of the length of the reactor from the front surface, and the Z dimension is adjusted in ZR 1008 so that K[sub eff] is the same as for RZ 501.
Date: February 14, 1963
Creator: Kane, W.E. & Cole, A.G.
Partner: UNT Libraries Government Documents Department
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Waste Management Program: Chemical Processing Department

Description: During the 18-year history of Hanford operations, a high degree of safety has been provided at reasonable cost by the storage of high-activity liquid wastes in underground tanks, by the percolation of low-activity liquid wastes (principally water) through the soil to the ground water, and by the adsorption or filtration of radioactive materials from gaseous effluents prior to their discharge to the atmosphere. Studies of the Hanford area indicate that current practices could be continued almost indefinitely without jeopardizing environmental safety, provided the stored liquid wastes are periodically transferred to new tanks before the existing ones fail. In 1960, a Fission Product Recovery Program was prepared outlining a plan to meet the Atomic Energy Commission`s needs for isolated fission products. Emphasis was placed on developing processes for isolating selected fission products and on providing interim production capability for recovering the fission products of immediate interest. In 1961, development efforts were channeled almost exclusively toward meeting the immediate needs of the Commission for separated strontium-90 and cesium-137. During this time, it became increasingly evident that substantial economies could be realized, both in immediate development and subsequent operating efforts, if the separate fission product recovery and waste management programs were merged. The integration of these programs was therefore effected, as described in the 1962 Waste Management Program. This document describes the current status and goals of the integrated program.
Date: February 25, 1963
Creator: Tomlinson, R. E
Partner: UNT Libraries Government Documents Department
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Status of Harvey aluminum component evaluation: Production test IP-12-A

Description: About 298,000 OIIIN aluminum components were received from Harvey for evaluation after major steps were take in the vendor`s plant to upgrade product quality. This material met HAPO specifications and was comparable to Alcoa control components. Finished fuel elements (non-bumper and bumper) canned in the test and control components are tabulated by uranium core type and canning month. Non-destructive and destructive test data did not show any differences in clad fuel elements attributable to component quality. Irradiation status of non-bumper and bumper fuel elements clad in Harvey improved components as of Dec. 31, 1962, is tabulated, as is a summary of ruptures. It was recommended that Harvey Aluminum Co. be allowed to bit competitively on all future Al component orders except for the KVN and KVE component models.
Date: February 13, 1963
Creator: Blanton, W. A.
Partner: UNT Libraries Government Documents Department
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Ionization Chambers for Environmental Radiation Measurements

Description: From Introduction: "In this report, a detailed description will be given of each of the ionization chambers used, including in each case a discussion of the methods of calibration and of techniques utilized in inferring dose readings."
Date: February 1963
Creator: Shambon, Arthur; Lowder, Wayne M. & Condon, William J.
Partner: UNT Libraries Government Documents Department
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Test Results for Unrestrained Reactor, Gunbarrel-Nozzle Assemblies

Description: These tests were performed in accordance with a letter fran R. C. Breisch to J. R. Spink, May 7, 1962. An unrestrained gunbarrel condition was simulated for each of the standard process tube inlet assemblies for B,C and K type reactors. Primary objects of the testing were to obtain data on movement, pigtail damage, and effect on flow to the process tube in case of a Van Stone flange failure without key restraint of the gunbarrel. All test conditions were relative to actual conditions, but these conditions were not necessarily typical or maximum. The gunbarrels were not loaded with do-nuts or thermal shield pieces. All of the assemblies moved instantly and rapidly when released under pressure. The B and K braided type pigtails crimped just upstream of the ferrule on the nozzle connection. The helical tube C-type pigtail stretched about six inches, but did not travel far enough to cause flow restriction. Tube flow for the B case was 54 per cent of that prior to Van Stone flange failure. For the K test, the flow was reduced to 69 per cent of that prior to Van Stone flange failure.
Date: February 14, 1963
Creator: Goff, J. M., Jr.
Partner: UNT Libraries Government Documents Department
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Energy Dependence Determinations in the 60-180 KeV Range with an X-Ray Machine of Varying Output

Description: Report covering a Victoreen Cavity Chamber which utilizes filtered beams from a 250 KVP, Ox 250 General Electric pulsating industrial X-ray machine. The facility, equipment, and procedure is described.
Date: February 1963
Creator: Shambon, Arthur; Zila, Albert & Sanna, Robert S.
Partner: UNT Libraries Government Documents Department
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Aeroradioactivity Survey and Geology of the Gnome (Carlsbad) Area, New Mexico and Texas (ARMS-I)

Description: Report regarding an airborne radioactivity survey that took place in the 7,000 square mile area around the GNOME test site near Carlsbad, New Mexico. Topics include the types of bedrock noted in the area as well as their levels of radioactivity.
Date: February 1963
Creator: MacKallor, Jules A.
Partner: UNT Libraries Government Documents Department
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Experimental Radiation Measurements in Conventional Structures: Part 2. Comparison of Measurements in Above-Ground and Below-Ground Structures From Simulated and Actual Fallout Radiation

Description: Report concerning the protection offered against radioactive fallout offered by two types of structures at the Nevada Test Site. Differences between above ground and underground structures are measured and compared to data taken from actual fallout conditions.
Date: February 1963
Creator: Burson, Z. G. (Zolin G.)
Partner: UNT Libraries Government Documents Department
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