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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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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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Acid-Base Reactions in Fused Salts. Dichromate-Bromate Reaction

Description: Technical report. From Abstract : "The reaction of Lewis acid and base, Cr2O7= and BrO3_, in fused KNO3 - NaNO3 mixtures has been shown to involve an equilibrium followed by a slow decomposition to gaseous products."
Date: February 1963
Creator: Duke, F. R. & Schlegel, James
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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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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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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Reactor instrumentation and safety circuit status review and program document

Description: This document has been prepared for internal use by the General Electric Company to serve as a program for evaluating reactor instrumentation and safety circuit equipment needs. It is intended that this document be used as a guide for defining, planning and scheduling engineering effort; budgeting of capital money; and project planning for new instrumentation systems. Effort will be made to periodically evaluate the status of the programs presented and provide updating information accordingly.After a plant has been built and operated for a number of years, it becomes apparent to operating and engineering personnel that certain modifications in controls and monitoring systems would provide both tangible and intangible benefits. Systems which were once thought to be the primary points of control shift in importance as others become recognized. As time passes this shifting spreads the main control focus from the central control desk to various other areas in the control room. Production rate increases cause instrument ranges and scales to be changed so that information on the process can still be obtained from existing equipment. Response times, sensitivity, limits, and time constants which were figured for one level must be used or revised for new levels. Further, it is discovered that the process monitoring points could be relocated or increased in number to provide more and better data on plant operation. New monitoring equipment is developed and installed to fill voids in information so production can continue meeting high standards for safety and process control. Equipment is fitted here and there in an already crowded control room, and some is even relocated to less advantageous positions to make available the necessary panel space. This in brief, is the rather complex status of Hanford Production Reactor instrumentation today.
Date: February 15, 1963
Creator: Deichman, J. L.
Partner: UNT Libraries Government Documents Department
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Operating Characteristics of the Lauterbach and Dautrebande Aerosol Generators

Description: From Abstract: "The air flow through the jet, the effect of a pre-humidifier on the water vapor content of the jet air, the cooling effect of the jet air on the generator solution, and the amount of water vapor carried away by the jet air were also determined and the results are discussed."
Date: February 1963
Creator: Mercer, T. T.; Tillery, M. I. & Flores, M. A.
Partner: UNT Libraries Government Documents Department
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Interim report one to Production Test-IP-549-A, half-plant low alum feed water treatment at F Reactor

Description: A half-plant low alum water treatment test began at F Reactor on January 16, 1963 at startup from the scheduled January 3 tube replacement outage. The test, which was prompted by results obtained from a statistical analysis of fuel ledge corrosion attack, will demonstrate whether or not high alum feed is responsible for increasing the frequency of ledge corrosion attack on fuel element surfaces. The effect will be evaluated by comparing visual examination results obtained from normal production fuel irradiated in two different alum treated process waters. This report discusses the results obtained from twenty fuel charges, ten from each side of F Reactor, which were discharged prior to the reduction in alum feed to establish the pre-test corrosion environment.
Date: February 11, 1963
Creator: Clinton, M. A. & Geier, R. G.
Partner: UNT Libraries Government Documents Department
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