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Vacuum Arc Melting : a Bibliography

Description: This partially annotated bibliography contains 334 references from papers published from 1945 to 1959 and includes references on the consumable - and nonconsumable - electrode vacuum arc melting process. References are also given on electrode preparation, furnace construction and operation, melting, sintering, vacuum techniques, and theory.
Date: March 16, 1960
Creator: Cernak, Elizabeth A.; Doyle, J. & Aconsky, S.
Partner: UNT Libraries Government Documents Department
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Neutron Diffusion Theory Programs and Their Application to Simple Critical Systems

Description: Introduction. The Lawrence Radiation Laboratory of the University of California has developed a series of reactor neutronic programs for an IBM 709 Data Processing System.. This paper presents a brief outline of these codes and includes the results of one- and two-dimensional diffusion calculations used to interpret data from a series of enriched-uranium beryllium-oxide moderated critical measurements. These were performed for the specific purpose of evaluating the computer programs. The time-independent neutron diffusion theory criticality codes are 9ZOOM, a one-dimensional multigroup program; and 9ANGIE, a two-dimensional multigroup program. A series of codes, named SOPHIST, are described which prepare neutronic input data for the criticality codes. Examples of modification of the data to account for disadvantage factors, anisotropic scattering and for the (n,2n) reaction of Be9 are given. The critical assemblies include bare and graphite-reflected systems, using atomic BeO/U235 ratios from 247/1 to 7660/1, arranged in simple one- and two-dimensional rectangular parallelepiped arrays. All of the assemblies utilized heterogeneous arrangements of moderator and thin uranium foils. These systems are not truly thermal and are in a range where critical mass is extremely sensitive to size. The constants used in the multigroup (18 energy groups were used) calculations are presented in tabular form. Certain problems are used as test examples to show sensitivities to mesh spacing, extrapolation parameters and shelf-shielding factors. The results of the diffusion calculations of the critical mass are within 10% of experimental values.
Date: March 1960
Creator: Stone, Stuart P. & Lingenfelter, Richard E.
Partner: UNT Libraries Government Documents Department
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Tory II-A Instrumentation System : Brief Description

Description: Abstract. The Tory II-A reactor is a small, air cooled, high power-density reactor which is to operate at quite high temperatures. Design of the reactor is essentially complete. First operation is scheduled for late 1960 at the Nevada Test Site of the Atomic Energy Commission. Since the reactor is unshielded, the control room which houses the recording and indicting equipment is located approximately two miles from the test bunker. Signals from reactor and facility transducers are amplified in the test bunker and transmitted by cable to the control point. The kinds of quantities measures include neutron flux level, temperatures, pressures, vibration amplitudes, strain and air mass flow rate. The recording and indicating system is centered around 258 channels of 1.5 cycle per second, pulse-width modulation tape recording equipment and 72 channels of 120 cps, analogue strip-chart records. In addition, there is a number of the usual meters, scalers and slow-response strip-chart recorders.
Date: March 3, 1960
Creator: Barnett, Charles S.; McDonald, Henry C. & Uthe, Paul M.
Partner: UNT Libraries Government Documents Department
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Zero Power Experiments for the SM-1 Core II : Task XV

Description: Abstract: An element by element reactivity check for SM-1 Core II fuel elements and control rod absorber sections was performed and the burnable nuclear poison loading in the SM-1 Core II stationary fuel elements was established. An approach to criticality of the SM-1 Core II was performed by the inverse multiplication method and the critical rod bank position obtained as a function of fuel loading up to the full SM-1 Core II loading. Maximum and minimum core reactivity measurements were obtained by selective loading of stationary fuel elements and the total "excess K" for the core established. Power distribution measurements in the region of the core-reflector interface and the fuel-absorber interface in the control rod assemblies were performed. The effectiveness of europium flux suppressors in the top of control rod fuel elements and the power peaking in stationary elements adjacent to water gaps in control rod assemblies were measured. Survey measurements established the worth of spiking cold clean SM-1 cores with SM-2 elements, and of water holes in the SM-1 core which might be utilized as flux traps for materials irradiation.
Date: March 15, 1960
Creator: Robinson, R. A.; Weiss, S. H.; McCool, W. J. & Schrader, E. W.
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department monthly report for February 1960

Description: Production Pu nitrate and unfabricated Pu metal during Feb. was below forecast; however FY output is above forecast. Production of UO{sub 3} exceeded commitments; shipments met schedule. Decontamination performance of Purex solvent extraction system was subnormal. Pu nitrate solutions were concentrated. A fire occurred in Purex N Cell during conversion of ion exchange prototype to production facility.
Date: March 21, 1960
Partner: UNT Libraries Government Documents Department
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Purex Plant flowsheet for high capacity study

Description: This report contains a flowsheet which was prepared to serve as a guide for an engineering study to be made to determine the costs and revisions required to increase the capacity of the Purex Plant to a 4.0 capacity factor. The needs for such a study are outlined in documents HW-62952 (Ref. 1) and HW-63927 (Ref. 2), which include increased 100 Area production forecasts and maximizing Palm recovery by continuous recovery equipment as primary factors. The flowsheet, shown graphically on the flowsketch and specifically in tabular form under Table 1, is a ``best estimate`` of process conditions and modifications which will be in operation by the third quarter of FY 1962. The modifications included are: Formaldehyde Treatment of Concentrated Wastes -- IWW (Ref. 5 and 6); A Continuous Palm Recovery Cycle; A Palm Ion Exchange Purification and Loadout Facility (Ref. 3); Alkaline-Permanganate Washing of the No. 2 Organic System Solvent; and Rough-cut Fission Product Recovery and Shipping (Ref. 4). Since the fission product recovery and shipping operations do not effect the equilibrium conditions of the plant, they are not included in the flowsheet.
Date: March 28, 1960
Creator: Geier, R. G. & Duckworth, J. P.
Partner: UNT Libraries Government Documents Department
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Hanford Laboratories Operation monthly activities report, February 1960

Description: This is the monthly report for the Hanford Laboratories Operation, February, 1960. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.
Date: March 15, 1960
Partner: UNT Libraries Government Documents Department
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Status report - C Reactor process tubes

Description: Data have recently been obtained on a number of C-Reactor process tubes. These data make is possible to reassess the current conditions of the tubes in the C-Reactor and hence to re-evaluate the probable data when retubing of the reactor will have to be started. The results of this reassessment are presented below.
Date: March 21, 1960
Creator: Miller, N. R.
Partner: UNT Libraries Government Documents Department
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Flux distribution problems at C Reactor

Description: This report discusses an outbreak of ruptures in January and February, 1960, which motivated serious consideration of ail phases of reactor operation so that a combined efforts to reduce rupture potential might be made. Items investigated include mixer location, gas composition control, rod movement, rod configuration, tube power, and the axial flux profile of the reactor.
Date: March 16, 1960
Creator: Chitwood, R. A.
Partner: UNT Libraries Government Documents Department
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Resume of KER Loop irradiation tests for 1957, 1958, and 1959

Description: In 1957 three of the four high temperature recirculating loops in KE Reactor were put into service and in 1958 the fourth loop was started up. The primary purpose of the loops has been high temperature irradiation testing of fuel elements in support of the NPR fuel element development program, although tests have been run to provide information for PRTR fuel development and high temperature aluminum corrosion programs. Coolant technology studies relating to activity build-up, crude formation, corrosion, failure detection, and decontamination are carried on in conjunction with the fuel element tests. The purpose of this document is to provide a resume of all fuel element test irradiations in the KER Loops from the time they started up to the end of CY-1959. A description of each test, its operating conditions, a chronological history of each loop, and a bibliography of documents pertaining to the tests are included. Supplements to this report will be issued periodically to bring the information up to date.
Date: March 28, 1960
Creator: Kratzer, W. K.
Partner: UNT Libraries Government Documents Department
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Piping Changes for Increased Production at B, D, DR, F, C and H Reactors calculations

Description: On January 22, 1960, HW-63487 Piping Changes for Increased Production at B, D, DR, F, C, and R Reactors, was published. This study investigates the valve pit piping, front and rear face piping,and effluent lines between the 105 Buildings,and the retention basins to determine modifications necessary to increase power levels in the 100-B, D, DR, F, C, and H Areas by increasing either or both temperatures and flows. The study was based on detailed hydraulic and stress calculations of the existing and proposed piping systems which because of their detailed and voluminous nature were not included in the study. It is the purpose of this study to document, in so far as possible, these calculations together with pertinent information which was not included in the original study.
Date: March 24, 1960
Creator: Bauer, G. H.; Harrison, C. W.; Hill, V. R.; McLenegan, D. W. & Mondt, J. F.
Partner: UNT Libraries Government Documents Department
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Automatic alum feed device to produce water of any given clarity

Description: This report documents the research and testing of an automatic alum feed process at the Hanford reservation. This process generates water of varying qualities which is used to cool fuel elements in nuclear reactors.
Date: March 7, 1960
Creator: Conley, W. R. & Pitman, R. W.
Partner: UNT Libraries Government Documents Department
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Burst testing of irradiated Zircaloy tubing. Revision 1

Description: An extensive knowledge of the effect on the mechanical properties of metals of prolonged exposure to neutron radiation is considered necessary to properly establish design and operating criteria for in-reactor pressure tubes and test loops. An opportunity to obtain a limited amount of this information on Zircaloy-2 presented itself when, after two years of service, the pressure tubes were replaced in the RE reactor recirculating test facility. Three Zircaloy-2 tubes, with a two-inch inside diameter and 48 feet long, had operated intermittently with prototypical fuel elements at water temperatures up to 250 C (480 F) and pressures up to 1350 psi. During this period, the tubes received an estimated integrated neutron exposure of 1.9 {times} 10{sup 22} nvt. After the tubes were removed from the reactor, metallographic examinations, longitudinal-tensile tests, flattening tests, and burst tests were performed. In this report, the techniques for performing the burst tests are described and the results of the burst tests are compared with the results from tensile tests on coupons cut from corresponding locations along the tube.
Date: March 4, 1960
Creator: Kahle, V. E.
Partner: UNT Libraries Government Documents Department
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Thermal conductivity studies on various calcined ``cold`` waste: Interim report

Description: Accelerated accumulation of high level radioactive wastes has given impetus to the development of safer and more economical waste storage methods. Several processes for converting these wastes to granular or porous-solid form are being investigated. In any waste volume-reduction process containment of the final material in a sealed metal shell is desirable as a precaution against accidental release of radioactive material. While the final waste forms are generally stable, they are, if uncontained, subject to some degree to leaching, volatilization, and dusting caused by fracturing due to thermal stresses. An experimental program is now underway to develop an understanding of the variables in waste systems so that suitable storage containers may be designed. This report covers the first phase of the program, a study of heat transfer properties of self-heating granular solids.
Date: March 11, 1960
Creator: DeMier, W. V.
Partner: UNT Libraries Government Documents Department
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Summary of KER-1 operation, February 15, 1958--March 1, 1960

Description: Recent borescoping of the KER-1 tube revealed several scratches, pits, and gall marks on the internal wall of the tube. These deformations could limit the operating temperature and pressure of KER-1. This report is a summary of operating history and is compiles to assist in determining what contributed to the condition of the tube.
Date: March 3, 1960
Creator: Buckner, C. L.
Partner: UNT Libraries Government Documents Department
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Scope report Safety Circuit Trip Identification System

Description: The purpose of this report is to establish the scope of a project to provide a system which will quickly and accurately identify the sources of all reactor scrams.
Date: March 23, 1960
Creator: Deichman, J. L.
Partner: UNT Libraries Government Documents Department
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Some considerations concerning the accuracy of power level calculations in the context of the control of SS materials

Description: This report investigates a study of the accuracy of the power level calculations. Some characteristics of this calculation can be adduced but the accuracy in the sense of freedom from bias leads to an impasse. It presumes that there is another measurement for comparison purposes for which there are engineering reasons to believe, the inherent error is smaller. For the power level values as calculated by the Foxboro Power Level Calculator no such measurement or calculation exits. However, the calculations can be studied to determine whether it is worth-while to make further refinements relative to the various functions of the power level calculation. The accuracy requirements vary according to use where the most stringent requirements are in the control of SS Materials.
Date: March 14, 1960
Creator: Stewart, K. B.
Partner: UNT Libraries Government Documents Department
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Alpha correlation

Description: This study was developed to provide a correlation for the evaluation of the pile C{sub RI}/Tube C{sub RI} ratio (alpha value) for each of the Hanford reactors.
Date: March 24, 1960
Creator: Cremer, B. R.
Partner: UNT Libraries Government Documents Department
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The poison spline system

Description: No Description Available.
Date: March 10, 1960
Creator: Smithers, R. M.
Partner: UNT Libraries Government Documents Department
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Hydraulic demand curves for standard BDF geometry at low tube powers

Description: Information concerning the pressure-flow relations in reactor process tubes at very low heat generation rates is of value for determining flow requirements during shutdown conditions. Since such information is quite difficult to calculate when boiling occurs, a brief laboratory investigation was conducted to obtain experimental data. The data obtained for BDF geometry are recorded in this report for distribution to those persons having an interest in the application of the results to reactor operation.
Date: March 24, 1960
Creator: Waters, E. D. & Fitzsimmons, D. E.
Partner: UNT Libraries Government Documents Department
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An assessment of the zirconium tube program -- C Reactor pilot demonstration installation

Description: Production Test IP-272-A-FP authorizes the installation of up to 100 smooth bore Zircaloy-2 process tubes in C Reactor to demonstrate the feasibility of self-supported fuel elements for production use. An additional 200 zirconium tubes are expected to be delivered by mid-year and con be used to expand the initial demonstration facility. It is the purpose of this document to assess the status of the pilot demonstration program from the B-C Reactor Operation viewpoint.
Date: March 18, 1960
Creator: Amy, G. O.
Partner: UNT Libraries Government Documents Department
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Travel to Oak Ridge and Savannah River Plant to Study Processing Plant Containment Philosophy. Trip Report, January 26--29, 1960

Description: This report discusses travel to the Oak Ridge National Laboratory on January 26 and 27 and the Savannah River Laboratory and Plant on January 28 and 29, 1960. The primary objectives of the trip were to obtain information on the containment philosophy for processing plants recently adopted by Oak Ridge National Laboratory and on the Palm Program at Savannah River.
Date: March 9, 1960
Creator: Beard, S. J. & Oberg, G. C.
Partner: UNT Libraries Government Documents Department
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