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HRT Reactor Hazards

Description: Several potential hazards that have been recognized and anticipated in the design and fabrication of the pressure vessel in the Homogeneous Reactor Test are discussed. These hazards results from the high operating pressure and temperature of the reactor, the exposure of the reactor vessel material to potential embrittlement and other affects of fast-neutron irradiation, and the need for containment of corrosive flowing liquids. The steps taken in recognition of these hazards are also discussed.… more
Date: August 3, 1956
Creator: Miller, E. C.
Partner: UNT Libraries Government Documents Department
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HRP Radiation Corrosion Studies

Description: A fifth in-pile loop experiment, L-4-8, was completed. The loop operated in-pile for a total of 1637 hr, during which time the LITR energy output was 4377 Mwhr. The average fission power in the loop based o cesium analyses was 622 w when the LITR was at full power (3 Mw). Based on oxygen data, the generalized corrosion rate for the first 300 hr was 4.0 mpy; the rate for the remaining 1357 hr was 0.7 mpy. The nickel data gave parallel results. The corrosion of the type 347 stainless steel, Zirca… more
Date: August 21, 1956
Creator: Baker, J. E.; Bradley, N. C.; Jenks, G. H.; Olsen, A. R.; Savage, H. C. & Walter, F. J.
Partner: UNT Libraries Government Documents Department
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Investigation of Materials for a Water Cooled and Moderated Reactor [Secret Version]

Description: An investigation of the materials for use in the water-moderated and cooled Aray Package Power Reactor (APPR) operating at about 500°F was made. The available literature was analyzed, and the results of the different investigators were compared and averaged. Twenty different materials, including stainless steels, nickel alloys, Stellites and others, were investigated from the point of view of physical properties, susceptibility to radiation damage, and corrosion resistance. Corrosion rates were… more
Date: August 1954
Creator: Scheib, Louis
Partner: UNT Libraries Government Documents Department
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Investigation of Materials for a Water Cooled and Moderated Reactor [Declassified Version]

Description: An investigation of the materials for use in the water-moderated and cooled Aray Package Power Reactor (APPR) operating at about 500°F was made. The available literature was analyzed, and the results of the different investigators were compared and averaged. Twenty different materials, including stainless steels, nickel alloys, Stellites and others, were investigated from the point of view of physical properties, susceptibility to radiation damage, and corrosion resistance. Corrosion rates were… more
Date: August 1954
Creator: Scheib, Louis
Partner: UNT Libraries Government Documents Department
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Remarks on the Double Dispersion Approach to the Bethe-Salpeter Equation

Description: The following remarks are made on the applicability of the double dispersion approach to the Beth-Salpeter equation introduced previously. 1) Any invariant solution of the Bethe-Salpeter equation in ladder approximation satisfies the double dispersion representation when the total energy-momentum is space-lake. 2) There are some exceptional invariant solutions which are not given by the previous method in the equal-mass case, but the existence of such solutions is very unlikely in the unequal-m… more
Date: August 7, 1962
Creator: Nakanishi, Noboru
Partner: UNT Libraries Government Documents Department
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Theory of Final State Interactions

Description: Using requirements of analyticity and the unitarity of the S-matrix we obtain the dependence of a transition amplitude on the invariant mass of two particles strongly coupled to other two particle channels. As an example, we consider the production of a Σπ state near the Y*₀ resonance assuming it is coupled to a KN state in an s 1/2 state.
Date: August 20, 1962
Creator: Nauenberg, Michael
Partner: UNT Libraries Government Documents Department
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Pion Resonances in π⁻-p Interactions at 4.65 Bev/c

Description: This note describes some results of the study of single pion production in π⁻-p interactions at 4.65 Bev/c, using the BNL 20" Hydrogen Bubble Chamber. It is well known that the observability of some of the particle resonances (e.g. 33 Isobar and η) varies markedly with the energy of the incident particle. The ρ meson has been observed in π⁻-p interactions at 1.25 Bev/c and 1.9 Bev/c incident pion energies. Evidence will be shown that this resonance persists with the much higher incident pion en… more
Date: August 9, 1962
Creator: Munir, B.A. & Zorn, G. T.
Partner: UNT Libraries Government Documents Department
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Rates of Reaction of Irradiated UO2 and Uranium Metal with Sulfuric Acid

Description: In the decladding of stainless steel clad fuel elements with sulfuric acid (the Sulfex process), the loss of core material to the decladding solution is determined by the rate of reaction of the core material with the solution and the time of exposure if the core to the solution. Since very little was known about the effects of irradiation history on the rates at which core materials dissolve in sulfuric acid, the present study was undertaken in an effort to determine the magnitude of such effe… more
Date: August 13, 1959
Creator: Swanson, J. L.
Partner: UNT Libraries Government Documents Department
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Plant Modification for Reprocessing Non-Production Reactor Fuels Design Criteria for Fuel Element Storage Facility Building 221-U

Description: Facilities shall be provided in the 221-U Building for removing fuel elements from the casks as placed in the railroad tunnel from the transfer facility and moving the elements to modified existing 10' X 16' X 14' storage tanks in ten existing cells where they will be stored, until scheduled for processing.
Date: August 17, 1959
Creator: Yates, M. E.
Partner: UNT Libraries Government Documents Department
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Out-of-Reactor Tests on Pu-Al Type PRTR Elements for 1706-KER Testing

Description: The small amount of irradiation tenting experience on the plutonium-aluminum type elements planned for the Plutonium Recycle Test Reactor (PRTR) has made such testing of great importance. The high temperature pressurized recirculating water 1706 KER facility is one possible place for conducting investigations of the irradiation behavior of this type fuel element. To obtain the maximum information from the in-reactor testing and to detect possible problems, out-of-reactor test both at room and … more
Date: August 7, 1959
Creator: Doman, D. R.
Partner: UNT Libraries Government Documents Department
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Heat Transfer Calculations for CO2 Gas-Cooled Loop-PRTR

Description: At the request of Design Development Operation, various heat transfer and fluid flow problems were examined which are peculiar to the CO2 Gas-Cooled Loop in the PRTR. The results of these calculations are desired primarily to aid in demonstrating the adequacy of the design proposal. In addition, the operational limits of the loop and the consequences of the gas loop installation on the PRT reactor are of interest.
Date: August 4, 1959
Creator: Muraoka, J.
Partner: UNT Libraries Government Documents Department
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Field Experiments with Model Crib I. Location, Facility Design and First Experiment

Description: One of the research studies of the Chemical Effluents Technology Operation is the improvement of the method for predicting the capacity of a crib for the retention of wastes. In addition to laboratory work the research was extended a field experiment using a simulated crib fed with a solution containing a radioactive tracer. The purpose is twofold: (1) to check the validity of laboratory findings and (2) to observe several features of the behavior of solutions put to ground in the field.
Date: August 4, 1959
Creator: Knoll, K. C. & Nelson, J. L.
Partner: UNT Libraries Government Documents Department
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A Closed Circuit Television System for In-Well Use -- Interim Report

Description: Wells drilled to date on the Hanford project represent and initial investment of over one million dollars. These nearly six hundred wells have been used and will continue to be used for observation and monitoring purposes of direct interest to ground disposal of radioactive wastes. Through measurement of depth to the water table the changing gradients as a result of large volume waste disposal are determined and direction of ground water flow established. The extent of contamination in ground … more
Date: August 5, 1959
Creator: Ratcliffe, C. A.
Partner: UNT Libraries Government Documents Department
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Cofit - A 709 Program for Determining Extrapolation Length from Horizontal Traverse Data

Description: A program has been prepared for the 709 computer which will determine extrapolation length from horizontal traverses measurements taken in an exponential pile. The flux across the pile is assured to fit a cosine function of the form y = A cos B (X-C)
Date: August 11, 1959
Creator: Matsumoto, D. D.
Partner: UNT Libraries Government Documents Department
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Quarterly Report - October, November, December 1958 Plutonium Fuels Development Plutonium Metallurgy Operation

Description: A number of Pu-Al and UO2-PuO2 Zircaloy clad capsules have been fabricated for irradiation in the MTR. In addition, a four rod cluster containing Al 8 w/o Pu and Al 12 w/o Si 8 w/o Pu cores has been successfully irradiated and discharged from Loop 3 of the KER. A second four rod cluster is awaiting irradiation and design and fabrication of a seven rod cluster test element is underway.
Date: August 17, 1959
Creator: Wick, O.J.
Partner: UNT Libraries Government Documents Department
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709 Program for Reduction of Exponential Pile Data

Description: A multi-purpose program for processing exponential data has been prepared for the 709 computer. The main purposes of the program is to compute the material buckling from raw data (given counts, time, and counter information) or from previously calculated Athermal's. It is also possible to compute only CeCh (end and harmonic corrections) for a given B11 or series if B11's no counting data being entered. In every case, pile measurements must be submitted as input for corrections.
Date: August 20, 1959
Creator: Matsumoto, D. D.
Partner: UNT Libraries Government Documents Department
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Calculation of Geometrical Efficiency of Counters

Description: Let F be the flux of radiation going from a sample of radius R2 to a counter of radius B1 then the emitted intensity of radiation per unit solid angle. Then the flux between two elements of area do1 and do2 will be given by [equation] since [equation] and [equation]. Calculations and equations follow.
Date: August 8, 1952
Creator: Henrich, Louis R. (Louis Richard), 1908-
Partner: UNT Libraries Government Documents Department
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Three Lectures On Controlled Thermonuclear Power Production

Description: This report was written from the notes used by Dr. York in delivering his three lectures on considerations pertinent to the problem of utilizing controlled thermonuclear reactions for the production of power. The first lecture discussed fundamental properties of the DD and DT reactions and the reacting substances. The second lecture described the stellarator, a proposed machine for the controlled production of power from the above reactions. The third lecture described the pinch effect and cons… more
Date: August 29, 1952
Creator: York, Herbert F.
Partner: UNT Libraries Government Documents Department
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Sparking and X-Rays in a Mercury Pumped Vacuum System (Excerpt From Quarterly Report for March, April, May, 1952 - Linac Group - UCRL-1903)

Description: Sparking: The most obvious conclusion about 200 m.c. sparking is that it follows strictly surface gradient and does not depend upon total voltage. In order to arrive at this conclusion, a quantitative means for measuring the probability of sparking had to be constructed, since it was clearly evident that the d.c. notion of sparking was inadequate.
Date: August 1952
Creator: Kilpatrick, W.
Partner: UNT Libraries Government Documents Department
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Sheet Metal Can Furnace

Description: A need for a small vertical cylinder-type furnace arises frequently in the Chemistry Department at the Lawrence Radiation Laboratory (LRL). Adequate heat is the major requirement; close control or calibration is not usually necessary. A heating unit of this type can either be used for quickly concentrating solutions in centrifuge cones or, by the addition of a refractory pedestal--can be made into a crucible furnace for size 0 and 00 crucibles. Because much of the chemistry done at LRL is with … more
Date: August 17, 1961
Creator: Doyle, Richard C. & Phillips, Will D.
Partner: UNT Libraries Government Documents Department
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Fabricating Liquid-Hydrogen Targets From Mylar

Description: The increasing popularity of liquid-hydrogen targets in physics research has emphasized the need for containers with maximum beam transparency (i.e., thin walls and low Z) and suitable strength at cryogenic temperatures. Fabrication of a Mylar container satisfying these requirements is described here.
Date: August 17, 1961
Creator: Mehr, David L.
Partner: UNT Libraries Government Documents Department
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Calibration Of Bridgman Anvils, A Pressure Scale To 125 Kbars

Description: It is shown that a radial pressure gradient exists in the silver chloride when it is used as the pressure transmitting medium in Bridgman anvils. The gradient can be obviated by the use of circular sections of wire. The center of curvature of the wire hoop is made coincident with the anvil center. When the inner and outer diameters of the pyrophyllite retaining ring are 1/2 and 7/16" respectively, the pressure, P, is P = (0.725 + 0.468R) L where R is the fractional displacement from the center,… more
Date: August 1961
Creator: Montgomery, Peter W.; Stromberg, Harold; Lura, George H. & Jura, George
Partner: UNT Libraries Government Documents Department
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