Resource Type
Serial/Series Title
Atomic Energy Commission Reports
264
University of California Radiation Laboratory Reports
112
HW (Series)
110
Hanford Works Reports
103
AEC research and development report
91
Oak Ridge National Laboratory Reports
76
TID
60
NYO (Series) (New York)
49
Report (U.S. Atomic Energy Commission)
43
UC (Series)
29
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Nuclear Track Image Intensifier
"The design of the nuclear track intensifier was further analyzed to compare performance with design objectives. A preliminary analysis of the electron optics showed that the tube design suffers a small degree of astigmatism, which is increased in actual tabes by misalignment of parts, One tube was successfully completed and tested. Transit time of electrons from cathode to screen was determined to be 2.5 x 10/sup -8/ sec, 0.5 x 10/sup -8/ sec. Decay characteristics of several standard phosphors were measured. In the phosphor development phase, a latin square test was designed to evaluate combinations of thallium-activated rubidium iodide and cesium iodide phosphors under various evaporating conditions. Data were taken on various tests and analyzed statistically. On target samples submitted for tube evaluation, a reaction, which reduced light output, occurred between the aluminum and phosphor during vacuum bake. Oue image tube prepared with an alkali iodide mixture showed 10 to 25% improvement in screen resolution as compared to a P-11 screen."
Date:
December 30, 1960
Creator:
DesRochers, R. D.; Stern, H. A. & Ezard, L. A.
Object Type:
Report
System:
The UNT Digital Library
Status Report on the Pneumatic Temperature Measuring system Studies for the EGCR
The pneumatic temperature probe (PIM) is a device for measuring gas temperatures by utilizing the dependency of the flow of gases through a restriction on the temperature and pressure conditions. The determination is made by measuring critical mass flow across a restrictive element such as a nozzle and by knowing the upstream pressure and other variables pertinent to the critical flow equation, computing the temperature at the entrance to the restrictive element. In practice it has been found useful to use two critical flow nozzles in series and measure the ratio of the pressures at the nozzle inlets, together with the temperature at the downstream nozzle. The limitations of present thermocouple materials for long term use at elevated temperatures makes resort to this device attractive on many installations.
Date:
December 30, 1960
Creator:
Hochreiter, H. M.
Object Type:
Report
System:
The UNT Digital Library
Steady-State Radial and Axial Temperature Profiles of an E. G. C. R. 5 1/2" O. D. Through Tube During 1500 KW Operation - Part II
The steady-state radial and axial temperature profiles of an E. G. C. R. 5 1/2" O. D. through tube are determined for the test condition of an attemperated fuel assembly operating at 1500 KW in the loop. The profiles are determined for the case of the central control rod fully inserted and bank insertion to 62 inches (Δk = 0.025). The data are presented in the form of tables and curves.
Date:
December 30, 1960
Creator:
Noggle, L. W.
Object Type:
Report
System:
The UNT Digital Library
After Shutdown Heating in the HFIR
After shutdown heating rates have been calculated for the target, control plates, and the beryllium reflector of the HFIR. Hilvety previously calculated the after shutdown heating rates in the element and his results are reported in ORNL CP-60-4-110. Decay times of 1.0 10, 10^2, 10^3, 10^4, and 10^5 seconds have been considered, and heat fluxes have been computed for all of the mentioned components. The greatest heat fluxes were found to be at the surfaces of the control plates and the permanent beryllium reflector.
Date:
December 29, 1960
Creator:
McLain, H. A.
Object Type:
Report
System:
The UNT Digital Library
Progress Report for August-September 1960
A chemical flowsheet is proposed for recovery of strontium and rare earths from Purex wastes. The iron in the waste is first complexed with tartrate and the pH is adjusted with caustic. Strontium and rare earths are extracted by a solvent comprised of di(2-ethylhexyl)phosphoric--sodium di (2-ethylhexyl) phosphate--tributyl phosphate -- Amsco 125-82. and are stripped with nitric acid. Processing the strip product through additional solvent extraction cycles yields isolated, concentrated strontium and rare earth fractions.
Date:
December 29, 1960
Creator:
Brown, K. B.
Object Type:
Report
System:
The UNT Digital Library
The Boundary Layer Between a Plasma and a Magnetic Field - I
"The problem of a steady boundary layer or sheath between a plasma and a magnetic field is considered. A self-consistent transition layer is found which joins a uniform magnetic field at plus infinity with a collisionless field-free plasma region with arbitrary velocity distribution at minus infinity, i.e., a magnetic field profile is found such that the exact particle orbits in this field produce a current which gives rise to this field. An interesting feature of the solution is that, with any nonsingular velocity distribution at minus infinity, the magnetic field the plasma extends to infinity, exponentially attenuated, into the magnetic field region. The scale of length is the Larmor radius. Electric fields arising from charge separation in the case of particles of different mass are ignored."
Date:
December 28, 1960
Creator:
Grad, Harold, 1923-
Object Type:
Report
System:
The UNT Digital Library
Tory II-A Aerothermodynamics. Part II
This technical report describes the digital computer codes used for the aerothermodynamic calculations that were involved in evaluating the Tory II-A reactor.
Date:
December 28, 1960
Creator:
Uthe, P. M.
Object Type:
Report
System:
The UNT Digital Library
Analysis of Uranium Fuel-Element Wafers from Atomics International for Uranium, Plutonium and Samarium
Five irradiated and five unirradiated wafers were analyzed. Each wafer was analyzed for samarium by emission spectrography. The unirradiated wafers were analyzed for uranium by coulometric and potentiometric methods and for uranium isotopes by mass spectrometry. The irradiated wafers were analyzed for uranium and plutonium by coulometric methods, for plutonium isotopes by the 256-channel alpha pulse analyzer, and for the isotopes of uranium and of plutonium by mass spectrometry. The methods of preparing wafers for analysis are discussed; the data are tabulated.
Date:
December 27, 1960
Creator:
Gaitanis, M. J.
Object Type:
Report
System:
The UNT Digital Library
Dispersion Strengthening of Iron-Aluminum Base Alloys: A Feasibility Study
The feasibility of improving the mechanical properties at 1700-1800°F of oxidation-resistant Fe-Al-Cr alloys by means of a refractory dispersion has been explored. A literature search was conducted, preliminary experimental determinations of properties of the alloy and its oxides were carried out, and certain mathematical relations between dispersion characteristics and metallurgical variables were derived. The results indicate that the alloys can be strengthened sufficiently by using a dispersion with an interparticle spacing of about 2-3 µ. High-temperature native oxides of the Fe-Al-Cr alloy consist largely of Al2O3 and in theory would serve as a satisfactory second phase.
Date:
December 27, 1960
Creator:
King, Blake
Object Type:
Report
System:
The UNT Digital Library
Prediction of Two-Phase Flow From Mixing Length Theory
It is proposed in this report to describe a new two-phase flow mixing length model. It consists of treating the two-phase system as a continuous medium and applying to it the methods and assumptions so widely accepted in single-phase turbulent flow. Because it reduces a two-phase problem to an equivalent one in single-phase flow, the proposed model can be readily used to predict the effects of flow rate, channel geometry, and channel direction in two-phase flow.
Date:
December 27, 1960
Creator:
Levy, S.
Object Type:
Report
System:
The UNT Digital Library
Assembly of Fifty Prototype Fuel Elements for the Experimental Gas-Cooled Reactor
Report that describes the Oak Ridge National Laboratory Experimental Gas-Cooled Reactor, problems with the procurement and assembly of its components, and its economic feasibility.
Date:
December 23, 1960
Creator:
Wick, E. A. & Heestand, R. L.
Object Type:
Report
System:
The UNT Digital Library
Vapor Pressures of the Rare Earths
Abstract: This report presents the vapor pressures versus temperature data graphically for the rare earth elements, yttrium and scandium.
Date:
December 23, 1960
Creator:
Beavis, L. C.
Object Type:
Report
System:
The UNT Digital Library
Molten-Salt Reactor Program Quarterly Progress Report: July 1960
Report containing ongoing projects and experiments undertaken by the Oak Ridge National Laboratory's Molten-Salt Reactor Program.
Date:
December 22, 1960
Creator:
Oak Ridge National Laboratory
Object Type:
Report
System:
The UNT Digital Library
Kinematics of Nuclear Reactions Calculated with the IBM-704 Computer
Program using the IBM-704 computer to calculate certain kinematic quantities for any non-relativistic reaction of the form.
Date:
December 20, 1960
Creator:
Williams, B. D.
Object Type:
Report
System:
The UNT Digital Library
Thalluim in Meteorites
Procedures for the separation and concentration of microgram to nanogram amounts of thallium from gram amounts to galena and meteorite metal, sulfide, and silicate phases were developed and are described. The thallium is extracted from aqueous bromide of chloride solutions of moderate acidity using diethyl ether. A device for elimination of the large volumes of solvent by dropwise evaporation is described. Organic matter in the residue is destroyed by treatment with aqua regia, and the thallium is the residue is converted to the nitrate for spectrochemical or mass-spectrometric examination. The presence of thallium in the residue is tested by Rhodamine B. test.
Date:
December 20, 1960
Creator:
El-Badry, Hamed M.; Hodge, Edwin S.; Baer, William K. & Kohman, Truman Paul, 1916-
Object Type:
Report
System:
The UNT Digital Library
Thermal-Neutron Flux at the HRE-2 Core Wall, Determined from Zircaloy-2 Induced-Activity Measurements During Runs 13, 14, 16, 17, 18, 19, 20 and 21.
The thermal-neutron flux prevailing near the upper hole in the HRE-2 core wall was determined from measurements of the induced activity in a specimen cut from the edge of the hole. The specimen was removed following run 21 and was thus exposed to reactor neutrons during runs 13, 14, 16,17, 18. 19, 20, and 21. The neutron flux, calculated for an average core power level of 2 Mw, was 2.8 x10^13 neutrons/cm^2 sec. the core wall area from which the specimen was removed was located approximately 16-in. from the core center.
Date:
December 20, 1960
Creator:
Baker, J. E.
Object Type:
Report
System:
The UNT Digital Library
Feasibility Study of a New Mass Flow System : Quarterly Report No. 2 Covering the Period from September 1 to November 30, 1960
This is the second quarterly report that documents a system of mass flow that can record measurements of homogeneous flow, slurries, highly corrosive fluids and multiphase fluids, additionally considering pressure drops, measuring external to the flow, ruggedness and reliability.
Date:
December 19, 1960
Creator:
Burgwald, G. M.; Stone, C. A. & Genthe, William K.
Object Type:
Report
System:
The UNT Digital Library
Analog Computer Analysis of the Thermal Behavior of the EDCR Due to Reactivity Accidents
The ORNL analog computer was used to examine one aspect of a safety system for the EGCR. The thermal behavior of the fuel as a result of increases in reactivity at various power levels and gas flows was examined. Safety actions initiated by wither a flux-minus-flow signal or a reactor outlet gas temperature signal were included in simulation.
Date:
December 16, 1960
Creator:
Pierce, R. M.
Object Type:
Report
System:
The UNT Digital Library
Report of the Forty-Fifth National Conference on Weights and Measures, 1960
Report of the annual conference on weights and measures, hosted by the U.S. National Bureau of Standards in Washington D.C. It includes conference proceedings, a list of attendees, information about committees and officers, and other reports or commentaries discussed at the meetings.
Date:
December 16, 1960
Creator:
United States. National Bureau of Standards.
Object Type:
Report
System:
The UNT Digital Library
Bounce III
BOUNCE III is a program which was written for the IBM-704 as part of a study of the parameters of the neutron distribution in a large thermal column. The program calculates the eigenvalues and corresponding eigenvectors of the matrix resulting from a diffusion-theory, multigroup description of the thermal neutron spectrum.
Date:
December 15, 1960
Creator:
Kerr, B. A.
Object Type:
Report
System:
The UNT Digital Library
A Device for Continuous Detection of Hydrogen in Sodium
Abstract: A device to detect the presence of hydrogen in sodium has been developed. Such a device, installed in a sodium heated steam generator, would signal the presence of water in the sodium resulting from a leak in the sodium-water barrier.
Date:
December 15, 1960
Creator:
Strahl, H.
Object Type:
Report
System:
The UNT Digital Library
Final Report: 300 KWe Capsule Nuclear Power Plant Study
This document presents the results of investigations concerned with the conceptual design of a 300 KWe "Capsule" nuclear power plant.
Date:
December 15, 1960
Creator:
General Electric Company
Object Type:
Report
System:
The UNT Digital Library
On the Green's Function for Two-Dimensional Magnetohydrodynamic Waves. II
"As an extension of an earlier paper the Green's function is evaluated for the Lundquist equation linearized about uniform magnetic field, constant matter density, and zero flow velocity. It is assumed that all quantities are functions of two space variables and time only. In the general magnetic field configuration considered here a pure Alfvén disturbance no longer exists; there is instead a wave with properties of both the Alfvén and fast‐slow disturbance."
Date:
December 15, 1960
Creator:
Weitzner, Harold
Object Type:
Report
System:
The UNT Digital Library
Power Reactor Fuel Processing Pilot Plant: Brookhaven Fuel Program
Results of processing 47 metric tons of Brookhaven spent reactor fuel are summarized.
Date:
December 15, 1960
Creator:
McDuffee, W. T.
Object Type:
Report
System:
The UNT Digital Library