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CIVILIAN POWER REACTOR PROGRAM. PART III. CORE-PARAMETER STUDIES FOR SELECTED REACTOR TYPES
A report is presented to provide a tool for evaluating the relative economic incentives for changing reactor core parameters. The cost relations are shown in terms of differential cost in lieu of total cost. A total cost for each reactor described is included so that power costs for a specified set of parameters can be obtained. A description is also included concerning 5 reactor types considered along with a discussion of the effects on power costs of varying the significant core parameters. A listing of basic references is given. (J.R.D.)
Date:
January 1, 1959
Creator:
Atomic Energy Commission, Washington, D.C. & Jackson and Moreland, Inc., Boston
System:
The UNT Digital Library
Hanford Laboratories Operation monthly activities report, March 1959
This document details activities of the Hanford Laboratories Operation during the month of March 1959. (FI)
Date:
April 15, 1959
Creator:
unknown
System:
The UNT Digital Library
Creep Rupture in the Presence of a Fast Neutron Flux
Possible mechanisms for creep rupture during irradiation are examined. Evidence that the rupture occurs by grain boundary sliding alone, or by vacancy condensation, is compared. It is observed that vacancy condensation is the more probable mechanism, and that this mechanism predicts a reduction in creep rupture life for metals exposed to a fast neutron flux (neglecting effects of radiation annealing). (T.F.H.)
Date:
January 14, 1959
Creator:
Gregory, D. P.
System:
The UNT Digital Library
GCRE-I HAZARD SUMMARY REPORT
The GCRE-I hazard summary report is supplemented in the following areas: geometry and operation of the steam cooling system, the reactor coolant by-pass, and by-pass valving; the means by which by-passed circuits are prevented from remaining unintentionally disabled; design details, and details of procedure for core flooding operations. (A.C.)
Date:
March 1, 1959
Creator:
unknown
System:
The UNT Digital Library
REACTOR FUEL WASTE DISPOSAL PROJECT PRESSURE-TEMPERATURE EFFECT ON SALT CAVITIES AND SURVEY OF LIQUEFIED PETROLEUM GAS STORAGE
It is deemed feasible to store reactor fuel wastes in a salt dome cavity to a depth where the differential in pressure between the soil over-burden pressure and pressure of the fluid inside the cavity does not exceed 3000 psi, and the temperature is less than 400 deg F. Tests at pressure increments of 1000 psi were conducted on a 2" cylindrical cavity contained in a 6-in. long by 6-in. cylindrical salt core. Tests indicate that the cavity exhibited complete stability under pressures to 3000 psi and temperatures to 300 deg F. At temperatures of 100 to 400 deg F and pressures to 5000 psi continuous deformation of the cavity resulted. Initial movement of the salt was observed at all pressures. This was evidenced by vertical deformation and cavity size reduction. It was noted that a point of structural equilibrium was reached at lower temperatures when the pressure did not exceed 5000 psi. A literature study reveals that the most common type of cavity utilized in liquefied petroleum gas storage is either cylindrical or ellipsoidal. A few are pear or inverted cone shaped. There was no indication of leakage for cavities when pressure tested for as long as 72 hr. …
Date:
January 15, 1959
Creator:
Brown, K. E.; Jessen, F. W. & Gloyna, E. F.
System:
The UNT Digital Library
THE ELECTROMAGNETIC PINCH EFFECT FOR SPACE PROPULSION
The phenomenon of the electromagnetic pinch effect is used to accelerate ionized gases for space propulsion. Electrical energy, initially stored in capacitors, is discharged across two nozzle shaped electrodes wherein the radial pinch is converted to axial motion of the effected gases instead of confinement at the axis. The gas dynamics of a pinch using the hydrodynamical model of a msgnetic piston driving a shock wave is combined with the electrodynamics of the circuit to calculate the discharge behavior. Experiments on three different electrode designs are discussed and results compared with calculated values. Results are applied to one particular space propulsion system consisting of a nuclear energy source, a space radiator, a turbine-generator, capacitor, and a pinch tube. The specific mission analyzed is a one-way unmanned flight to a Mars orbit, starting from an Earth orbit. (auth)
Date:
August 1, 1959
Creator:
Kunen, A.E. & McIlroy, W.
System:
The UNT Digital Library
Atmospheric Signals From Explosions and Their Interpretation
Results are reported from a series of experimental highexplosive shots under inversion conditions at the Nevada Test Site which were made in an attempt to refine blast prediction techniques. Applications of the data in determinations of the amount of energy which remains in the blast wave as it reaches acoustic level and in determinations of the magnitude of the reflection factor when the blast wave strikes the ground are discussed. Data on shock wave propagation are presented graphically. It is concluded that the blast phenomenology of high-altitude shots can be predicted by using modified Sach's scaling. With some extrapolation to the height-of-burst versus blast-yield curve, it should be possible to make order-of-magnitude predictions of blast effects from high-altitude shots up to heights of burst of 1,000,000 ft. (C.H.)
Date:
December 1, 1959
Creator:
Reed, J. W.
System:
The UNT Digital Library
RELEASE OF FISSION GASES FROM THE AE-6 REACTOR ON MARCH 25, 1959
An analysis was made of the fission-gas-release incident during the pressure pumpdown of the AE-6 Reactor resulting in the contamination of the reactor room and members of the operating staff. Descriptions are given of the normal core pumping procedures, procedural alterations during the incident, the discovery of the contamination and its possible causes, and the remedial actions taken. Steps taken to minimize the chance of the occurrence of the contamination in the future are listed. (B.O.G.)
Date:
April 15, 1959
Creator:
Blackshaw, G.L.
System:
The UNT Digital Library
Steady State Thermal Behavior of Hnpf Sodium Heat Transfer System
The performance of the Hallam Nuclear Power Facility heat transfer components was investigated in order to determine the steady-state, part load characteristics under various operating conditions. The complete steady-state temperature distributions, variations of flow rates and heat transfer coefficients throughout the sodium heat transfer systems as functions of reactor load are shown in a series of graphs. (M.C.G.)
Date:
August 10, 1959
Creator:
Stell, A.T.
System:
The UNT Digital Library
PLUTONIUM OXALATE DISK FILTER AND FILTER MEDIA STUDIES
for filtration of plutonium oxalate slurries. A scalpel produces a slit in the filter precoat, leading to increased filtration in this slit, and the oxalate is removed by a doctor knife; this technique results in prolonged blowback cycles and more uniform delivery of filtered oxalate to subsequent processing steps. Several types of filter media were tested, and rigid porous aluminum oxide was found to be the best one. (D.L.C.)
Date:
October 19, 1959
Creator:
Rey, G.
System:
The UNT Digital Library
Reactor Materials Study. Research and Development of Metal Hydrides. Quarterly Report No. 4 for July 1, 1959 to September 30, 1959
Activities during the period were directed primarily toward determination of the engineering properties of hydrided materials. The tensile strength and elongation, thermal expansion, thermal conductivity, and heat capacity of ZrH were determined as functions of temperature and H content. Preliminary results of Ti-base material studies indicate that these materials can be used for shielding and structural materials with the incorporation of rare earth hydrides. A summary of the work from Oct. l958 to Sept. 1959 is included. (J.R.D.)
Date:
October 30, 1959
Creator:
Beck, R. L.
System:
The UNT Digital Library
Positional Tolerancing at Sandia Corporation
The positional tolerance method of dimensioning is described. The emphasis is placed on the elimination of ambiguities and increase in tolerances provided by this method as compared to the older, bilateral method. (auth)
Date:
May 1, 1959
Creator:
Eichert, F. F. & Nicovich, P. A.
System:
The UNT Digital Library
Dissolution of aluminium oxide as a regulating factor in aqueous aluminum corrosion
The solubility of aluminum corrosion product in contact with metallic aluminum in deionized water has been determined over the range 80 to 350/sup 0/C. Evidence is presented to show that oxide dissolution results in the formation of a porous oxide on aluminum exposed in refreshed dynamic systems. Dynamic corrosion rate data have been analyzed on the basis of parabolic film growth and a linear oxide degradation process acting simultaneously on the system. The degradation process has been shown to be a function of refreshment rate.
Date:
August 31, 1959
Creator:
Dillon, R.L.
System:
The UNT Digital Library
Ophthalmologic survey of atomic bomb survivors in Japan, 1949. Atomic bomb radiation cataract case report with histopathologic study. Medical examination of Hiroshima patients with radiation cataracts
This document contains 3 reports dealing with the delayed effects of radiation on the eyes of survivors of the atomic explosions in Hiroshima and Nagasaki. In the first study, 1000 persons who were listed as having been in the open and within two kilometers of the hypocenter at the time of the explosion were selected at random from the census files of the Atomic Bomb Casualty Commission for study. In addition, 231 others, comprising the total available number of surviving persons listed at present in the census files as having been within one kilometer of the hypocenter, were examined, as were several hundred others who were contacted through newspaper publicity, referrals from local ophthalmologists, or through hearsay. The survey resulted in bringing in persons having, or having had, a variety of ocular conditions. Those connected with the atomic bomb included the following diagnoses; multiple injuries of eyes and eyelids; keratoconjunctivitis from ultraviolet and ionizing radiations; thermal burn of the cornea and of the retina; retinitis proliferans; and radiation cataracts. The cataracts were the only delayed manifestations of ocular injury from the atomic bomb. The second paper is a case report of a histopathologic study of atomic bomb radiation cataract. The …
Date:
January 1, 1959
Creator:
Cogan, D.G.; Martin, S.F.; Kimura, S.J.; Ikui, Hiroshi & Fillmore, Paul G.
System:
The UNT Digital Library
Concentration of Plutonium by Cation Exchange--Stabilization of Pu(III) in Nitric Acid
A study to define the effectiveness limits of sulfamic acid and to discover other better stabilizers for Pu(III) is described. Ascorbic and isoascorbic acids, used in conjunction with sulfamic acid reduced Pu(IV) to stable Pu(III) in nitric acid. Aminoguanidine sulfate also retarded the oxidation of Pu(III) but did not reduce Pu(IV). (J.R.D.)
Date:
February 1, 1959
Creator:
Tober, F. W. & Russel, E. R.
System:
The UNT Digital Library
DISCUSSION OF PERFORMANCE CALCULATIONS OF NUCLEAR ROCKET ENGINES
BS>Some of the fundamental relationships in a nuclear rocket engine are discussed. The equations required to calculate the performance of the rocket are presented. The problems associated with these calculations are also pointed out. (auth)
Date:
December 21, 1959
Creator:
Semple, E.L.
System:
The UNT Digital Library
REACTIVITY LIFETIME. TEST RESULTS DL-S-225(T-612118A). Section I, Second Performance
The performance, reliability, stability, and reactivity lifetime variations of the Shippingport PWR are determined under normal steady state conditions. These characteristics are studied over a period of 758 EFPH, at a power level of about 60 Mw(e). Flux-tilt corrections and plant operations during this time are described. (T.F.H.)
Date:
March 1, 1959
Creator:
unknown
System:
The UNT Digital Library
A Transistorized Pulse Height Analyzer for Gamma Spectroscopy
From abstract: "A scintillation detector has a pulse height output which is a linear function of the energy of impinging gamma radiation. A pulse height analyzer system determines the amplitude distribution of this train of pulses. The system also displays this information graphically in a form which is convenient for further analysis."
Date:
March 23, 1959
Creator:
Graveson, R. T.
System:
The UNT Digital Library
In Vivo Gamma Counting Method of Determining Uranium Lung Burden in Humans
Scintillation spectrometry is used to measure the gamma activity from uranium for determining lung burden in the human body.
Date:
June 23, 1959
Creator:
Cofield, Rogers E.
System:
The UNT Digital Library
Report of the Forty-Fourth National Conference on Weights and Measures, 1959
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 18, 1959
Creator:
United States. National Bureau of Standards.
System:
The UNT Digital Library
Thermal Bowing of Core Subassemblies
Report issued by the APDA over studies conducted on thermal bowing of core sub-assemblies at the Enrico Fermi Atomic Power Plant. As stated in the introduction and summary, "the present report deals with this problem in the design of the Enrico Fermi Reactor and with the method which has been adopted to avoid a positive temperature coefficient of reactivity" (p. 1). This report includes illustrations, and photographs.
Date:
February 20, 1959
Creator:
De Stordeur, Arnold
System:
The UNT Digital Library
Fuel Enrichment for the Enrico Fermi Reactor
Report issued by the APDA over fuel enrichment processes at the Enrico Fermi Atomic Power Plant. As stated in the introduction, "the results that directly apply to the determination of the enrichment will be given" (p. 6). This report includes tables, and illustrations.
Date:
March 12, 1959
Creator:
Garelis, Edward
System:
The UNT Digital Library
Preliminary Report on Sodium Temperature Coefficients in Large Fast Reactors
Report issued by the APDA over preliminary studies conducted on temperature coefficients in fast breeder reactors. Methods and results of the studies are presented and discussed. This report includes tables, and illustrations.
Date:
1959
Creator:
Nims, J. B. & Zweifel, P. F.
System:
The UNT Digital Library
University of Chicago Laboratory of Molecular Structure and Spectra Technical Report: 1957-1959, Part 2
Report containing articles, manuscripts, and tabulations of recorded spectra created by the Spectroscopic Laboratory of the University of Chicago.
Date:
1959~
Creator:
University of Chicago. Laboratory of Molecular Structure and Spectra.
System:
The UNT Digital Library