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CIVILIAN POWER REACTOR PROGRAM. PART III. CORE-PARAMETER STUDIES FOR SELECTED REACTOR TYPES

Description: 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… more
Date: January 1, 1959
Creator: Atomic Energy Commission, Washington, D.C. & Jackson and Moreland, Inc., Boston
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Creep Rupture in the Presence of a Fast Neutron Flux

Description: 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.
open access

GCRE-I HAZARD SUMMARY REPORT

Description: 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
open access

REACTOR FUEL WASTE DISPOSAL PROJECT PRESSURE-TEMPERATURE EFFECT ON SALT CAVITIES AND SURVEY OF LIQUEFIED PETROLEUM GAS STORAGE

Description: 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 300… more
Date: January 15, 1959
Creator: Brown, K. E.; Jessen, F. W. & Gloyna, E. F.
open access

THE ELECTROMAGNETIC PINCH EFFECT FOR SPACE PROPULSION

Description: 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 dischar… more
Date: August 1, 1959
Creator: Kunen, A.E. & McIlroy, W.
open access

Atmospheric Signals From Explosions and Their Interpretation

Description: 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 i… more
Date: December 1, 1959
Creator: Reed, J. W.
open access

RELEASE OF FISSION GASES FROM THE AE-6 REACTOR ON MARCH 25, 1959

Description: 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.
open access

Steady State Thermal Behavior of Hnpf Sodium Heat Transfer System

Description: 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.
open access

PLUTONIUM OXALATE DISK FILTER AND FILTER MEDIA STUDIES

Description: 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.
open access

Reactor Materials Study. Research and Development of Metal Hydrides. Quarterly Report No. 4 for July 1, 1959 to September 30, 1959

Description: 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. l9… more
Date: October 30, 1959
Creator: Beck, R. L.
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Positional Tolerancing at Sandia Corporation

Description: 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.
open access

Dissolution of aluminium oxide as a regulating factor in aqueous aluminum corrosion

Description: 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 t… more
Date: August 31, 1959
Creator: Dillon, R.L.
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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

Description: 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 pres… more
Date: January 1, 1959
Creator: Cogan, D.G.; Martin, S.F.; Kimura, S.J.; Ikui, Hiroshi & Fillmore, Paul G.
open access

Concentration of Plutonium by Cation Exchange--Stabilization of Pu(III) in Nitric Acid

Description: 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.
open access

DISCUSSION OF PERFORMANCE CALCULATIONS OF NUCLEAR ROCKET ENGINES

Description: 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.
open access

REACTIVITY LIFETIME. TEST RESULTS DL-S-225(T-612118A). Section I, Second Performance

Description: 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
open access

A Transistorized Pulse Height Analyzer for Gamma Spectroscopy

Description: 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.
open access

Report of the Forty-Fourth National Conference on Weights and Measures, 1959

Description: 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.
open access

Thermal Bowing of Core Subassemblies

Description: 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
open access

Fuel Enrichment for the Enrico Fermi Reactor

Description: 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
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