Search Results

open access

Chemistry of Cement: Proceedings of the Fourth International Symposium, Volume 1, 1960

Description: Document containing principle and supplementary papers presented at the Fourth International Symposium on the Chemistry of Cement, as well as discussions of those papers by members of the Symposium. Index begins on page 551.
Date: August 31, 1962
Creator: United States. National Bureau of Standards.
Partner: UNT Libraries Government Documents Department
open access

HAZARDS ANALYSIS. RADIOLOGICAL HAZARDS

Description: ABS>Doses were calculated for persons off site and in the EGCR cortrol room following the maximum credible accident (depressurization), and for the public due to normal operational stack release. The assumptions and calculations used in the study are given in detail. (D.L.C.)
Date: August 31, 1962
Creator: Courtney, J.C.
Partner: UNT Libraries Government Documents Department
open access

On the Calibration of Cascade Impactors

Description: From Abstract: "In the following paper, the two customary methods of calibrating cascade impactors are compared. It is shown that the method of determining collection efficiency as a function of particle size for each stage provides information for interpreting results in terms of impactor theory, making it possible to establish adequate jet performance."
Date: August 31, 1962
Creator: Mercer, T. T.
Partner: UNT Libraries Government Documents Department
open access

Z Plant Filtrate Ion Exchange Facility (CGC-978) start-up slowsheep

Description: A flowsheet representing start-up conditions of the Filtrate Ion Exchange Facility is given. These flowsheet conditions are used for the routine recovery of plutonium from oxalate precipitation filtrates. (LK)
Date: August 31, 1962
Creator: Berglund, C. J.
Partner: UNT Libraries Government Documents Department
open access

THE FERRITE BIASING SYSTEM FOR THE RADIO FREQUENCY CAVITIES OF THE PRINCETON-PENNSYLVANIA 3 Bev PROTON SYNCHROTRON

Description: A description is given of the ferrite biasing system for the four tuned radio frequency cavities of the synchrotron. Each ferrite loaded double cavity has a single turn bias winding which is driven to a peak current of 13,500 amperes by a push-pull transformer arrangement. There is automatic tap changing of the transformer to accommodate the variable impedance load (for power considerations). The programming and frequency response of the system have to be such that each cavity can operate as the reso nant circuit of a self tracking radio frequency amplifier over the frequency range 6.5 to 30 Mc at the 20 cps repetition rate of the synchrotron. Between acceleration cycles it is necessary to program the ferrite to a given magnetic state, near that of maximum radio frequency permeability. (auth)
Date: August 29, 1962
Creator: Rees, G.H.
Partner: UNT Libraries Government Documents Department
open access

High-Temperature Reactions of Type 304 Stainless Steel in Low Concentrations of Carbon Dioxide and Carbon Monoxide

Description: Compatibility studies of type 304 stainless steel in helium containing low concentrations of CO and CO/sub 2/ were conducted. The oxidation rates were insensitive to impurity concentrations between 0.0006--0.3 vol% in the temperature range 400--1000 deg C when P/sub co2/P/sub co/ was less than 0.66. Ratios above this value resulted initially in a slow oxidation rate, but was followed by an accelerated attack. The incubation period for the break-away varied with the P/sub co2//P/sub co/ ratio and the pressure of the two gases. The oxidation reactions proceeded through a selective depletion of chromium from the alloy which increased the carbon solubility and depletion of nickel which led to the transformation of austenite to ferrite. Parabolic reaction rates were observed for the formation of the protective oxides. Arrhenius plots of rate constants versus 1/T indicated the presence of several oxides which was confirmed by other methods. Carburization or decarburization reactions occurred coincidentally with oxidation and depended upon temperature and (P/sub CO/)/sup 2/ /P/sub CO2/ and the P/sub co2//P /sub CO/. Neither was detected below 600 deg C. Between 600--900 deg C, only carburization occurred and appeared to be mainly dependent on the temperature. Above 900 deg C, both carburization and decarburization occurred depending upon the (P/sub co/)/sup 2//P/sub co2/ and the P/sub co2//P/sub co/. The interactions of the oxidizing and carburization reactions resulted in carbon maxima at a (P/sub co/)/sup 2//P/sub co2/ ratio of 0.227. The results indicate that it may be impractical or unnecessary to reduce impurity gases to levels which do not cause surface reactions. It is concluded that undesirable oxidation and carburization reactions can be eliminated by controlling the ratios of the impurity gases. (auth)
Date: August 29, 1962
Creator: Inouye, H.
Partner: UNT Libraries Government Documents Department
open access

Pathfinder Atomic Power Plant. Thermal and Hydraulic Design of the Pathfinder Boiling Water Integral Nuclear Superheating Reactor

Description: A thermal and hydraulic design investigation of the Pathfinder Reactor, including analytical and experimental determinations, as well as a complete set of performance calculations, was carried out. A detailed analysis of the reactor energy balance was conducted. Results of the analyses indicated that the reactor will perform within the limits of the material design criteria and operational requirements. Fuel element temperatures are not excessive under the worst combination of circumstances. Thermal stresses in the superheater were minimized by designing the annular element so that temperatures are kept as uniform as possible at every axial location. In all cases, sufficient heat dissipation capacity was found to exist to ensure an ample margin of safety. (M.C.G.)
Date: August 29, 1962
Partner: UNT Libraries Government Documents Department
open access

The Radiation Leakage Survey of the Shield of the Nuclear Ship Savannah

Description: A detailed 4urvey of the radiation from the N.S. Savannah shield was made. The study was accomplished with the reactor at its full power of 69 Mw during a cruise of 2821 miles. The results of the detailed shield survey show that the design dose rate of 0.5 rem/yr for passenger spaces is not exceeded in any region to which passengers have access. ln the area restricted to crew access the design dose rate of 5.0 rem/yr is nowhere exceeded except in a small region on D'' deck in a room to which entry can readily be controlled. Specifications for cargohold dose rates, 0.5 rem/yr at 1/5 full power, are satisfactorily met. Additional data obtained include measurements of special points for comparison with dose rates predicted in design calculations, and an experiment examining the result of loss of water from the Savannah's subreactor shield tanks. Predicted dose rates were conservatively higher than the dose rates measured, and the result of the water-loss experiment showed that even with a total emptying of the tanks a safe condition exists only a few feet from the shield. (auth)
Date: August 29, 1962
Creator: Blizard, E.P.; Blosser, T.V. & Freestone, R.M. Jr.
Partner: UNT Libraries Government Documents Department
open access

The Scale Transformation in Physics

Description: Some criteria are established to test whether invariance under a continuous transformation will lead to a conservation law. The scale transformation is examined as a special case, and shown not only to lead to no general conservation law, but aiso in fact to be of a trivial nature. This is due to the rather artificial way in which scale invariance is usually introduced. A theory is then constructed by introducing an internal coordinate of dimension (length) in order to allow only the dimensionless ratio of lengths to enter; and by exploiting the gauge-like structure of the scale transformation. In this theory the scale transformation does iead to a new conserved current (as well as to an almost conserved'' one), and the internal coordinate is shown to play the same role for the scale transformation as the internal coordinate spin plays for the case of rotations. (auth)
Date: August 29, 1962
Creator: Greenberger, D. M.
Partner: UNT Libraries Government Documents Department
open access

THE OAK RIDGE RESEARCH REACTOR (ORR), THE LOW-INTENSITY TESTING REACTOR (LITR), AND THE OAK RIDGE GRAPHITE REACTOR (OGR) AS EXPERIMENT FACILITIES

Description: >Characteristics of the ORR, LITR, and OGR that experimenters have found to be important are listed. The results of a survey conducted among experimenters on the utility of the reactors for various types of experiments are discussed, and some changes which might be made to improve the utilization are listed. A brief outline, with references, of most of the experiments currently being performed is included. (auth)
Date: August 28, 1962
Creator: George, K.D.
Partner: UNT Libraries Government Documents Department
open access

Preliminary hazards review: Overboring Hanford reactors (condensed version)

Description: This is a condensed version of an extended hazards safety review of a proposal to modify the six 8 3/8-inch lattice reactors on the Hanford site. The review was intended to satisfy the specifications for a Preliminary Hazards Review as adopted at the third meeting of the General Electric Technological Hazards Council at New York City on June 15-16, 1961. This supplement is a tabular condensation of the information in the general document. One departure is made from the specifications for such a review: since the overbore proposal is a modification to existent production reactors, those items which will not be changed by the modification are not as a rule included.
Date: August 28, 1962
Creator: Nilson, R. & Carlson, P. A.
Partner: UNT Libraries Government Documents Department
open access

Reactor Controls Reliability and Maintenance at the ORR

Description: Early evaluation and study of the various criteria for the ORR clearly established the requirements for the fundarnental safety and control instrumentation, and the instrumentation was well integrated into the design and construction of the plant. However, it was not designed for the optimum of maintenance convenience and minimum reactor down time in the event of instrument failure. The revisions and additions that have been made in the physical plant and maintenance which have resulted in a definite reduction of reactor down time resulting from instrument failure in the reactor and in the experiments are described. (auth)
Date: August 28, 1962
Creator: West, K.W.
Partner: UNT Libraries Government Documents Department
open access

Technology of ceramic components. Part 3 of the Tory II-C program

Description: Declassified 26 Nov 1973. Fuel elements for the Tory II-C reactor are described along with fuel fabrication processes and mechanical and physical properties of the BeO-- UO/sub 2/ fuel materials. (JRD)
Date: August 28, 1962
Creator: Rothman, A.J.
Partner: UNT Libraries Government Documents Department
open access

A Method of Solving the Time Dependent Neutron Thermalization Problem

Description: The method of singular eigenfunctions introduced first by Van Kampen and developed later by Case and Mika in connection with a one velocity transport problem, was adapted to solve the time and energy dependent infinite medium problem. The expansion of neutron density and scattering kernel in series of Hermite functions reduces the Boltzmann equation to a system of homogeneous linear equations. The resulting set of regular and singular eigenfunctions is shown to be complete and explicit formulas are found for the normalization integrals and Green's function. (auth)
Date: August 27, 1962
Creator: Koppel, J. U.
Partner: UNT Libraries Government Documents Department
open access

An Analysis of the Inherent Stability of the EOCR

Description: The inherent stability of the EOCR at full power, exclusive of the heat exchanger, is investigated. Space and time dependent differential equations and transfer functions for the nuclear and thermal processes occurring in the reactor core and vessel are derived. Reactor stability is analyzed by application of the Nyquist stability criterion. The results show that the EOCR has an extremely large margin of inherent stability. (auth)
Date: August 24, 1962
Creator: Gossmann, S.R.
Partner: UNT Libraries Government Documents Department
open access

A feasibility study: The application of cooling towers for reduction of Hanford Plant heat load to the Columbia River

Description: Hanford production reactor operation requires the rejection of very large heat loads. At the present time the heat load is rejected to the Columbia River by the reactor effluent. At low river flows the hot effluent can have appreciable effects on river temperatures. The purpose of this study is to evaluate the feasibility and costs of Cooling Towers as a means of reducing the heat load rejected to the Columbia River. After evaluation of published information, available data, and Hanford plant conditions, it is concluded that: (1) That an induced draft cooling tower, because of its longer cooling range,, would be an effective cooling device for reduction of gross heat load rejected to the Columbia River. Additional study will be required to determine effective use on an area to area basis. (2) That a basically wood, counter-flow, induced draft cooling tower could be installed for approximately $1600 to $2000 per megawatt capacity. This cost is a probable minimum and might be increased by the cost of auxiliary features required for radiation control. (3) That additional study and developmental testing would be required to determine the extent of contamination problems which would result from the cooling tower installation. These problems would include the degree of contamination buildup both within the cooling tower and the surrounding area, the effect on operation and maintenance, and the economics and use of materials other than wood. (4) That certain areas of consideration which affect the installation of cooling towers at Hanford be studied. These areas (beyond the scope of this report) which require study are: cooling economics for reactors, total effluent facilities, and impact of atmospheric loading of contaminated moisture on the Hanford Plant area.
Date: August 24, 1962
Creator: Peck, G. E.
Partner: UNT Libraries Government Documents Department
open access

General parameter study of a bare, cylindrical reactor having the same materials as Tory II-C

Description: This memorandum describes studies undertaken to investigate the properties of Tory II-C with the aims of reducing weight and size and in increasing performance. Space and weight limitations aboard existing sea-going launch vehicles required this general parameter study which utilizes a bare, cylindrical reactor having the same materials as Tory II-C.
Date: August 24, 1962
Creator: Stubbs, T.
Partner: UNT Libraries Government Documents Department
open access

Nuclear Safety Program Semiannual Progress Report for Period Ending June 30, 1962

Description: Progress in nuclear safety research and development is reported. Topics covered include: reactivity effects of fuel displacements in a pool-type reactor, release of fission products on out-of-pile melting of reactor fuels, release of fission products on in-pile melting of reactor fuels, fission product transport evaluations, characterization and control of accident-released fission products, nuclear safety pilot plant, preparation of reactor containment hardbook, and radiochemical plant safety studies. (M.C.G.)
Date: August 24, 1962
Partner: UNT Libraries Government Documents Department
open access

Recrystallization of Beta-Heat-Treated Dingot-Uranium Cores. Topical Report

Description: Annealing beta-heat-treated production-size dingoturanium core blanks in the high alpha range (1150 to 1200 deg F) produced a fine, equiaxed grain size by a recrystallization process. The extent of recrystallization is dependent upon the rate of cooling through the beta-to-alpha transformation, the time and temperature of annealing, and whether or not impurities that retard grain growth are present. The cooling rate through the beta-to-alpha transformation was varied by using a range of beta temperatures and air cooling times prior to quenching into water. Longer air cooling times are permissible at the higher beta temperatures; however, the greatest amount of induced lattice strain was obtained after an air delay of only 2 seconds before quenching. Decreasing the annealing temperature results in a corresponding increase in the annealing time required for an equivalent amount of recrystallization. A second phase, present in the alloyed dingot metal, inhibited recrystallization and grain growth. Alloyed metal recrystallized progressively from the outer periphery to the center of the core, whereas unalloyed metal subjected to identical annealing conditions exhibited recrystallized grains throughout the cross section. A reduction in grain size from 0.38 mm to 0.25 mm occurred in a beta-treated, unalloyed core after annealing at 1200 deg F for 4 hours. The grain size of betaquenched, alloyed metal decreased from 0.28 mm to 0.19 mm on recrystallization. There appears to be change in the orientation of a beta-quenched core as a result of recrystallization. The beta quench-alpha anneal process could be integrated with an alpha-phase vacuum outgassing process to produce fine-grained metal that is essentially free of strain and preferred orientation and has a low hydrogen c ontent. (auth)
Date: August 24, 1962
Creator: Guyer, R. R. & Neumann, N .F.
Partner: UNT Libraries Government Documents Department
open access

Chemical Technology Division, Unit Operations Section Monthly Progress Report, February 1962

Description: In the operation of 6-in.-dia. foam-liquid columns, increase in either the liquid flow or foam flow caused increased channeling with increased HTU. Flooding values for the Immi mixer-settler were obtalned using the amine extraction final cycle Pu flowsheet. Two tests of the addltlon of uranyl nitrate to a thoria sol were made, one of which gave a good product and the other a product which disintegrated during calcination. Material balances for 22 waste calcination runs are summarized. (auth)
Date: August 23, 1962
Creator: Whatley, M. E.; Haas, P. A.; Horton, R. W.; Ryon, A. D.; Suddath, J. C. & Watson, C. D.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen