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Training of Consumers Public Power District Personnel for the Operation of the Hallam Nuclear Power Facility

Description: Training of Consumers Public Power District (CPPD) operating personnel for the Hallam Nuclear Power Facility (HNPF) was carried out under two formalized training programs. Both programs were organized and directed by Atomics International (AI). The first program was conducted in 1960 while he HNPF was under construction. The second program was begun in September 1961, prior to the initial HNPF dry critical loading experiment, and was completed in February 1963. The conventional portion of Sheldon Station has been a commercial power plant since July 1, 1961. Sheldon Station CPPD personnel were utilized extensively as instructors for the two formalized HNPF training programs and as responsible engineers for numerous test of the HNPF. CPPD shift personnel constituted the principal operating force throughout HNPF construction, reactor startup, and testing.
Date: October 1963
Creator: Loomis, J. S.
Partner: UNT Libraries Government Documents Department
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A Talk on NMR Applied to Polymer Research Given at the Eastern Analytical Symposium - November 14, 1962

Description: The nature and types of internal molecular and thermal motions that polymer chains and polymer segments undergo have a great bearing on the physical behavior of polymeric solids. A relatively new tool is now available that permits us to observe and study internal thermally-induced motions directly at the atomic or molecular level rather than from macroscopic observations. this tool is nuclear magnetic resonance spectroscopy. This talk discusses (1) the nature of nuclear magnetic resonance, (2) NMR line shapes and the influence of temperature, (3) NMR line widths and second moments as a function of temperature, and (4) lists six general conclusions.
Date: November 14, 1962
Creator: Sauer, John A.
Partner: UNT Libraries Government Documents Department
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Thin Film Measurements by X-Ray Emission Spectrography

Description: When a beam of X-rays penetrates through a layer of material, the intensity of the beam is reduced by absorption. some of the energy that has been absorbed may be re-emitted as X-ray quanta, by the atoms that absorbed it, at a wavelength characteristic of the emitting atom but longer than the quantum absorbed. Four methods of measuring thin films that use X-ray emission apparatus have been described, each of which is useful over a limited range of thickness, and for certain kinds of samples.
Date: 1963
Creator: Zemany, P. D.
Partner: UNT Libraries Government Documents Department
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[Delta]I = 1/2 Rule for Non-Leptonic Strangeness-Changing Decay Processes

Description: Gell-Mann and Pais were the first to suggest that the non-leptonic decay processes of strange particles may be subject to an isospin selection rule, allowing only those decay transitions which involve a change [delta]I = 1/2 in to total isopin of the system. At present, however, there is really no theoretical framework for the description of weak interactions into which this selection rule fits in a natural and compelling way. The report includes sections on the 91) decay processes of the [caret] hyperon, (2) decay processes, (3) [complex conjugate] decay processes, and (6) K[pi]3 decay processes. We have considered the evidence on all of the known non-leeptonic non-radiative decay modes of strange particles. All of this evidence is in good qualitative accord with the [delta]I = 1/2 selection rule.
Date: December 2, 1963
Creator: Dalitz, R. H. (Richard Henry), 1925-2006.
Partner: UNT Libraries Government Documents Department
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Operational Physics Data from the HWCTR

Description: The Heavy Water Components Test Reactor (HWCTR) was built for the Atomic Energy Commission by the Du Pont Company to satisfy a need for fuel testing in the AEC's Heavy Water Power Reactor Program. The reactor was designed to provide a realistic test environment for full size fuel candidates. The report contains sections on (1) the containment building, (2) vertical cross section of the reactor vessel, (3) core layout, (4) low power physics tests and comparison with calculations, (5) rod worths, (6) temperature coefficients, (7) flux shapes, and (8) the operating philosophy of a test reactor.
Date: September 20, 1963
Creator: Rusche, Benard Clements, 1931-
Partner: UNT Libraries Government Documents Department
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Fuel Failure Detection in the Heavy Water Components Test Reactor

Description: The Heavy Water Components Test Reactor (HWCTR) is a pressurized reactor, cooled and moderated with D2O, and has the capability of testing fuel assemblies under operating conditions of coolant flow, temperate, and pressure that are typical of those proposed for modern power reactors. The report contains (1) description of the four systems used for failed element detection, (2) discussion of the laboratory analyses of water samples used a as backup for the fuel failure instruments, (3) description of 3 monitors, Cyclic Air Sampling Monitor, Stack Gas Activity Monitor, Health Physics Building Monitors, (4) normal full power activity readings, (5) discussion of the experience during fuel failure.
Date: September 20, 1963
Creator: Kiger, E. O.
Partner: UNT Libraries Government Documents Department
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Control of the Dissolved Gases in the Moderator of the HWCTR

Description: The Heavy Water Components Test Reactor (HWCTR) is used to test prototype fuel elements for power reactors that are moderated with heavy water and fueled with natural or slightly enriched uranium. During the initial critical experiments in the HWCTR, it was observed that there were unexpected variations in nuclear reactivity. Investigations revealed that this effect was due to bubble of helium gas appearing and disappearing in the moderator. An examination of the expected operating conditions of the HWCTR and the solubility of helium in D2O showed that it was possible during normal operation for the helium content of the moderator to exceed saturation and thus for helium to appear as bubbles in the moderator. The possibility of helium bubbles appearing in the moderator because of solubility characteristics was eliminated by modifications to the process system so as to maintain the gas content of the moderator appreciably below saturation.
Date: September 20, 1963
Creator: Arnett, L. M.
Partner: UNT Libraries Government Documents Department
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Operating and Safety Problems in a Research Reactor

Description: Abstract. The purpose of this paper is to present, in the light of 20 years of reactor-operation experience at ORNL, what is being done in preparation for operation of the HFIR (High Flux Isotope Reactor). This paper considers only the areas of staffing and training; development of operating and maintenance procedures; preoperational testing of water systems; and testing of remote handling tools. The preparatory work in other areas such as the hydraulic tests, neutron tests, etc., is not covered in this presentation.
Date: October 23, 1963
Creator: McCord, R. V.
Partner: UNT Libraries Government Documents Department
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The Education, Experience, Training, and Certification of Reactor Operators at AEC-Owned Reactors

Description: Results of a questionnaire survey are presented on reactor supervisor and operator education, experience, and training, and on certification procedures by reactor category. The questionnaires were obtained from 362 supervisors, 393 operators, 44 supervisor trainees, and 139 operator trainees.
Date: October 31, 1964
Creator: Wilgus, Walter S.; McCool, Whittie J. & Biles, Martin B.
Partner: UNT Libraries Government Documents Department
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Selection of Personnel for Reactor Operator Training

Description: Over the past six years, the hiring practices of the Reactor Operations Division of Argonne National Laboratory have been conducted to determine the highest level of personnel who would be willing to remain in the position of reactor operator. We have discontinued the hiring of personnel who have a bachelor's degree from an accredited institution or who are close to receiving such a degree. We now hire men from three general categories: (1) graduates from two-year technical institutes, (2) men who have had a number of years of experience in related operating jobs such as the petroleum industry or the chemical industry, and (3) men who have served in the nuclear programs of the armed forces. The following tests are given: (1) Wonderlic personnel Test, score above 43 percentile is mandatory, (2) Oral Directions Test, score above 80 percentile is expected, (3) mechanical Comprehension Test, score above 80 percentile is expected, (4) Arithmetic Reasoning Test, score above 60 percentile is expected, and (5) Primary Mental Abilities Test, used primarily as a check on the other tests given. Applicant is interviewed by at least three supervisors in the Division. All three supervisors must concur before an offer of employment is made.
Date: October 23, 1963
Creator: Martens, Frederick H. (Frederick Hilbert), 1921-2012.
Partner: UNT Libraries Government Documents Department
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The Scattering of Lattice Vibrations by Vacancy Type Defects

Description: Abstract. A brief review of the development of the subject of lattice defects in solids is given. The relation of this problem to field theory methodology is discussed; the defect is regarded as a particle imbedded in the phonon field. One may then discuss scattering states in the field, or “dressed” states of the particle. Specific application is then made to a defect in a simple cubic crystal including interactions between the defect site and its six nearest neighbors. Scattering solutions and scattering cross-sections are calculated and show that vacancies can cause strong resonant scattering, or pseudo-localized modes, at frequencies well below the Debye frequency. Applications to thermal conductivity and other experiments are discussed briefly.
Date: August 1963
Creator: Krumhansi, James A.
Partner: UNT Libraries Government Documents Department
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Pulse Radiolysis Studies of the Reactivity of the Solvated Electron in Ethanol and Methanol

Description: Abstract. By means of the pulse radiolysis technique a short-lived transient species has been observed in irradiated de-aerated ethanol and methanol, exhibiting an optical absorption throughout the visible and near infra-red. This transient is suggested to be the solvated electron on the basis of the nature of the spectrum, the reactivity with hydrogen ion and with various organic electron acceptors, and the formation of mononegative ions of some of these acceptors. The absolute rate constants have been determined for the reactions of the solvated electron with hydrogen ion, oxygen and benzyl chloride in ethanol and methanol. The diphenylide ion was found to be short-lived in ethanol. The absolute rate constant for the first-order decay of the diphenylide ion has been determined.
Date: June 10, 1963
Creator: Taub, Irwin A.; Sauer, Myran, C., Jr. & Dorfman, Leon M.
Partner: UNT Libraries Government Documents Department
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Staffing Experience for Operation of the Plutonium Recycle Test Reactor

Description: The Plutonium Recycle Test Reactor is a research and development tool supporting the Plutonium Recycle Program and the research activities at Hanford. The present organization directly associated with the PRTR is composed of Operating, Technical Assistance, Maintenance, and Engineering Groups. Liaison with research groups utilizing PRTR facilities is accomplished through the Technical Assistance Group. the other three groups serve the PRTR in the manner suggest by the group name. This paper limits its interest to the staffing experience of the Operating Group.
Date: September 23, 1963
Creator: Koberg, D. R.
Partner: UNT Libraries Government Documents Department
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ML-1 Power Determination

Description: The ML-1 is a nuclearly heated, electrical power producing plant being developed for the U. S. atomic Energy commission and the U. S. Army by Aeroject-General Nucleonics. The power plant is a compact, water-moderated, gas-cooled, nuclear reactor, coupled in a single closed cycle to a gas driven turbine-compressor set and alternator. The plant is designed to produce power up to 500 Kw electrical,using 3 Mw thermal supplied by the reactor. It will operate 10,000 hours without refueling and have a plant life of five years. The total weight is less than 40 tons and no single package weighs more than 15 tons.
Date: October 23, 1963
Creator: Lightle, Robert E.
Partner: UNT Libraries Government Documents Department
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The Diffusion of Fast Neutrons

Description: From American Nuclear Society Meeting, New York, Nov. 1963. The use of the asymptotic solution to the one-velocity transport equation is considered. The angular distribution for fast neutron elastic scattering by heavy elements is discussed. An exponential angular distribution on is assumed to simplify the decay length calculation. The diffusion length of 1 to 15 Mev neutrons in iron is calculated, as well as the vector flux angular dependence. The asymptotic solution for an arbitrary angular distribution of a plane delta -function source is also found. An isotropic source is investigated, and some applications of the model are examined.
Date: November 1963
Creator: Francis, N. C.; Brooks, E. J. & Watson, R. A.
Partner: UNT Libraries Government Documents Department
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Effect of Fluoride Ions on the Aqueous Corrosion of Zirconium Alloys

Description: Abstract. A review has been made of the effects of fluoride ions on the corrosion behavior of zirconium alloys in high-temperature water. Corrosion was found to occur as the result of contamination of the water or the zirconium surface. A major source of fluorides is undue delay in rinsing the HF-HNO3 pickling solution during surface preparation. The oxide on corrosion-resistant material has been found to contain up to 7600 ppm fluoride from this source. The threshold concentration of fluoride in the oxide film which produces poor corrosion resistance ranges from 8500 to 17,000 ppm. Accelerated corrosion from fluorides in water at 300 to 360 C occurs at about 100 ppm, although increased corrosion has been reported at 10 ppm fluoride in water at 300 C. Fluorocarbon plastics degrade and contribute fluorides to the high-temperature water or to the alloy surface when in direct contact with zirconium. Chlorides (1 to 10,000 ppm) and iodides (1270 ppm) do not adversely affect the corrosion behavior of zirconium alloys in water at 360 C. The mechanism of corrosion is not well understood but apparently is related to the formation of insoluble zirconium oxyfluorides during pickling and during exposure to fluoride-contaminated water.
Date: November 1963
Creator: Berry, Warren E., 1922-
Partner: UNT Libraries Government Documents Department
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A High Speed Readout for Multi-Channel Pulse Height Analyzers

Description: From American Nuclear Society Meeting, New York, Nov. 1963. In computer-coupled automated activation analysis such as in the Mark II system, conventional methods of data readout impose a serious restriction on the minimum handling time per sample. A data coupler for operating between the data accumulation system and the computer tape unit was developed which contributes nothing to the handling time per sample, does not distort the data, and prepares the data for direct computer entry. In addition to activation analysis, the coupler may be used to obtain successive spectra separated in time by 0.16 sec in the study of short-lived isotopes.
Date: November 1963
Creator: Wilkins, W. W.; Fite, L. E. & Wainerdi, Richard E., 1931-
Partner: UNT Libraries Government Documents Department
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Energy Deposition by Fast Neutrons. [Part] II, Yield of the Fricke Dosimeter at 14.6 Mev

Description: A measurement of the yield of the aerated, ferrous sulfate-sulfuric acid (Fricke) dosimeter for 14.6-Mev neutrons gave a value of GF /sub Fe/sup +5/= 11.5 plus or minus 1.8. G/sub Fe/ number of ferric ions produced per 100 ev deposited. The determination combined an analysis of the energy deposit by scattering and charged particle reactions with a determination of the neutron flux by two independent means: (1) a "long counter" method and (2) an activation technique. The result is in reasonable agreement with a prediction for G/sub Fe// sup plus or minus 5/ based on measured yields of the dosimeter to irradiations by monoenergetic charged particles.
Date: November 1963
Creator: Axtmann, Robert C. & Licari, Joseph A.
Partner: UNT Libraries Government Documents Department
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Recent Developments in the Physics and Safety of Large Fast Power Reactors

Description: Technical report discussing three principal areas: (1) some recent cross section measurements and their effect on fast reactor calculations; (2) the question of Doppler and sodium void reactivity effects in large fast power reactors and the conflicts inherent in simultaneous optimization of performance, breeding, and safety characteristics; (3) the matter of hybrid fuel cycles.
Date: November 1963
Creator: Okrent, David
Partner: UNT Libraries Government Documents Department
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Automatic Exit Steam Quality Control for Boiling Water Reactors

Description: From American Nuclear Society Meeting, New York, Nov. 1963. The need for control of the flow distribution and/or steam quality in boiling reactors is discussed. A quality control device is being developed which consists of an entrance venturi and an exit venturi for measuring the flow rates into and out of the channel, means for comparing the two flow rate signals, and a value for regulating the flow rate. This device can be used either as a constant quality device or as a controlled-quality device. Results are given of air-water studies of two-phase flow in a vertical venturi.
Date: November 1963
Creator: Gall, D. A. & Doyle, E. F.
Partner: UNT Libraries Government Documents Department
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Nuclear Analysis of PM Long Life Core 3

Description: Introduction. Under AEC contract the Martin Company has followed up the design and construction of the PM-1 and PM-3A nuclear power plants with R&D efforts seeking improved plant efficiency, increased core life and higher operating power. The Advanced PM cores have evolved step by step, with the addition of degrees of freedom to design latitude. A first replacement core, Core 2, has been designed to achieve 50 percent greater life than PM-1 through relatively minor design changes. Core 3 realizes the potential extensive modifications in the fuel element and control element configurations. This paper outlines an analysis effort undertaken to define what may be called a performance profile over a range of configurations of interest for Core 3. It should be emphasized that this is a parametric or concept study and not a final design effort. The results of this study clearly indicate that a lifetime of 100 Mw-yr can be obtained from a 7 ft pressurized water core. If employed as a 10-Mw heat source for present PM equipment, this core has a lifetime approaching that of the plant equipment, 90,000 full-power hours. Core 3 will be suitable for applications demanding up to 40-Mw operating thermal power.
Date: November 1963
Creator: Bagley, Raymond. & George, Critz.
Partner: UNT Libraries Government Documents Department
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Feasibility of a Liquid Phase Chemonuclear Ozone Process

Description: At the Chemonuclear Workshop held at Brookhaven National laboratory in November 1962 it was pointed out that the production of ozone from oxygen by a liquid phase fission fragment chemonuclear process appears to have reasonable economic potential. The maximum theoretical reaction yield for the formation of ozone from oxygen is a "G" value of 68 molecules for 100 ev based on heat of reaction data. The authors felt a "G" value of 15 to be reasonable for this study. the reactor system chosen has liquid oxygen as its moderator and the operating pressure and temperature were selected so as to allow boiling of the oxygen-ozone mixture. The total plant investment cost is estimated to be in the range of $100,000,000. Other system designs will be considered in the future.
Date: November 19, 1963
Creator: Cagnetta, J. P.; Goellner, D. & Steinberg, M.
Partner: UNT Libraries Government Documents Department
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Fluxes and Reaction Rates in the Presence of Interferring Resonances

Description: The effects of competition between resonances of different isotopes were investigated. Flux and reaction rate calculations on a Pu/sup 239/-- U/sup 238/ system revealed that U/sup 238/ exhibits both self-shielding and interference effects, the latter becoming noticeable at enrichment of a few per cent. Gold activation was also found to be depressed by the presence of U, but was insensitive at low enrichment values, Investigation of the Pu/sup 239/ resonance integral showed an asymmetric effect involving both interference between potential and resonant scattering and interference with resonance absorption in another isotope. The interference scattering arising in each resonance level had a notable effect on the average change in the Doppler coefficient. (D.C.W.)
Date: November 1963
Creator: Kelber, Charles N.
Partner: UNT Libraries Government Documents Department
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