Office of Scientific & Technical Information Technical Reports - 203 Matching Results

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04 nuclear safety: pressure piping crack monitoring detection of metal overstress by acoustic emission. Progress report, July-September 1966

Description: The three main areas of effort have been: (1) definition of the general acoustic response pattern related to the gross aspects of forming and extending a crack in various materials, (2) development of a monitor system prototype concept exclusive of transducers and (3) development of a suitable, high temperature transducer. Tests using double cantilever beam (DCB) specimens of various materials to establish conditions of crack formation and growth have indicated that material ductility is a majo… more
Date: October 28, 1966
Creator: Hutton, P H
Partner: UNT Libraries Government Documents Department
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EEN-333, revised getter flash procedure

Description: EWR No. VTE-188--Tubes processed by flashing getters immediately prior to seal-off from vacuum systems are compared for total residual gas pressure to tubes processed by flashing getters after tubes were sealed off vacuum systems. Comparisons of residual pressures determined from current flows in the cold cathode ion gauge.
Date: June 28, 1960
Creator: Brown, W.C.
Partner: UNT Libraries Government Documents Department
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710 reactor program, progress report No. 12

Description: Declassified 4 Sep 1973. Information on the development of the 710 Reactor is presented concerning the performance testing of refractory-metal fuel elements, critical experiment mockup of 710 Reactor, reactor component design and development, and test facilities and pilot loop design. (DCC)
Date: January 28, 1965
Partner: UNT Libraries Government Documents Department
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ANALOG SOLUTION OF A MODEL OF THE SOURCES OF ELUTRIATABLE FINES IN THE FLUIDIZED BED CLACINATION PROCESS

Description: A model is proposed which depicts the sources of elutriatable fines in the fluidized bed calcination process as being in two major groups, spray drying mechanisms and attrition mechanisms. Based on this model, equations are derived which express the rate of change of the concentration of a chemical tracer material in the elutriated fines, following introduction of the tracer into the feed and following its removal from the feed. This system has been simulated on an analog computer, and by match… more
Date: February 28, 1964
Creator: Grimmett, E.S.
Partner: UNT Libraries Government Documents Department
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Analysis of E-N loadings

Description: Three E-N loaded tubes were dissolved, sampled and analyzed, starting November 9, 1960. The results of these analyses and an explanation of the methods used are the subject of this report. Each tube loading received an identification code in each facility in which it was processed. All of these codes are listed for future reference. Each batch of slugs was dissolved in a preflushed dissolver. When complete solution was indicated by a leveling off of the specific gravity, two 1 ml samples were t… more
Date: December 28, 1960
Creator: Zimmer, W. H.
Partner: UNT Libraries Government Documents Department
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Analytical considerations for K-downcomer and bellows

Description: A free body diagram of the bellows will show the possibility of three forces -- one in each direction, three moments -- one in each plane, and the internal pressure. Any or all of these forces and moments may fluctuate due to variations in a driving force, e.g., separation of streamlines which creates slugging of flow through an elbow. Whereas the static equilibrium condition can be analyzed and stresses and strains computed, the dynamic condition cannot be approached without information on the… more
Date: February 28, 1961
Creator: Lomax, C. C.
Partner: UNT Libraries Government Documents Department
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Analytical considerations for K-Downcomer and bellows for General Electric Company

Description: This report details model studies performed as required by the design, development, and research contract between the General Electric Company and Washington State University. These studies provide analytical considerations for K-Downcomer and Bellows.
Date: June 28, 1961
Creator: Lomax, C. C.
Partner: UNT Libraries Government Documents Department
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ANNEALING OF GAMMA RAY INDUCED CHANGES IN ANTIMONY DOPED GERMANIUM

Description: An investigatiori of the annealing of the radioinduced carrier concentration change in Sb-doped Ge in the range 370 to 455 l K was made. The irradiations were conducted at liquid nitrogen temperature using Co/ sup 60/ gamma irradiation. A model that explains the observed behavior is presented. On the basis of the model, the observed annealing consists of vacancy diffusion simultaneously to impurity sites and annihilation centers. Analysis of the activation energy for the annealing process yield… more
Date: May 28, 1963
Creator: Pigg, J.C.
Partner: UNT Libraries Government Documents Department
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Authorization request for potential non-compliance with the American Standard Safety Code for Elevators Dumbwaiters and Escalators

Description: A Third Party inspection of the reactor work platforms was conducted by representatives of the Travelers Insurance Company in 1958. An inspection report submitted by these representatives described hazardous conditions noted and presented a series of recommendations to improve the operational safety of the systems. Project CGI-960, ``C`` & ``D`` Work Platform Safety Improvements -- All Reactors, vas initiated to modify the platforms in compliance with the Third Party recommendations. The Americ… more
Date: September 28, 1964
Creator: Boyd, J. E.
Partner: UNT Libraries Government Documents Department
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Automatic Neutronics Calibration

Description: This report describes some present practices in regard to power calibration techniques and goes on to propose an automatic calibrator based on thermal power.
Date: January 28, 1963
Creator: Kendziorek, W.M.
Partner: UNT Libraries Government Documents Department
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B, D, F, DR, H reactor new aluminum HCR concept: Temperature study

Description: The horizontal control rods presently installed in the older Hanford Reactors have inadequate heat transfer characteristics for present and predicted future operation of the reactors. Continued graphite stack distortion, coupled with higher graphite temperatures, has resulted in ECR failure during reactor operation, such as swelling of the outer aluminum sheaths to the extent that rod movement in the graphite channel is severely restricted. Continued graphite stack distortion will tend to furth… more
Date: July 28, 1964
Creator: Agar, J. D.
Partner: UNT Libraries Government Documents Department
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Bioenvironmental and radiological-safety feasibility studies, Atlantic-Pacific Interoceanic Canal. Phase 2, Freshwater ecology: Final report

Description: The purpose of this program is to conduct studies in the freshwater environment to acquire data needed to evaluate and predict the potential radiation hazards to human populations in the defined regions of proposed nuclear excavations in the Republics of Panama and Colombia. The results of the field surveys conducted in Phase II are presented in this report. Specifically, the data describes the elemental composition of the major components of the ecosystem, and reports the calculated stable ele… more
Date: June 28, 1968
Creator: Templeton, W. L.; Dean, J. M.; Watson, D. G.; Rancitelli, L. A. & Loftin, H. G.
Partner: UNT Libraries Government Documents Department
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Bubble Chamber Safety Meeting

Description: A description is given of bubble chambers in use and those in the design stages. Safety factors in the design and operation of a bubble chamber are discussed. Data are presented on fatige and rupture tests on glass. Data are contained on the effects of liquid helium on the tensile properties of various stainless steels. (C.J.G.)
Date: June 28, 1960
Creator: Harrer, J. M.
Partner: UNT Libraries Government Documents Department
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Calculated fission product release from PRTR rupture

Description: Approximately 15 minutes after shutdown on August 21, 1962, evidence of a rupture was observed in the form of high radiation levels in the containment vessel and rupture monitor indications. Discharge of a special MgO-PuO{sub 2} test element revealed a cladding break of about 1.5 inches in length and about 1/4 inch wide in the widest place, located 36 inches from the top of the fuel element as it would have been oriented in the reactor. A visual examination in Radiometallurgy revealed that appr… more
Date: September 28, 1962
Creator: Stoddard, J. A.
Partner: UNT Libraries Government Documents Department
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CARBIDE FUEL DEVELOPMENT. Progress Report, January 1, 1962 to March 31, 1962

Description: Reproducibly high density UC-PuC pellets containing minor amounts of (U,Pu)/sub 2/C/sub 3/ were made with nickel sintering aid. Average densities of 95% and maximum densities of 96.6% of theoretical were obtained. High density, singlephase UC-PuC pellets were made by sintering at high temperatures. Densities of 94% of theoretical appear to be attainable. Improved identification of microstructural constituents was made by means of metallography, x-ray diffraction, and microprobe analysis. Develo… more
Date: May 28, 1962
Creator: Strasser, A. & Taylor, K.
Partner: UNT Libraries Government Documents Department
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Chemical Processing Technology Quarterly Progress Report, July-September 1962

Description: Aqueous zirconium fuel processing studies, directed at adapting the hydrofluoric acid process to continuous dissolution-complexing in order to increase the capacity of the ICPP process, resulted in two successful approaches to the complexing-feed adjustment step. Continuous in-line adjustment (conversion of uranium(IV) to uranium(VI) necessary for extraction) was accomplished in one minute or less at approximately 90 deg C; surges of dissolver product from the operating dissolver up to 1.9 time… more
Date: December 28, 1962
Creator: Bower, J.R. ed.
Partner: UNT Libraries Government Documents Department
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