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Reference fuel studies. Seventh quarterly report May-July 1976. [LMFBR]

Description: Task 3 of Contract AT03-76SF78003 consists of the following programs: fuel rod chemistry and thermodynamics; fuel rod engineering; fuel irradiations testing and analysis; reference structural materials. The four parts are closely interrelated and in combination are aimed at providing a sound basis for the design and performance evaluation of LMFBR mixed oxide fuel rods.
Date: August 1, 1976
Partner: UNT Libraries Government Documents Department
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Liquid-metal fast-breeder-reactor program: reference fuel studies. Eighth quarterly report, August-October 1976. [LMFBR]

Description: In FY-76, Task 3 of Contract E(04-3)-893 consisted of the following programs: fuel rod chemistry and thermodynamics; fuel rod engineering; fuel irradiations testing and analysis; and reference structural materials. Starting in FY-77, the Fuel Rod Engineering Program was reorganized into other existing G.E. programs under the E(04-3)-893 contract. Continuation of the reports on technical progress of this program can be found under 189 No. SG009, Task 3, or 189 No. SG023, Task 11.
Date: November 1, 1976
Partner: UNT Libraries Government Documents Department
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High-burnup performance of mixed-oxide fuel rods clad in type 316SS of 0. 010- and 0. 015-inch wall thickness. [LMFBR]

Description: Two short mixed-oxide fuel rods of LMFBR design configuration were irradiated to a burnup of approx. 12.5 atom % in GETR. Profilometry at several intervals during the test indicated that the rod with a 0.010 inch thick cladding exhibited a diametral strain of 0.17% per atom % burnup, while the rod with a 0.015 inch thick cladding exhibited a lower diametral strain rate of 0.12% per atom % burnup. These data present the opportunity for analytical methods to evaluate fuel rod dimensional changes … more
Date: June 1, 1976
Creator: Wadekamper, D. C.; Plumlee, D. E. & Hilbert, R. F.
Partner: UNT Libraries Government Documents Department
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In-reactor corrosion behavior of stainless steel cladding in high temperature sodium

Description: Sodium-cladding chemical interaction has been studied on fuel pins clad with 20% cold worked type 316 stainless steel and irradiated in the EBR-II at temperatures up to 705/sup 0/C and for exposures to 5300 hours. The measured corrosion rate of the cladding surface immediately above the top of the fuel column was 12.5 ..mu..m per year at 690/sup 0/C. The loss of Ni at 700/sup 0/C resulted in the formation of a ferrite layer approximately 5 ..mu..m thick. A zone depleted in Ni and Cr extends int… more
Date: April 1, 1976
Creator: Weber, J.W.
Partner: UNT Libraries Government Documents Department
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Corrosion of valve metals

Description: A general survey related to the corrosion of valve metals or film-forming metals. The way these metals corrode with some general examples is described. Valve metals form relatively perfect oxide films with little breakdown or leakage when anodized. (FS)
Date: January 1, 1976
Creator: Draley, J. E.
Partner: UNT Libraries Government Documents Department
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Burrs produced by grinding

Description: An investigation was conducted to determine the influence of variables in controlling the size and repeatability of grinding burrs to minimize burr-removal costs and improve the quality and reliability of parts for small precision mechanisms. Each of the three types of burrs produced by surface-grinding a rectangular block responds differently to changes in cutting conditions. Reducing the downfeed rate generally produces shorter burrs. Although the size of the abrasive grain affected the thick… more
Date: August 1, 1976
Creator: Gillespie, L. K.
Partner: UNT Libraries Government Documents Department
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Effect of hydrogen on the fracture toughness of 17-4 PH stainless steel

Description: Fracture toughness (K/sub c/) of 17-4 PH stainless steel decreased significantly with increased hydrogen test pressure for a variety of heat treatment conditions: solution annealed, underaged, peak-aged, and overaged. Minimum toughness (13 MPa..sqrt..m) was obtained with peak-aged samples tested in 69.5-MPa hydrogen; toughness was maximum (100 MPa..sqrt..m) for samples tested in helium. Aging treatments increased the hardness from 28 R/sub c/ for solution-annealed material to 42 R/c/ for peak-a… more
Date: January 1, 1976
Creator: Capeletti, T. L.
Partner: UNT Libraries Government Documents Department
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Concept of frequency separation in life prediction for time-dependent fatigue

Description: Two methods are described to improve the predictive capability of the frequency-modified fatigue equations for time-dependent fatigue. These built-on the earlier approach and are applicable to severely unbalanced hysteresis loops. Comparisons made with various wave-shape investigations show favorable results. A new form of hysteresis loop is introduced utilizing frequency separation concepts. 4 tables, 11 fig.
Date: January 1, 1976
Creator: Coffin, L. F.
Partner: UNT Libraries Government Documents Department
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Hanford waste encapsulation: strontium and cesium. [SrF/sub 2/ encapsulated in Hastelloy C-276 and CsCl in stainless steel 316L]

Description: The strontium and cesium fractions separated from high radiation level wastes at Hanford are converted to the solid strontium fluoride and cesium chloride salts, doubly encapsulated, and stored underwater in the Waste Encapsulation and Storage Facility (WESF). A capsule contains approximately 70,000 Ci of /sup 137/Cs or 70,000 to 140,000 Ci of /sup 90/Sr. Materials for fabrication of process equipment and capsules must withstand a combination of corrosive chemicals, high radiation dosages and f… more
Date: June 1, 1976
Creator: Jackson, R. R.
Partner: UNT Libraries Government Documents Department
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Atom-probe field-ion microscope for the study of the interaction of impurity atoms or alloying elements with defects

Description: A time-of-flight (TOF) atom-probe field-ion microscope (FIM) designed for the study of defects is described. This atom probe features: (1) a variable magnification internal-image-intensification system; (2) a liquid-helium goniometer stage; (3) a low-energy (less than or equal 3 keV) gas-ion gun for in-situ irradiations; (4) an ultra-high vacuum (approximately 3.10/sup -10/ torr) chamber; (5) a high vacuum (approximately 10/sup -6/ torr) specimen-exchange device; (6) a Chevron ion detector; and… more
Date: October 1, 1976
Creator: Wagner, A.; Hall, T. M. & Seidman, D. N.
Partner: UNT Libraries Government Documents Department
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Effect of sodium environment on the creep-rupture behavior of austenitic stainless steel. [600 to 700/sup 0/C]

Description: Uniaxial creep-rupture data were obtained for Type 304 stainless steel in the solution-annealed condition and after exposure to a flowing sodium environment at temperatures of 700, 650, and 600/sup 0/C. The specimens were exposed to sodium for time periods between 120 and 5012 h to produce carbon penetration depths of approximately 0.010, 0.020, and 0.038 cm in the steel. The results showed that, as the depth of carbon penetration and the average carbon concentration in the steel increase, the … more
Date: January 1, 1976
Creator: Natesan, K.; Chopra, O. K. & Kassner, T. F.
Partner: UNT Libraries Government Documents Department
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Estimating heat-to-heat variation from a statistician's point of view. [Creep, tensile]

Description: Heat-to-heat variability is the change in results that occurs when the same tests under the same conditions are applied to samples from different heats of the same material. Heat-to-heat variability reflects, among other things, difference in chemistry and in processing history. Published Japanese tensile and creep tests on types 304 and 316 stainless steel tube are used to illustrate the analysis of variance technique as a tool for isolating heat-to-heat variation. The importance of the underl… more
Date: January 1, 1976
Creator: Hebble, T. L.
Partner: UNT Libraries Government Documents Department
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Tokamak Experimental Power Reactor. [Conceptual design for operation at net electrical power conditions]

Description: A conceptual design has been developed for a Tokamak Experimental Power Reactor to operate at net electrical power conditions with a plant capacity factor of 50 percent for 10 yr. The EPR operates in a pulsed mode at a frequency of approximately 1/min, with an approximately 75 percent duty cycle, is capable of producing approximately 72 MWe and requires 42 MWe. The EPR vacuum chamber is 6.25 m in major radius and 2.4 m in minor radius, is constructed of 2 cm thick stainless steel, and has 2 cm … more
Date: October 1, 1976
Creator: Stacey, W. M. Jr.; Abdou, M. A. & Bertoncini, P. J.
Partner: UNT Libraries Government Documents Department
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Statistical analysis of elevated-temperature, strain-controlled fatigue data on Type 304 stainless steel. [430-816/sup 0/C]

Description: The available elevated-temperature, strain-controlled, uniaxial fatigue data on Type 304 stainless steel (435 data points) are summarized, and variables that influence cyclic life are divided into first- and second-order categories. The first-order variables, which include strain range, strain rate, temperature, and tensile hold time, were used in a multivariable regression analysis to describe the observed variation in fatigue life. Goodness of fit with respect to these variables as well as th… more
Date: January 1, 1976
Creator: Diercks, D. R. & Raske, D. T.
Partner: UNT Libraries Government Documents Department
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Product from variability in the mechanical behavior of type 304 stainless steel at room temperature and 593/sup 0/C (1100/sup 0/F)

Description: Data are presented that describe the variability of 15 products of a reference heat of type 304 stainless steel tested in the laboratory reannealed condition: chemistry hardness, grain size, yield strength at room temperature, tensile curves at 593/sup 0/C (1100/sup 0/F), and creep-rupture curves to 1000 h at 593/sup 0/C (1100/sup 0/F). The standard deviation, representing the variation in the yield strength of the 15 products about the average, is near+-l.7 MPa at room temperature and +-6.3 MP… more
Date: January 1, 1976
Creator: Swindeman, R. W.; McAffee, W. J. & Sikka, V. K.
Partner: UNT Libraries Government Documents Department
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Effect of sodium on the creep-rupture behavior of type 304 stainless steel

Description: Uniaxial creep-rupture data have been obtained for Type 304 stainless steel in the solution-annealed condition and after exposure to a flowing sodium environment at temperatures of 700, 650, and 600/sup 0/C.The specimens were exposed to sodium for time periods between 120 and 5012 h to produce carbon penetration depths of approximately 0.010, 0.020, and 0.038 cm in the steel. Results showed that, as the depth of carbon penetration and the average carbon concentration in the steel increase, the … more
Date: January 1, 1976
Creator: Natesan, K.; Chopra, O. K. & Kassner, T. F.
Partner: UNT Libraries Government Documents Department
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Temperature Distributions in Electron Beam Welding Cavities

Description: Surface temperatures in electron beam welding cavities in stainless steel 304 and aluminum 1100, 2024, and 6061 were measured with a narrow band infrared radiation pyrometer. A special device was designed for mounting the radiation-sensing probe next to the electron beam gun in the welding chamber. This mounting device included a mechanism for oscillating the probe so as to scan the cavity region both perpendicular and parallel to the welding direction. At the center of its movement the probe v… more
Date: July 15, 1976
Creator: Shintaku, S. M.
Partner: UNT Libraries Government Documents Department
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Properties for LMFBR safety analysis. [Thermodynamic, transport, mechanical]

Description: This handbook brings together the most current data on thermodynamic, transport, and mechanical properties of reactor materials (fuel, coolant, structural material) for reactor safety analysis. NSMH (Nuclear Systems Materials Handbook) property code numbers and formats were used. The materials covered are UO/sub 2/, (U, Pu)O/sub 2/, Na, and Types 304 and 316 stainless steels. (DLC)
Date: March 1, 1976
Partner: UNT Libraries Government Documents Department
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Influence of strain rate and temperature on the yield and fracture toughness behavior of selected steels for an LMFBR spent fuel shipping cask, a literature assessment

Description: The literature has been reviewed to determine the possible influences of strain rate and temperature on the yield and fracture toughness behavior of selected steels suggested for use in an LMFBR Spent Fuel Shipping Cask. Based on this information, recommendations have been made for further work which is intended to alleviate potential problems prior to their having a major impact on the shipping cask program.
Date: February 1, 1976
Creator: Rack, H. J.
Partner: UNT Libraries Government Documents Department
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Tritium processing and containment technology for fusion reactors. Annual report, July 1975--June 1976

Description: The hydrogen permeabilities of selected metals, alloys, and multiplex preparations that are of interest to fusion reactor technology are being characterized. A high-vacuum hydrogen-permeation apparatus has been constructed for this purpose. A program of studies has been initiated to develop design details for the tritium-handling systems of near-term fusion reactors. This program has resulted in a better definition of reactor-fuel-cycle and enrichment requirements and has helped to identify maj… more
Date: January 1, 1976
Creator: Maroni, V A; Calaway, W F; Misra, B; Van Deventer, E H; Weston, J R; Yonco, R M et al.
Partner: UNT Libraries Government Documents Department
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Liquid lithium corrosion research. Progress report, April 1, 1976--December 31, 1976. [Summaries of research activities at Colorado School of Mines]

Description: Stress enhanced lithium grain boundary penetration of iron was investigated under both tensile and compressive loads. Plastic deformation was found to control the penetration behavior regardless of the stress state that causes the plastic deformation. The penetration rate of stressed specimens is much larger than unstressed iron specimens. The creep rate was found to be rate controlling the penetration kinetics. Mossbauer technique and analysis is in progress to determine the nature of the corr… more
Date: 1976~
Creator: Olson, D. L. & Matlock, D. K.
Partner: UNT Libraries Government Documents Department
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Materials Science Division coal technology ninth quarterly report, October--December 1976

Description: Research on ceramic and refractory materials is reported in sections on evaluation of ceramic refractories for slugging gasifiers nondestrictive evaluation methods for coal conversion processes, corrosion behavior of materials in coal-conversion processes, erosion of materials in coal-conversion processes, and component performance. (JRD)
Date: January 1, 1976
Partner: UNT Libraries Government Documents Department
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Chemistry of the KALC process. The CO/sub 2/--I/sub 2/--CH/sub 3/I--H/sub 2/O system

Description: The chemistry of the CO/sub 2/--I/sub 2/--CH/sub 3/I--H/sub 2/O system in stainless steel has been investigated with respect to the probable reactions of these components in the KALC process. Iodine is stable in dry CO/sub 2/ contained in stainless steel; but in the presence of organic impurities or water, it is lost from solution via reactions which produce solid phases. Methyl iodide, however, is stable in either wet or dry CO/sub 2/ solutions. Distribution coefficients for I/sub 2/ and CH/su… more
Date: November 1, 1976
Creator: Toth, L. M.; Bell, J. T.; Fuller, D. W.; Buxton, S. R.; Friedman, H. A. & Billings, M. R.
Partner: UNT Libraries Government Documents Department
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Joining uranium to steel

Description: A method has been devised which will allow the joining of uranium to steel by fusion welding through the use of an intermediate material. Uranium-0.5 titanium was joined to AISI 304L stainless steel by using a vanadium insert. Also, a method is now available for selecting possible filler metals when two entirely dissimilar metals need to be joined. This method allows a quantitative ranking to be made of the possible filler metals and thus the most likely candidate can be selected.
Date: May 1, 1976
Creator: Perkins, M. A.
Partner: UNT Libraries Government Documents Department
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