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36,494 Matching Results
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36,481 - 36,494 of
36,494
Zircaloy-2 Tubing for Fuel Sheathing
Scope. This specification covers Zircaloy-2 tubing, both seamless and welded, for reactor fuel rod sheathing where high integrity, and satisfactory corrosion resistance at elevated temperatures ae required.
Date:
July 15, 1960
Creator:
Perryman, E. C. W.
Object Type:
Report
System:
The UNT Digital Library
Zircaloy-2 Wire Material
Scope. This specification covers Zircaloy-2 wire material for reactor use where high integrity and satisfactory corrosion resistance at elevated temperatures are required.
Date:
July 15, 1960
Creator:
Perryman, E. C. W.
Object Type:
Report
System:
The UNT Digital Library
Zircaloy-4 Sheet and Strip Material
Scope. This specification covers Zircaloy-4 sheet and strip material for reactor use where high integrity and satisfactory corrosion resistance at elevated temperatures are required.
Date:
July 15, 1960
Creator:
Perryman, E. C. W.
Object Type:
Report
System:
The UNT Digital Library
Zircaloy-4 Wire Material
Scope. This specification covers Zircaloy-4 wire material for reactor use where high integrity and satisfactory corrosion resistance at elevated temperatures are required.
Date:
July 15, 1960
Creator:
Perryman, E. C. W.
Object Type:
Report
System:
The UNT Digital Library
Zirconium-95 as a Fission Monitor
None
Date:
July 17, 1956
Creator:
Brooksbank, W. A., Jr.
Object Type:
Report
System:
The UNT Digital Library
Zirconium Diboride, Boron Nitride, And Boron Carbide Compatibility with Austenitic Stainless Steel
The compatibility of zirconium diboride, boron carbide, and boron nitride with type 304 stainless steel was evaluated as a function of temperature (1000-1200°C), time (1-3 hr). Appropriate loadings of the boron compounds and stainless steel powder were blended and fashioned into a compact powder metallurgically. Each compact was roll clad into a plate and subsequently heat treated at a temperature equal to the initial sintering temperature. Metallographic examination of the fabricated and heat-treated plates demonstrated that none of the systems were metallurgically stable. The instability was generally manifested by the (1) interaction of the discrete boron compounds with the matrix and (2) precipitation of a hypothetically boron-rich phase throughout the stainless steel matrix material.
Date:
July 31, 1959
Creator:
Cherubini, Julian H. & Leitten, C. F., Jr.
Object Type:
Report
System:
The UNT Digital Library
Zirconium Diboride, Boron Nitride, and Boron Carbide Compatibility With Austenitic Stainless Steel
The compatibility of zirconium diboride, boron carbide, and boron nitride with type 304 stainless steel was evaluated as a function of temperature (1000 to 12OO deg C), time (1-3 hr). Appropriate loadings of the boron compounds and stainless steel powder were blended and fashioned into a compact powder metallurgically. Each compact was roll clad into a plate and subsequently heat treated at a temperature equal to the initial sintering temperature. Metallographic examination of the fabricated and heat-treated plates demonstrated that none of the systems was metallurgically stable. The instability was generally manifested by the interaction of the discrete boron compounds with the matrix and precipitation of a hypothetically boron-rich phase throughout the stainless steel matrix material. Of the three compounds, boron nitride was relatively the most stable in a stainless steel matrix under the test conditions. (auth)
Date:
July 31, 1959
Creator:
Cherubini, J. H. & Leitten, C. F. Jr.
Object Type:
Report
System:
The UNT Digital Library
Zirconium hydride as a storage medium for tritium
Conditions necessary for rapid production (approximately 20 minutes preparation time) have been determined for a 6-g sample of zirconium hydride with a composition of ZrH/sub 1.5/ to ZrH/sub 1.9/. Two alternate sets of conditions were found to produce a hydride of suitable physical integrity for tritium storage: the first condition involves isothermal absorption of H/sub 2/ at 760 torr and 600/sup 0/C; the second involves addition of H/sub 2/ at 760 torr as the temperature is increased from 600/sup 0/C until absorption ceases. The latter method appears to produce a hydride which is essentially crack-free. Small amounts of air in the hydrogen were found to have a very deleterious effect on the hydriding reaction. The cost of zirconium is a disadvantage. However, the use of scrap metal may make the method more attractive and the possible use of irradiated Zircaloy cladding hulls would be even more economically favorable. Questions to be answered mainly concern the actinide and other residual activity remaining in the hulls after decladding. Zircaloy-2 tubing, cladding scrap, was studied and found to be very easily hydrided. Hydrides were produced from 0.25- and 0.50-in. diameter Zircaloy rods, 0.50-in. diameter Zircaloy tubing, and a 0.25-in. diameter zirconium rod.
Date:
July 1, 1976
Creator:
Scheele, R. D. & Burger, L. L.
Object Type:
Report
System:
The UNT Digital Library
Zirconium Hydride Reactor Technology Program. Progress report, April-June 1976
None
Date:
July 21, 1976
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Zirconium metal--water oxidation kinetics. II. Oxygen-18 diffusion in. beta. -Zircaloy
The diffusion of oxygen-18 in ..beta..-Zircaloy-4 was measured from 900 to 1500/sup 0/C and survey measurements were made for ..beta..-zirconium and ..beta..-Zircaloy-2. The tracer diffusivity was measured over the entire temperature range and the chemical diffusivity from 1100 to 1500/sup 0/C. The experiments were performed by using oxygen-18 as the tracer and activating it by proton bombardment. Complementary measurements were also made using Auger Electron Spectroscopy. Results indicated that the tracer and chemical diffusivity of oxygen in ..beta..-Zircaloy-4 are statistically identical, and there is no oxygen concentration dependence over the oxygen concentration range studied, 0.1 to 0.6 wt percent. The temperature dependence of the diffusivity from 1000 to 1500/sup 0/C is D = 2.48 x 10/sup -2/ exp (-28200/RT) cm/sup 2//s. Below 1000/sup 0/C, the diffusivity dropped sharply because a two-phase ..cap alpha.. + ..beta.. mixture was present. Results for the ..beta..-Zircaloy-2 and ..beta..-zirconium indicated that the alloying additions have no influence upon the oxygen diffusivity. Combination of three sets of boundary conditions (thin-film tracer diffusion, single-phase chemical diffusion couple, and phase-boundary-movement chemical diffusion couple) and two methods of oxygen profiling (oxygen-18 radioactivation and Auger Electron Spectroscopy) were used to increase the confidence in the results. Current results are about …
Date:
July 1, 1976
Creator:
Perkins, R. A.
Object Type:
Report
System:
The UNT Digital Library
THE ZIRCONIUM-URANIUM DIOXIDE REACTION
None
Date:
July 22, 1957
Creator:
Mallett, M.W.; Droege, J.W.; Gerds, A.F. & Lemmon, A.W. Jr.
Object Type:
Report
System:
The UNT Digital Library
Zonal Flow Dynamics and Size-scaling of Anomalous Transport
Nonlinear equations for the slow space-time evolution of the radial drift wave envelope and zonal flow amplitude have been self-consistently derived for a model nonuniform tokamak equilibrium within the coherent 4-wave drift wave-zonal flow modulation interaction model of Chen, Lin, and White [Phys. Plasmas 7 (2000) 3129]. Solutions clearly demonstrate turbulence spreading due to nonlinearly enhanced dispersiveness and, consequently, the device-size dependence of the saturated wave intensities and transport coefficients.
Date:
July 30, 2003
Creator:
Chen, Liu; White, Roscoe B. & Zonca, F.
Object Type:
Report
System:
The UNT Digital Library
Zone refining of sintered, microwave-derived YBCO superconductors
Post-sintering treatments such as zone melting under thermal gradient has been conducted on sintered YBCO tape cast films. YBCO precursor powder was derived through decomposition of a mixture of nitrates of cations in a microwave oven for {approx}4 min. The resulting powder was characterized and made into thin sheets by tape casting and then sintered at 945 C for 5 h. The sintered tapes were subjected to repeated zone refining operations at relatively high speeds of {approx}30 mm/h. A microstructure having uniformly oriented grains in the a-b plane throughout the bulk of the sample was obtained by three repeated zone refining operations. Details of precursor preparation, microwave processing and its advantages, zone refining conditions, and microstructural features are presented in this paper.
Date:
July 1, 1993
Creator:
Warrier, K. G. K.; Varma, H. K.; Mani, T. V.; Damodaran, A. D. & Balachandran, U.
Object Type:
Report
System:
The UNT Digital Library
ZrH-reactor-technology program. Progress report, April-June 1974
The report on the 2 kW(e) reactor-organic Rankine system was drafted. This report details the design parameters of a minimum weight, 2 kW(e) reactor-organic Rankine system. The system is designed for 5 years unattended life in space. The reactor produces 16.2 kW of thermal power with a NaK outlet temperature of 800/sup 0/F and a 200/sup 0/F ..delta..T. The reactor contains 19 fuel elements, 1.25'' in diameter by 10'' long, hydrided to an N/sub H/ of 6.35. The terrestrial applications effort was oriented towards the establishment of the feasibility of utilizing the zirconium hydride reactor technology in a subsea application for supplying electrical power to deep water, and other environmentally severe, oil well installations. The overall system concept is shown. The power system is composed of three basic modules (i.e., a reactor module, a generator module, and a heat rejection system) mounted on a barge. The barge is then towed to the installation site and submerged to mate with a previously installed seafloor foundation. An assembly/disassembly sequence was drafted detailing the steps required to assemble the reactor module and to disassemble it after 4 years of operations.
Date:
July 12, 1974
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library