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Wiencek, T. C.; Prokofiev, I. G.
Argonne National Lab., Argonne, IL (United States). Funding organisation: US Department of Energy (United States)2000
Argonne National Lab., Argonne, IL (United States). Funding organisation: US Department of Energy (United States)2000
AbstractAbstract
No abstract available
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Source
13 Oct 2000; 23 p; 23. International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR); Las Vegas, NV (United States); 1-6 Oct 2000; W-31109-ENG-38; Also available from OSTI as DE00766339; PURL: https://www.osti.gov/servlets/purl/766339-nXM78S/webviewable/
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Davidsmeier, T.; Koehl, R.; Lanham, R.; O'Hare, E.; Wiencek, T.
2007 international meeting on Reduced Enrichment for Research and Test Reactors (RERTR). Abstracts and available papers presented at the meeting2008
2007 international meeting on Reduced Enrichment for Research and Test Reactors (RERTR). Abstracts and available papers presented at the meeting2008
AbstractAbstract
[en] The current design and fabrication process for RERTR fuel plates utilizes film radiography during the nondestructive testing and characterization. Digital radiographic methods offer a potential increases in efficiency and accuracy. The traditional and digital radiographic methods are described and demonstrated on a fuel plate constructed with and average of 51% by volume fuel using the dispersion method. Fuel loading data from each method is analyzed and compared to a third baseline method to assess accuracy. The new digital method is shown to be more accurate, save hours of work, and provide additional information not easily available in the traditional method. Additional possible improvements suggested by the new digital method are also raised. (author)
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Argonne National Laboratory, Nuclear Engineering Division, RERTR Department, Argonne, IL (United States); Czech Technical University, Prague (Czech Republic); vp; Jul 2008; 18 p; RERTR-2007: 29. international meeting on reduced enrichment for research and test reactors; Prague (Czech Republic); 23-27 Sep 2007; Also available on-line: http://www.rertr.anl.gov/RERTR29/; Country of input: International Atomic Energy Agency (IAEA); 5 refs, 6 figs, 4 tabs
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Glagolenko, I.; Wachs, D.; Woolstenhulme, N.; Chang, G.; Rabin, B.; Clark, C.; Wiencek, T.
Idaho National Laboratory (United States). Funding organisation: DOE - NA (United States)2010
Idaho National Laboratory (United States). Funding organisation: DOE - NA (United States)2010
AbstractAbstract
[en] Based on the results of the reactor physics assessment, conversion of the Advanced Test Reactor (ATR) at the Idaho National Laboratory (INL) can be potentially accomplished in two ways, by either using U-10Mo monolithic or U-7Mo dispersion type plates in the ATR fuel element. Both designs, however, would require incorporation of the burnable absorber in several plates of the fuel element to compensate for the excess reactivity and to flatten the radial power profile. Several different types of burnable absorbers were considered initially, but only borated compounds, such as B4C, ZrB2 and Al-B alloys, were selected for testing primarily due to the length of the ATR fuel cycle and fuel manufacturing constraints. To assess and compare irradiation performance of the U-Mo fuels with different burnable absorbers we have designed and manufactured 28 RERTR miniplates (20 fueled and 8 non-fueled) containing fore-mentioned borated compounds. These miniplates will be tested in the ATR as part of the RERTR-13 experiment, which is described in this paper. Detailed plate design, compositions and irradiations conditions are discussed.
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1 Oct 2010; vp; RERTR 2010: 32. international meeting on reduced enrichment for research and test reactors; Lisbon (Portugal); 10-14 Oct 2010; AC07-05ID14517; Available from http://www.inl.gov/technicalpublications/Documents/4702552.pdf; PURL: https://www.osti.gov/servlets/purl/1000544-TgByEo/
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Wiencek, T.; Totev, T.
Argonne National Laboratory (United States). Funding organisation: NNSA (US)2007
Argonne National Laboratory (United States). Funding organisation: NNSA (US)2007
AbstractAbstract
[en] Advanced Materials Fabrication Facilities at Argonne National Laboratory have been involved in development of LEU dispersion fuel for research and test reactors from the beginning of RERTR program. This paper presents development of technology of high density LEU dispersion fuel fabrication for full size plate type fuel elements. A brief description of Advanced Materials Fabrication Facilities where development of the technology was carried out is given. A flow diagram of the manufacturing process is presented. U-Mo powder was manufactured by the rotating electrode process. The atomization produced a U-Mo alloy powder with a relatively uniform size distribution and a nearly spherical shape. Test plates were fabricated using tungsten and depleted U-7 wt.% Mo alloy, 4043 Al and Al-2 wt% Si matrices with Al 6061 aluminum alloy for the cladding. During the development of the technology of manufacturing of full size high density LEU dispersion fuel plates special attention was paid to meet the required homogeneity, bonding, dimensions, fuel out of zone and other mechanical characteristics of the plates.
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Source
1 Jan 2007; vp; 2007 RERTR International Meeting; Prague (Czech Republic); 23-27 Sep 2007; AC02-06CH11357; Available from Argonne National Laboratory, Argonne, IL (US)
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Miscellaneous
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Snelgrove, J. L.; Vandegrift, G. F.; Conner, C.; Wiencek, T. C.; Hofman, G. L.
Argonne National Lab., IL (United States). Funding organisation: US Department of Energy (United States)1999
Argonne National Lab., IL (United States). Funding organisation: US Department of Energy (United States)1999
AbstractAbstract
[en] Over this past year, extraordinary progress has been made in executing our charter to assist in converting Mo-99 production worldwide from HEU to LEU. Building on the successful development of the experimental LEU-foil target, we have designed a new, economical irradiation target. We have also successfully demonstrated, in collaboration with BATAN in Indonesia, that LEU can be substituted for HEU in the Cintichem target without loss of product yield or purity; in fact, conversion may make economic sense. We are interacting with a number of commercial producers--we have begun active collaborations with the CNEA and ANSTO; we are working to define the scope of collaborations with MDS Nordion and Mallinckrodt; and IRE has offered its services to irradiate and test a target at the appropriate time. Conversion of the CNEA process is on schedule. Other papers presented at this meeting will present specific results on the demonstration of the LEU-modified Cintichem process, the development of the new target, and progress in converting the CNEA process
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29 Sep 1999; 13 p; 22. International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR); Budapest (Hungary); 3-8 Oct 1999; W-31-109-ENG-38; Also available from OSTI as DE00750515; PURL: https://www.osti.gov/servlets/purl/750515-DgaWcy/webviewable/
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ACTINIDES, BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, DAYS LIVING RADIOISOTOPES, ELEMENTS, ENRICHED URANIUM, EVEN-ODD NUCLEI, INTERMEDIATE MASS NUCLEI, ISOTOPE ENRICHED MATERIALS, ISOTOPES, MATERIALS, METALS, MOLYBDENUM ISOTOPES, NUCLEI, RADIATION FLUX, RADIOISOTOPES, REACTORS, URANIUM
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AbstractAbstract
[en] Several Ag-Cu alloys (0-0.25 at.% Cu) were studied as potential substrates for the direct pulsed laser deposition of YBCO without intermediate buffer layer. The microstructural characteristics of films and substrates were analyzed by X-ray diffraction, Raman spectroscopy, and scanning electron microscopy, whereas the superconducting properties of the films were determined by inductive and transport methods. The properties of the YBCO films were significantly influenced by small concentrations of Cu in the substrate; YBCO films on a substrate with 0.2 at.% Cu exhibited the best superconducting properties
Source
S0921453404008238; Copyright (c) 2004 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.; Country of input: International Atomic Energy Agency (IAEA)
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Journal Article
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ALKALINE EARTH METAL COMPOUNDS, COHERENT SCATTERING, COPPER COMPOUNDS, DEPOSITION, DIFFRACTION, ELECTROMAGNETIC RADIATION, ELECTRON MICROSCOPY, ELEMENTS, FILMS, IRRADIATION, LASER SPECTROSCOPY, METALS, MICROSCOPY, OXYGEN COMPOUNDS, RADIATIONS, SCATTERING, SPECTROSCOPY, SUPERCONDUCTORS, SURFACE COATING, TRANSITION ELEMENT COMPOUNDS, TRANSITION ELEMENTS, TYPE-II SUPERCONDUCTORS
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Hayes, S. L.; Meyer, M. K.; Clark, C. R.; Stuart, J. R.; Prokofiev, I. G.; Wiencek, T. C.
Argonne National Lab., IL (United States). Funding organisation: US Department of Energy (United States)2001
Argonne National Lab., IL (United States). Funding organisation: US Department of Energy (United States)2001
AbstractAbstract
No abstract available
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Source
12 Sep 2001; [vp.]; 1999 International Meeting on Reduced Enrichment for Research and Test Reactors; Budapest (Hungary); 3-8 Oct 1999; W-31-109-ENG-38; Available from PURL: https://www.osti.gov/servlets/purl/789682-Iq2eKv/native/
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Hayes, S. L.; Hofman, G. L.; Meyer, M. K; Snelgrove, J. L.; Strain, R. V.; Wiencek, T. C.
Argonne National Lab., IL (United States). Funding organisation: US Department of Energy (United States)1999
Argonne National Lab., IL (United States). Funding organisation: US Department of Energy (United States)1999
AbstractAbstract
[en] Preliminary results from the postirradiation examinations of microplates irradiated in the RERTR-1 and -2 experiments in the ATR have shown several binary and ternary U-MO alloys to be promising candidates for use in aluminum-based dispersion fuels with uranium densities up to 8 to 9 g/cm3. Ternary alloys of uranium, niobium, and zirconium performed poorly, however, both in terms of fuel/matrix reaction and fission-gas-bubble behavior, and have been dropped from further study. Since irradiation temperatures achieved in the present experiments (approximately 70 C) are considerably lower than might be experienced in a high-performance reactor, a new experiment is being planned with beginning-of-cycle temperatures greater than 200 C in 8-g U/cm3 fuel
Primary Subject
Source
19 Feb 1999; 9 p; 3. International Topical Meeting on Research Reactor Fuel Management (RRFM '99); Bruges (Belgium); 28-30 Mar 1999; W-31109-ENG-38; Also available from OSTI as DE00012359; PURL: https://www.osti.gov/servlets/purl/12359-8YL3hx/webviewable/
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ACTINIDE ALLOYS, ALLOYS, ENERGY SOURCES, ENRICHED URANIUM REACTORS, FUELS, IRRADIATION REACTORS, ISOTOPES, MATERIALS, MATERIALS TESTING REACTORS, NUCLEAR FUELS, RADIOACTIVE MATERIALS, REACTOR MATERIALS, REACTORS, RESEARCH AND TEST REACTORS, SOLID FUELS, TANK TYPE REACTORS, TEST FACILITIES, TEST REACTORS, THERMAL REACTORS, TRANSITION ELEMENT ALLOYS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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AbstractAbstract
[en] High-frequency electromagnetic (EM) fields are investigated for the levitation of thin horizontal sheets of liquid metal. A magnetic configuration is analyzed in which inductance stabilization provides global stability and magnetic flux compression provides local stability. Stability analysis indicates that frequencies greater than about 24 kHz are desirable to stably levitate 6 mm thick steel. For stability in systems without active feedback, a conducting screen is required below the metal, with a gap between the screen and the molten metal of no more than twice the metal thickness. Experiments in which 10 kHz EM fields were used to statically levitate sheets of molten tin indicate that dominant magnetohydrodynamic instabilities are of the Rayleigh--Taylor type and correspond to theory
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Journal Article
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Physics of Fluids A; CODEN PFADE; v. 1(6); p. 1069-1076
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Hayes, S. L.; Clark, C. R.; Stuart, J. R.; Meyer, M. K.; Snelgrove, J. L.; Hofman, G. L.; Wiencek, T. C.
Argonne National Lab., Argonne, IL (United States). Funding organisation: US Department of Energy (United States)2000
Argonne National Lab., Argonne, IL (United States). Funding organisation: US Department of Energy (United States)2000
AbstractAbstract
No abstract available
Primary Subject
Source
10 Oct 2000; 10 p; 23. International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR); Las Vegas, NV (United States); 1-6 Oct 2000; W-31109-ENG-38; Also available from OSTI as DE00766331; PURL: https://www.osti.gov/servlets/purl/766331-FsyIF6/webviewable/
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