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Argonne National Lab

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Works: 13,746 works in 14,749 publications in 1 language and 58,135 library holdings
Roles: Researcher, Sponsor
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Publications about Argonne National Lab
Publications by Argonne National Lab
Most widely held works by Argonne National Lab
Real-time LMR control parameter generation using advanced adaptive synthesis ( file )
6 editions published in 1990 in English and held by 0 libraries worldwide
A technique to quantify fuel damage in an LMR through analysis of delayed neutron data is presented, which is suitable for analysis of both small-scale in-pile experiments and full-scale plants. Validating analyses are described for five in-pile severe accident simulations performed within the SLSF and Mol 7C test programs. Comparison is made of measured and calculated amounts of fuel damage. 8 refs., 5 figs., 2 tabs
Elastic modulus calculations from load ( file )
3 editions published in 1997 in English and held by 0 libraries worldwide
Shock-loading has been used to introduce a variety of defects into superconducting BSCCO/Ag tapes. In theory, these defects will pin the movement of flux in these superconductors, allowing higher current densities to be passed through them. The tapes in the present study have been subjected to different peak shock pressures and pulse durations. Critical current density (J{sub c}) and magnetization measurements have been made on shock-loaded and pressed samples. The shocked samples have shown a degradation of transport current properties, but have maintained their high transition temperatures. It is thought that a postshock annealing to heal the microcracks in the material may improve the superconducting transport properties. It is also believed that the pressures to which these tapes were subjected completely saturated the material with defects. Investigation of the use of lower pressures may be advisable
SANS2-high-resolution small-angle diffractometer-reference instrument WBS 1.7.9 ( file )
3 editions published in 1999 in English and held by 0 libraries worldwide
REF1 is designed to-study the reflectivity of horizontal surfaces, such as a free liquid surface. Figure 1 provides a schematic representation of REF1, and Table 1 gives the parameters for this instrument. The instrument will be useful for a wide range of science, including interfacial studies in polymers and surface chemistry involving thin layers of surfactants or other materials on the surfaces of liquids. The instrument geometry will be flexible so that other capabilities (e.g., polarized neutrons) can be added at a later date. Data rates will be sufficiently high to permit kinetic studies on many systems
Nanophase materials assembled from atomic clusters ( file )
3 editions published between 1989 and 1992 in English and held by 0 libraries worldwide
The preparation of atomic clusters of metals and ceramics by means of the gas-condensation method, followed by their in situ consolidation under high-vacuum conditions, has recently led to the synthesis of a new class of ultrafine-grained materials for which their physics is intimately coupled with their application. These nanophase materials, with 2 to 20 nm grain sizes, appear to have properties that are often rather different from conventional materials, and also processing characteristics that are greatly improved. The nanophase synthesis method described here should enable the design of materials heretofore unavailable, with improved or unique properties, based upon an understanding of the physics of these new materials. 23 refs., 8 figs
Surveillance of site A and plot M : report for 1994 by Norbert W Golchert( file )
4 editions published between 1991 and 1993 in English and held by 0 libraries worldwide
The results of the environmental surveillance program conducted at Site A/Plot M in the Palos Forest Preserve area for CY 1990 are presented. The surveillance program is the ongoing remedial action that resulted from the 1976-1978 radiological characterization of the site. That study determined that very low levels of hydrogen-3 (as tritiated water) had migrated from the burial ground and were present in two nearby hand-pumped picnic wells. The current program consists of sample collection and analysis of air, surface and subsurface water, and bottom sediment. The results of the analyses are used to determine the migration pathway of water from the burial ground (plot M) to the hand-pumped picnic wells, establish if buries radionuclides other than hydrogen-3 have migrated, and generally characterize the radiological environment of the area. Tritiated water continues to be detected in a number of wells, boreholes, dolomite holes, and a surface stream. Analyses since 1984 have indicated the presence of low levels of strontium-90 in water from a number of boreholes next to Plot M. The results of the surveillance program continues to indicate that the radioactivity remaining at Site A/Plot M does not endanger the health or safety of the public visiting the site or those living in the vicinity
Geophysics : Building E5282 decommissioning, Aberdeen Proving Ground ( file )
11 editions published in 1992 in English and held by 0 libraries worldwide
This report discusses Building E5282 which was one of 10 potentially contaminated sites in the Canal Creek area of the Edgewood section of Aberdeen Proving Ground examined by a geophysical team from Argonne National Laboratory in April and May of 1992. Noninvasive geophysical surveys, including magnetics, electrical resistivity, and ground-penetrating radar (GPR), were conducted around the perimeter of the building to guide a sampling program prior to decommissioning and dismantling. Magnetic surveys identified small, complicated, multiple anomalies west, north, and northeast of the building that may be caused by construction fill. Two underground storage tanks, at the northeast and southeast corners, were identified. A large magnetic anomaly complex east of the building was caused by aboveground pipes and unexploded ordnance fragments scattered at the surface. Electrical resistivity profiling showed a broad, conductive terrain superimposed over magnetic anomalies on the north and west. A broad, high-resistivity, nonmagnetic area centered 25 ft east of the building has an unknown origin, but it may be due to nonconductive organic liquids, construction fill, or a buried concrete slab; GPR imaging showed this area as a highly reflective zone at a depth of about 5 ft. The GPR data also showed a small-diameter pipe oriented north-south located east of the building
Parallel programming with PCN by Ian Foster( file )
4 editions published between 1991 and 1993 in English and held by 0 libraries worldwide
This document provides all the information required to develop parallel programs with the PCN programming system. It includes both tutorial and reference material. It also presents the basic concepts that underlie PCN, particularly where these are likely to be unfamiliar to the reader, and provides pointers to other documentation on the PCN language, programming techniques, and tools
The RERTR Program : a status report ( file )
4 editions published between 1991 and 1998 in English and held by 0 libraries worldwide
This paper describes the progress achieved by the Reduced Enrichment for Research and Test Reactors (RERTR) Program in collaboration with its many international partners since its inception in 1978. A brief summary of the results that the program had attained by the end of 1997 is followed by a detailed review of the major events, findings, and activities that took place in 1998. The past year was characterized by exceptionally important accomplishments and events for the RERTR program. Four additional shipments of spent fuel from foreign research reactors were accepted by the U.S. Altogether, 2,231 spent fuel assemblies from foreign research reactors have been received by the U.S. under the acceptance policy. Fuel development activities began to yield solid results. Irradiations of the first two batches of microplates were completed. Preliminary postirradiation examinations of these microplates indicate excellent irradiation behavior of some of the fuel materials that were tested. These materials hold the promise of achieving the pro am goal of developing LEU research reactor fuels with uranium density in the 8-9 g /cm³ range. Progress was made in the Russian RERTR program, which aims to develop and demonstrate the technical means needed to convert Russian-supplied research reactors to LEU fuels. Feasibility studies for converting to LEU fuel four Russian-designed research reactors (IR-8 in Russia, Budapest research reactor in Hungary, MARIA in Poland, and WWR-SM in Uzbekistan) were completed. A new program activity began to study the feasibility of converting three Russian plutonium production reactors to the use of low-enriched U0₂-Al dispersion fuel, so that they can continue to produce heat and electricity without producing significant amounts of plutonium. The study of an alternative LEU core for the FRM-II design has been extended to address, with favorable results, the transient performance of the core under hypothetical accident conditions. A major milestone was accomplished in the development of a process to produce molybdenum-99 from fission targets utilizing LEU instead of HEU. Targets containing LEU metal foils were irradiated in the RAS-GAS reactor at BATAN, Indonesia, and molybdenum-99 was successfully extracted through the ensuing process. These are exciting times for the program and for all those involved in it, and last year's successes augur well for the future. However, as in the past, the success of the RERTR program will depend on the international friendship and cooperation that have always been its trademark
Undulator A characteristics and specifications : Enhanced capabilities ( file )
3 editions published between 1993 and 1994 in English and held by 0 libraries worldwide
The Advanced Photon Source (APS) Undulator A is a planar device optimized for the hard x-ray region. In the mature phase of operation, it satisfies the requirement of providing high brilliance x-rays continuously over the tuning range from 4.2 key to above 30 key, using the first and the third harmonic radiation from the undulator. This is achieved through the choice of the 3.3-cm long period, the hybrid undulator design, and the stringent requirements on the magnetic field quality. The undulator is 2.4 m long (including the end sections) with 72 periods. The magnetic structure consists of Nd-Fe-B magnets with vanadium permendur poles. The field errors are specified in this paper to ensure that the third harmonic radiation from the actual device will achieve at least 70% of its theoretical brilliance. The first harmonic is less sensitive to field errors and thus should attain brilliance even closer to the theoretical value. The predicted magnetic fields at various gap values based on a detail design of the magnetic structure of Undulator A are listed in this paper
Structural concerns in dynamic drop loads on transfer lock mechanisms ( file )
3 editions published in 1997 in English and held by 0 libraries worldwide
This paper describes the metallurgical characterization of deposits produced in molten salt electrorefining of uranium and uranium - 10.% zirconium alloy. The techniques of characterization are described with emphasis on considerations given to the radioactive and pyrophoric nature of the samples. The morphologies observed and their implications for deposit performance are also presented - samples from pure uranium deposits were comprised of chains of uranium crystals with a characteristic rhomboidal shape, while morphologies of samples from deposits containing zirconium showed more polycrystalline features. Zirconium was found to be present as a second, zirconium metal phase at or very near the uranium-zirconium dendrite surfaces. Higher collection efficiencies and total deposit weights were observed for the uranium-zirconium deposits; this performance increase is likely a result of better mechanical properties exhibited by the uranium-zirconium dendrite morphology. 18 refs., 10 figs., 1 tab
Fast-neutron total and scattering cross sections of niobium ( file )
11 editions published in 1982 in English and held by 0 libraries worldwide
Broad-resolution neutron total cross sections of elemental indium were measured from 0.8 to 4.5 MeV. Differential-elastic-scattering cross sections were measured from approx. = 1.5 to 3.8 MeV at intervals of approx. = 50 to 200 keV and at scattering angles in the range 20 to 160 degrees. The experimental results are interpreted in terms of the optical-statistical model and are compared with respective values given in ENDF/B-V
Prediction of aging degradation of cast stainless steel components in LWR systems ( file )
3 editions published between 1983 and 1992 in English and held by 0 libraries worldwide
A program has been initiated to investigate the significance of in-service embrittlement of cast duplex stainless steels under light-water reactor operating conditions. The existing data are reviewed to determine the critical parameters that control the aging behavior and to define the objectives and scope of the investigation. The test matrices for microstructural studies and mechanical property measurements are presented. The initial experimental effort is focussed on characterizing the microstructure of long-term, low-temperature aged material. Specimens from three heats of cast CF-8 and CF-8M stainless steel aged for up to 70,000 h at 300, 350, and 400°C were obtained from George Fisher Ltd., of Switzerland. Initial analyses reveal the formation of three different types of precipitates which are not .cap alpha.'. An FCC phase, similar to the M₂₃C₆ precipitates, was present in all the long-term aged material. 15 references, 10 figures, 2 tables
The RERTR Program status and progress ( file )
3 editions published between 1995 and 1999 in English and held by 0 libraries worldwide
The progress of the Reduced Enrichment Research and Test Reactor (RERTR) Program is described. The major events, findings, and activities of 1995 are reviewed after a brief summary of the results which the RERTR Program had achieved by the end of 1994. The revelation that Iraq was on the verge of developing a nuclear weapon at the time of the Gulf War, and that it was planning to do so by extracting HEU from the fuel of its research reactors, has given new impetus and urgency to the RERTR commitment of eliminating HEU use in research and test reactors worldwide. Development of advanced LEU research reactor fuels is scheduled to begin in October 1995. The Russian RERTR program, which aims to develop and demonstrate within the next five years the technical means needed to convert Russian-supplied research reactors to LEU fuels, is now in operation. A Statement of Intent was signed by high US and Chinese officials, endorsing cooperative activities between the RERTR program and Chinese laboratories involved in similar activities. Joint studies of LEU technical feasibility were completed for the SAFARI-I reactor in South Africa and for the ANS reactor in the US. A new study has been initiated for the FRM-II reactor in Germany. Significant progress was made on several aspects of producing ⁹⁹Mo from fission targets utilizing LEU instead of HEU. A cooperation agreements is in place with the Indonesian BATAN. The first prototypical irradiation of an LEU metal-foil target for ⁹⁹Mo production was accomplished in Indonesia. The TR-2 reactor, in Turkey, began conversion. SAPHIR, in Switzerland, was shut down. LEU fuel fabrication has begun for the conversion of two more US reactors. Twelve foreign reactors and nine domestic reactors have been fully converted. Approximately 60 % of the work required to eliminate the use of HEU in US-supplied research reactors has been accomplished
Measures to implement the Chemical Weapons Convention ( file )
3 editions published between 1995 and 1999 in English and held by 0 libraries worldwide
It is an honor to address this distinguished audience. We are grateful to the Republique Gabonaise for hosting this important gathering and to the staff of the Organization for the Prohibition of Chemical Weapons (OPCW) for supporting it. This seminar is another excellent opportunity for all of us to learn from each other about how the Chemical Weapons Convention (CWC) can become a foundation of arms control in Africa and around the world. At this meeting we speak only for ourselves, neither for the government of the United States of America nor for any other institution. This paper discusses model national implementing legislation under the CWC. Every State Party likely must enact implementing legislation - not only the few States Parties that will declare and destroy chemical weapons, but also the many States Parties that have never had a chemical weapons programme
Magnesium transport extraction of transuranium elements from LWR fuel ( file )
3 editions published in 1991 in English and held by 0 libraries worldwide
A process of separating transuranium actinide values from uranium values present in spent nuclear oxide fuels containing rare earth and noble metal fission products as well as other fission products is disclosed. The oxide fuel is reduced with Ca metal in the presence of Ca chloride and a U-Fe alloy which is liquid at about 800°C to dissolve uranium metal and the noble metal fission product metals and transuranium actinide metals and rare earth fission product metals leaving Ca chloride having CaO and fission products of alkali metals and the alkali earth metals and iodine dissolved therein. The Ca chloride and CaO and the fission products contained therein are separated from the U-Fe alloy and the metal values dissolved therein. The U-Fe alloy having dissolved therein reduced metals from the spent nuclear fuel is contacted with a mixture of one or more alkali metal or alkaline earth metal halides selected from the class consisting of alkali metal or alkaline earth metal and Fe or U halide or a combination thereof to transfer transuranium actinide metals and rare earth metals to the halide salt leaving the uranium and some noble metal fission products in the U-Fe alloy and thereafter separating the halide salt and the transuranium metals dissolved therein from the U-Fe alloy and the metals dissolved therein
RERTR program activities related to the development and application of new LEU fuels. [Reduced Enrichment Research and Test Reactor ; low-enriched uranium] ( file )
5 editions published between 1983 and 2000 in English and held by 0 libraries worldwide
The status of the US Reduced Enrichment Research and Test Reactor (RERTR) Program is reviewed. After a summary of the accomplishments which the RERTR Program had achieved by the end of 1984 with its many international partners, emphasis is placed on the progress achieved during 1985 and on current plans and schedules. A new miniplate series, concentrating on U₃Si₂-Al and U₃Si-Al fuels, was fabricated and is well into irradiation. The whole-core ORR demonstration is scheduled to begin in November 1985, with U₃Si₂-Al fuel at 4.8 g U/cm³. Altogether, 921 full-size test and prototype elements have been ordered for fabrication with reduced enrichment and the new technologies. Qualification of U₃Si-Al fuel with approx. 7 g U/cm³ is still projected for 1989. This progress could not have been achieved without the close international cooperation which has existed since the beginning, and whose continuation and intensification will be essential to the achievement of the long-term RERTR goals
System administrator's manual (SAM) for the enhanced logistics intratheater support tool (ELIST) database segment version 8.1.0.0 for solaris 7 ( file )
3 editions published in 2002 in English and held by 0 libraries worldwide
This document is the User's Manual (UM) for the Enhanced Logistics Intratheater Support Tool (ELIST) Software Segment. It tells how to use the end-user and administrative features of the segment. The instructions in Sections 4.2.1, 5.3.1, and 5.3.2 for the end-user features (Run ELIST and Run ETEdit) only cover the launching of those features in the DII COE environment; full details on the operation of ELIST and ETEdit in any environment can be found in the documents listed in Section 2.1.3 and referenced elsewhere in this document. On the other hand, complete instructions for the administrative features (Add Map Data and Delete Map Data) are presented in Sections 4.2.2, 5.3.3, and 5.3.4 of this document
Development of mixed-conducting ceramic membranes for hydrogen separation ( file )
4 editions published between 1998 and 2002 in English and held by 0 libraries worldwide
SrCeO₃- and BaCeO₃-based proton conductors have been prepared and their transport properties have been investigated by impedance spectroscopy in conjunction with open circuit voltage and water vapor evolution measurements. BaCe{sub 0.8}Y{sub 0.2}O{sub 3-{delta}} exhibits the highest conductivity in a hydrogen-containing atmosphere; however, its electronic conductivity is not adequate for hydrogen separation in a nongalvanic mode. In an effort to enhance ambipolar conductivity and improve interfacial catalytic properties, BaCe{sub 0.8}Y{sub 0.2}O{sub 3-{delta}} cermets have been fabricated into membranes. The effects of ambipolar conductivity, membrane thickness, and interfacial resistance on permeation rates have been investigated. In particular, the significance of interfacial resistance is emphasized
Testing of optical components to assure performance in a high acerage power environment ( file )
5 editions published in 1997 in English and held by 0 libraries worldwide
A number of different applications for high resolution Bragg Focusing Optics are reviewed. Applications include Sagittal Focusing, Energy Dispersive optics for x-ray absorption and diffraction, a curved analyzer-multichannel detector method for efficient acquisition of powder and small angle scattering data, the use of Backscattering Analyzers for very high resolution inelastic scattering, and curved crystals for high energy applications
Diamond monochromator for high heat flux synchrotron x-ray beams ( file )
3 editions published between 1992 and 1993 in English and held by 0 libraries worldwide
Single crystal silicon has been the material of choice for x-ray monochromators for the past several decades. However, the need for suitable monochromators to handle the high heat load of the next generation synchrotron x-ray beams on the one hand and the rapid and on-going advances in synthetic diamond technology on the other make a compelling case for the consideration of a diamond mollochromator system. In this Paper, we consider various aspects, advantage and disadvantages, and promises and pitfalls of such a system and evaluate the comparative an monochromator subjected to the high heat load of the most powerful x-ray beam that will become available in the next few years. The results of experiments performed to evaluate the diffraction properties of a currently available synthetic single crystal diamond are also presented. Fabrication of diamond-based monochromator is within present technical means
 
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