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Argonne National Lab

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Works: 13,749 works in 14,751 publications in 1 language and 58,125 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
The incorporation of technetium into a representative low-activity waste glass ( file )
3 editions published in 1997 in English and held by 0 libraries worldwide
The National Academy of Sciences recommended dissolution in a silicate matrix, with fission products to provide a protective radiation field, as one option for dispositioning excess weapons-grade plutonium. Candidate materials and processing conditions have been developed to pursue this option using high-level waste stored at the Idaho Chemical Processing Plant. Devitrification of glassy host materials achieves increased plutonium loading by partitioning plutonium into durable crystalline host phases. Results of devitrification experiments are summarized, and several unique plutonium host phases are reported. These phases were initially synthesized and characterized using cerium as a plutonium surrogate, to simplify operational requirements. Tests using plutonium were performed to validate results obtained with surrogate materials. Characterization and leach test results are reported
RERTR program activities related to the development and application of new LEU fuels. [Reduced Enrichment Research and Test Reactor ; low-enriched uranium] ( file )
6 editions published between 1980 and 2000 in English and held by 0 libraries worldwide
The statue of the U.S. Reduced Enrichment Research and Test Reactor (RERTR) Program is reviewed. After a brief outline of RERTR Program objectives and goals, program accomplishments are discussed with emphasis on the development, demonstration and application of new LEU fuels. Most program activities have proceeded as planned, and a combination of two silicide fuels (U₃Si₂-Al and U₃Si-Al) holds excellent promise for achieving the long-term program goals. Current plans and schedules project the uranium density of qualified RERTR fuels for plate-type reactors to grow by approximately 1 g U/cm³ each year, from the current 1.7 g U/cm³ to the 7.0 g U/cm³ which will be reached in late 1988. The technical needs of research and test reactors for HEU exports are also forecasted to undergo a gradual but dramatic decline in the coming years
Current status of dense ceramic membranes for hydrogen separation ( file )
4 editions published between 1998 and 2002 in English and held by 0 libraries worldwide
We have developed cermet membranes that nongalvanically separate hydrogen from gas mixtures. The highest measured hydrogen flux was 16.2 cm³ (STP)/min-cm² for an ANL-3a membrane at 900 C. For ANL-3 membranes with thickness of 0.04-0.5 mm, permeation rate is limited by the bulk diffusion of hydrogen through the metal phase. The effect of hydrogen partial pressure on permeation rate confirmed this conclusion and suggested that higher permeation rates may be obtained by decreasing the membrane thickness. Permeation rate in a syngas atmosphere for times up to 190 h showed no degradation in performance, which indicates that ANL-3 may be suitable for long-term, practical hydrogen separation
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
High energy wigglers produce extremely high total powers. For example, the insertion device for one beamline of the Basic Energy Sciences Synchrotron Research Center (BESSRC) is an elliptical multipole wiggler (EMPW) which can generate circularly polarized X-rays on axis and produces a total power of (approximately)8 kW. This insertion device will be used to simultaneously provide x-rays to three branch lines, a branch equipped with a normal double crystal monochromator feeding a scattering and spectroscopy station, and two branches with single-bounce horizontally deflecting monochromators for Compton scattering and High Energy Diffraction. The crystal optics for this type of device require substantially different heat load solutions than those used for undulator beamlines. We will discuss how the beam is split and shared among the beamline branch lines and present the crystal cooling strategies employed for both the double-crystal monochromator and horizontally deflecting single-bounce monochromators
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
The RERTR Program status and progress ( file )
3 editions published between 1995 and 1999 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 during 1999 and discusses planned activities for the coming year
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
INEL4 is designed to be the workhorse instrument for inelastic studies requiring good resolution and extended ranges in both Q and E. Figure 1 provides a schematic representation of INEL4, and Table 1 provides the parameters for this instrument. This instrument is capable of studies involving energy transfers ranging from a few meV to more than 1 eV. The wide angular coverage and large solid angle of detectors provide relatively high data rates and an extensive Q range
An evaluated neutronic data file for elemental zirconium ( file )
3 editions published between 1992 and 1994 in English and held by 0 libraries worldwide
A comprehensive evaluated neutronic data file for elemental zirconium is derived and presented in the ENDF/B-VI formats. The derivation is based upon measured microscopic nuclear data, augmented by model calculations as necessary. The primary objective is a quality contemporary file suitable for fission-reactor development extending from conventional thermal to fast and innovative systems. This new file is a significant improvement over previously available evaluated zirconium files, in part, as a consequence of extensive new experimental measurements reported elsewhere
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
Surveillance of site A and plot M : report for 1994 by Norbert W Golchert( file )
5 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 1991 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 (1) determine the migration pathway of water from the burial ground (Plot M) to the hand-pumped picnic wells, (2) establish if buried radionuclides other than hydrogen-3 have migrated, and (3) generally characterize the radiological environment of the area. Hydrogen-3 in the Red Gate Woods picnic wells was still detected this year, but the average and maximum concentrations were significantly less than found earlier. Tritiated water continues to be detected in a number of wells, boreholes, dolomite holes, and surface stream. For many years it was the only radionclide found to have migrated in measurable quantities. Analyses since 1984 have indicated the presence of low levels of strontium-90 in water from a number of borehole next to Plot M. The available data does not allow a firm conclusion as to whether the presence of this nuclide represents recent migration or movement that may have occurred before Plot M was capped. The results of the surveillance program continue 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
ADIFOR : Fortran source translation for efficient derivatives. ADIFOR Working Note No. 4 ( file )
3 editions published in 1992 in English and held by 0 libraries worldwide
The numerical methods employed in the solution of many scientific computing problems require the computation of derivatives of a function f: R(superscript n) --> R{sup m}. Both the accuracy and the computational requirements of the derivative computation are usually of critical importance for the robustness and speed of the numerical method. ADIFOR (Automatic Differentiation In FORtran) is a source translation tool implemented using the data abstractions and program analysis capabilities of the ParaScope Parallel Programming Environment. ADIFOR accepts arbitrary Fortran-77 code defining the computation of a function and writes portable Fortran-77 code for the computation of its derivatives. In contrast to previous approaches, ADIFOR views automatic differentiation as a process of source translation that exploits computational context to reduce the cost of derivative computations. Experimental results show that ADIFOR can handle real-life codes, providing exact derivatives with a running time that is competitive with the standard divided-difference approximations of derivatives and which may perform orders of magnitude faster than divided-differences in cases. The computational scientist using ADIFOR is freed from worrying about the accurate and efficient computation of derivatives, even for complicated ''functions, '' and hence, is able to concentrate on the more important issues of algorithm design or system modeling. 35 refs
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
The RERTR Program. A status report ( file )
6 editions published between 1983 and 1998 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 brief outline of the RERTR Program objectives, goals and past accomplishments, emphasis is placed on the developments which took place during 1983 and on current program plans and schedules. Most program activities have proceeded as planned and a combination of two silicide fuels (U₃Si₂-Al and U₃Si-Al) was found to hold excellent promise for achieving the long-term program goals. A modification of the program plan, including the development and demonstration of those fuels, was prepared and is now being implemented. The uranium density of qualified RERTR fuels for plate-type reactors is forecasted to grow by approximately 1 g U/cm³ each year, from the current 1.7 g U/cm³ to the 7.0 g U/cm³ which will be reached in 1988. The technical needs of research reactors for HEU exports are also forecasted to undergo a gradual and dramatic decline in the coming years
User's manual (UM) for the enhanced logistics intratheater support tool (ELIST) software 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
Salt 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
Model National Implementing Legislation for the Chemical Weapons Convention ( file )
3 editions published between 1995 and 1999 in English and held by 0 libraries worldwide
Good day. It is an honor to address this distinguished audience. I am grateful to the Federal Democratic Republic of Ethiopia for hosting this important gathering and to the staff of the Provisional Technical Secretariat of the Organization for the Prohibition of Chemical Weapons (PTS) for sponsoring it. I also want to express my gratitude to the DePaul University Human Rights Law Institute, the Merck Foundation, and Argonne National Laboratory for supporting my participation here. This workshop is an 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 I speak only for myself, neither for the government of the United States of America nor for any other institution. Today, I shall discuss model national implementing legislation under the CWC. Such implementing legislation is likely to be required in every State Party--not only to the few States Parties that will declare and destroy chemical weapons, but also to the many States Parties that have never had a chemical weapons programme. This new need for national measures to implement multilateral arms control agreements has generated unease due to a perception that implementation may be burdensome and at odds with existing national law. In 1993, concerns arose that the complexity of integrating the treaty with national law would cause each nation to implement the Convention without regard to what other nations were doing, thereby causing inconsistencies among States Parties in how the Convention would be carried but
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
A measurement-based method for predicting margins and uncertainties for unprotected accidents in the Integral Fast Reactor concept ( file )
6 editions published in 1990 in English and held by 0 libraries worldwide
Simple methods are described for bounding the passive response of a metal fueled liquid-metal cooled reactor to the chilled inlet accident. Calculation of these bounds for a prototype of the Integral Fast Reactor concept shows that failure limits -- eutectic melting, sodium boiling and fuel pin failure -- are not exceeded. 2 refs., 1 fig., 2 tabs
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. In 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
Scattering of fast neutrons from elemental molybdenum ( file )
11 editions published in 1982 in English and held by 0 libraries worldwide
Differential-neutron-emission cross sections of ²³²Th, ²³³U, ²³⁵U, ²³⁸U, ²³⁹Pu and ²⁴°Pu are measured between approx. = 1.0 and 3.5 MeV with the angle and magnitude detail needed to provide angle-integrated emission cross sections to approx. <3% accuracies. Emitted-neutron resolutions are quantitatively defined and vary from approx. = 0.1 to 0.35 MeV. The experimental results are corrected for fisson-neutron contributions to obtain pseudo-elastic-neutron-scattering cross sections which, together with the neutron total cross sections, define the non-elastic cross sections to within well specified energy resolutions. These results imply inelastic-neutron-scattering cross sections which are compared with comparable quantities derived from ENDF/B-V. Good general agreement is noted for ²³²Th, ²³³U, ²³⁵U and ²³⁸U inelastic-scattering values, poor agreement is observed for ²⁴°Pu, and a serious discrepancy exists in the case of ²³⁹Pu
 
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