WorldCat Identities

Argonne National Laboratory-West

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Works: 281 works in 303 publications in 1 language and 953 library holdings
Roles: Researcher
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Most widely held works by Argonne National Laboratory-West
Survey of licensee control room habitability practices ( Book )
2 editions published in 1985 in English and held by 14 WorldCat member libraries worldwide
Contamination control aspects of attaching waste drums to the WIPP Waste Characterization Chamber ( )
3 editions published in 1998 in English and held by 12 WorldCat member libraries worldwide
The Casting Laboratory (CL) alpha glove box was used to melt and cast metallic uranium and plutonium fuels as part of the Department of Energy's Liquid Metal Fast Breeder Reactor Program. This highly contaminated alpha glove box was decontaminated and reconditioned to allow a change in mission. The goal of reconditioning was to install experimental apparatus and to improve contamination control prior to introducing plutonium-238 into the CL glove box. Construction of a glove box containment structure and an increase in room ventilation were required. A temporary breathing air station was provided for personnel protection as well as personnel comfort. The historical contamination levels, the decontamination techniques, and the results of decontamination also are presented. The health physics aspects of the CL alpha glove box project may be applicable to other glove box refurbishment or decommissioning projects
Security preparation for receipt of SNF from the FRR to the INEEL ( )
2 editions published in 1997 in English and held by 8 WorldCat member libraries worldwide
Twelve uranium alloys have been selected for incorporation into very high density aluminum dispersion fuel plates for irradiation testing. These alloys are (nominally) U-10Mo, U-8Mo, U-6Mo, U-4Mo, U-9Nb-3Zr, U-6Nb-4Zr, U-5Nb-3Zr, U-2Mo-1Nb-1Zr, U-6Mo-1Pt, U-6Mo-0.6Ru, U-6Mo-0.6Si, and U-10Mo-0.05Sn. The rationale for selection of these fuels based on gamma phase stability, reports of good irradiation performance, and high uranium density will be discussed. The microstructures of these fuels were examined by SEM/EDS and XRD at three storage during the powder fabrication process. Microstructures of selected alloys are discussed
Performance of U-Pu-Zr fuel cast into zirconium molds ( )
2 editions published in 1992 in English and held by 5 WorldCat member libraries worldwide
U-3Zr and U-20.5Pu-3Zr were injection cast into Zr tubes, or sheaths, rather than into quartz molds and clad in 316SS. These elements and standard-cast U-l0Zr and U-IgPu-l0Zr elements were irradiated in EBR-II to 2 at.% and removed for interim examination. Measurements of axial growth at indicate that the Zr-sheathed elements exhibited significantly less axial elongation than the standard-cast elements (1.3 to 1.8% versus 4.9 to 8.1%). Fuel material extruded through the ends of the Zr sheaths. allowing the low-Zr fuel to contact the cladding in some cases. Transverse metallographic sections reveal cracks in the Zr sheath through which fuel extruded and contacted cladding. The sheath is not a sufficient barrier between fuel and cladding to reduce FCCI. and any adverse effects due to increased FCCI will be evident as the elements attain higher burnup
Probabilistic treatment of rod run-in accident initiators and the reactivity feedback responses in EBR-II ( )
2 editions published in 1993 in English and held by 5 WorldCat member libraries worldwide
The idea of treating an accident initiator in a probabilistic manner is developed. Instead of using a bounding value, the rod reactivity insertion in an unprotected transient overpower accident is described realistically as a distribution of insertion magnitudes. The initiator analysis uses EBR-II Operating Instructions and data files of rod worths and position histories. The average insertion magnitude is found to be 16{cents}, which is only about hall of the feedback reactivity from zero to full power. The probability of inserting 130{cents} or more, the Technical Specification limit, is less than 10⁻⁶. The initiator characteristics are then propagated through a probabilistic analysis of the reactivity feedback response to the initiator. This analysis shows that reactivity feedbacks reduce by four orders of magnitude the probability of a rod run-in event resulting in substantial core damage, in addition to the more than five order of magnitude margin afforded by the scram system
Instrumentation and control improvements at Experimental Breeder Reactor II ( )
2 editions published in 1993 in English and held by 5 WorldCat member libraries worldwide
The purpose of this paper is to describe instrumentation and control (I & C) system improvements at Experimental Breeder Reactor 11 (EBR-11). The improvements are focused on three objectives; to keep the reactor and balance of plant (BOP) I & C systems at a high level of reliability, to provide diagnostic systems that can provide accurate information needed for analysis of fuel performance, and to provide systems that will be prototypic of I & C systems of the next generation of liquid metal reactor (LMR) plants
Characterization of mixed CH-TRU waste for the WIPP Experimental Test Program conducted at ANL-W ( )
2 editions published in 1992 in English and held by 5 WorldCat member libraries worldwide
Argonne National Laboratory is participating in the Department of Energy's Waste Isolation Pilot Plant (WIPP) Experimental Test Program by characterizing and repackaging mixed contact-handled transuranic waste. Characterization activities include gas sampling the waste containers, visually examining the waste contents, categorizing the contents according to their gas generation potentials, and weighing the contents. The waste is repackaged from 0.21m³ (55 gallon) drums into instrumented steel test bins which can hold up to six drum-equivalents in volume. Eventually the loaded test bins will be shipped to WIPP where they will be evaluated during a five-year test program. Three test bins of inorganic solids (primarily glass) were prepared between March and September 1991 and are ready for shipment to WIPP. The characterization activities confirmed process knowledge of the waste and verified the nondestructive examinations; the gas sample analyses showed the target constituents to be within allowable regulatory limits. A new waste characterization chamber is being developed at ANL-W which will improve worker safety, decrease the potential for contamination spread, and increase the waste characterization throughput. The new facility is expected to begin operations by Fall 1992. A comprehensive summary of the project is contained herein
Experience with advanced driver fuels in EBR-II ( )
2 editions published in 1992 in English and held by 5 WorldCat member libraries worldwide
This paper discusses several metallic fuel element designs which have been tested and used as driver fuel in Experimental Breeder Reactor II (EBR-II). The most recent advanced designs have all performed acceptably in EBR-H and can provide reliable performance to high burnups. Fuel elements tested have included use of U-l0Zr metallic fuel with either D9, 316 or HT9 stainless steel cladding; the D9 and 316-clad designs have been used as standard driver fuel. Experimental data indicate that fuel performance characteristics are very similar for the various designs tested. Cladding materials can be selected that optimize performance based on reactor design and operational goals
Integral Fast Reactor fuel pin processor ( )
2 editions published in 1993 in English and held by 5 WorldCat member libraries worldwide
This report discusses the pin processor which receives metal alloy pins cast from recycled Integral Fast Reactor (IFR) fuel and prepares them for assembly into new IFR fuel elements. Either full length as-cast or precut pins are fed to the machine from a magazine, cut if necessary, and measured for length, weight, diameter and deviation from straightness. Accepted pins are loaded into cladding jackets located in a magazine, while rejects and cutting scraps are separated into trays. The magazines, trays, and the individual modules that perform the different machine functions are assembled and removed using remote manipulators and master-slaves
Minimization of heat slab nodes with higher order boundary conditions ( )
2 editions published in 1992 in English and held by 5 WorldCat member libraries worldwide
The accuracy of a numerical solution can be limited by the numerical approximation to the boundary conditions rather than the accuracy of the equations which describe the interior. The study presented in this paper compares the results from two different numerical formulations of the convective boundary condition on the face of a heat transfer slab. The standard representation of the boundary condition in a test problem yielded an unacceptable error even when the heat transfer slab was partitioned into over 300 nodes. A higher order boundary condition representation was obtained by using a second order approximation for the first derivative at the boundary and combining it with the general equation used for inner nodes. This latter formulation produced reasonable results when as few as ten nodes were used
Development of a Monolithic Research Reactor Fuel Type at Argonne National Laboratory ( )
1 edition published in 2004 in English and held by 5 WorldCat member libraries worldwide
The Reduced Enrichment for Research and Test Reactors (RERTR) program has been tasked with the conversion of research reactors from highly enriched to low-enriched uranium (LEU). To convert several high power reactors, monolithic fuel, a new fuel type, is being developed. This fuel type replaces the standard fuel dispersion with a fuel alloy foil, which allows for fuel densities far in excess of that found in dispersion fuel. The single-piece fuel foil also contains a significantly lower interface area between the fuel and the aluminum in the plate than the standard fuel type, limiting the amount of detrimental fuel-aluminum interaction that can occur. Implementation of monolithic fuel is dependant on the development of a suitable fabrication method as traditional roll-bonding techniques are inadequate
Remote real time x-ray examination of fuel elements in a hot cell environment ( )
2 editions published in 1993 in English and held by 5 WorldCat member libraries worldwide
This report discusses the Remote Real Time X-ray System which will allow for detailed examination of fuel elements. This task will be accomplished in a highly radioactive hot cell environment. Two remote handling systems win be utilized at the examination station. One handling system will transfer the fuel element to and from the shielded x-ray system. A second handling system will allow for vertical and rotational inspection of the fuel elements. The process win include removing a single nuclear fuel element from a element fabrication magazine(EFM), positioning the fuel element within the shielding envelope of the x-ray system and transferring the fuel element from the station manipulator to the x-ray system manipulator, performing the x-ray inspection, and then transferring the fuel element to either the element storage magazine(ESM) or a reject bin
Performance of HT9 clad metallic fuel at high temperature ( )
2 editions published in 1992 in English and held by 5 WorldCat member libraries worldwide
Steady-state testing of HT9 clad metallic fuel at high temperatures was initiated in EBR-II in November of 1987. At that time U-10 wt. % Zr fuel clad with the low-swelling ferritic/martensitic alloy HT9 was being considered as driver fuel options for both EBR-II and FFTF. The objective of the X447 test described here was to determine the lifetime of HT9 cladding when operated with metallic fuel at beginning of life inside wall temperatures approaching [approximately]660[degree]C. Though stress-temperature design limits for HT9 preclude its use for high burnup applications under these conditions due to excessive thermal creep, the X447 test was carried out to obtain data on high temperature breach phenomena involving metallic fuel since little data existed in that area
Beam characterization at the Neutron Radiography Facility (NRAD) ( )
2 editions published in 1992 in English and held by 5 WorldCat member libraries worldwide
An ongoing project to characterize the neutron beams at the Neutron Radiography Reactor (NRAD) is described in this paper. The effort has consisted of computer modelling with three dimensional diffusion theory to obtain a trail spectrum, foil activation measurements, and the use of SAND-II unfolding code. It was expected and found that diffusion theory will underpredict the fast flux. However, it is claimed that precise characterization of the entire spectrum is not necessary for comparisons among neutron radiography facilities; rather, the use of simple fast neutron indicators should be adequate. A specific example used at NRAD is the U-235/U-238 fission reaction rate ratio. A ratio such as this could be used in the same manner as the classic gold cadmium ratio for interfacility comparisons with regard to fast neutrons. 5 refs
Advanced control system for the Integral Fast Reactor fuel pin processor ( )
2 editions published in 1993 in English and held by 5 WorldCat member libraries worldwide
A computerized control system has been developed for the remotely-operated fuel pin processor used in the Integral Fast Reactor Program, Fuel Cycle Facility (FCF). The pin processor remotely shears cast EBR- reactor fuel pins to length, inspects them for diameter, straightness, length, and weight, and then inserts acceptable pins into new sodium-loaded stainless-steel fuel element jackets. Two main components comprise the control system: (1) a programmable logic controller (PLC), together with various input/output modules and associated relay ladder-logic associated computer software. The PLC system controls the remote operation of the machine as directed by the OCS, and also monitors the machine operation to make operational data available to the OCS. The OCS allows operator control of the machine, provides nearly real-time viewing of the operational data, allows on-line changes of machine operational parameters, and records the collected data for each acceptable pin on a central data archiving computer. The two main components of the control system provide the operator with various levels of control ranging from manual operation to completely automatic operation by means of a graphic touch screen interface
Reusable molds for casting U-Zr alloys ( )
2 editions published in 1992 in English and held by 5 WorldCat member libraries worldwide
Refractory oxides, carbides, nitrides and sulfides were examined as mold coating materials for use in casting nuclear fuel. The molds require excellent high temperature chemical and mechanical stability combined with reasonable room temperature ductility to allow for fuel removal. Coatings were applied onto quartz and refractory metal coupons using various techniques. Sessile drop tests employing molten U-10%Zr (by weight) at 1550°C were used to characterize coating performance. Results indicate that NbC, TiN, and Y₂O₃ were non-wetting with U-10%Zr. However, only the Y₂O₃ coating completely prevented adhesion of the fuel. The paper describes coating methods and details of the sessile drop experiments
Removal of an acid fume system contaminated with perchlorates located within hot cell ( )
2 editions published in 1992 in English and held by 5 WorldCat member libraries worldwide
An add scrubbing system located within the confines of a highly radioactive hot cell at Argonne National Laboratory-West (ANL-W) was remotely removed. The acid scrubbing system was routinely used for the dissolution of irradiated reactor fuel samples and structural materials. Perchloric acid was one of the acids used in the dissolution process and remained in the system with its inherent risks. Personnel could not enter the hot cell to perform the dismantling of the acid scabbing system due to the high radiation field and the explosion potential associated with the perchlorates. A robot was designed and built at ANL-W and used to dismantle the system without the need for personnel entry into the hot cell. The robot was also used for size reduction of removed components and loading of the removed components into waste containers
Real-time monitoring and control of the plasma hearth process ( )
1 edition published in 1996 in English and held by 4 WorldCat member libraries worldwide
A distributed monitoring and control system is proposed for a plasma hearth, which will be used to decompose hazardous organic materials, encapsulate actinide waste in an obsidian-like slag, and reduce storage volume of actinide waste. The plasma hearth will be installed at ANL-West with the assistance of SAIC. Real-time monitoring of the off-gas system is accomplished using a Sun Workstation and embedded PCs. LabWindows/CVI software serves as the graphical user interface
Applying programmatic risk assessment to nuclear materials stabilization R and D planning ( )
1 edition published in 1997 in English and held by 4 WorldCat member libraries worldwide
A systems engineering approach to programmatic risk assessment, derived from the aerospace industry, was applied to various stabilization technologies to assess their relative maturity and availability for use in stabilizing nuclear materials. The assessment provided valuable information for trading off available technologies and identified the at-risk technologies that will require close tracking by the Department of Energy (DOE) to mitigate programmatic risks. This paper presents the programmatic risk assessment methodology developed for the 1995 R and D Plan and updated for the 1996 R and D Plan. Results of the 1996 assessment also are presented (DOE/ID-10561, 1996)
Criticality safety strategy for the Fuel Cycle Facility electrorefiner at Argonne National Laboratory, West ( )
1 edition published in 1993 in English and held by 4 WorldCat member libraries worldwide
The Integral Fast Reactor being developed by Argonne National Laboratory (ANL) combines the advantages of metal-fueled, liquid-metal-cooled reactors and a closed fuel cycle. Presently, the Fuel Cycle Facility (FCF) at ANL-West in Idaho Falls, Idaho is being modified to recycle spent metallic fuel from Experimental Breeder Reactor II as part of a demonstration project sponsored by the Department of Energy. A key component of the FCF is the electrorefiner (ER) in which the actinides are separated from the fission products. In the electrorefining process, the metal fuel is anodically dissolved into a high-temperature molten salt and refined uranium or uranium/plutonium products are deposited at cathodes. In this report, the criticality safety strategy for the FCF ER is summarized. FCF ER operations and processes formed the basis for evaluating criticality safety and control during actinide metal fuel refining. In order to show criticality safety for the FCF ER, the reference operating conditions for the ER had to be defined. Normal operating envelopes (NOES) were then defined to bracket the important operating conditions. To keep the operating conditions within their NOES, process controls were identified that can be used to regulate the actinide forms and content within the ER. A series of operational checks were developed for each operation that wig verify the extent or success of an operation. The criticality analysis considered the ER operating conditions at their NOE values as the point of departure for credible and incredible failure modes. As a result of the analysis, FCF ER operations were found to be safe with respect to criticality
 
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Alternative Names

controlled identity Idaho National Laboratory

Argonne National Laboratory - West
Idaho National Engineering and Environmental Laboratory
INEEL
INL
National Reactor Testing Station
Languages
English (53)