WorldCat Identities

Argonne National Laboratory-West

Overview
Works: 274 works in 297 publications in 1 language and 590 library holdings
Genres: Conference proceedings 
Roles: Researcher
Publication Timeline
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Publications about Argonne National Laboratory-West Publications about Argonne National Laboratory-West
Publications by Argonne National Laboratory-West Publications by Argonne National Laboratory-West
Most widely held works about Argonne National Laboratory-West
 
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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 13 WorldCat member libraries worldwide
Proceedings American Nuclear Society meeting on fission-product behavior and source term research by Martin F Huebner ( Book )
1 edition published in 1985 in English and held by 3 WorldCat member libraries worldwide
A universal, fault-tolerant, non-linear analytic network for modeling and fault detection ( )
2 editions published in 1992 in English and held by 2 WorldCat member libraries worldwide
The similarities and differences of a universal network to normal neural networks are outlined. The description and application of a universal network is discussed by showing how a simple linear system is modeled by normal techniques and by universal network techniques. A full implementation of the universal network as universal process modeling software on a dedicated computer system at EBR-II is described and example results are presented. It is concluded that the universal network provides different feature recognition capabilities than a neural network and that the universal network can provide extremely fast, accurate, and fault-tolerant estimation, validation, and replacement of signals in a real system
Combination of artificial intelligence and procedural language programs in a computer application system supporting nuclear reactor operations ( )
2 editions published in 1985 in English and held by 2 WorldCat member libraries worldwide
A computer application system is described which provides nuclear reactor power plant operators with an improved decision support system. This system combines traditional computer applications such as graphics display with artifical intelligence methodologies such as reasoning and diagnosis so as to improve plant operability. This paper discusses the issues, and a solution, involved with the system integration of applications developed using traditional and artificial intelligence languages
Development of a Monolithic Research Reactor Fuel Type at Argonne National Laboratory ( )
1 edition published in 2004 in English and held by 2 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
Performance of HT9 clad metallic fuel at high temperature ( )
2 editions published in 1992 in English and held by 2 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°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
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 2 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
EBR-II Cover Gas Cleanup System upgrade process control system structure ( )
2 editions published in 1992 in English and held by 2 WorldCat member libraries worldwide
The Experimental Breeder Reactor II (EBR-II) Cover Gas Cleanup System (CGCS) control system was upgraded in 1991 to improve control and provide a graphical operator interface. The upgrade consisted of a main control computer, a distributed control computer, a front end input/output computer, a main graphics interface terminal, and a remote graphics interface terminal. This paper briefly describes the Cover Gas Cleanup System and the overall control system; describes the main control computer hardware and system software features in more detail; and, then, describes the real-time control tasks, and how they interact with each other, and how they interact with the operator interface task
Experience with advanced driver fuels in EBR-II ( )
2 editions published in 1992 in English and held by 2 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
Surveillance application using patten recognition software at the EBR-II Reactor Facility ( )
2 editions published in 1992 in English and held by 2 WorldCat member libraries worldwide
The System State Analyzer (SSA) is a software based pattern recognition system. For the past several year this system has been used at Argonne National Laboratory's Experimental Breeder Reactor 2 (EBR-2) reactor for detection of degradation and other abnormalities in plant systems. Currently there are two versions of the SSA being used at EBR-2. One version of SSA is used for daily surveillance and trending of the reactor delta-T and startups of the reactor. Another version of the SSA is the QSSA which is used to monitor individual systems of the reactor such as the Secondary Sodium System, Secondary Sodium Pumps, and Steam Generator. This system has been able to detect problems such as signals being affected by temperature variations due to a failing temperature controller
Integral Fast Reactor fuel pin processor ( )
2 editions published in 1993 in English and held by 2 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
IFR fuel cycle ( )
2 editions published in 1992 in English and held by 2 WorldCat member libraries worldwide
The next major milestone of the IFR program is engineering-scale demonstration of the pyroprocess fuel cycle. The EBR-II Fuel Cycle Facility has just entered a startup phase, which includes completion of facility modifications and installation and cold checkout of process equipment. This paper reviews the development of the electrorefining pyroprocess, the design and construction of the facility for the hot demonstration, the design and fabrication of the equipment, and the schedule and initial plan for its operation
Remote real time x-ray examination of fuel elements in a hot cell environment ( )
2 editions published in 1993 in English and held by 2 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
Computer imaging of EBR-II handling equipment ( )
2 editions published between 1994 and 1995 in English and held by 2 WorldCat member libraries worldwide
This paper describes a three-dimensional graphics application used to visualize the positions of remotely operated fuel handling equipment in the EBR-II reactor. A three-dimensional (3D) visualization technique is necessary to simulate direct visual observation of the transfers of fuel and experiments into and out of the reactor because the fuel handling equipment is submerged in liquid sodium and therefore is not visible to the operator. The system described in this paper uses actual signals to drive a three-dimensional computer-generated model in real-time in response to movements of equipment in the plant This paper will present details on how the 3D model of the intank equipment was created and how real-time dynamic behavior was added to each of the moving components
EBR-II spent fuel treatment demonstration project ( )
2 editions published between 1997 and 1998 in English and held by 2 WorldCat member libraries worldwide
The application of electrometallurgical technology to spent nuclear fuel treatment is being demonstrated by treating 410 kg uranium spent driver fuel and 1,200 kg uranium spent blanket fuel from the Experimental Breeder Reactor-II (EBR-II) spent driver and blanket fuel. This fuel is a metallic uranium alloy and contains elemental sodium, which is a reactive material. Since reactive material is considered hazardous by US Environmental Protection Agency regulations, this fuel requires treatment before disposal in a geologic repository. The EBR-II spent fuel treatment demonstration conditions this fuel in an integrated process where the fuel is converted into three different products: low enriched uranium (LEU), ceramic waste and metallic waste. This demonstration was initiated in June 1996 and has treated approximately 50% of the driver fuel. The higher throughput equipment that will be used for blanket treatment processes has been installed in the hot cell facility and is being tested with depleted uranium. Metal waste forms have been produced from the irradiated metals from the driver fuel. Ceramic waste process equipment has been built and is being tested before installation in the hot cell facilities. This paper discusses the processes and the current results from the first 20 months of operation
Reusable molds for casting U-Zr alloys ( )
2 editions published in 1992 in English and held by 2 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
Advanced control system for the Integral Fast Reactor fuel pin processor ( )
2 editions published in 1993 in English and held by 2 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
Performance of U-Pu-Zr fuel cast into zirconium molds ( )
2 editions published in 1992 in English and held by 2 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
Instrumentation and control improvements at Experimental Breeder Reactor II ( )
2 editions published in 1993 in English and held by 2 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
A system for fast neutron radiography ( )
2 editions published between 1996 and 1997 in English and held by 2 WorldCat member libraries worldwide
A system has been designed and a neutron generator installed to perform fast neutron radiography. With this sytem, objects as small as a coin or as large as a waste drum can be radiographed. The neutron source is an MF Physics A-711 neutron generator which produces 3x10¹° neutrons/second with an average energy of 14.5 MeV. The radiography system uses x-ray scintillation screens and film in commercially available cassettes. The cassettes have been modified to include a thin sheet of plastic to convert neutrons to protons through elastic scattering from hydrogen and other low Z materials in the plastic. For film densities from 1.8 to 3.0, exposures range from 1.9x10⁷ to 3.8x10⁸ n/cm² depending on the type of screen and film
 
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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 (54)