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State-of-the-Art Review of Materials-Related Problems in Flue Gas Desulfurization Systems

Description: This report characterizes the chemical and mechanical environments to which the structural components used in flue-gas desulfurization (FGD) are exposed. It summarizes the necessary background information pertinent to various FGD processes currently in use, with particular emphasis on lime/limestone scrubbing technology, so that the materials problems and processing variables encountered in FGD systems can be better defined and appreciated. The report also describes the materials currently used… more
Date: October 1980
Creator: Maiya, P. S.
Item Type: Refine your search to only Report
open access

Statistical Identification of Effective Input Variables

Description: This report provides background and procedural information for the use of a general-purpose Stirling-engine analysis code developed at Argonne National Laboratory and available through the National Energy Software Center. Different engine configurations are easily specified, or the user may make use of provided data for existing engines, both kinematic and free piston. The code models heat transfer and fluid mechanics throughout the engine and accounts for system energy flows and losses. Good a… more
Date: September 1982
Creator: Vaurio, J. K.
Item Type: Refine your search to only Report
open access

A Statistical Study of EBR-II Fuel Elements Manufactured by the Cold Line at Argonne-West and by Atomics International

Description: Nine elements from each batch of fuel elements manufactured for the EBR-II reactor have been analyzed for uranium-235 content by NDA methods. These values, together with those of the manufacturer, are used to estimate the product variance and the variances of the two measuring methods. These variances are compared with the variances computed from the stipulations of the contract. A method is derived for resolving the several variances into their within-batch and between-batch components. Some o… more
Date: September 1977
Creator: Harkness, A. L.
Item Type: Refine your search to only Report
open access

The Status and Development Potential of Plate-Type Fuels for Research and Test Reactors

Description: A program of transient in-reactor experiments is being conducted by Argonne National Laboratory in the Transient Reactor Test (TREAT) facility to guide and support analyses of hypothetical core-disruptive accidents (HCDA) in liquid-metal fast breeder reactors (LMFBR). Test results provide data needed to establish the response of LMFBR cores to hypothetical accidents producing fuel failure, coolant boiling, and the movement of coolant, molten fuel, and molten cladding. These data include margins… more
Date: March 1979
Creator: Stahl, D.
Item Type: Refine your search to only Report
open access

Status of the Li-Al/FeS Battery Manufacturing Technology. Final Report. November 1983. An Evaluation for the US Army, Belvoir R and D Center

Description: Research and development work on rechargeable lithium/molten salt batteries, sponsored by the US Department of Energy, has been under way at Argonne National Laboratory and several industrial laboratories for the past decade. In 1978, a program for the US Army (Belvoir R and D Center) was initiated with ANL and Eagle-Picher Industries to ascertain the status and to aid the development of the manufacturing technology of the Li-Al/FeS battery as a power source for forklift trucks. A long-lived ce… more
Date: August 1984
Creator: Chilenskas, A. A.; Shimotake, H.; Malecha, R.; Battles, J.; Miller, W.; Yao, N. P. et al.
Item Type: Refine your search to only Report
open access

Status Report on NASA Electronic Power-Factor Control Technology and Development

Description: This report assesses the development of the electronic power-factor control technology as it applies to use with alternating-current induction motors and to identify the potential market of this device and the potential savings this device could produce in the United States energy economy. Included are a status report of the Interagency Agreement between NASA and DOE and the recommendations regarding future efforts of the DOE in the demonstration and commercialization of the power-factor contro… more
Date: 1981
Creator: Koehl, E. R.
Item Type: Refine your search to only Report
open access

Status Report on the Argonne Advanced Research Reactor

Description: From Introduction: "This is a status report on the interim design and development for an advanced research reactor (AARR) that will produce a maximum thermal neutron flux of 5 x 10 to the fifteenth power neutrons/ (cm2) (sec). As a result, this report also contains sections covering shielding, plant layout, fuel charging, maintenance, and auxiliary facilities."
Date: November 1961
Creator: Lennox, D. H.; Barts, E. W.; Batch, R. V.; Beyer, F. C.; Jorgensen, G. L.; Kelber, C. N. et al.
Item Type: Refine your search to only Report
open access

Stirling-Engine Thermodynamic Analysis: A Users Guide To SEAM1

Description: From Abstract: This report provides background and procedural information for the use of a general-purpose Stirling-engine analysis code developed at Argonne National Laboratory and available through the National Energy Software Center. Different engine configurations are easily specified, or the user may make use of provided data for existing engines, both kinematic and free piston. The code models heat transfer and fluid mechanics throughout the engine and accounts for system energy flows and… more
Date: September 1982
Creator: Heames, T. J.; Uherka, D. J.; Zabel, J. C & Daley, J. C.
Item Type: Refine your search to only Report
open access

Strategy for Experimental Validation of Waste Package Performance Assessment

Description: A strategy for the experimental validation of waste package performance assessment has been developed as part of a program supported by the Repository Technology Program. The strategy was developed by reviewing the results of laboratory analog experiments, in-situ tests, repository simulation tests, and material interaction tests. As a result of the review, a listing of dependent and independent variables that influence the ingress of water into the near-field environment, the reaction between … more
Date: January 1990
Creator: Bates, John K.; Abrajano, Teofilo Aniag; Wronkiewicz, D. J.; Gerding, Thomas J. & Seils, C. A.
Item Type: Refine your search to only Report
open access

Stress Corrosion Cracking of Candidate Waste Container Materials

Description: Six alloys have been selected as candidate container materials for the storage of high-level nuclear waste at the proposed Yucca Mountain site in Nevada. These materials are Type 304L stainless steel (SS), Type 316L SS, Incoloy 825, P-deoxidized Cu, Cu-30%Ni, and Cu-7%A1. The present program has been initiated to determine whether any of these materials can survive for 300 years in the site environment without developing through-wall stress corrosion cracks, and to assess the relative resistanc… more
Date: November 1990
Creator: Maiya, P. S.; Soppet, W. K.; Park, J. Y.; Kassner, T. F.; Shack, W. J. & Diercks, D. R.
Item Type: Refine your search to only Report
open access

Stress Corrosion Cracking of Candidate Waste Container Materials: Final Report

Description: Six alloys have been selected as candidate container materials for the storage of high-level nuclear waste at the proposed Yucca mountain site in Nevada. These materials are Type 304L stainless steel (SS). Type 316L SS, Incoloy 825, phosphorus-deoxidized Cu, Cu-30%Ni, and Cu-7%Al. The present program has been initiated to determine whether any of these materials can survive for 300 years in the site environment without developing through-wall stress corrosion cracks. and to assess the relative … more
Date: June 1992
Creator: Park, J. Y.; Malya, P. S.; Soppet, W. K.; Diercks, D. R.; Shack, W. J. & Kassner, T. F.
Item Type: Refine your search to only Report
open access

Studies of Acute and Chronic Radiation Injury at the Biological and Medical Research Division, Argonne National Laboratory, 1953-1970 : Description of Individual Studies, Data Files, Codes, and Summaries of Significant Findings

Description: Between 1953 and 1970, studies on the long-term effects of external x-ray and {gamma} irradiation on inbred and hybrid mouse stocks were carried out at the Biological and Medical Research Division, Argonne National Laboratory. The results of these studies, plus the mating, litter, and pre-experimental stock records, were routinely coded on IBM cards for statistical analysis and record maintenance.
Date: May 1994
Creator: Grahn, D.
Item Type: Refine your search to only Report
open access

Studies of Acute and Chronic Radiation Injury at the Biological and Medical Research Division, Argonne National Laboratory, 1970-1992 : the JANUS Program Survival and Pathology Data

Description: A research reactor for exclusive use in experimental radiobiology was designed and built at Argonne National Laboratory in the 1960`s. It was located in a special addition to Building 202, which housed the Division of Biological and Medical Research. Its location assured easy access for all users to the animal facilities, and it was also near the existing gamma-irradiation facilities. The water-cooled, heterogeneous 200-kW(th) reactor, named JANUS, became the focal point for a range of radiobio… more
Date: February 1995
Creator: Grahn, D.; Wright, B. J.; Carnes, B. A.; Williamson, F. S. & Fox, C.
Item Type: Refine your search to only Report
open access

Studies of Axial-Leakage Simulations for Homogeneous and Heterogeneous EBR-II Core Configurations

Description: When calculations of flux are done in less than three dimensions, leakage-absorption cross sections are normally used to model leakages (flows) in the dimensions for which the flux is not calculated. Since the neutron flux is axially dependent, the leakages, and hence the leakage-absorption cross sections, are also axially dependent. Therefore, to obtain axial flux profiles (or reaction rates) for individual subassemblies, an XY-geometry calculation delineating each subassembly has to be done a… more
Date: August 1985
Creator: Grimm, K. N. & Meneghetti, D.
Item Type: Refine your search to only Report
open access

Studies of Nuclear Waste Migration in Geologic Media, Annual Report: November 1976-October 1977

Description: Annual report of the Argonne National Laboratory Chemical Engineering Division regarding studies of nuclear waste migration in geologic media. This report discusses research regarding confinement of nuclear waste in geologic formations as a method of permanently disposing of the waste.
Date: March 1978
Creator: Argonne National Laboratory. Chemical Engineering Division.
Item Type: Refine your search to only Report
open access

Studies of Nuclear Waste Migration in Geologic Media, Annual Report: October 1978-September 1979

Description: Annual report of the Argonne National Laboratory Chemical Engineering Division regarding studies of nuclear waste migration in geologic media. This report discusses research regarding nuclide migration by fluid flow in rock.
Date: September 1979
Creator: Seitz, M. G.; Rickert, P. G.; Couture, R. A.; Williams, J.; Meldgin, N.; Fried, Sherman M. et al.
Item Type: Refine your search to only Report
open access

Studies of Unprotected Loss-of-Flow Accidents for the Clinch River Breeder Reactor

Description: Studies of unprotected loss-of-flow accidents in the CRBR for various rates of flow coast-down and with various options in the SAS 3A code did not lead to conditions for a violent disassembly. Maximum fuel temperatures using the SLUMPY module for disassembly were in the range 4000-4500 deg C. An approximate treatment of the LOF-driven TOP accident, not properly modeled by SAS 3A, indicates the possibility of some increase in accident severity. The effect of fission gas in dispersing fuel was no… more
Date: April 1976
Creator: Hummel, Harry H.; Pizzica, P. A. & Kalimullah
Item Type: Refine your search to only Report
open access

Study of Chromium-Free and Chromium-Reduced Steels

Description: The goal of this study was to develop an iron-based alloy, similar to Type 316 stainless steel in mechanical and corrosion properties but with a reduced chromium content or, ideally, no chromium. A total of twenty-six 225-g ingots and ten 2.5 to 12 kg ingots of various compositions in the Fe-Si-Mn-Ni-C system were prepared. All ingots contained from 5 to 11 w/o silicon and drew their corrosion resistance primarily from this component. The composition ranges of the remaining major alloying eleme… more
Date: May 1983
Creator: Wiencek, T. C. & Thresh, H. R.
Item Type: Refine your search to only Report
open access

Study of the State-of-the-Art of Instrumentation for Process Control and Safety in Large-Scale Coal Gasification, Liquefaction, and Fluidized-Bed Combustion Systems

Description: A study has been carried out to determine the state-of-the-art of instrumentation which is available for process control and safety in planned demonstration and commercial scale coal gasification, liquefaction, and fluidized-bed combustion systems. The study identified available instrumentation which will perform satisfactorily in these systems and pinpointed deficiencies for which instruments must be developed. The identified deficiencies fall into the same few categories for all processes con… more
Date: 1976
Creator: O'Fallon, N. M.; Beyerlein, R. A.; Managan, W. W.; Karplus, H. B. & Mulcahey, T. P.
Item Type: Refine your search to only Report
open access

A Study of the Transient Correction Factor Used in TREAT Reactor In-Pile Experiments

Description: The transient correction factor (TCF) is used in TREAT reactor experiments to predict the power calibration coefficient (PC) for prototype LMFBR fuel pins at transient conditions without subjecting the pins to a reactor transient. The TCF is defined as the fissions in a monitor wire per MW of reactor power at transient conditions divided by the fissions in a monitor wire per MW of reactor power at low power conditions. The power calibration factor is the power in the target fuel gram of Uranium… more
Date: 1978?
Creator: Graff, Dale L.
Item Type: Refine your search to only Report
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