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in subjects: "Materials Testing"

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Arctic Energy Technology Development Laboratory (Part 3)

Various laboratory tests were carried at the R & D facility of BJ Services in Tomball, TX with BJ Services staff to predict and evaluate the performance of the Ceramicrete slurry for its effective use in permafrost cementing operations. Although other standards such as those of the American Standard for Testing Materials (ASTM) and Construction Specification Institute (CSI) exist, all these tests were standardized by the API. A summary of the tests traditionally used in the cement slurry design… more

Date: December 31, 2008

Creator: 960443, See OSTI ID Number

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Testing Miller Wavelength Scaling of the Second-Order Nonlinear Coefficients of KNbO{sub 3}, KTiOPO{sub 4}, KTiOAsO{sub 4}, LiNbO{sub 3}, LiIO{sub 3}, B-BaB{sub 2}O{sub 4}, KH{sub 2}OP{sub 4}, and LiB{sub 3}O{sub 5}

No Description Available.

Date: October 20, 2000

Creator: ALFORD,WILLIAM J. & SMITH,ARLEE V.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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TCT hybrid preconceptual blanket design studies

The conceptual design of a tokamak fusion-fission (hybrid) reactor, which produces electric power and fissile material, has been performed in a cooperative effort between Princeton's Plasma Physics Laboratory (PPPL) and Battelle's Pacific Northwest Laboratories (PNL). PPPL, who had overall project lead responsibility, designed the fusion driver system. Its core consists of a tokamak plasma maintained in the two-component torus (TCT) mode by both D and T beams and having a single null poloidal d… more

Date: January 1, 1978

Creator: Aase, D. T.; Bampton, M. C. C.; Doherty, T. J.; Leonard, B. R.; McCann, R. A.; Newman, D. F. et al.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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NOVEL GAS CLEANING/CONDITIONING FOR INTEGRATED GASIFICATION COMBINED CYCLE

The objective of this program is to develop and evaluate novel sorbents for the Siemens Westinghouse Power Company's (SWPC's) ''Ultra-Clean Gas Cleaning Process'' for reducing to near-zero levels the sulfur- and chlorine-containing gas emissions and fine particulate matter (PM2.5) caused by fuel bound constituents found in carbonaceous materials, which are processed in Integrated Gasification Combined Cycle (IGCC) technologies.

Date: July 1, 2001

Creator: Abbasian, Javad

Item Type: Report

Partner: UNT Libraries Government Documents Department

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FINESSE: study of the issues, experiments and facilities for fusion nuclear technology research and development. Interim report. Volume II

The Nuclear Fusion Issues chapter contains a comprehensive list of engineering issues for fusion reactor nuclear components. The list explicitly defines the uncertainties associated with the engineering option of a fusion reactor and addresses the potential consequences resulting from each issue. The next chapter identifies the fusion nuclear technology testing needs up to the engineering demonstration stage. (MOW)

Date: October 1, 1984

Creator: Abdou, M.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Important aspects of radiation shielding for fusion reactor tokamaks

Radiation shielding is a key subsystem in tokamak reactors. Design of this shield must evolve from economic and technological trade-off studies that account for the strong interrelations among the various components of the reactor system. These trade-offs are examined for the bulk shield on the inner side of the torus and for the special shields of major penetrations. Results derived are applicable for a large class of tokamak-type reactors.

Date: April 30, 1977

Creator: Abdou, M. A.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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INTOR Impurity Control and First Wall System

The highlights of the recent INTOR effort on examining the key issues of the impurity control/first wall system are summarized. The emphasis of the work was an integrated study of the edge-region physics, plasma-wall interaction, materials, engineering and magnetic considerations associated with the poloidal divertor and pump limiter. The development of limiter and divertor collector plate designs with an acceptable lifetime was a major part of the work.

Date: April 1, 1983

Creator: Abdou, M. A.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Key Issues of FED/INTOR Impurity Control System

A key part of the FED/INTOR activity over the past year has focused on examining the critical issues and developing credible physics and engineering solutions for the impurity control system. The primary emphasis of the work was on the edge-region physics, plasma-wall interaction, materials, engineering and magnetic considerations of the poloidal divertor and pump limiter.

Date: October 1, 1982

Creator: Abdou, M. A.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Tritium Breeding in Fusion Reactors

Key technological problems that influence tritium breeding in fusion blankets are reviewed. The breeding potential of candidate materials is evaluated and compared to the tritium breeding requirements. The sensitivity of tritium breeding to design and nuclear data parameters is reviewed. A framework for an integrated approach to improve tritium breeding prediction is discussed with emphasis on nuclear data requirements.

Date: October 1, 1982

Creator: Abdou, M. A.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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MACK/MACKLIB System for Nuclear Response Functions

The MACK computer program calculates energy pointwise and multigroup nuclear response functions from basic nuclear data in ENDF/B format. The new version of the program MACK-IV, incorporates major developments and improvements aimed at maximizing the utilization of available nuclear data and ensuring energy conservation in nuclear heating calculations. A new library, MACKLIB-IV, of nuclear response functions was generated in the CTR energy group structure of 171 neutron groups and 36 gamma grou… more

Date: March 15, 1978

Creator: Abdou, M. A. & Gohar, Y. M.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Magnetic Fusion Energy Plasma Interactive and High Heat Flux Components. Volume II. Technical Assessment of the Critical Issues and Problem Areas in High Heat Flux Materials and Component Development

A technical assessment of the critical issues and problem areas for high heat flux materials and components (HHFMC) in magnetic fusion devices shows these problems to be of critical importance for the successful operation of near-term fusion experiments and for the feasibility and attractiveness of long-term fusion reactors. A number of subgroups were formed to assess the critical HHFMC issues along the following major lines: (1) source conditions, (2) systems integration, (3) materials and pro… more

Date: June 1, 1984

Creator: Abdou, M. A.; Boyd, R. D.; Easor, J. R.; Gauster, W. B.; Gordon, J. D.; Mattas, R. F. et al.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Shielding and Maintainability in an Experimental Tokamak

This paper presents the results of an attempt to develop an understanding of the various factors involved. This work was performed as a part of the task assigned to one of the expert groups on the International Tokamak Reactor (INTOR). However, the results of this investigation are believed to be generally applicable to the broad class of the next generation of experimental tokamak facilities such as ETF. The shielding penalties for requiring personnel access are quantified. This is followed by… more

Date: January 1, 1979

Creator: Abdou, M. A.; Fuller, G.; Hager, E. R. & Vogelsang, W. F.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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MACK-IV, a new version of MACK: a program to calculate nuclear response functions from data in ENDF/B format

MACK-IV calculates nuclear response functions important to the neutronics analysis of nuclear and fusion systems. A central part of the code deals with the calculation of the nuclear response function for nuclear heating more commonly known as the kerma factor. Pointwise and multigroup neutron kerma factors, individual reactions, helium, hydrogen, and tritium production response functions are calculated from any basic nuclear data library in ENDF/B format. The program processes all reactions in… more

Date: July 1, 1978

Creator: Abdou, M. A.; Gohar, Y. & Wright, R. Q.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Important material considerations in INTOR

A number of important material-related problems were identified and analyzed during the Phase-I study for INTOR. The first wall and divertor collector plate are subjected to severe normal and off-normal conditions. A melt layer is predicted to develop in a bare stainless steel wall under plasma disruptions. Graphite tiles will not melt but they introduce other serious uncertainties into the design. The design strategy for the divertor collector plate focused on separating the surface and high h… more

Date: January 1, 1981

Creator: Abdou, M. A.; Mattas, R. F. & Smith, D. L.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Limiter/Vacuum System for Plasma Impurity Control and Exhaust in Tokamaks

A detailed design of a limiter/vacuum system for plasma impurity control and exhaust has been developed for the STARFIRE tokamak power plant. It is shown that the limiter/vacuum concept is a very attractive option for power reactors. It is relatively simple and inexpensive and deserves serious experimental verification.

Date: January 1, 1980

Creator: Abdou, M.; Brooks, J. & Mattas, R.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Scintillating glass fiber neutron sensors: 1, Production and optical characterization

The production and optical characterization of cerium-doped lithium silicate scintillating fibers used as thermal neutron detectors are discussed. The bulk glass continuing enriched {sup 6}Li is produced starting from high-purity commercial materials which are further purified at Pacific Northwest Laboratory (PNL). The fibers are drawn at PNL in a hot down-draw process. The fibers are coated with a silicone polymer that serves as both an optical cladding and a physical buffer coat. Optical char… more

Date: October 1, 1993

Creator: Abel, K. H.; Arthur, R. J. & Bliss, M.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Plated-through hole testing. Final repot

An improved microresistance testing method to measure the thickness of copper plating in plated-through holes of double-sided printed wiring boards is presented. A new probe design, combined with a microprocessor controller, makes it possible for a direct reading tester to provide variables data. Tester design and software programs for the system are included. Results of correlation studies, comparing the improved resistance method to cross-sectional measurements are presented. Limitations on t… more

Date: May 1, 1980

Creator: Abel, W.B.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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The design and performance of the research reactor fuel counter

This paper describes the design features, hardware specifications, and performance characteristics of the Research Reactor Fuel Counter (RRFC) System. The system is an active mode neutron coincidence counter intended to assay material test reactor fuel assemblies under water. The RRFC contains 12 {sup 3}He tubes, each with its own preamplifier, and a single ion chamber. The neutron counting electronics are based on the Los Alamos Portable Shift Register (PSR) and the gamma readout is a manual-r… more

Date: September 1, 1996

Creator: Abhold, M. E.; Hsue, S. T.; Menlove, H. O.; Walton, G. & Holt, S.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Corrosion testing of stainless steel-zirconium metal waste form.

Stainless steel-zirconium (SS-Zr) alloys are being considered as waste forms for the disposition of metallic waste generated during the electrometallurgical treatment of spent nuclear fuel. The waste forms contain irradiated cladding hulls, components of the alloy fuel, noble metal fission products, and actinide elements. The baseline waste form is a stainless steel-15 wt% zirconium (SS-15Zr) alloy. This article presents microstructure and some of the corrosion studies being conducted on the wa… more

Date: December 14, 1998

Creator: Abraham, D. P.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Diffusion of gases in solids: rare gas diffusion in solids; tritium diffusion in fission and fusion reactor metals. Final report

Major results of tritium and rare gas diffusion research conducted under the contract are summarized. The materials studied were austenitic stainless steels, Zircaloy, and niobium. In all three of the metal systems investigated, tritium release rates were found to be inhibited by surface oxide films. The effective diffusion coefficients that control tritium release from surface films on Zircaloy and niobium were determined to be eight to ten orders of magnitude lower than the bulk diffusion coe… more

Date: September 1, 1976

Creator: Abraham, P. M.; Chandra, D.; Mintz, J. M.; Elleman, T. S. & Verghese, K.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Stress corrosion cracking tests on high-level-waste container materials in simulated tuff repository environments

Types 304L, 316L, and 321 austenitic stainless steel and Incoloy 825 are being considered as candidate container materials for emplacing high-level waste in a tuff repository. The stress corrosion cracking susceptibility of these materials under simulated tuff repository conditions was evaluated by using the notched C-ring method. The tests were conducted in boiling synthetic groundwater as well as in the steam/air phase above the boiling solutions. All specimens were in contact with crushed To… more

Date: June 1, 1986

Creator: Abraham, T.; Jain, H. & Soo, P.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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K-Basin spent nuclear fuel characterization data report 2

An Integrated Process Strategy has been developed to package, condition, transport, and store in an interim storage facility the spent nuclear fuel (SNF) currently residing in the K-Basins at Hanford. Information required to support the development of the condition process and to support the safety analyses must be obtained from characterization testing activities conducted on fuel samples from the Basins. Some of the information obtained in the testing was reported in PNL-10778, K-Basin Spent … more

Date: March 1, 1996

Creator: Abrefah, J.; Gray, W.J.; Ketner, G.L.; Marschman, S.C.; Pyecha, T.D. & Thornton, T.A.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Analysis of Ignition Testing on K-West Basin Fuel

Approximately 2100 metric tons of spent nuclear fuel (SNF) discharged from the N-Reactor have been stored underwater at the K-Basins in the 100 Area of the Hanford Site. The spent fuel has been stored in the K-East Basin since 1975 and in the K-West Basin since 1981. Some of the SNF elements in these basins have corroded because of various breaches in the Zircaloy cladding that occurred during fuel discharge operations and/or subsequent handling and storage in the basins. Consequently, radioact… more

Date: August 10, 1999

Creator: Abrefah, J.; Huang, F.H.; Gerry, W.M.; Gray, W.J.; Marschman, S.C. & Thornton, T.A.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Polycube Oxidation and Factors Affecting the Concentrations of Gaseous Products

The degraded polycube samples were tested in air and argon/oxygen atmospheres to determine the effect of size increase on the flammable gases concentrations. Within the size range tested, the flammable gas generation rate increases with increasing size but the extrapolation of the data to actual processing polycube size yielded flammable gas species concentration in the off-gas stream below the lower flammable limit of all the major gas species identified. Extreme surface area increase with a p… more

Date: April 4, 2000

Creator: Abrefah, John; MacFarlan, Paul J. & Sell, Rachel L.

Item Type: Text

Partner: UNT Libraries Government Documents Department