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in creator/contributor: "Smith, D. L."

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Energy-differential cross section measurement for the /sup 51/V(n,. cap alpha. )/sup 48/Sc reaction

The activation method was used to measure cross sections for the /sup 51/V(n,..cap alpha..)/sup 48/Sc reaction in the threshold region, from 5.515 MeV up to 9.567 MeV. Twenty approximately-monoenergetic cross section values were obtained in this experiment. These data points span the energy region at roughly equal intervals. The experimental resolutions were in the range 0.153 to 0.233 MeV (FWHM). The present differential data cover approx. 50% of the total integral response of this reaction fo… more

Date: July 1984

Creator: Kanno, I.; Meadows, J. W. & Smith, D. L.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Liquid metal breeder-coolant blanket concept

This paper discusses the results and conclusions of a self-cooled, liquid-metal design for a D-T fusion reactor, which is part of the Blanket Comparison and Selection Study (BCSS). The effort reported in this paper emphasizes the inboard blanket of a tokamak since the problem is most severe in this region. The work on a self-cooled TMR is also reported.

Date: January 1, 1984

Creator: Sze, D. K.; Cha, Y. S.; Gohar, Y.; Majumdar, S.; Picologlou, P. & Smith, D. L.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Neutron inelastic scattering studies for lead-204. [Threshold energy to 10 MeV, transitions, cross sections, angular distributions]

A 9.57-g sample of lead metal, enriched to 99.7 percent /sup 204/Pb, was used in an investigation of neutron inelastic scattering from this rare isotope at the Argonne National Laboratory Fast-Neutron Generator Facility. Neutron excitation of the 66.9-m isomeric state at 2.186 MeV in /sup 204/Pb was measured from near threshold to approximately 10 MeV using activation techniques. Cross sections and a value for the isomeric half life were derived from these data. Time-of-flight techniques were e… more

Date: December 1, 1977

Creator: Smith, D. L. & Meadows, J. W.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Covariances for measured activation and fission ratios data

Methods which are routinely used in the determination of covariance matrices for both integral and differential activation and fission-ratios data acquired at the Argonne National Laboratory Fast-Neutron Generator Facility (FNG) are discussed. Special consideration is given to problems associated with the estimation of correlations between various identified sources of experimental error. Approximation methods which are commonly used to reduce the labor involved in this analysis to manageable l… more

Date: January 1, 1986

Creator: Smith, D. L.; Meadows, J. W. & Watanabe, Y.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

D-D tokamak reactor studies

A tokamak D-D reactor design, utilizing the advantages of a deuterium-fueled reactor but with parameters not unnecessarily extended from existing D-T designs, is presented. Studies leading to the choice of a design and initial studies of the design are described. The studies are in the areas of plasma engineering, first-wall/blanket/shield design, magnet design, and tritium/fuel/vacuum requirements. Conclusions concerning D-D tokamak reactors are stated.

Date: November 1, 1980

Creator: Evans Jr., K. E.; Baker, C. C.; Brooks, J. N.; Ehst, D. A.; Finn, P. A.; Jung, J. et al.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

The TEXTOR helium self-pumping experiment: Design, plans, and supporting ion-beam data on helium retention in nickel

A proof-of-principle experiment to demonstrate helium self-pumping in a tokamak is being undertaken in TEXTOR. The experiment will use a helium self-pumping module installed in a modified ALT-I limiter head. The module consists of two, {approximately}25 {times} 25 cm{sup 2} heated nickel alloy trapping plates, a nickel deposition filament array, and associated diagnostics. Between plasma shots a coating of {approximately}50 {angstrom} nickel will be deposited on the two trapping plates. During … more

Date: January 1, 1990

Creator: Brooks, J. N.; Krauss, A.; Mattas, R. F.; Smith, D. L.; Nygren, R. E.; Doyle, B. L. et al.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Generation of covariance data among values from a single set of experiments

Modern nuclear data evaluation methods demand detailed uncertainty information for all input results to be considered. It can be shown from basic statistical principles that provision of a covariance matrix for a set of data provides the necessary information for its proper consideration in the context of other included experimental data and/or a priori representations of the physical parameters in question. This paper examines how an experimenter should go about preparing the covariance matrix… more

Date: January 1, 1992

Creator: Smith, D. L.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Nonlinear optical absorption in intrinsic Stark effect superlattices

We have investigated the nonlinear optical properties of a new class of strained-layer superlattices, the intrinsic Stark effect superlattices (ISES). The superlattices consisted of GaInAs/GaAs grown along the (211)B direction. We observed a shift of the excitonic absorption to higher energies (blue shift) with increasing intensity of the transmitted beam. The observed optical nonlinearity was one order of magnitude stronger than the one due to excitonic screening in the (100) oriented referenc… more

Date: January 1, 1990

Creator: Laurich, B. K.; Smith, D. L.; Watkins, D. E.; Sela, I. (Los Alamos National Lab., NM (USA)); Kroemer, H. & Subbanna, S. (California Univ., Santa Barbara, CA (USA). Dept. of Electrical and Computer Engineering)

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Least-squares method for deriving reaction differential-cross-section information from measurements performed in diverse neutron fields

A generalized least-squares algorithm which refiens a prior multi-group energy-differential neutron-reaction cross-section evaluation by addition of new experimental data is described. Complete covariance information for the prior evaluation and for the new experimentla information is required in this procedure. The result is a revised best-estimate multi-group cross-section evaluation with complete covariance information. The algorithm tests the consistency of the ew and apriori information, a… more

Date: November 1, 1982

Creator: Smith, D. L.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Photoabsorption modulation in GaAs: Ga sub 1-x In sub x as strained-layer superlattices

Photoabsorption modulation measurements have been made on Ga{sub 1 {minus}x}In{sub x}As -- GaAs strained-layer superlattices using two approaches: In the first the modulating beam and the test beam have the same wavelength (near the exciton resonance). In the second, the modulation wavelength is much shorter than the test beam wavelength. A dramatic difference is observed in the modulated transmission spectra near the excitonic level for the two modulating wavelengths. The difference in behavio… more

Date: January 1, 1990

Creator: Sella, I.; Watkins, D. E.; Laurich, B. K.; Smith, D. L.; Subbanna, S. & Kroemer, H.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Vanadium-base alloys for fusion reactor applications

Vanadium-base alloys offer potentially significant advantages over other candidate alloys as a structural material for fusion reactor first wall/blanket applications. Although the data base is more limited than that for the other leading candidate structural materials, viz., austenitic and ferritic steels, vanadium-base alloys exhibit several properties that make them particularly attractive for the fusion reactor environment. This paper presents a review of the structural material requirements… more

Date: October 1, 1984

Creator: Smith, D. L.; Loomis, B. A. & Diercks, D. R.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Tokamak power systems studies, FY 1985

The Tokamak Power System Studies (TPSS) at ANL in FY-1985 were devoted to exploring innovative design concepts which have the potential for making substantial improvements in the tokamak as a commercial power reactor. Major objectives of this work included improved reactor economics, improved environmental and safety features, and the exploration of a wide range of reactor plant outputs with emphasis on reduced plant sizes compared to STARFIRE. The activities concentrated on three areas: plasma… more

Date: December 1985

Creator: Baker, C. C.; Brooks, J. N.; Ehst, D. A.; Smith, D. L. & Sze, D. K.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Modeling of liquid-metal corrosion/deposition in a fusion reactor blanket

A model has been developed for the investigation of the liquid-metal corrosion and the corrosion product transport in a liquid-metal-cooled fusion reactor blanket. The model describes the two-dimensional transport of wall material in the liquid-metal flow and is based on the following assumptions: (1) parallel flow in a straight circular tube; (2) transport of wall material perpendicular to the flow direction by diffusion and turbulent exchange; in flow direction by the flow motion only; (3) ma… more

Date: April 1, 1984

Creator: Malang, S. & Smith, D. L.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Mechanical Design and Thermal Hydraulic Considerations for Self-Cooled Lithium-Lead Blanket

Liquid lithium-lead eutectic alloy (17 at % Li-83 at % Pb, referred to herein as Li-Pb) is currently being considered as a candidate breeding material for fusion reactors. Some important considerations in the design of a Li-Pb blanket are compatibility with the structure, tritium containment and recovery, and safety. Additional design complexities arise because of the high density of Li-Pb, the relatively high melting temperature (235/sup 0/C), and the high tritium over-pressure associated with… more

Date: March 1, 1983

Creator: Misra, B.; Smith, D. L.; Burk, R. C. & Morgan, G. D.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Partitioning of hydrogen in the vanadium-lithium-hydrogen system at elevated temperatures

Equilibrium concentrations of hydrogen in vanadium-base alloys exposed to flowing lithium at temperatures from 350 to 550/degree/C in a forced-circulation loop were measured by residual gas analysis and the vacuum fusion method. Residual gas analysis and removal of material from the surface allowed a determination of the spatial hydrogen distribution in the alloys. These experimental results were compared with calculated thermodynamic distribution coefficients for hydrogen in the vanadium/lithi… more

Date: September 1, 1988

Creator: Hull, A. B.; Chopra, O. K.; Loomis, B. A. & Smith, D. L.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Microstructural examination of fast-neutron irradiated Li/sub 2/O

Scanning Electron Microscopy examinations of fast-neutron irradiated Li/sub 2/O at 608 to 625/sup 0/C to 1 and 3 at. % /sup 6/Li burnups have been performed. Of particular interests are the helium bubble morphologies and their relationships to the reported tritium/helium retentions and swelling in Li/sub 2/O. Possible defect trapping of tritium is suggested, along with discussions of two other phenomena (microcracking, swelling) on the performance of an Li/sub 2/O fusion reactor blanket.

Date: October 1, 1984

Creator: Liu, Y. Y.; Mattas, R. F.; Smith, D. L. & Porter, D. L.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Solvent recycle/recovery

This report describes Phase I of the Solvent Recycle/Recovery Task of the DOE Chlorinated Solvent Substitution Program for the US Air Force by the Idaho National Engineering Laboratory, EG G Idaho, Inc., through the US Department of Energy, Idaho Operations Office. The purpose of the task is to identify and test recovery and recycling technologies for proposed substitution solvents identified by the Biodegradable Solvent Substitution Program and the Alternative Solvents/Technologies for Paint S… more

Date: September 1, 1990

Creator: Paffhausen, M. W.; Smith, D. L. & Ugaki, S. N.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Swelling dependence of neutron-irradiated vanadium alloys on temperature, neutron fluence, and thermomechanical treatment

Swelling of vanadium alloys was determined after irradiation at 420 and 600{degree}C to neutron fluences ranging from 0.3 {times} 10{sup 27} neutrons/m{sup 2} (17 dpa) to 1.9 {times} 10{sup 27} neutrons/m{sup 2} (114 dpa). Binary and ternary vanadium alloys with Cr, Ti, Mo, W, Ni, Fe, Zr, and Si additions were irradiated in either the fully annealed, partially annealed, or 10% cold-worked condition. The addition of Cr to vanadium greatly exacerbated swelling of vanadium upon irradiation at 600{… more

Date: January 1, 1990

Creator: Loomis, B. A. & Smith, D. L.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Evaluation of liquid metal protection of a limiter/divertor in fusion reactors

The liquid metal protection concept is proposed mainly to prolong the lifetime of a divertor or a limiter in a fusion reactor. This attractive idea for protection requires studying a wide range of problems associated with the use of liquid-metals in fusion reactors. In this work the protection by liquid-metals has concentrated on predictions of the loss rate of the film to the plasma, the operating surface temperatures required for the film, and the potential tritium inventory requirement. The … more

Date: January 1, 1988

Creator: Hassanein, A. M. & Smith, D. L.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Nuclear data uncertainties: I, Basic concepts of probability

Some basic concepts of probability theory are presented from a nuclear-data perspective, in order to provide a foundation for thorough understanding of the role of uncertainties in nuclear data research. Topics included in this report are: events, event spaces, calculus of events, randomness, random variables, random-variable distributions, intuitive and axiomatic probability, calculus of probability, conditional probability and independence, probability distributions, binomial and multinomial … more

Date: December 1, 1988

Creator: Smith, D. L.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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ITER blanket and shield studies for high aspect ratio design option

The attractiveness of the high aspect ratio design (HARD) option for ITER has motivated a study to assess the blanket and shield design performance for this configuration relative to the ITER reference design. The blanket and shield have been configured to take an advantage of the HARD option. The layered solid breeder blanket concept with water-coolant and steel-structure and the water-steel shield have been used. The changes in the neutron wall loading distribution, the mechanical design, the… more

Date: January 1, 1991

Creator: Gohar, Y.; Attaya, H.; Billone, M.; Johnson, C.; Kopasz, J.; Majumdar, S. et al.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Swelling and tensile properties of neutron-irradiated vanadium alloys

Vanadium-base alloys are candidates for use as structural material in magnetic fusion reactors. In comparison to other candidate structural materials (e.g., Type 316 stainless and HT-9 ferritic steels), vanadium-base alloys such as V-15Cr-5Ti and V-20Ti have intrinsically lower long-term neutron activation, neutron irradiation after-heat, biological hazard potential, and neutron-induced helium and hydrogen transmutation rates. Moreover, vanadium-base alloys can withstand a higher surface-heat, … more

Date: July 1, 1990

Creator: Loomis, B. A. & Smith, D. L.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Conceptual Design of the INTOR First-Wall System

The design concept and performance characteristics of the first-wall design for the phase-1 INTOR (International Tokamak Reactor) study is described. The reference design consists of a water-cooled stainless steel panel. The major uncertainty regarding the performance of the bare stainless steel wall relates to the response of a thin-melt layer predicted to form on limited regions during a plasma disruption. A more-complex backup design, which incorporates radiatively cooled graphite tiles on t… more

Date: October 1, 1981

Creator: Smith, D. L.; Majumdar, S.; Mattas, R. F.; Turner, L.; Jung, J.; Abdou, M. A. et al.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Demonstration Tokamak Power Plant

A conceptual design for a tokamak demonstration power plant (DEMO) was developed. A large part of the study focused on examining the key issues and identifying the R and D needs for: (1) current drive for steady-state operation, (2) impurity control and exhaust, (3) tritium breeding blanket, and (4) reactor configuration and maintenance. Impurity control and exhaust will not be covered in this paper but is discussed in another paper in these proceedings, entitled Key Issues of FED/INTOR Impurit… more

Date: January 1, 1983

Creator: Abdou, M.; Baker, C.; Brooks, J.; Ehst, D.; Mattas, R.; Smith, D. L. et al.

Item Type: Article

Partner: UNT Libraries Government Documents Department