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

Description: 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.
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Partner: UNT Libraries Government Documents Department
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Compilation and evaluation of 14-MeV neutron-activation cross sections for nuclear technology applications. Set I

Description: Available 14-MeV experimental neutron activation cross sections are compiled and evaluated for the following reactions of interest for nuclear-energy technology applications: /sup 27/Al(n,p)/sup 27/Mg, Si(n,X)/sup 28/Al, Ti(n,X)/sup 46/Sc, Ti(n,X)/sup 47/Sc, Ti(n,X)/sup 48/Sc, /sup 51/V(n,p)/sup 51/Ti, /sup 51/V(n,..cap alpha..)/sup 48/Sc, Cr(n,X)/sup 52/V, /sup 55/Mn(n,..cap alpha..)/sup 52/V, /sup 55/Mn(n,2n)/sup 54/Mn, Fe(n,X)/sup 54/Mn, /sup 54/Fe(n,..cap alpha..)/sup 51/Cr, /sup 59/Co(n,p)… more
Date: April 1, 1985
Creator: Evain, B. P.; Smith, D. L. & Lucchese, P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Evaluation of liquid metal protection of a limiter/divertor in fusion reactors

Description: 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: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Nuclear data uncertainties: I, Basic concepts of probability

Description: 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: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Low-cycle fatigue behavior of HT-9 alloy in a flowing-lithium environment

Description: Low-cycle fatigue data have been obtained on normalized/tempered or lithium-preexposed HT-9 alloy at 755 K in flowing lithium of controlled purity. The results show that the fatigue life of this material decreases with an increase in nitrogen content in lithium. A reduction in strain rate also decreases the fatigue life in high-nitrogen lithium. However, in the range from approx. 4 x 10/sup -4/ to 4 x 10/sup -2/ s/sup -1/, the strain rate has no effect on fatigue life in lithium containing <200… more
Date: June 1, 1983
Creator: Chopra, O. K. & Smith, D. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Influence of a flowing-lithium environment on the fatigue and tensile properties of Type 316 stainless steel

Description: Low-cycle fatigue and tensile data have been obtained on Type 316 stainless steel in a flowing lithium environment of controlled purity. The results show that the fatigue life of the steel in flowing lithium at 755 K is greater than in air. Preexposure of the material to lithium reduces fatigue life. The reduction in fatigue life may be attributed to the formation of a weak ferrite layer after lithium exposure. Tensile data for cold-worked Type 316 stainless steel indicate that at temperatures … more
Date: September 1, 1983
Creator: Chopra, O. K. & Smith, D. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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STARFIRE-II studies. Summary. [Reactor parameters]

Description: The US Department of Energy's Office of Fusion Energy has initiated several studies during FY-1985 called Tokamak Power System Studies (TPSS). The TPSS is being carried out by several laboratories, universities and industry with the general objective of developing innovative physics and technology concepts to improve the commercial attractiveness of tokamak power reactors. The effort of Argonne National Laboratory, entitled STARFIRE-II, is an effort to update and improve STARFIRE, which was the… more
Date: January 1, 1985
Creator: Baker, C. C.; Brooks, J. N.; Ehst, D. A.; Smith, D. L. & Sze, D. K.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Compatibility of ferritic steels with sintered Li/sub 2/O pellets in a flowing-helium environment

Description: The compatibility of ferritic HT-9 alloy and Fe-9Cr-1Mo steel with Li/sub 2/O pellets has been investigated at 823 K (550/sup 0/C) in flowing helium containing 93 or 1 ppM H/sub 2/O and 1 ppM H/sub 2/. The results indicate that the alloy specimens gain weight whereas the Li/sub 2/O pellets lose weight after exposure. There is a net loss in weight of the total reaction couple. Both steels develop an iron-rich outer scale and chromium-rich subscale. The reaction rates in helium containing 93 ppM … more
Date: January 1, 1983
Creator: Chopra, O. K.; Kurasawa, T. & Smith, D. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Experimental method for investigating helium effects in irradiated vanadium

Description: Analyses have been performed which indicate that an effective method for experimentally investigating helium effects in neutron irradiated vanadium base alloys can be developed. The experimental procedure involves only modest modifications to existing procedures currently used for irradiation testing of vanadium-base alloys in the FFTF reactor. Helium is generated in the vanadium alloy by decay of tritium which is either preinjected or generated within the test capsule. Calculations indicate th… more
Date: October 1, 1987
Creator: Smith, D. L.; Matsui, H.; Greenwood, L. & Loomis, B.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Fast-neutron-spectrum measurements for the thick-target /sup 9/Be(d,n)/sup 10/B reaction at E/sub d/ = 7 MeV

Description: Spectra of neutrons with energies greater than or equal to 800 keV which are emitted from a metallic beryllium target that is thick enough to completely stop 7-MeV incident deuterons are measured using organic scintillators and the pulse-beam time-of-flight method. Data are acquired for twenty different emission angles in the laboratory over the range 0 to 155 degrees. The resulting information on the energy-angle detail of neutron emission is then employed in calculations which are performed i… more
Date: April 1, 1985
Creator: Smith, D. L.; Meadows, J. W. & Guenther, P. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Application of high temperature ceramic superconductors (CSC) to commercial tokamak reactors

Description: Ceramic superconductors operating near liquid nitrogen temperature may experience higher heating rates without losing stability, compared to conventional superconductors. This will permit cable design with less stabilizer, reducing fabrication costs for large fusion magnets. Magnet performance is studied for different operating current densities in the superconductor, and cost benefits to commercial tokamak reactors are estimated. It appears that 10 kA . cm/sup -2/ (at 77 K and approx.10 T) is … more
Date: October 1, 1987
Creator: Ehst, D. A.; Kim, S.; Gohar, Y.; Turner, L.; Smith, D. L. & Mattas, R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Strength, ductility, and ductile-brittle transition temperature for MFR (magnetic fusion reactor) candidate vanadium alloys

Description: The dependence of the yield strength, tensile strength, elongation, and reduction in area on temperature for the V-15Ti-7.5Cr, V-20Ti, V-15Cr-5Ti, V-12Cr-5Ti, V-10Cr-5Ti, and V-3Ti-1Si alloys was determined from tensile tests at temperatures ranging from 25 to 700/sup 0/C. The strength of the alloys increased with an increase of the combined Cr and Ti concentration. The total elongation for the alloys ranged between 20% and 38%. The reduction in area ranged from 30% to 90%. The DBTT, which was … more
Date: September 1, 1987
Creator: Loomis, B. A.; Lee, R. H.; Smith, D. L. & Peterson, J. R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Stress-corrosion cracking susceptibility of V-15Cr-5Ti in pressurized water at 288/sup 0/C

Description: The stress-corrosion cracking susceptibility of V-15Cr-5Ti in pressurized water at 288/sup 0/C has been evaluated by means of constant extension rate tensile (CERT) tests in a refreshed autoclave system. The test environments included high-purity water as well as water containing SO/sub 4//sup 2 -/ and NO/sub 3//sup -/ impurities at a concentration of 10 wppM. Strain rates from 1 x 10/sup -6/ to 5 x 10/sup -8/ s/sup -1/ were employed, and dissolved oxygen levels ranged from <0.005 to 7.9 wppM. … more
Date: July 1, 1987
Creator: Diercks, D. R. & Smith, D. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Investigation of the influence of the neutron spectrum in determinations of integral cross-section ratios

Description: Ratio measurements are routinely employed in studies of neutron interaction processes in order to generate new differential cross-section data or to test existing differential cross-section information through examination of the corresponding response in integral neutron spectra. Interpretation of such data requires that careful attention be given to details of the neutron spectra involved in these measurements. Two specific tasks are undertaken in the present investigation: (1) Using perturbat… more
Date: November 1, 1987
Creator: Smith, D. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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INTOR first wall/blanket/shield activity

Description: The main emphasis of the INTOR first wall/blanket/shield (FWBS) during this period has been upon the tritium breeding issues. The objective is to develop a FWBS concept which produces the tritium requirement for INTOR operation and uses a small fraction of the first wall surface area. The FWBS is constrained by the dimensions of the reference design and the protection criteria required for different reactor components. The blanket extrapolation to commercial power reactor conditions and the pro… more
Date: January 1, 1986
Creator: Gohar, Y.; Billone, M. C.; Cha, Y. S.; Finn, P. A.; Hassanein, A. M.; Liu, Y. Y. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Conceptual Design of the INTOR First-Wall System

Description: 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: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Measurement and evaluation of selected 14-MeV neutron cross sections for fusion

Description: Experimental neutron-activation cross-section data in the vicinity of 14 MeV are evaluated for several reactions of fusion-related interest using a least-squares method. New experimental measurements are performed at 14.7 MeV for all of these considered reactions and for some commonly-used standard reactions as well. Comparison is made between measured and evaluated results.
Date: January 1, 1985
Creator: Meadows, J. W.; Smith, D. L. & Cox, S. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Demonstration Tokamak Power Plant

Description: 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: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Influence of temperature and lithium purity on corrosion of ferrous alloys in a flowing lithium environment

Description: Corrosion data have been obtained on ferritic HT-9 and Fe-9Cr-1Mo steel and austenitic Type 316 stainless steel in a flowing lithium environment at temperatures between 372 and 538/sup 0/C. The corrosion behavior is evaluated by measurements of weight loss as a function of time and temperature. A metallographic characterization of materials exposed to a flowing lithium environment is presented.
Date: March 1, 1986
Creator: Chopra, O. K. & Smith, D. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Fast-neutron interaction with niobium

Description: Results of a comprehensive study of the interaction of fast neutrons with niobium are presented, including measurement and interpretation of neutron total, differential-scattering and radiative-capture cross sections. The experimental results are interpreted in the context of the optical-statistical model, with attention to the Fermi-surface anomaly. Experimental results, physical interpretations and rigorous statistical methods are used to provide a comprehensive evaluated nuclear data file su… more
Date: January 1, 1985
Creator: Smith, A. B.; Guenther, P. T.; Poenitz, W. P.; Smith, D. L.; Whalen, J. F. & Howerton, R. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Evaluated nuclear-data file for niobium

Description: A comprehensive evaluated nuclear-data file for elemental niobium is provided in the ENDF/B format. This file, extending over the energy range 10/sup -11/-20 MeV, is suitable for comprehensive neutronic calculations, particulary those dealing with fusion-energy systems. It also provides dosimetry information. Attention is given to the internal consistancy of the file, energy balance, and the quantitative specification of uncertainties. Comparisons are made with experimental data and previous ev… more
Date: March 1, 1985
Creator: Smith, A. B.; Smith, D. L. & Howerton, R. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Low technology high tritium breeding blanket concept

Description: The main function of this low technology blanket is to produce the necessary tritium for INTOR operation with minimum first wall coverage. The INTOR first wall, blanket, and shield are constrained by the dimensions of the reference design and the protection criteria required for different reactor components and dose equivalent after shutdown in the reactor hall. It is assumed that the blanket operation at commercial power reactor conditions and the proper temperature for power generation can be… more
Date: October 1, 1987
Creator: Gohar, Y.; Baker, C. C.; Smith, D. L.; Billone, M. C.; Cha, Y. S.; Clemmer, R. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Status of fusion reactor blanket design

Description: The recent Blanket Comparison and Selection Study (BCSS), which was a comprehensive evaluation of fusion reactor blanket design and the status of blanket technology, serves as an excellent basis for further development of blanket technology. This study provided an evaluation of over 130 blanket concepts for the reference case of electric power producing, DT fueled reactors in both Tokamak and Tandem Mirror (TMR) configurations. Based on a specific set of reactor operating parameters, the curren… more
Date: February 1, 1986
Creator: Smith, D. L. & Sze, D. K.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Low activation materials for fusion

Description: The viability of fusion as a future energy source may eventually be determined by safety and environmental factors. Control of the induced radioactivity characteristics of the materials used in the first wall and blanket could have a major favorable impact on these issues. In the United States, materials program efforts are focused on developing new structural alloys with radioactive decay characteristics which would greatly simplify long-term waste disposal of reactor components. A range of al… more
Date: January 1, 1988
Creator: Rowcliffe, A. F.; Bloom, E. E.; Doran, D. G.; Smith, D. L. & Reuther, T. C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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