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Perkins, H.K.; Noda, T.
Princeton Univ., N.J. (USA). Dept. of Chemical Engineering1976
Princeton Univ., N.J. (USA). Dept. of Chemical Engineering1976
AbstractAbstract
[en] The permeation rate of D2 through 304 and 304L stainless steel for driving pressures 10-5 to 10-1 Pa (10-7 to 10-3 torr) were measured over the temperature range 650 to 10500K. Two 51 mu m and one 127 mu m, 304 samples and one 127 mu m, electropolished 304L sample were studied. The steady-state permeation rate varied linearly with p/sup 1/2/ in the 10-2 to 10-1 Pa range but had a higher dependence below 10-3 Pa. The steady-state and transient data at 10-1 Pa were used to calculate the permeability phi = 1.9 x 1015 exp (-6300 T-10K) molecules D2 cm-1 sec-1 Pa/-1/2/ and the diffusion coefficient D = 3.5 x 10-4 exp (-5100 T-10K) cm2 sec-1. The processes involved in permeation are discussed and time-dependent formulae for the permeation rate are given for a number of simple cases. Following thermal permeation experiments, permeation rates resulting from bombardment with a 10 mu amp, 15 keV deuteron beam were measured. A high transient permeation rate was observed which is attributed to a surface impedance to reemission which decreases under bombardment
Primary Subject
Source
1976; 64 p; Available from NTIS. $4.50.
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Report
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ALLOYS, CARBON ADDITIONS, CHROMIUM ALLOYS, CHROMIUM STEELS, CHROMIUM-NICKEL STEELS, CORROSION RESISTANT ALLOYS, ENERGY RANGE, HEAT RESISTING ALLOYS, HYDROGEN ISOTOPES, IRON ALLOYS, IRON BASE ALLOYS, ISOTOPES, KEV RANGE, LIGHT NUCLEI, NICKEL ALLOYS, NUCLEI, ODD-ODD NUCLEI, STABLE ISOTOPES, STAINLESS STEELS, STEELS, TRANSITION ELEMENT ALLOYS
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AbstractAbstract
[en] The Fe-Cr-Mn austenitic alloy system is being studied as a replacemnet of the Fe-Cr-Ni system for fusion applications in which reduced long-term radioactivation is an important consideration. This paper describes two aspects of the respone of this alloy system to material and environmental variables. First, the neutron-induced void swelling of simple binary and ternary alloys is investigated as a function of composition, thermal-mechanical treatment, temperature (693 to 873K) and displacement level (9 to 76 dpa). The swelling rate of this alloy system approaches 1%/dpa for those conditions which do not favor formation of large levels of ferrite phases. Second, the tendency of the potentially detrimental sigma phase to form during thermal aging is explored at high manganese levels. Variables such as carbon concentration, cold-work level and aging time are shown to influence the distribution and rate of sigma formation. 18 refs., 10 figs., 1 tab
Primary Subject
Source
Sep 1987; 20 p; 3. international conference on fusion reactor materials; Karlsruhe (Germany, F.R.); 4-8 Oct 1987; CONF-871036--29; Available from NTIS, PC A03/MF A01; 1 as DE88003415; Portions of this document are illegible in microfiche products.
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Report
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Axtmann, R.C.; Perkins, H.K.; Noda, T.; Fish, J.D.
Princeton Univ., N.J. (USA). Dept. of Chemical Engineering1976
Princeton Univ., N.J. (USA). Dept. of Chemical Engineering1976
AbstractAbstract
[en] Two investigations are described that are pertinent to hydrogen hold-up and re-emission in the first wall of fusion reactors. The first employs existing theory to calculate the range distributions for light ions normally incident on metallic targets at energies of one to 20 keV. Three different statistical atomic potentials were used to approximate the interaction between a swift atom and a target atom. A surface correction to the theory of ion penetration was developed to account for the presence of a free surface in the target. The second study employed the diffusion equation to calculate the time dependent fluxes and concentration profiles of a gas originating at a planar source within a finite slab. The purpose of this procedure was to model the transport of gas implanted beneath a metal surface by the impingement of energetic, gaseous ions. Some studies on radiolytic fuel production are briefly reviewed
Original Title
Hydrogen permeation through first wall, radiolytic fuel production
Primary Subject
Source
1976; 6 p; Available from NTIS. $3.50.
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Report
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Progress Report
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AbstractAbstract
[en] The effects of fusion neutron spectrum and fluence on the evaluation of transmutation and induced radioactivity of candidate reduced and/or low activation materials such as 9Cr-2W ferritic steel, V-5Cr-5Ti and SiCf/SiC composite have been examined by simulation calculations using structural models based on ITER design. The transmutations from W to Re and Os in the ferritic steel and from V to Cr in the V alloy were predicted to considerably occur depending on thermal neutron fluxes mainly determined by the composition of blanket/shields while induced radioactivity decay behaviours are not appreciably affected by the spectrum change of fusion neutrons. The acceptable concentrations of impurities such as Mo, Nb and Tb for waste disposal and hands-on recycling have been more restricted with increasing fluence because of the accumulation of nuclides controlling the radioactivity. In the effort of manufacturing high-purity materials, fused-salt electrolysis for vanadium and chemical vapor infiltration for SiCf/SiC composite have been shown to be potential processes to obtain purified materials satisfying the low activation criteria. (orig.)
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7. international conference on fusion reactor materials (ICFRM-7); Obninsk (Russian Federation); 25-29 Sep 1995
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Journal Article
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ACTIVATION ANALYSIS, CHROMIUM ALLOYS, COMPOSITE MATERIALS, ELECTROLYSIS, FERRITIC STEELS, ITER TOKAMAK, NEUTRON FLUX, NEUTRON SPECTRA, RADIOACTIVE WASTE DISPOSAL, RADIOACTIVE WASTE PROCESSING, RADIOACTIVITY, RADIOISOTOPES, RECYCLING, SILICON CARBIDES, THERMONUCLEAR REACTOR MATERIALS, TITANIUM ALLOYS, TRANSMUTATION, VANADIUM ALLOYS
ALLOYS, CARBIDES, CARBON ADDITIONS, CARBON COMPOUNDS, CHEMICAL ANALYSIS, CLOSED PLASMA DEVICES, IRON ALLOYS, IRON BASE ALLOYS, ISOTOPES, MANAGEMENT, MATERIALS, NONDESTRUCTIVE ANALYSIS, RADIATION FLUX, SILICON COMPOUNDS, SPECTRA, STEELS, THERMONUCLEAR DEVICES, THERMONUCLEAR REACTORS, TOKAMAK DEVICES, TOKAMAK TYPE REACTORS, TRANSITION ELEMENT ALLOYS, WASTE DISPOSAL, WASTE MANAGEMENT, WASTE PROCESSING
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AbstractAbstract
[en] Published in summary form only
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Secondary Subject
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Japan Atomic Energy Research Inst., Tokyo (Japan); 346 p; Mar 1989; p. 195-199; JAERI symposium on high energy neutron source for material research and development; Tokyo (Japan); 12-13 Jan 1989
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Miscellaneous
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AbstractAbstract
No abstract available
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Journal Article
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Progress Report
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Nuclear Science and Engineering; v. 41 p. 299-303
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AbstractAbstract
[en] The effects of exposure to helium containing oxygen of 0.1-115 vpm at 10000C on the mechanical properties of molybdenum and TZM-Mo alloy at room temperature were studied. The stress-relieved molybdenum specimen which was not recrystallized at test temperature showed the ductility after exposure to helium containing oxygen. The recrystallized molybdenum and TZM lost ductility after exposure to helium containing oxygen of 0.1-13 vpm in a few hours. The embrittlement of molybdenum was considered to be due to the grain boundary weakening. Molybdenum to which carbon was added seemed to hinder the grain boundary weakening by the oxygen contamination. Both stress-relieved and recrystallized TZM specimens picked up oxygen linearly with time of exposure to helium. The increase in oxygen content of TZM, which was considered to be caused by the internal oxidation of titanium and zirconium, results in the embrittlement of TZM. (orig.)
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Journal Article
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Journal of Nuclear Materials; ISSN 0022-3115; ; v. 91(1); p. 103-116
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Noda, T.; Takeuchi, T.; Fujita, M., E-mail: noda.tetsuji@nims.go.jp2004
AbstractAbstract
[en] The induced activity and compositional change of several superconducting materials such as Nb-based alloys, V-based alloys and MgB2 have been evaluated with a numerical calculation. We assume that the materials are irradiated for 10 MW a/m2 at the magnet of the inboard position of a tokamak-type fusion reactor with a neutron wall loading of 1 MW/m2. The materials are Nb3Sn, Nb3Al, NbTi, NbZr, V2Zr, V2(Zr,Hf), V3Ga, V3Si and MgB2. Most of the induced activity of V-based alloys and MgB2 after the shutdown of the reactor is controlled by the 60Co formed from Cu. After the irradiation, the dose rate decreases to a safe level of 10 μSv/h within 30 years. However, Nb-based alloys are predicted to emit gamma rays for tens of thousands years. The compositional changes and irradiation damage of V-based alloys and MgB2 are minimal
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Source
ICFRM-11: 11. International conference on fusion reactor materials; Kyoto (Japan); 7-12 Dec 2003; S0022311504003290; Copyright (c) 2004 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.; Country of input: International Atomic Energy Agency (IAEA)
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Journal Article
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ALUMINIUM ALLOYS, COBALT 60, DOSE RATES, GALLIUM ALLOYS, GAMMA RADIATION, HAFNIUM ALLOYS, IRRADIATION, MAGNESIUM BORIDES, MAGNETS, NEUTRONS, NIOBIUM ALLOYS, SILICON ALLOYS, SUPERCONDUCTORS, THERMONUCLEAR REACTORS, TIN ALLOYS, TITANIUM ALLOYS, TOKAMAK DEVICES, VANADIUM ALLOYS, VANADIUM SILICIDES, WALL LOADING, ZIRCONIUM ALLOYS
ALKALINE EARTH METAL COMPOUNDS, ALLOYS, BARYONS, BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, BORIDES, BORON COMPOUNDS, CLOSED PLASMA DEVICES, COBALT ISOTOPES, ELECTROMAGNETIC RADIATION, ELEMENTARY PARTICLES, EQUIPMENT, FERMIONS, HADRONS, INTERMEDIATE MASS NUCLEI, INTERNAL CONVERSION RADIOISOTOPES, IONIZING RADIATIONS, ISOMERIC TRANSITION ISOTOPES, ISOTOPES, MAGNESIUM COMPOUNDS, MINUTES LIVING RADIOISOTOPES, NUCLEI, NUCLEONS, ODD-ODD NUCLEI, POWER DENSITY, RADIATIONS, RADIOISOTOPES, SILICIDES, SILICON COMPOUNDS, THERMONUCLEAR DEVICES, TRANSITION ELEMENT ALLOYS, TRANSITION ELEMENT COMPOUNDS, VANADIUM COMPOUNDS, YEARS LIVING RADIOISOTOPES
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Fukui Daigaku Kogakubu Kenkyu Hokoku; v. 20(2); p. 169-179
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[en] Analysis of permeation rates of D2 gas at 10-4 to 10-1 Pa through 304 and 304L stainless steel membranes (51 μm and 127 μm thick) at 650 to 1050 K revealed that the chemisorption rate constant, k1, permeability and diffusion coefficient were 5.0 X 1015 + 2.2 X 1026 exp(-2.1 X 104T-1K) molecules D2.cm-2.sec-1.Pa-1, 1.4 X 1016 exp(-7700T-1K) molecules D2.cm-2.sec-1.Pasup(-1/2), and 3.5 X 10-4 exp(-5100T-1K) cm2 s-1, respectively. The value of k1 indicates two chemisorption sites (one unactivated). The scaling laws and the transition between the high and low pressure asymptotes were clarified by developing a dimensionless form of permeation equation applicable for low D2 activities. Following gas permeation experiments, permeation rates resulting from bombardment with 10 μA, 15 keV deuteron beams were measured. A high transient permeation rate was observed which was attributed to a surface impedance to reemission which decreased under bombardment. (Auth.)
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Journal Article
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Journal of Nuclear Materials; v. 71(2); p. 349-364
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BOUNDARY CONDITIONS, CHEMISORPTION, DEUTERIUM, DEUTERIUM IONS, DEUTERON BEAMS, DIFFUSION, FICK LAWS, HIGH TEMPERATURE, HIGH VACUUM, IRRADIATION, KEV RANGE 10-100, OXIDATION, PERMEABILITY, PRESSURE DEPENDENCE, SCALING LAWS, STAINLESS STEEL-304, STAINLESS STEEL-304L, VACUUM SYSTEMS, VERY HIGH TEMPERATURE
ALLOYS, BEAMS, CARBON ADDITIONS, CHARGED PARTICLES, CHEMICAL REACTIONS, CHROMIUM ALLOYS, CHROMIUM STEELS, CHROMIUM-NICKEL STEELS, CORROSION RESISTANT ALLOYS, ENERGY RANGE, HEAT RESISTING ALLOYS, HYDROGEN ISOTOPES, ION BEAMS, IONS, IRON ALLOYS, IRON BASE ALLOYS, ISOTOPES, KEV RANGE, LIGHT NUCLEI, NICKEL ALLOYS, NUCLEI, ODD-ODD NUCLEI, SEPARATION PROCESSES, STABLE ISOTOPES, STAINLESS STEELS, STEELS, TRANSITION ELEMENT ALLOYS
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