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AbstractAbstract
No abstract available
Source
Letter-to-the-editor; Published in summary form only.
Record Type
Journal Article
Journal
Journal of Nuclear Materials; ISSN 0022-3115;
; v. 101(1/2); p. 238-239

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AbstractAbstract
[en] Chromium gettering has been proven to be a trouble-free and efficient method of surface pumping in tokamaks. The impurity control capabilities are excellent and comparable to that of titanium. The hydrogen uptake is reduced to monolayer quantities on the surface. The expansion of the operating space is similar to that seen with titanium without the disadvantage of strongly increased hydrogen fluxes. Possible applications of chromium gettering are: impurity control in contemporary tokamaks; surface pumping in short pulse DT-burning devices to minimize tritium inventory, and wall-conditioning of future large machines prior to operation. (orig.)
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6. international conference on plasma surface interactions in controlled fusion devices; Nagoya (Japan); 14-18 May 1984; CONTRACT DE-AC05-840R21400; Also published as report CONF-840520--20.; CODEN: JNUMA.
Record Type
Journal Article
Literature Type
Conference
Journal
Journal of Nuclear Materials; ISSN 0022-3115;
; v. 128/129 p. 884-885

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Gabbard, W.A.; Simpkins, J.E.; Mioduszewski, P.; Edmonds, P.H.
Oak Ridge National Lab., TN (USA)1983
Oak Ridge National Lab., TN (USA)1983
AbstractAbstract
[en] Design and fabrication techniques are described for the manufacture of large-capacity chromium getter sources, analogous to the commercially available titanium getter source known as Ti-Ball, manufactured by Varian Associates
Primary Subject
Source
1983; 3 p; 3. topical meeting on fusion reactor materials; Albuquerque, NM (USA); 19-23 Sep 1983; Available from NTIS, PC A02/MF A01 as DE84000342
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Report
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Conference
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AbstractAbstract
[en] A nuclear fuel element for use in the core of a nuclear reactor is disclosed and has disposed therein an improved getter capable of gettering reactive gases including a source of hydrogen. The getter comprises a composite with a substrate having thereon a coating capable of gettering reactive gases. The substrate has a greater coefficient of thermal expansion than does the coating, and over a period of time at reactor operating temperatures any protective film on the coating is fractured at various places and fresh portions of the coating are exposed to getter reactive gases. With further passage of time at reactor operating temperatures a fracture of the protective film on the coating will grow into a crack in the coating exposing further portions of the coating capable of gettering reactive gases
Original Title
Patent
Primary Subject
Source
13 Jul 1976; 10 p; US PATENT DOCUMENT 3,969,185
Record Type
Patent
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Mehrhoff, T.K.
General Electric Co., St. Petersburg, FL (USA). Neutron Devices Dept1980
General Electric Co., St. Petersburg, FL (USA). Neutron Devices Dept1980
AbstractAbstract
[en] The interaction of carbon dioxide and erbium thin films is characterized for temperatures in the region of 300 to 9000C and partial pressure of carbon dioxide near 5 x 10-7 Torr. Dynamic film pumping speeds were measured against a mercury diffusion pump of known pumping speed and conductance. A quadrupole mass spectrometer was used to monitor the carbon dioxide flow which originated from a calibrated leak in the 10-6 standard cm3/s range. Data reduction was via a dedicated minicomputer with associated printer/plotter. Temperature ramp experiments with thin erbium films indicated a significant reaction above 3000C. The reaction was preceded by the desorption of water vapor, hydrogen and nitrogen and/or carbon monoxide from the film surface
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Source
10 Oct 1980; 24 p; Available from NTIS., PC A02/MF A01
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Report
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AbstractAbstract
[en] In connection with the setting up of an installation for the containment and handling of 10 g tritium, pressure resistant tritium storage vessels which could be heated to 5500C, and which had a nominal capacity of 1,9 g and a maximum capacity of 5,7 g tritium, were developed. The report gives, in addition to estimations and calculations, the results of measurements on individual components of the storage vessel and its accessories, together with those on a prototype storage vessel. The measurements carried out with hydrogen showed that under suitably chosen operating conditions, a storage vessel can be loaded in 15 minutes and discharged in 2 1/2 hours (limited by thermal capacity), without any carryover of uranium being observed. Most of the measurements were carried out on the thermal behaviour and flow resistance of the vessel, as well as hydrogenation, dehydrogenation, hydrogen adsorption from helium and isotopic mixture effects. The sensitivity of a calorimetric tritium determination of this prototype storage vessel was determined. (orig./HP)
[de]
Im Zusammenhang mit der Errichtung einer Anlage zur Einschliessung und Handhabung von 10 g Tritium wurden druckfeste, bis 5500C heizbare Tritium-Lagerbehaelter mit einer Nenn-Speicherkapazitaet von 1,9 g und einer Maximalkapazitaet von 5,7 g T2 entwickelt. Der Bericht gibt neben Abschaetzungen und Berechnungen insbesondere die Resultate von Messungen an Einzelkomponenten des Lagerbehaelters und seinen Betriebseinrichtungen sowie an einem Prototyp-Lagerbehaelter wieder. Die mit Wasserstoff durchgefuehrten Messungen ergaben, dass bei geeignet gewaehlten Betriebsbedingungen ein Lagerbehaelter innerhalb von etwa 15 Minuten beladen und innerhalb von 2 1/2 Stunden entladen (begrenzt durch thermische Traegheit) werden kann, ohne dass eine Uran-Verschleppung beobachtet wird. Im wesentlichen wurden Messungen zum thermischen Verhalten und Stroemungswiderstand, zur Hydrierung, Dehydrierung und Wasserstoffaufnahme aus Helium und zum Isotopenvermischungseffekt durchgefuehrt. Die Empfindlichkeit einer kalorimetrischen Tritium-Mengenmessung in diesem Prototyp-Behaelter wurde bestimmt. (orig./HP)Original Title
Der U/UT3-Lagerbehaelter im Tritium-Lager
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Secondary Subject
Source
May 1984; 92 p
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Report
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Manini, P.; Marino, M.; Belloni, F.; Porro, M.
Proceedings of the 1993 Particle Accelerator Conference: Volume 51993
Proceedings of the 1993 Particle Accelerator Conference: Volume 51993
AbstractAbstract
[en] UHV pumps based on non-evaporable getter coated strips find widespread use in particle accelerators, synchrotron radiation machines and nuclear fusion experimental devices. Depending on the geometric constraints, pressure operation conditions and the foreseen gas loads, optimized getter structures, such as modules and cartridges, can be designed and assembled into a high-efficiency pump. In the present paper, the design and performance of a newly conceived High Capacity Getter Pump (HCGP) based on sintered getter bodies, in the shape of blades instead of strips, is illustrated. The porosity and the specific surface area of the blades and their arrangement in the cartridge have been optimized to significantly increase sorption capacity at a given speed. These pumps are well suited for those applications where a very high gas load is expected during the machine operation. The sintered getter bodies increase surface area and capacity, requiring less frequent reactivation and facilitating greater overall life of the pump. A discussion of the experimental results in terms of sorption speed and capacity for various gases is presented
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Secondary Subject
Source
Institute of Electrical and Electronics Engineers, Inc., New York, NY (United States); American Physical Society, Washington, DC (United States); 829 p; 1993; p. 3839-3841; PAC '93: international particle accelerator conference; Washington, DC (United States); 17-20 May 1993; Available from IEEE Service Center, 445 Hoes Lane, Piscataway, NJ 08854-4150
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Report
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Conference
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Mote, M.W. Jr.; Mintz, J.M.
Sandia National Labs., Livermore, CA (USA)1986
Sandia National Labs., Livermore, CA (USA)1986
AbstractAbstract
[en] A uranium gettering bed was cycled between room temperature/zero pressure and 600C/275 psi (D2) for 210 cycles over a period of 8 months. Metallographic examination of the hardware revealed an acceptable amount of reaction between the uranium and the stainless steel container. This exposure is estimated to represent about ten years of normal use
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Source
Dec 1986; 17 p; Available from NTIS, PC A02/MF A01; 1 as DE87003590; Portions of this document are illegible in microfiche products. Original copy available until stock is exhausted.
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Report
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Miller, H.H.; Bissell, E.R.; Tsugawa, R.T.; Souers, P.C.
Proceedings: tritium technology in fission, fusion, and isotopic applications1980
Proceedings: tritium technology in fission, fusion, and isotopic applications1980
AbstractAbstract
[en] Research on the acetylene compound 1,4-diphenylbutadiyne is an effort to develop a tritium gas getter that will operate in the presence of air and minimize the formation of water. T2 adds to the acetylene bond of the getter in the presence of a metal catalyst. The catalyst stimulates the T2-O2 reaction as well. The butadiyne compound has shown good reaction efficiency for 300 ppM T2 in static dry air at room temperature and one atmosphere pressure. Metalacetylene complexes are being synthesized, positioning the metal catalyst atom as close to the triple bond as possible to maximize the organic reaction. Organometallics such as triphenyl phosphine iridium are being investigated as possible regenerative getters for T2 in air. Gas mixtures as low as 1 ppM T2 in air will be tested under flow conditions in future work
Primary Subject
Source
Wittenberg, L.J. (comp.); p. 208-212; 1980; p. 208-212; American Nuclear Society; La Grange Park, IL; Tritium technology in fission, fusion, and isotopic applications; Dayton, OH, USA; 29 Apr - 1 May 1980
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Book
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Conference
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AbstractAbstract
No abstract available
Original Title
Sostoyanie razrabotki i proizvodstva sredstv vakuumnykh izmerenij v Rossii i stranakh SNG
Primary Subject
Source
2. Scientific-practical symposium 'Vacuum technology and equipment'; 2. Nauchno-prakticheskij simpozium ' Vakuumnye tekhnologii i oborudovanie'; Khar'kov (Ukraine); Nov 1998
Record Type
Journal Article
Literature Type
Conference
Journal
Voprosy Atomnoj Nauki i Tekhniki. Vakuum, Chistye Materialy, Sverkhprovodniki; ISSN 1680-192X;
; v. 4,5(5,6); p. 6-10

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