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[en] Short communication
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Israel Nuclear Society, Yavne (Israel); 149 p; Dec 1996; (pt.3.3) p. 1; 19. conference of the Israel Nuclear Societies; Herzliya (Israel); 9-10 Dec 1996
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Khimchenko, L.N.; Krasil'nikov, A.V.
Book of abstracts of the XXXVIII International (Zvenigorod) conference on plasma physics and controlled fusion2011
Book of abstracts of the XXXVIII International (Zvenigorod) conference on plasma physics and controlled fusion2011
AbstractAbstract
No abstract available
Original Title
Pervaya stenka i divertor - kriticheskaya problema pri sozdanii ITEhR
Primary Subject
Source
Rossijskaya Akademiya Nauk, Moscow (Russian Federation); Nauchnyj Sovet RAN po Fizike Plazmy, Moscow (Russian Federation); Nauchnyj Sovet RAN po Kompleksnoj Probleme Fizika Nizkotemperaturnoj Plazmy, Moscow (Russian Federation); Inst. Obshchej Fiziki im. A.M. Prokhorova RAN, Moscow (Russian Federation); Nauchno-Tekhnologicheskij Tsentr PLASMAIOFAN, Moscow (Russian Federation); Moskovskij Gosudarstvennyj Univ. im. M.V. Lomonosova, Moscow (Russian Federation); Ob''edinennyj Inst. Vysokikh Temperatur RAN, Moscow (Russian Federation); 416 p; ISBN 978-5-242-01171-6;
; 2011; p. 10; XXXVIII International (Zvenigorod) conference on plasma physics and controlled fusion; XXXVIII Mezhdunarodnaya (Zvenigorodskaya) konferentsiya po fizike plazmy i UTS; Zvenigorod (Russian Federation); 14-18 Feb 2011

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Xia, Guoliang; Ham, C.J.; Liu, Yueqiang; Li, L.; Wang, Z.R.; Wang, Shuo, E-mail: Guoliang.Xia@ukaea.uk, E-mail: liuy@fusion.gat.com2019
AbstractAbstract
[en] Effects of parallel and poloidal flows, as well as the flow shear, on the resistive wall mode (RWM) instability have been numerically investigated in toroidally rotating plasmas, utilizing a recently updated version of the MARS-F code (Liu et al 2000 Phys. Plasmas 7 3681). A significant difference between these flows is that the background toroidal flow frequency is symmetric with respect to the poloidal angle, whilst both the poloidal and toroidal projections of the additional parallel flow are functions of both the plasma minor radius and poloidal angle. It is found that the stability of the RWM is hardly modified by the parallel flow, as a consequence of cancellation of the stabilizing effect provided by the poloidal projection of the parallel flow from one side, and the destabilizing effect provided by the toroidal projection from the other side. The destabilizing effect of the toroidal projection comes predominantly from the m = 1 poloidal Fourier harmonic of the flow contribution. The shear of the parallel flow is found to generally weaken the stabilization/destabilization effect on the RWM, compared to the case of uniform parallel flow. (paper)
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Available from http://dx.doi.org/10.1088/1741-4326/ab415d; Country of input: International Atomic Energy Agency (IAEA)
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AbstractAbstract
No abstract available
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Transactions of the American Nuclear Society 1976 international meeting; Washington, DC, USA; 14 Nov 1976; Published in summary form only.
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Transactions of the American Nuclear Society; v. 24 p. 43-44
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Casini, G.; Farfaletti-Casali, F.
Transactions of the 8. international conference on structural mechanics in reactor technology. Vol. N1985
Transactions of the 8. international conference on structural mechanics in reactor technology. Vol. N1985
AbstractAbstract
[en] A review of the engineering problems related to the structures in front of the plasma of experimental Tokamak-type reactors is made. Attention is focused on the so-named ''first wall'', i.e. the wall side of the blanket segments facing the plasma, and on the collector plates of the impurity control system, in particular for the case of the single-null poloidal divertor. Even if the uncertainties related to the plasma-wall interaction are stil relevant, some engineering solutions which look manageable are identified and described. (orig.)
Primary Subject
Source
Stalpaert, J. (ed.); Commission of the European Communities, Luxembourg. Directorate General Information Market and Innovation; 189 p; ISBN 0444 86968 9;
; 1985; p. 69-75; North-Holland; Amsterdam (Netherlands); 8. international conference on structural mechanics in reactor technology (SMIRT-8); Brussels (Belgium); 19-23 Aug 1985

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[en] A global model is described which calculates the impurity levels resulting from plasma and impurity sputtering. The edge temperature is determined in a self consistent way from the input power and the particle containment time. Calculations are presented for the specific case of INTOR considering both carbon and iron walls. The impurity level is very dependent on the global particle containment time. For iron walls the impurity level is probably tolerable but a large fraction of the α heating power is radiated. For carbon walls the radiation level is much lower. (orig.)
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5. international conference on plasma surface interactions in controlled fusion devices; Gatlinburg, TN (USA); 3 - 7 May 1982; CODEN: JNUMA.
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Journal Article
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Journal of Nuclear Materials; ISSN 0022-3115;
; v. 111/112 p. 396-402

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AbstractAbstract
[en] Serious problems have to be faced at present in linking present plasma research to fusion reactor engineering. Even in fusion devices of the near-term and of the next generation which aim to evaluate the fusion engineering feasibility of burning plasma experiments such as TFTR, JET, R-tokamak, ZEPHYR and INTOR, plasma-material interactions cause many technological difficulties such as large heat loads, large erosion rates, large magnetic forces and large induced radioactivities. Moreover, impurity control, tritium handling, ash exhaust and refuelling need to be solved by realistic methods with technological justifications. Since present fusion approaches might not give hopeful predictions to an economical, safe, and reliable fusion reactor, it is most important at present to find a possible window of promising fusion research. In this paper, we review technological restrictions from viewpoints of plasma-material interactions, then discuss the fusion research and related material investigations that are necessary to realize reasonable fusion reactor concepts. (orig.)
Primary Subject
Source
5. international conference on plasma surface interactions in controlled fusion devices; Gatlinburg, TN (USA); 3 - 7 May 1982; With 80 refs.; CODEN: JNUMA.
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Journal Article
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Conference
Journal
Journal of Nuclear Materials; ISSN 0022-3115;
; v. 111/112 p. 461-478

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Barengol'ts, S.A.; Mesyats, G.A.; Tsventukh, M.M.
Book of abstracts of the XXXIX International (Zvenigorod) conference on plasma physics and controlled fusion2012
Book of abstracts of the XXXIX International (Zvenigorod) conference on plasma physics and controlled fusion2012
AbstractAbstract
No abstract available
Original Title
Initsiirovanie impul'sov vzryvnoj ehmissii - ehktonov pri vozdejstvii plazmy na pervuyu stenku termoyadernykh ustanovok, i ikh rol' v formirovanii ehrozionnoj plazmy
Primary Subject
Source
Rossijskaya Akademiya Nauk, Moscow (Russian Federation); Nauchnyj Sovet RAN po Fizike Plazmy, Moscow (Russian Federation); Nauchnyj Sovet RAN po Kompleksnoj Probleme Fizika Nizkotemperaturnoj Plazmy, Moscow (Russian Federation); Inst. Obshchej Fiziki im. A.M. Prokhorova RAN, Moscow (Russian Federation); Nauchno-Tekhnologicheskij Tsentr PLASMAIOFAN, Moscow (Russian Federation); Moskovskij Gosudarstvennyj Univ. im. M.V. Lomonosova, Moscow (Russian Federation); Ob''edinennyj Inst. Vysokikh Temperatur RAN, Moscow (Russian Federation); 317 p; ISBN 978-5-9903264-1-5;
; 2012; p. 57; 39. International (Zvenigorod) conference on plasma physics and controlled fusion; XXXIX Mezhdunarodnaya (Zvenigorodskaya) konferentsiya po fizike plazmy i UTS; Zvenigorod (Russian Federation); 6-10 Feb 2012; 8 refs.

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AbstractAbstract
[en] The sputtering characteristics of various types of carbon limiter surfaces, e.g. pyrolitic graphite (PG), pulverized carbon film and carbon film produced by methane discharges, are tested. Arcing is only observed on the pulverized carbon surface in a stable discharge or the other surfaces in an unstable discharge. Ion sputtering is shown to be the dominant process of carbon efflux from the normal surfaces. Employing PG limiters and a carbon wall coated by rf-sputtering method, very low q plasmas with a good confinement characteristic are obtained. The coated carbon surface is pure and still not contaminated after 600 or more discharges. (orig.)
Primary Subject
Source
4. international conference on plasma surface interactions and controlled fusion devices; Garmisch-Partenkirchen, Germany, F.R; 21 - 25 Apr 1980
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Journal Article
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Conference
Journal
Journal of Nuclear Materials; ISSN 0022-3115;
; v. 93/94(pt.A); p. 178-184

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AbstractAbstract
No abstract available
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(c) 2006 American Institute of Physics; Country of input: International Atomic Energy Agency (IAEA)
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