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- 저자 : Artaud, J.F. (검색결과 2 건)
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A lower hybrid current drive system for ITER
Hoang, G.T.,Bé,coulet, A.,Jacquinot, J.,Artaud, J.F.,Bae, Y.S.,Beaumont, B.,Belo, J.H.,Berger-By, G.,Bizarro, Joã,o P.S.,Bonoli, P.,Cho, M.H.,Decker, J.,Delpech, L.,Ekedahl, A.,Garcia, J. International Atomic Energy Agency 2009 Nuclear fusion Vol.49 No.7
<P>A 20 MW/5 GHz lower hybrid current drive (LHCD) system was initially due to be commissioned and used for the second mission of ITER, i.e. the <I>Q</I> = 5 steady state target. Though not part of the currently planned procurement phase, it is now under consideration for an earlier delivery. In this paper, both physics and technology conceptual designs are reviewed. Furthermore, an appropriate work plan is also developed. This work plan for design, R&D, procurement and installation of a 20 MW LHCD system on ITER follows the ITER Scientific and Technical Advisory Committee (STAC) T13-05 task instructions. It gives more details on the various scientific and technical implications of the system, without presuming on any work or procurement sharing amongst the possible ITER partners. This document does not commit the Institutions or Domestic Agencies of the various authors in that respect.</P>
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Simulation of the hybrid and steady state advanced operating modes in ITER
Kessel, C.E.,Giruzzi, G.,Sips, A.C.C.,Budny, R.V.,Artaud, J.F.,Basiuk, V.,Imbeaux, F.,Joffrin, E.,Schneider, M.,Murakami, M.,Luce, T.,St John, Holger,Oikawa, T.,Hayashi, N.,Takizuka, T.,Ozeki, T.,Na, International Atomic Energy Agency 2007 Nuclear fusion Vol.47 No.9
<P>Integrated simulations are performed to establish a physics basis, in conjunction with present tokamak experiments, for the operating modes in the International Thermonuclear Experimental Reactor (ITER). Simulations of the hybrid mode are done using both fixed and free-boundary 1.5D transport evolution codes including CRONOS, ONETWO, TSC/TRANSP, TOPICS and ASTRA. The hybrid operating mode is simulated using the GLF23 and CDBM05 energy transport models. The injected powers are limited to the negative ion neutral beam, ion cyclotron and electron cyclotron heating systems. Several plasma parameters and source parameters are specified for the hybrid cases to provide a comparison of 1.5D core transport modelling assumptions, source physics modelling assumptions, as well as numerous peripheral physics modelling. Initial results indicate that very strict guidelines will need to be imposed on the application of GLF23, for example, to make useful comparisons. Some of the variations among the simulations are due to source models which vary widely among the codes used. In addition, there are a number of peripheral physics models that should be examined, some of which include fusion power production, bootstrap current, treatment of fast particles and treatment of impurities. The hybrid simulations project to fusion gains of 5.6–8.3, β<SUB>N</SUB> values of 2.1–2.6 and fusion powers ranging from 350 to 500 MW, under the assumptions outlined in section 3. Simulations of the steady state operating mode are done with the same 1.5D transport evolution codes cited above, except the ASTRA code. In these cases the energy transport model is more difficult to prescribe, so that energy confinement models will range from theory based to empirically based. The injected powers include the same sources as used for the hybrid with the possible addition of lower hybrid. The simulations of the steady state mode project to fusion gains of 3.5–7, β<SUB>N</SUB> values of 2.3–3.0 and fusion powers of 290 to 415 MW, under the assumptions described in section 4. These simulations will be presented and compared with particular focus on the resulting temperature profiles, source profiles and peripheral physics profiles. The steady state simulations are at an early stage and are focused on developing a range of safety factor profiles with 100% non-inductive current.</P>
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