Zobrazeno 1 - 10
of 113
pro vyhledávání: '"P.H. Edmonds"'
Publikováno v:
Fusion Technology. 31:350-369
Recently, there have been several proposals to build low-aspect-ratio or spherical tokamaks with plasma currents in the range of 1 MA. These low-aspect-ratio tokamaks employ conventional engineering, except in the central core, which contains the cen
Publikováno v:
IEEE Thirteenth Symposium on Fusion Engineering.
A first-wall design and analysis for the proposed Fusion Ignition Experiment (IGNITEX) is presented. The design of the first wall system emphasizes plasma cleanness, simplicity of design, minimum complexity of remote maintenance systems and operation
Autor:
S.S. Medley, P.H. Edmonds
A procedure is described for precision modeling of the views for imaging diagnostics monitoring tokamak internal components, particularly high heat flux divertor components. These models are required to enable predictions of resolution and viewing an
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8f25808281b28942759e7546bfd5b328
https://doi.org/10.2172/238597
https://doi.org/10.2172/238597
The diagnostics for TPX are at an early design phase, with emphasis on the diagnostic access interface with the major tokamak components. Account has to be taken of the very severe environment for diagnostic components located inside the vacuum vesse
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::bb2b8ea1c4ede196047f0515466c71bd
https://doi.org/10.2172/100240
https://doi.org/10.2172/100240
Autor:
P.W. King, P.H. Edmonds, D.H. McNeill, C.E. Bush, J.L. Dunlap, Masakatsu Murakami, R.C. Isler, J. F. Lyon, G.R. Dyer, L. A. Berry
Publikováno v:
Physical Review Letters. 39:615-618
Substantial electron heating by energetic neutral beam injection has been observed in Oak Ridge Tokamak (ORMAK) plasmas. Impurity radiation is enhanced by injection but only to the degree expected for ohmically heated discharges with the same total p
Autor:
Alan J Wootton, P.H. Edmonds, A.C. England, P.K. Mioduszewski, P.E. Stott, G.H. Neilson, W.A. Gabbard, C.E. Bush, R. A. Langley, P.D. Morgan, James B. Roberto, K.H. Behringer, C. H. Ma, C. E. Thomas, A. Carnevali, R. E. Clausing, D.H.J. Goodall, R. B. Clayton, J. von Seggern, E. A. Lazarus, N. J. Peacock, M. Murakami, J. G. Dietz, R.A. Zuhr, R. D. Watson, L.C. Emerson, J. E. Simpkins, R.R. Kindsfather, K.G. Tschersich, A. Tanga, P. J. Lomas, R.C. Isler, T.B. Cook, K. Yokoyama, J.B. Whitley, L. Heatherly, J.G. Watkins, K.H. Sonnenberg, E. Källne, P.W. King, D. P. Hutchinson, M.F. Smith
Publikováno v:
Nuclear Fusion. 26:1171-1192
An experiment to test beryllium as a limiter material has been performed in the ISX-B tokamak. The effect of the plasma on the limiter and the effect of the limiter on the plasma were studied in detail. Heat and particle fluxes to the limiter were me
Autor:
C. E. Thomas, Cheng Ma, L.C. Emerson, H.C. Howe, A. Carnevali, D. P. Hutchinson, M. Murakami, J.L. Dunlap, R. A. Langley, W. L. Gardner, S.D. Scott, W.R. Wing, Alan J Wootton, J.B. Whitley, P.H. Edmonds, K. E. Yokoyama, P.K. Mioduszewski, R.R. Kindsfather, R.C. Isler, J. E. Simpkins, G. H. Neilson, V.K. Paré, C.E. Bush, E. A. Lazarus
Publikováno v:
Journal of Nuclear Materials. 121:285-293
The first pump limiter experiments were performed on ISX-B. Two pump limiter modules were installed in the top and bottom of one toroidal sector of the tokamak. The modules consist of inertia cooled, TiC-coated graphite heads and ZrAl getter pumps
Publikováno v:
Journal of Nuclear Materials. 138:268-276
One of 12 beryllium tiles on a top rail limiter in the Impurity Study Experiment (ISX-B) tokamak was intentionally made radioactive. The migration of the radioactivity due to melting, ablation, and general excoriation of the radioactive tile was stud
Autor:
E. A. Lazarus, C. E. Thomas, S.D. Scott, Cheng Ma, J.K. Munro, C.E. Bush, P.H. Edmonds, G. H. Neilson, D. P. Hutchinson, L.E. Murray, M. Murakami, A. Carnevali, J.D. Bell, R.C. Isler, R.R. Kindsfather, R. A. Langley, Alan J Wootton
Publikováno v:
Nuclear Fusion. 26:391-413
Scalings of the central rotation in non-gettered, co-injected ISX-B discharges have been measured as a function of beam power, electron density and plasma current. Extensive studies are made possible by exploiting charge-exchange excitation (CXE) of
Autor:
A.C. England, P.H. Edmonds
Publikováno v:
Nuclear Fusion. 18:23-27
Measurements of temperature rise of the wall and of a movable limiter have been made in the Oak Ridge Tokamak (ORMAK). For a normal discharge without injection, approximately 70% of the energy in the discharge is deposited on the wall. Very little en