Zobrazeno 1 - 10
of 59
pro vyhledávání: '"J. Mandrekas"'
Publikováno v:
Nuclear Fusion. 37:1015-1031
The robustness of impurity seeded radiative mantle plasma power exhaust solutions for the ITER ignited operating point to uncertainties in the energy and impurity transport and in several physics and operating parameters is examined. Our results indi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::00a6cf657c6819207569730d253999ce
https://doi.org/10.1088/0029-5515/37/7/i09
https://doi.org/10.1088/0029-5515/37/7/i09
Autor:
J. Dietz, M. Sugihara, D. Mitin, S. Chiocchio, J. Mandrekas, E. Martin, M. Gouge, A. Kukushkin, G. Janeschitz, T. Ando, R. Tivey, P. Ladd, A. Antipenkov, H.D. Pacher, G. Federici, Yu. Igitkhanov, H Nakamura, Weston M. Stacey, D. Post
Publikováno v:
Fusion Technology. 30:594-600
The ITER power and particle control system is designed to exhaust the 300 to 400 MW of alpha and auxiliary heating power and the 5 x 10{sup 20} He atoms per second created by the fusion reactions, to control the density and to fuel the plasma. The po
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::95163eb002bd70ec558a5a9cad0a347b
https://doi.org/10.13182/fst96-a11963003
https://doi.org/10.13182/fst96-a11963003
Autor:
Jr. W.M. Stacey, J. Mandrekas
Publikováno v:
Nuclear Fusion. 35:843-852
Self-consistent, coupled transport/MHD/scrape-off layer (SOL) divertor calculations indicate that a stable, radiating mantle can be maintained just inside the separatrix by iron impurity injection into the SOL in an ITER EDA model. The power flux to
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6ed5ad90d2b531dfb6eb2edbba71d3e6
https://doi.org/10.1088/0029-5515/35/7/i07
https://doi.org/10.1088/0029-5515/35/7/i07
Autor:
Jr. W.M. Stacey, J. Mandrekas
Publikováno v:
Nuclear Fusion. 34:1385-1399
A new computational model for neutral particle transport in the outer regions of a diverted tokamak plasma chamber is presented. The model is based on the calculation of transmission and escape probabilities using first-flight integral transport theo
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::bfe8bdc181dbd4dd07a299c76dbb8f3d
https://doi.org/10.1088/0029-5515/34/10/i07
https://doi.org/10.1088/0029-5515/34/10/i07
Publikováno v:
Transport Theory and Statistical Physics. 21:119-131
We consider systems of general nonlinear PDEs that arise in the extended kinetic theory of gases describing mixtures of spatially inhomogeneous, mutually interacting species. For general, autonomous, space-independent interaction laws, these systems
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a1815ddcd17b9604132e7501b7d13026
https://doi.org/10.1080/00411459208203525
https://doi.org/10.1080/00411459208203525
Autor:
R.C. Martin, S.P. Grotz, J. S. Herring, Y-K.M. Peng, Tomoaki Kunugi, John F. Santarius, Charles G. Bathke, Daniel R. Cohn, Shahram Sharafat, Marc Klasky, Dennis J Strickler, Ronald L. Miller, M.J. Schaffer, Justin Schwartz, S.A. Jardin, Nasr M. Ghoniem, C.E. Singer, P.I.H. Cooke, J.H. Schultz, J.T. Hogan, J. Mandrekas, J.A. Leuer, Farrokh Najmabadi, D.J. Ward, Edward T. Cheng, D.K. Sze, K.R. Schultz, K. Evans, A.W. Hyatt, T. K. Mau, L. Snead, Leslie Bromberg, Robert W. Conn, R.A. Krakowski, Layton J. Wittenberg, Don Steiner, R.L. Reid, J.E.C. Williams, E. Ibrahim, M. Valenti, C.P.C. Wong, Charles Kessel, R.L. Creedon, David A. Ehst, M.Z. Hasan
Publikováno v:
Fusion Technology. 19:783-790
The ARIES research program is a multi-institutional effort to develop several visions of tokamak reactors with enhanced economic, safety, and environmental features. Three ARIES visions are currently planned for the ARIES program. The ARIES-I design
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a1630e3cd38adc0e83a7e6dc26127113
https://doi.org/10.13182/fst91-a29440
https://doi.org/10.13182/fst91-a29440
Autor:
W.M. Stacey, J. Mandrekas
Publikováno v:
IEEE Thirteenth Symposium on Fusion Engineering.
A 0-D time-dependent particle and power balance code has been developed and used to evaluate the effectiveness of different methods of controlling thermally unstable ignited and subignited operating points of the physics phase ITER machine. Based on
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9b3ef02a7b2d9ea906594e6017e37c4b
https://doi.org/10.1109/fusion.1989.102250
https://doi.org/10.1109/fusion.1989.102250
Autor:
E.T. Cheng, J.A. Leuer, J.T. Hogan, Farrokh Najmabadi, J.F. Santarius, J.S. Herring, S.P. Grotz, W. Kernbichler, G.A. Emmert, Shahram Sharafat, W.R. Beecraft, C.E. Singer, D.J. Ward, D.J. Stricker, Marc Klasky, L.J. Wittenberg, L. Snead, D.-K. Sze, S.A. Jardin, J. Brooks, T. K. Mau, I.N. Sviatoslavsky, M.Z. Hasan, J. Schwartz, J. Schultz, G.H. Miley, R.C. Martin, Y.-K.M. Peng, J.C. Whitson, J. Mandrekas, Robert W. Conn, L. Bromberg, R.A. Krakowski, E. Greenspan, P.I.H. Cooke, M.J. Schaffer, T. Kungi, D.A. Ehst, A.W. Hyatt, A.C. Klein, C.G. Bathke, R.L. Reid, J.R. Bartlit, James Blanchard, K. Evans, D.R. Cohn, K.R. Schultz, R.L. Creedon, D. Steiner, R.L. Miller, M. Valenti, C.P.C. Wong, Nasr M. Ghoniem, E. Ibrahim, J.E.C. Williams
Publikováno v:
IEEE Thirteenth Symposium on Fusion Engineering.
The Advanced Reactor Innovation and Evaluation Study (ARIES) is a community effort to develop several visions of the tokamak as a fusion power reactor. The aims are to determine its potential economics, safety, and environmental features and to ident
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::dd73dd0609de7436e1a03c12fea9d1dc
https://doi.org/10.1109/fusion.1989.102387
https://doi.org/10.1109/fusion.1989.102387
Publikováno v:
IEEE Thirteenth Symposium on Fusion Engineering.
Fast-wave current drive is selected as the primary scenario for steady-state operation of the Advanced Reactor Innovation and Evaluation Study-I (ARIES-I) tokamak reactor. With a projected efficiency of approximately=0.3-0.4, the current drive method
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2ed9ed186d9a44a41073ebb507077c0d
https://doi.org/10.1109/fusion.1989.102221
https://doi.org/10.1109/fusion.1989.102221
Autor:
G.L. Kuleinski, J.H. Schultz, T. J. Dolan, J.S. Herring, Robert A. Krakowski, David A. Ehst, Shahram Sharafat, J.F. Santarius, Edward T. Cheng, Jeffrey N. Brooks, J. Mandrekas, S.A. Jardin, M. Valenti, P. Titus, E. A. Mogahed, Mohamed E. Sawan, J.E.C. Williams, Dai-Kai Sze, Daniel R. Cohn, Don Steiner, E. Ibrahim, E.E. Reis, P. Gierszewski, Laila El-Guebaly, Jeffrey A Holmes, S.P. Grotz, K.R. Schultz, Layton J. Wittenberg, R.W. Conn, Charles G. Bathke, I.N. Sviatoslavsky, T. K. Mau, J.H. Whealton, Dennis J Strickler, S.K. Ho, Leslie Bromberg, Gilbert Emmert, K.A. Werley, A. Hollies, M.S. Hasan, C.P.C. Wong, C.E. Kessel, H.Y. Khater, Farrokh Najmabadi, James Blanchard, George H. Miley, Ronald L. Miller
Publikováno v:
[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering.
A description of the ARIES-III research effort is presented, and the general features of the ARIES-III reactor are described. The plasma engineering and fusion-power-core design are summarized, including the major results, the key technical issues, a
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c8284d7622b4953524079c85d024a74e
https://doi.org/10.1109/fusion.1991.218914
https://doi.org/10.1109/fusion.1991.218914