Refine your search:     
Report No.
 - 
Search Results: Records 1-7 displayed on this page of 7
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

The 2008 public release of the international multi-tokamak confinement profile database

Roach, C. M.*; Walters, M.*; Budny, R. V.*; Imbeaux, F.*; Fredian, T. W.*; Greenwald, M.*; Stillerman, J. A.*; Alexander, D. A.*; Carlsson, J.*; Cary, J. R.*; et al.

Nuclear Fusion, 48(12), p.125001_1 - 125001_19, 2008/12

 Times Cited Count:31 Percentile:26.98(Physics, Fluids & Plasmas)

This paper documents the public release PR08 of the International Tokamak Physics Activity profile database, which should be of particular interest to the magnetic confinement fusion community. Data from a wide variety of interesting discharges from many of the world's leading tokamak experiments are now made available in PR08, which also includes predictive simulations of an initial set of operating scenarios for ITER. In this paper we describe the discharges that have been included and the tools that are available to the reader who is interested in accessing and working with the data.

Journal Articles

Progress in the ITER physics basis, 1; Overview and summary

Shimada, Michiya; Campbell, D. J.*; Mukhovatov, V.*; Fujiwara, Masami*; Kirneva, N.*; Lackner, K.*; Nagami, Masayuki; Pustovitov, V. D.*; Uckan, N.*; Wesley, J.*; et al.

Nuclear Fusion, 47(6), p.S1 - S17, 2007/06

 Times Cited Count:624 Percentile:99.93(Physics, Fluids & Plasmas)

The Progress in the ITER Physics Basis document is an update of the ITER Physics Basis (IPB), which was published in 1999. The IPB provided methodologies for projecting the performance of burning plasmas, developed largely through coordinated experimental, modeling and theoretical activities carried out on today's tokamaks (ITER Physics R&D). In the IPB, projections for ITER (1998 Design) were also presented. The IPB also pointed out some outstanding issues. These issues have been addressed by the International Tokamak Physics Activities (ITPA), which were initiated by the European Union, Japan, Russia and the U.S.A.. The new methodologies of projection and control developed through the ITPA are applied to ITER, which was redesigned under revised technical objectives, but will nonetheless meet the programmatic objective of providing an integrated demonstration of the scientific and technological feasibility of fusion energy.

Journal Articles

Progress in the ITER physics basis, 2; Plasma confinement and transport

Doyle, E. J.*; Houlberg, W. A.*; Kamada, Yutaka; Mukhovatov, V.*; Osborne, T. H.*; Polevoi, A.*; Bateman, G.*; Connor, J. W.*; Cordey, J. G.*; Fujita, Takaaki; et al.

Nuclear Fusion, 47(6), p.S18 - S127, 2007/06

no abstracts in English

Journal Articles

Progress in physics basis and its impact on ITER

Shimada, Michiya; Campbell, D.*; Stambaugh, R.*; Polevoi, A. R.*; Mukhovatov, V.*; Asakura, Nobuyuki; Costley, A. E.*; Donn$'e$, A. J. H.*; Doyle, E. J.*; Federici, G.*; et al.

Proceedings of 20th IAEA Fusion Energy Conference (FEC 2004) (CD-ROM), 8 Pages, 2004/11

This paper summarises recent progress in the physics basis and its impact on the expected performance of ITER. Significant progress has been made in many outstanding issues and in the development of hybrid and steady state operation scenarios, leading to increased confidence of achieving ITER's goals. Experiments show that tailoring the current profile can improve confinement over the standard H-mode and allow an increase in beta up to the no-wall limit at safety factors $$sim$$ 4. Extrapolation to ITER suggests that at the reduced plasma current of $$sim$$ 12MA, high Q $$>$$ 10 and long pulse ($$>$$1000 s) operation is possible with benign ELMs. Analysis of disruption scenarios has been performed based on guidelines on current quench rates and halo currents, derived from the experimental database. With conservative assumptions, estimated electromagnetic forces on the in-vessel components are below the design target values, confirming the robustness of the ITER design against disruption forces.

Journal Articles

The International multi-tokamak profile database

Boucher, D.*; Connor, J. W.*; Houlberg, W. A.*; Turner, M. F.*; Bracco, G.*; Chudnovskiy, A.*; Cordey, J. G.*; Greenwald, M. J.*; Hoang, G. T.*; Hogeweij, G. M. D.*; et al.

Nuclear Fusion, 40(12), p.1955 - 1981, 2000/12

no abstracts in English

Journal Articles

Validation of 1-D transport and sawtooth models for ITER

Connor, J. W.*; M.Alexander*; Attenberger, S. E.*; G.Bateman*; Boucher, D.*; N.Chudnovskii*; Dnestrovskij, Y. N.*; W.Dorland*; A.Fukuyama*; Hoang, G. T.*; et al.

Fusion Energy 1996, 2, p.935 - 944, 1997/00

no abstracts in English

Oral presentation

Pellet fueling technology development for efficient fueling of burning plasma in ITER

Baylor, L. R.*; Parks, P. B.*; Jernigan, T. C.*; Caughman, J. B.*; Combs, S. K.*; Fenstermacher, M. E.*; Foust, C. R.*; Houlberg, W. A.*; Lasnier, C. J.*; Maruyama, So; et al.

no journal, , 

Pellet injection is the primary fuelling technique for efficient core fuelling of ITER burning plasma. Pellet survivability and pellet mass loss have been demonstrated using a mockup of ITER inboard injection line. This experiment has revealed that pellets survive intact up to 300m/s, which is required for inboard injection. The series of experiments have demonstrated that pellet mass loss at extremely high back pressure remains $$<$$20% ($$<$$10% at $$<$$300m/s). The pellet mass deposition has been numerically evaluated. It shows that inboard launching, present ITER reference, of 3 mm and 5mm cylindrical pellets at 300 m/s has a capability to fuel well inside the separatrix. The fuelling efficiency is predicted to be nearly 100%, which will help to minimize the tritium retention of the first wall. Pellet injected in to the present day tokamaks have been found to trigger ELMs in H-mode plasma. ITER will have the pellet injection technology as an ELM mitigation system.

7 (Records 1-7 displayed on this page)
  • 1