Refine your search:     
Report No.
 - 
Search Results: Records 1-20 displayed on this page of 23

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

Enhancement of resistance against high energy laser pulse injection with chevron beam dump

Yatsuka, Eiichi; Hatae, Takaki; Bassan, M.*; Vayakis, G.*; Walsh, M.*; Itami, Kiyoshi

Fusion Engineering and Design, 100, p.461 - 467, 2015/11

 Times Cited Count:6 Percentile:45.92(Nuclear Science & Technology)

Journal Articles

Progresses in development of the ITER edge Thomson scattering system

Yatsuka, Eiichi; Bassan, M.*; Hatae, Takaki; Ishikawa, Masao; Shimada, Takahiko; Vayakis, G.*; Walsh, M.*; Scannell, R.*; Huxford, R.*; Bilkova, P.*; et al.

Journal of Instrumentation (Internet), 8(12), p.C12001_1 - C12001_10, 2013/12

 Times Cited Count:12 Percentile:49.93(Instruments & Instrumentation)

Journal Articles

Chevron beam dump for ITER edge Thomson scattering system

Yatsuka, Eiichi; Hatae, Takaki; Vayakis, G.*; Bassan, M.*; Itami, Kiyoshi

Review of Scientific Instruments, 84(10), p.103503_1 - 103503_6, 2013/10

 Times Cited Count:10 Percentile:44.65(Instruments & Instrumentation)

Journal Articles

Port-based plasma diagnostic infrastructure on ITER

Pitcher, C. S.*; Barnsley, R.*; Bertalot, L.*; Encheva, A.*; Feder, R.*; Friconneau, J. P.*; Hu, Q.*; Levesy, B.*; Loesser, G. D.*; Lyublin, B.*; et al.

Fusion Science and Technology, 64(2), p.118 - 125, 2013/08

 Times Cited Count:4 Percentile:32.48(Nuclear Science & Technology)

The port-based plasma diagnostic infrastructure on ITER is described, including the port plugs, the interspace support structure and port cell structure. These systems are modular in nature with standardized dimensions. The design of the equatorial and upper port plugs and their modules is discussed, as well as the dominant loading mechanisms. The port infrastructure design has now matured to the point that port plugs are now being populated with multiple diagnostics supplied by a number of ITER partners - two port plug examples are given.

Journal Articles

Actuator and diagnostic requirements of the ITER plasma control system

Snipes, J. A.*; Beltran, D.*; Casper, T.*; Gribov, Y.*; Isayama, Akihiko; Lister, J.*; Simrock, S.*; Vayakis, G.*; Winter, A.*; Yang, Y.*; et al.

Fusion Engineering and Design, 87(12), p.1900 - 1906, 2012/12

 Times Cited Count:25 Percentile:85.94(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Neutronic analysis of the ITER poloidal polarimeter

Ishikawa, Masao; Kawano, Yasunori; Imazawa, Ryota; Sato, Satoshi; Vayakis, G.*; Bertalot, L.*; Yatsuka, Eiichi; Hatae, Takaki; Kondoh, Takashi; Kusama, Yoshinori

Fusion Engineering and Design, 86(6-8), p.1286 - 1289, 2011/10

 Times Cited Count:1 Percentile:10.73(Nuclear Science & Technology)

The nuclear heating rates of the optical mirrors of the poloidal polarimeter installed in the equatorial port plug of ITER are calculated. Since the system cannot have a sufficiently labyrinthine structure and the second mirrors are located nearly as close to the plasma as the first mirrors due to limited space, the nuclear heating rate of the second mirrors is as high as that of the first mirrors. However, it is possible to reduce the nuclear heating rates of the mirrors if the blanket shield module provides a sufficient degree of neutron shielding.

Journal Articles

Nuclear technology aspects of ITER vessel-mounted diagnostics

Vayakis, G.*; Bertalot, L.*; Encheva, A.*; Walker, C.*; Brichard, B.*; Cheon, M. S.*; Chitarin, G.*; Hodgson, E.*; Ingesson, C.*; Ishikawa, Masao; et al.

Journal of Nuclear Materials, 417(1-3), p.780 - 786, 2011/10

 Times Cited Count:27 Percentile:87.94(Materials Science, Multidisciplinary)

Journal Articles

Plasma boundary and first-wall diagnostics in ITER

Pitcher, C. S.*; Andrew, P.*; Barnsley, R.*; Bertalot, L.*; Counsell, G. G.*; Encheva, A.*; Feder, R. E.*; Hatae, Takaki; Johnson, D. W.*; Kim, J.*; et al.

Journal of Nuclear Materials, 415(Suppl.1), p.S1127 - S1132, 2011/08

 Times Cited Count:0 Percentile:0.01(Materials Science, Multidisciplinary)

Journal Articles

Overview of high priority ITER diagnostic systems status

Walsh, M.*; Andrew, P.*; Barnsley, R.*; Bertalot, L.*; Boivin, R.*; Bora, D.*; Bouhamou, R.*; Ciattaglia, S.*; Costley, A. E.*; Counsell, G.*; et al.

Proceedings of 23rd IAEA Fusion Energy Conference (FEC 2010) (CD-ROM), 8 Pages, 2011/03

Journal Articles

Defining the infrared systems for ITER

Reichle, R.*; Andrew, P.*; Counsell, G.*; Drevon, J.-M.*; Encheva, A.*; Janeschitz, G.*; Johnson, D. W.*; Kusama, Yoshinori; Levesy, B.*; Martin, A.*; et al.

Review of Scientific Instruments, 81(10), p.10E135_1 - 10E135_5, 2010/10

 Times Cited Count:30 Percentile:75.22(Instruments & Instrumentation)

Journal Articles

Progress in the ITER physics basis, 7; Diagnostics

Donn$'e$, A. J. H.*; Costley, A. E.*; Barnsley, R.*; Bindslev, H.*; Boivin, R.*; Conway, G.*; Fisher, R.*; Giannella, R.*; Hartfuss, H.*; von Hellermann, M. G.*; et al.

Nuclear Fusion, 47(6), p.S337 - S384, 2007/06

 Times Cited Count:331 Percentile:78.95(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

The Design and implementation of diagnostic systems on ITER

Costley, A. E.*; Walker, C. I.*; Bertalot, L.*; Barnsley, R.*; Itami, Kiyoshi; Sugie, Tatsuo; Vayakis, G.*

Proceedings of 21st IAEA Fusion Energy Conference (FEC 2006) (CD-ROM), 8 Pages, 2007/03

In order to meet the needs for first wall and plasma measurements, ITER will require about 40 different diagnostic systems drawn from all the main generic diagnostic groups - magnetics, neutron systems, optical and microwave systems, spectroscopic, bolometric, probes, pressure gauges and gas analysers. The design and implementation is a major challenge because of the harsh environment in which many of the diagnostic components are located coupled with the restricted access and the need to meet stringent engineering requirements arising from the fact that ITER will be a nuclear device. It has stimulated an extensive design and R&D programme and the development of some novel approaches to diagnostic installation: for example, the use of plugs with custom modules at the upper and equatorial levels that serve both to support the diagnostic components and to provide the necessary shielding of the neutrons. The difficulties of implementation are summarized and the novel solutions described.

Journal Articles

Multiplexing thermography for International Thermonuclear Experimental Reactor divertor targets

Itami, Kiyoshi; Sugie, Tatsuo; Vayakis, G.*; Walker, C.*

Review of Scientific Instruments, 75(10), p.4124 - 4128, 2004/10

 Times Cited Count:10 Percentile:48.76(Instruments & Instrumentation)

no abstracts in English

Journal Articles

Radiation-induced thermoelectric sensitivity in the mineral-insulated cable of magnetic diagnostic coils for ITER

Nishitani, Takeo; Vayakis, G.*; Yamauchi, Michinori*; Sugie, Tatsuo; Kondoh, Takashi; Shikama, Tatsuo*; Ishitsuka, Etsuo; Kawashima, Hisato

Journal of Nuclear Materials, 329-333(Part2), p.1461 - 1465, 2004/08

 Times Cited Count:16 Percentile:70(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Overview of physics basis for ITER

Mukhovatov, V.*; Shimada, Michiya; Chudnovskiy, A. N.*; Costley, A. E.*; Gribov, Y.*; Federici, G.*; Kardaun, O. J. F.*; Kukushkin, A. S.*; Polevoi, A. R.*; Pustovitov, V. D.*; et al.

Plasma Physics and Controlled Fusion, 45(12), p.235 - 252, 2003/12

 Times Cited Count:55 Percentile:82.78(Physics, Fluids & Plasmas)

ITER will be the first magnetic confinement device with burning DT plasma and fusion power of about 0.5 GW. During the past few years, new results have been obtained that substantiate the confidence in achieving Q $$>$$ 10 in ITER with inductive H-mode operation. These include achievement of a good H-mode confinement near the Greenwald density at high triangularity of the plasma cross section; improvements in theory-based confinement projections for the core plasma; improvement in helium ash removal due to the elastic collisions of He atoms with D/T ions in the divertor predicted by modelling; demonstration of feedback control of NTMs and resultant improvement in the achievable beta-values; better understanding of ELM physics and development of ELM mitigation techniques; and demonstration of mitigation of plasma disruptions. ITER will have a flexibility to operate also in steady state and intermediate (hybrid) regimes. The paper concentrates on inductively driven plasma performance and discusses requirements for steady-state operation in ITER.

Journal Articles

Performance assessment of ITER-FEAT

Murakami, Yoshiki*; Senda, Ikuo; Chudnovskiy, A.*; Vayakis, G.*; Polevoi, A. R.*; Shimada, Michiya

Purazuma, Kaku Yugo Gakkai-Shi, 73(7), p.712 - 729, 2001/07

no abstracts in English

Journal Articles

Plasma diagnostics for ITER-FEAT

Ebisawa, Katsuyuki*; Costley, A.*; Donn$'e$, A. J. H.*; Janeschitz, G.*; Kasai, Satoshi; Malaquias, A.*; Vayakis, G.*; Walker, C. I.*; Yamamoto, Shin; Zavariaev, V.*

Review of Scientific Instruments, 72(1), p.545 - 550, 2001/01

 Times Cited Count:18 Percentile:67.48(Instruments & Instrumentation)

no abstracts in English

Oral presentation

Study of an erosion measurement for ITER divertor targets

Itami, Kiyoshi; Sugie, Tatsuo; Vayakis, G.*; Walker, C.*

no journal, , 

no abstracts in English

Oral presentation

Neutronic analysis for ITER poloidal polarimeter

Ishikawa, Masao; Kawano, Yasunori; Imazawa, Ryota; Sato, Satoshi; Vayakis, G.*; Bertalot, L.*; Yatsuka, Eiichi; Hatae, Takaki; Kondoh, Takashi; Kusama, Yoshinori

no journal, , 

The nuclear heating rates of the optical mirrors of the poloidal polarimeter installed in the equatorial port plug of ITER are calculated. Since the system cannot have a sufficiently labyrinthine structure and the second mirrors are located nearly as close to the plasma as the first mirrors due to limited space, the nuclear heating rate of the second mirrors is as high as that of the first mirrors. However, it is possible to reduce the nuclear heating rates of the mirrors if the blanket shield module provides a sufficient degree of neutron shielding.

Oral presentation

Recent progress in development of the edge Thomson scattering in ITER

Hatae, Takaki; Yatsuka, Eiichi; Bassan, M.*; Vayakis, G.*; Walsh, M.*; Itami, Kiyoshi

no journal, , 

no abstracts in English

23 (Records 1-20 displayed on this page)