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Yatsuka, Eiichi; Hatae, Takaki; Suito, Satoshi*; Ohara, Miyuki*; Hagita, Koji*; Inoue, Kazunori*; Bassan, M.*; Walsh, M.*; Itami, Kiyoshi
Journal of Instrumentation (Internet), 11(1), p.C01006_1 - C01006_12, 2016/01
Times Cited Count：7 Percentile：32.76(Instruments & Instrumentation)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：42.97(Nuclear Science & Technology)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：15 Percentile：54.76(Instruments & Instrumentation)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：5 Percentile：36.52(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.
Vostner, A.*; Pong, I.*; Bessette, D.*; Devred, A.*; Sgobba, S.*; Jung, A.*; Weiss, K.-P.*; Jewell, M. C.*; Liu, S.*; Yu, W.*; et al.
IEEE Transactions on Applied Superconductivity, 23(3), p.9500705_1 - 9500705_5, 2013/06
Times Cited Count：13 Percentile：53.89(Engineering, Electrical & Electronic)The ITER Cable-In-Conduit Conductor (CICC) used in the superconducting magnet system consists of a cable made of 300 to 1440 strands housed in a stainless steel tube (a.k.a. jacket or conduit). There are circular, square, as well as circle-in-square jackets, made of either a very low carbon AISI 316LN grade stainless steel or a high Mn austenitic stainless steel developed for ITER called JK2LB. Selected mechanical properties of the base material and weld joint were tested at room temperature and/or cryogenic temperatures (
7 K). The Domestic Agencies (DAs) reference laboratories and the ITER-IO appointed reference laboratories, CERN and Karlsruhe Institute of Technology (KIT) performed mechanical tests. This paper will compare the test results (e.g. elongation to failure) from different laboratories.
Pitcher, C. S.*; Barnsley, R.*; Feder, R.*; Hu, Q.*; Loesser, G. D.*; Lyublin, B.*; Padasalagi, S.*; Pak, S.*; Reichle, R.*; Sato, Kazuyoshi; et al.
Fusion Engineering and Design, 87(5-6), p.667 - 674, 2012/08
Times Cited Count：12 Percentile：64.33(Nuclear Science & Technology)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：0.00(Materials Science, Multidisciplinary)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
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：35 Percentile：75.61(Instruments & Instrumentation)McDonald, D. C.*; Cordey, J. G.*; Thomsen, K.*; Kardaun, O. J. W. F.*; Snipes, J. A.*; Greenwald, M.*; Sugiyama, L.*; Ryter, F.*; Kus, A.*; Stober, J.*; et al.
Nuclear Fusion, 47(3), p.147 - 174, 2007/03
Times Cited Count：54 Percentile：28.07(Physics, Fluids & Plasmas)This paper describes the updates to and analysis of the International Tokamak Physics Activity (ITPA) Global H-node Confinement Database version 3 (DB3) over the period 1994-2004. Global data, for the energy confinement time and its controlling parameters, have now been collected from 18 machines of different sizes and shapes: ASDEX, ASDEX Upgrade, C-Mod CoMPASS-D, DIII-D, JET, JFT-2M, JT-60U, MAST, NSTX, PBX-M, PDX, START, T-10, TCV, TdeV, TFTR and TUMAN-3M. A wide range of physics studies has been performed on DB3 with particular progress made in the separation of core and edge behavior, dimensionless parameter analyses and the comparison of the database with one-dimensional transport code. A key aim of the database has always been to provide a basis for estimating the energy confinement properties of next step machines such as ITER, and so the impact of the database and its analysis on such machines is also discussed.
and collisionality approaching ITER conditionsCordey, J. G.*; Thomsen, K.*; Chudnovskiy, A.*; Kardaun, O. J. W. F.*; Takizuka, Tomonori; Snipes, J. A.*; Greenwald, M.*; Sugiyama, L.*; Ryter, F.*; Kus, A.*; et al.
Nuclear Fusion, 45(9), p.1078 - 1084, 2005/09
Times Cited Count：53 Percentile：82.21(Physics, Fluids & Plasmas)The condition of the latest version of the ELMy H-mode database has been re-examined. It is shown that there is bias in the ordinary least squares regression for some of the variables. To address these shortcomings three different techniques are employed: (a)principal component regression, (b)an error in variables technique and (c)the selection of a better conditioned dataset with fewer variables. Scalings in terms of the dimensionless physics valiables, as well as the standard set of engineering variables, are derived. The new scalings give a very similar performance for existing scalings for ITER at the standard beta, but a much improvement performance at higher beta.
Yatsuka, Eiichi; Hatae, Takaki; Bassan, M.*; Vayakis, G.*; Walsh, M.*; Itami, Kiyoshi
no journal, ,
no abstracts in English
Yatsuka, Eiichi; Hatae, Takaki; Kitazawa, Sin-iti; Vayakis, G.*; Bassan, M.*; Walsh, M.*; Itami, Kiyoshi
no journal, ,
no abstracts in English
Yatsuka, Eiichi; Hatae, Takaki; Takeyama, Shigeharu; Bassan, M.*; Vayakis, G.*; Walsh, M.*; Itami, Kiyoshi
no journal, ,
In ITER, 10
pulses of 5-J laser will be injected during its operation for 20 years. It was concerned that the surface damage was induced due to high incident laser energy density if conventional beam dump would be used. JAEA has proposed and modified the detailed shape of a new type beam dump in which the laser energy is reflected numerous times and absorbed gradually due to low absorptance of the S-polarized light. The new type beam dump withstands 10 pulses injection while conventional beam dump withstands 10
pulses (100 seconds) injection. In order to verify this design for drastically extending the beam dump life time, laser resistance test for molybdenum that is the beam dump material was carried out. As expected in design, beam energy absorption density is dominant factor for laser induced damage. Moreover, it was confirmed that interlaminating the bent sheets and shims and their diffuse bonding enable to manufacture complicated shape of the beam dump as designed.
Hatae, Takaki; Yatsuka, Eiichi; Bassan, M.*; Vayakis, G.*; Walsh, M.*; Itami, Kiyoshi
no journal, ,
no abstracts in English
