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                             142 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 A coupled EDDY/PIC/ELECTRAN simulation of erosion and deposition in gaps Inai, K.
 2010
 85 7-9 p. 1416-1420
5 p.
 artikel
2 Advances in inertial confinement fusion at the National Ignition Facility (NIF) Moses, Edward I.
 2010
 85 7-9 p. 983-986
4 p.
 artikel
3 Analysis of the tritium breeding ratio benchmark experiments using the Monte Carlo code TRIPOLI-4 Lee, Yi-Kang
 2010
 85 7-9 p. 1125-1128
4 p.
 artikel
4 An overview of the US DCLL ITER-TBM program Wong, C.P.C.
 2010
 85 7-9 p. 1129-1132
4 p.
 artikel
5 A recent version of MELCOR for fusion safety applications Merrill, Brad J.
 2010
 85 7-9 p. 1479-1483
5 p.
 artikel
6 Author Index 2010
 85 7-9 p. I-VIII
nvt p.
 artikel
7 Behavior of tritium accumulated on materials surface Otsuka, Teppei
 2010
 85 7-9 p. 1437-1441
5 p.
 artikel
8 Characterization and improvement of water compatibility of γ-LiAlO2 ceramic breeders Lin, Jiu
 2010
 85 7-9 p. 1162-1166
5 p.
 artikel
9 Characterization of SiC based composite materials by the infiltration of ultra-fine SiC particles Lee, J.K.
 2010
 85 7-9 p. 1376-1380
5 p.
 artikel
10 Chemical stability of LiYO2 as an insulating material Nagura, Masaru
 2010
 85 7-9 p. 1098-1101
4 p.
 artikel
11 Codes and standards and regulation issues for design and construction of the ITER mechanical components Barabash, V.
 2010
 85 7-9 p. 1290-1295
6 p.
 artikel
12 Compatibility of atmospheric plasma sprayed Al2O3 coatings on CLAM with liquid LiPb Guo, Zhihui
 2010
 85 7-9 p. 1469-1473
5 p.
 artikel
13 Compatibility of PIP SiCf/SiC with LiPb at 700°C Zhao, Shuang
 2010
 85 7-9 p. 1624-1626
3 p.
 artikel
14 Conceptual design of EAST flexible in-vessel inspection system Peng, X.B.
 2010
 85 7-9 p. 1362-1365
4 p.
 artikel
15 Configuration and operation of detritiation systems for ITER Tokamak Complex Beloglazov, S.
 2010
 85 7-9 p. 1670-1674
5 p.
 artikel
16 Construction of the plasma-wall experiment Magnum-PSI Rapp, J.
 2010
 85 7-9 p. 1455-1459
5 p.
 artikel
17 Corrosion of reduced activation ferritic martensitic steel JLF-1 in purified Flinak at static and flowing conditions Kondo, Masatoshi
 2010
 85 7-9 p. 1430-1436
7 p.
 artikel
18 3D assessment of nuclear heating, dose rate, and structural damage in the generic ITER diagnostics upper port plugs and adjacent magnet coils Youssef, Mahmoud Z.
 2010
 85 7-9 p. 1173-1180
8 p.
 artikel
19 3D CFD analysis of subcooled flow boiling heat transfer with hypervapotron configurations for ITER first wall designs Ying, A.
 2010
 85 7-9 p. 1348-1353
6 p.
 artikel
20 DEMO relevance of the test blanket modules in ITER—Application to the European test blanket modules Magnani, E.
 2010
 85 7-9 p. 1271-1278
8 p.
 artikel
21 Densification of nano-SiC by ultra-high pressure effects of time, temperature and pressure Mao-lin, Xie
 2010
 85 7-9 p. 964-968
5 p.
 artikel
22 Detection efficiency of plastic scintillator for gaseous tritium sampling and measurement system Uda, Tatsuhiko
 2010
 85 7-9 p. 1474-1478
5 p.
 artikel
23 Development and application of SN Auto-Modeling Tool SNAM 2.1 Long, Pengcheng
 2010
 85 7-9 p. 1113-1116
4 p.
 artikel
24 Development and testing of multigroup library with correction of self-shielding effects in fusion–fission hybrid reactor Zou, Jun
 2010
 85 7-9 p. 1587-1590
4 p.
 artikel
25 Development of anti-corrosion coating on low activation materials against fluoridation and oxidation in Flibe blanket environment Nagasaka, Takuya
 2010
 85 7-9 p. 1261-1265
5 p.
 artikel
26 Development of measurement technique for surface waves on high-speed liquid lithium jet for IFMIF target Kondo, Hiroo
 2010
 85 7-9 p. 1102-1105
4 p.
 artikel
27 Direct decomposition of methane using helium RF plasma Katayama, Kazunari
 2010
 85 7-9 p. 1381-1385
5 p.
 artikel
28 Direct numerical simulation of unstable stratified turbulent flow under a magnetic field Satake, Shin-ichi
 2010
 85 7-9 p. 1326-1330
5 p.
 artikel
29 3D Monte Carlo vacuum modeling of the neutral beam injection system of ITER Luo, X.
 2010
 85 7-9 p. 1446-1450
5 p.
 artikel
30 2D SiC/SiC composite for flow channel insert (FCI) application Yu, Haijiao
 2010
 85 7-9 p. 1693-1696
4 p.
 artikel
31 Effect of high temperature corrosion in liquid lithium on mechanical properties of beryllium Kupriyanov, I.B.
 2010
 85 7-9 p. 1702-1706
5 p.
 artikel
32 Effect of oxygen on hydrogen retention in W deposition layers formed by hydrogen RF plasma Fujiki, Toshiya
 2010
 85 7-9 p. 1094-1097
4 p.
 artikel
33 Effect of surface water on tritium release behavior from Li4SiO4 Hanada, T.
 2010
 85 7-9 p. 998-1001
4 p.
 artikel
34 Effect of Ta-doping on the ionic conductivity of lithium titanate Wu, Xiangwei
 2010
 85 7-9 p. 1442-1445
4 p.
 artikel
35 Effects of simultaneous transfer of heat and tritium through Li–Pb or Flibe blanket Fukada, S.
 2010
 85 7-9 p. 1314-1319
6 p.
 artikel
36 Evaluation of deuterium permeation reduction factor of various coatings deposited on ferritic/martensitic steels for development of tritium permeation barrier Nakamura, Hirofumi
 2010
 85 7-9 p. 1531-1536
6 p.
 artikel
37 Evaluation of microstructure and mechanical properties of liquid phase diffusion bonded ODS steels Noh, Sanghoon
 2010
 85 7-9 p. 1033-1037
5 p.
 artikel
38 Explosive detection system using pulsed 14MeV neutron source Sharma, Surender Kumar
 2010
 85 7-9 p. 1562-1564
3 p.
 artikel
39 Findings of the US research needs workshop on the topic of fusion power Meier, W.R.
 2010
 85 7-9 p. 969-973
5 p.
 artikel
40 First results on the effect of direct quenching on mechanical properties and anelastic relaxation in CLAM steel Qiu, J.
 2010
 85 7-9 p. 1556-1561
6 p.
 artikel
41 Heat transfer enhancement of free surface MHD-flow by a protrusion wall Huang, Hulin
 2010
 85 7-9 p. 1496-1502
7 p.
 artikel
42 Heat transfer in SiC compact heat exchanger Takeuchi, Y.
 2010
 85 7-9 p. 1266-1270
5 p.
 artikel
43 Hydraulic analysis of the water-cooled blanket based on the sub-critical water condition Liu, C.
 2010
 85 7-9 p. 979-982
4 p.
 artikel
44 Hydrogen/dust explosion hazard in ITER: Effect of nitrogen dilution on explosion behavior of hydrogen/tungsten dust/air mixtures Denkevits, A.
 2010
 85 7-9 p. 1059-1063
5 p.
 artikel
45 Impact of various plasma instabilities on reliability and performance of tokamak fusion devices Hassanein, A.
 2010
 85 7-9 p. 1331-1335
5 p.
 artikel
46 Integration of IC/EC systems in ITER Gassmann, T.
 2010
 85 7-9 p. 1245-1249
5 p.
 artikel
47 Interfacial reaction and diffusion control between SiC and F82H steel Zhong, Zhihong
 2010
 85 7-9 p. 992-997
6 p.
 artikel
48 Investigation of alternative configurations of the LLCB TBM to increase neutronic and thermo-hydraulics performances Kirillov, I.R.
 2010
 85 7-9 p. 1054-1058
5 p.
 artikel
49 Investigation of coating CLAM steel substrates with erbium oxide by a magnetron sputtering method Liu, Shuai
 2010
 85 7-9 p. 1401-1405
5 p.
 artikel
50 Ion-beam assisted deposition of coating interlayers for the joining of Be/CuCrZr Jung, Yang-Il
 2010
 85 7-9 p. 1689-1692
4 p.
 artikel
51 Isotopic exchange between hydrogen and deuterium in the process of permeating through Li0.17Pb0.83 Edao, Y.
 2010
 85 7-9 p. 1225-1228
4 p.
 artikel
52 ITER vacuum vessel design and construction Ioki, K.
 2010
 85 7-9 p. 1307-1313
7 p.
 artikel
53 JET operating experience: Global analysis of tritium plant failure Pinna, T.
 2010
 85 7-9 p. 1396-1400
5 p.
 artikel
54 Manufacturing of U–10wt% Mo powder by hydride–dehydride processing Xiong, Yi-Fu
 2010
 85 7-9 p. 1492-1495
4 p.
 artikel
55 Manufacturing studies of structural components for the ITER EC upper launcher Spaeh, Peter
 2010
 85 7-9 p. 1406-1409
4 p.
 artikel
56 Measurement of TPR distribution in natural Li2TiO3/Be assembly with DT neutrons Kondo, Keitaro
 2010
 85 7-9 p. 1229-1233
5 p.
 artikel
57 Mechanical design and first experimental results of an upgraded technical PERMCAT reactor for tritium recovery in the fuel cycle of a fusion machine Welte, S.
 2010
 85 7-9 p. 1320-1325
6 p.
 artikel
58 Mechanical measurements in RFX-mod experiment Palma, M. Dalla
 2010
 85 7-9 p. 1279-1282
4 p.
 artikel
59 MHD considerations for the DCLL inboard blanket and access ducts Smolentsev, Sergey
 2010
 85 7-9 p. 1007-1011
5 p.
 artikel
60 MHD pressure drop characteristics in a three-surface-multi-layered channel under a strong magnetic field Aoyagi, M.
 2010
 85 7-9 p. 1181-1184
4 p.
 artikel
61 MHD thermofluid issues of liquid-metal blankets: Phenomena and advances Smolentsev, Sergey
 2010
 85 7-9 p. 1196-1205
10 p.
 artikel
62 Microstructure and mechanical property of 12Cr oxide dispersion strengthened ferritic steel for fusion application Li, Ming
 2010
 85 7-9 p. 1573-1576
4 p.
 artikel
63 Microstructure and thermal property of tungsten coatings prepared by vacuum plasma spraying technology Niu, Yaran
 2010
 85 7-9 p. 1521-1526
6 p.
 artikel
64 Microstructure control and deuterium permeability of erbium oxide coating on ferritic/martensitic steels by metal-organic decomposition Chikada, Takumi
 2010
 85 7-9 p. 1537-1541
5 p.
 artikel
65 Modelling of wall and SOL processes and contamination of ITER plasma after impurity injection with the tokamak code TOKES Landman, I.S.
 2010
 85 7-9 p. 1366-1370
5 p.
 artikel
66 Modification of a solid polymer electrolyte (SPE) electrolyser to ensure tritium compatibility Eichelhardt, F.
 2010
 85 7-9 p. 1211-1214
4 p.
 artikel
67 Molecular dynamics and dynamic Monte Carlo studies of mixed materials and their impact on plasma wall interactions Ohya, K.
 2010
 85 7-9 p. 1167-1172
6 p.
 artikel
68 Molecular dynamics simulation of low-energy atomic hydrogen on tungsten surface Yang, Zhongshi
 2010
 85 7-9 p. 1517-1520
4 p.
 artikel
69 Neutronic analysis of the HCPB TBM in ITER utilizing an advanced integral approach Pereslavtsev, P.
 2010
 85 7-9 p. 1653-1658
6 p.
 artikel
70 Neutronics assessment of the shielding and breeding requirements for FNSF (standard aspect ratio) Liu, Haibo
 2010
 85 7-9 p. 1296-1300
5 p.
 artikel
71 Neutronics experiments on HCPB and HCLL TBM mock-ups in preparation of nuclear measurements in ITER Batistoni, P.
 2010
 85 7-9 p. 1675-1680
6 p.
 artikel
72 Nitride-strengthened reduced activation ferritic/martensitic steels Hu, Ping
 2010
 85 7-9 p. 1632-1637
6 p.
 artikel
73 Non-destructive examination with infrared thermography system for ITER divertor components Seki, Yohji
 2010
 85 7-9 p. 1451-1454
4 p.
 artikel
74 Nuclear design analyses of the helium cooled lithium lead blanket for a fusion power demonstration reactor Fischer, U.
 2010
 85 7-9 p. 1133-1138
6 p.
 artikel
75 Numerical analysis of heat transfer in the concentric recuperator for Chinese multifunctional experimental loop DRAGON-IV Wang, Wei-hua
 2010
 85 7-9 p. 1598-1602
5 p.
 artikel
76 Numerical Simulation of Nature Convection and Heat Transfer of the Liquid LiPb in Cubic Enclosure with a Magnetic Field Wang, H.Y.
 2010
 85 7-9 p. 1215-1219
5 p.
 artikel
77 Numerical simulation of turbulent flow in microscopic pore scale of pebble bed by large-eddy simulation Ebara, S.
 2010
 85 7-9 p. 1638-1641
4 p.
 artikel
78 Numerical simulation on bake-out of the ITER diagnostic upper port plug Pak, S.
 2010
 85 7-9 p. 1627-1631
5 p.
 artikel
79 On the hyperporous non-linear elasticity model for fusion-relevant pebble beds Di Maio, P.A.
 2010
 85 7-9 p. 1234-1244
11 p.
 artikel
80 Operating experiences from existing fusion facilities in view of ITER safety and reliability Pinna, T.
 2010
 85 7-9 p. 1410-1415
6 p.
 artikel
81 Out of pile tritium release behaviour and microscopic investigation of lithium metatitanate irradiated in the High Flux Reactor in Petten van Til, S.
 2010
 85 7-9 p. 1143-1146
4 p.
 artikel
82 Overview of the JET ITER-like Wall Project Philipps, V.
 2010
 85 7-9 p. 1581-1586
6 p.
 artikel
83 Packing experiment of breeder pebbles into water cooled solid breeder test blanket module for ITER Hirose, Takanori
 2010
 85 7-9 p. 1426-1429
4 p.
 artikel
84 Performances of inert gas glow discharges for reductions of fuel hydrogen retention and helium retention Hino, T.
 2010
 85 7-9 p. 974-978
5 p.
 artikel
85 Preliminary studies on MHD simulation and heat transfer analysis for LLCB TBM Goswami, K.S.
 2010
 85 7-9 p. 1371-1375
5 p.
 artikel
86 Preparation of Mg and Al phosphate coatings on ferritic steel by wet-chemical method as tritium permeation barrier Zhang, Kun
 2010
 85 7-9 p. 1090-1093
4 p.
 artikel
87 Proceedings of the Ninth International Symposium on Fusion Nuclear Technology Abdou, M.A.
 2010
 85 7-9 p. 963-
1 p.
 artikel
88 Progress in technology and experiment of superconducting tokamaks in ASIPP Wan, Baonian
 2010
 85 7-9 p. 1048-1053
6 p.
 artikel
89 Progress in the development of insulator coating for liquid lithium blankets Muroga, T.
 2010
 85 7-9 p. 1301-1306
6 p.
 artikel
90 Progress in the development of reduced activation ferritic-martensitic steels and fabrication technologies in India Raj, Baldev
 2010
 85 7-9 p. 1460-1468
9 p.
 artikel
91 Progress of conversion system from CAD data to MCNP geometry data in Japan Sato, S.
 2010
 85 7-9 p. 1546-1550
5 p.
 artikel
92 Progress on an integrated multi-physics simulation predictive capability for plasma chamber nuclear components Ying, A.
 2010
 85 7-9 p. 1681-1688
8 p.
 artikel
93 RAMI Approach for ITER van Houtte, D.
 2010
 85 7-9 p. 1220-1224
5 p.
 artikel
94 R&D activities on helium cooled solid breeder TBM in Korea Cho, S.
 2010
 85 7-9 p. 1608-1614
7 p.
 artikel
95 R&D issues of W/Cu divertor for EAST Li, Q.
 2010
 85 7-9 p. 1106-1112
7 p.
 artikel
96 R&D of atmosphere detritiation system for ITER in JAEA Hayashi, Takumi
 2010
 85 7-9 p. 1386-1390
5 p.
 artikel
97 R&D of the key components for ITER magnet supports Lee, P.Y.
 2010
 85 7-9 p. 1603-1607
5 p.
 artikel
98 R&D on major components of control system for ITER blanket maintenance equipment Takeda, Nobukazu
 2010
 85 7-9 p. 1190-1195
6 p.
 artikel
99 Real-time dose assessment and visualization of radiation field for EAST tokamak Tang, Zhengdao
 2010
 85 7-9 p. 1591-1594
4 p.
 artikel
100 Recent activities on tritium technologies of BA DEMO-R&D program in JAEA Yamanishi, Toshihiko
 2010
 85 7-9 p. 1002-1006
5 p.
 artikel
101 Recent R&D results on polymeric materials for a SPE-type high-level tritiated water electrolyzer system Iwai, Yasunori
 2010
 85 7-9 p. 1421-1425
5 p.
 artikel
102 Recovery of hydrogen from gas mixture by an intermediate-temperature type proton conductor Tanaka, M.
 2010
 85 7-9 p. 1038-1043
6 p.
 artikel
103 Removal rates of hydrogen isotope from liquid Li by HF-treated Y plate Wu, Y.
 2010
 85 7-9 p. 1484-1487
4 p.
 artikel
104 Renewed first wall coating in plasma shots at the T-11M tokamak Buzhinskij, O.I.
 2010
 85 7-9 p. 1615-1617
3 p.
 artikel
105 Requirements and proposals for control and monitoring measurements of the HCLL TBM Puma, A. Li
 2010
 85 7-9 p. 1642-1652
11 p.
 artikel
106 Research Needs Workshop for Magnetic Fusion Energy Science Hazeltine, R.D.
 2010
 85 7-9 p. 1016-1026
11 p.
 artikel
107 Research on the preparation of ceramic tritium breeders in SICCAS Wen, Zhaoyin
 2010
 85 7-9 p. 1551-1555
5 p.
 artikel
108 Results of acoustic monitoring of ITER divertor vertical target prototype Courtois, X.
 2010
 85 7-9 p. 1391-1395
5 p.
 artikel
109 Review of stellarator/heliotron design issues towards MFE DEMO Sagara, Akio
 2010
 85 7-9 p. 1336-1341
6 p.
 artikel
110 Risk mitigation strategy for the ITER electron cyclotron upper port launcher Goede, A.P.H.
 2010
 85 7-9 p. 1117-1124
8 p.
 artikel
111 Search for reality of solid breeder blanket for DEMO Tobita, K.
 2010
 85 7-9 p. 1342-1347
6 p.
 artikel
112 Selection of bounding events for ITER DFLL-TBM safety analysis Hu, Liqin
 2010
 85 7-9 p. 1577-1580
4 p.
 artikel
113 Simulation of tungsten armour cracking due to small ELMs in ITER Pestchanyi, S.
 2010
 85 7-9 p. 1697-1701
5 p.
 artikel
114 Simulation on the welding of CLAM steel Lei, Yu-cheng
 2010
 85 7-9 p. 1503-1507
5 p.
 artikel
115 Sol–gel prepared Al2O3 coatings for the application as tritium permeation barrier Wang, Tianshi
 2010
 85 7-9 p. 1068-1072
5 p.
 artikel
116 Status of R&D on fusion materials in institute of nuclear materials in USTB Chang-Chun, Ge
 2010
 85 7-9 p. 1080-1084
5 p.
 artikel
117 Strength analysis results for the RF “modified” option of the shielding block for ITER blanket module Sviridenko, M.N.
 2010
 85 7-9 p. 1354-1361
8 p.
 artikel
118 Study of isotope exchange reactions on ceramic breeder materials deposited with noble metal Mochizuki, Kazuhiro
 2010
 85 7-9 p. 1185-1189
5 p.
 artikel
119 Study on the fuel balance of a DT reactor Nishikawa, Masabumi
 2010
 85 7-9 p. 987-991
5 p.
 artikel
120 SVIP-N 1.0: An integrated visualization platform for neutronics analysis Luo, Yuetong
 2010
 85 7-9 p. 1527-1530
4 p.
 artikel
121 TechnoFusión, a relevant facility for fusion technologies: The remote handling area Ibarra, A.
 2010
 85 7-9 p. 1659-1663
5 p.
 artikel
122 The ancillary systems of the European test blanket modules: Configuration and integration in TIER Ricapito, I.
 2010
 85 7-9 p. 1154-1161
8 p.
 artikel
123 The development of joining doped graphite to copper for first wall application in HT-7 tokamak Zhou, Zhangjian
 2010
 85 7-9 p. 1513-1516
4 p.
 artikel
124 The first in-vessel cryopump for EAST divertor experiment Hu, Q.S.
 2010
 85 7-9 p. 1508-1512
5 p.
 artikel
125 The impact of lithium wall coatings on NSTX discharges and the engineering of the Lithium Tokamak eXperiment (LTX) Majeski, R.
 2010
 85 7-9 p. 1283-1289
7 p.
 artikel
126 The potential presence and minimisation of plutonium within the irradiated beryllium in fusion power plants Cambi, G.
 2010
 85 7-9 p. 1139-1142
4 p.
 artikel
127 The radiation analyses of ITER lower ports Petrizzi, L.
 2010
 85 7-9 p. 1085-1089
5 p.
 artikel
128 Thermal–mechanical and thermal–hydraulic integrated study of the Helium-Cooled Lithium Lead Test Blanket Module Chiovaro, P.
 2010
 85 7-9 p. 1147-1153
7 p.
 artikel
129 Thermo-hydraulic and thermo-mechanical analysis of Korean helium cooled solid breeder TBM Ahn, Mu-Young
 2010
 85 7-9 p. 1664-1669
6 p.
 artikel
130 Thermo-hydraulic testing and integrity of ITER Test Blanket Module (TBM) First Wall mock-up in JAEA Ezato, K.
 2010
 85 7-9 p. 1255-1260
6 p.
 artikel
131 Thermo-mechanical design of the Plasma Driver Plate for the MITICA ion source Pavei, Mauro
 2010
 85 7-9 p. 1073-1079
7 p.
 artikel
132 Three-dimensional nuclear analysis for the US dual coolant lead lithium ITER test blanket module Sawan, M.E.
 2010
 85 7-9 p. 1027-1032
6 p.
 artikel
133 Transient thermo-hydraulical/thermo-mechanical analysis of the HCLL-TBM for ITER Aiello, G.
 2010
 85 7-9 p. 1565-1572
8 p.
 artikel
134 Transuranic transmutation efficiency of a small fusion–fission facility for spent uranium-oxide and inert matrix fuels Di Sanzo, Christian
 2010
 85 7-9 p. 1488-1491
4 p.
 artikel
135 Tritium analysis of fusion-based hydrogen production reactor FDS-III Song, Yong
 2010
 85 7-9 p. 1044-1047
4 p.
 artikel
136 Tritium permeation barrier based on self-healing composite materials Gao, Jifeng
 2010
 85 7-9 p. 1618-1623
6 p.
 artikel
137 Tritium permeation behavior in SiC/SiC composites Isobe, Kanetsugu
 2010
 85 7-9 p. 1012-1015
4 p.
 artikel
138 Tritium release experiments with CATS and numerical simulation Munakata, Kenzo
 2010
 85 7-9 p. 1250-1254
5 p.
 artikel
139 Upgraded actively cooled high-field-side belt limiter and its preliminary results in HT-7 Ruan, J.F.
 2010
 85 7-9 p. 1595-1597
3 p.
 artikel
140 Vacuum plasma sprayed FeAl/Al2O3 functionally graded coatings for fusion reactor applications Yan, Zilin
 2010
 85 7-9 p. 1542-1545
4 p.
 artikel
141 Water vapor adsorption characteristics of honeycomb adsorbents Wajima, Takaaki
 2010
 85 7-9 p. 1064-1067
4 p.
 artikel
142 Wet scrubber technology for tritium confinement at ITER Perevezentsev, A.N.
 2010
 85 7-9 p. 1206-1210
5 p.
 artikel
                             142 gevonden resultaten
 
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