| 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
|
96-97 |
7-9 |
p. 1416-1420
5 p.
|
artikel
|
| 2 |
Advances in inertial confinement fusion at the National Ignition Facility (NIF)
|
Moses, Edward I.
|
|
2010
|
96-97 |
7-9 |
p. 983-986
4 p.
|
artikel
|
| 3 |
A high temperature blanket concept for hydrogen production
|
Chen, H.
|
|
2008
|
96-97 |
7-9 |
p. 903-911
9 p.
|
artikel
|
| 4 |
Analysis of the tritium breeding ratio benchmark experiments using the Monte Carlo code TRIPOLI-4
|
Lee, Yi-Kang
|
|
2010
|
96-97 |
7-9 |
p. 1125-1128
4 p.
|
artikel
|
| 5 |
An overview of fuel retention and morphology in a castellated tungsten limiter
|
Rubel, M.J.
|
|
2008
|
96-97 |
7-9 |
p. 1049-1053
5 p.
|
artikel
|
| 6 |
An overview of the US DCLL ITER-TBM program
|
Wong, C.P.C.
|
|
2010
|
96-97 |
7-9 |
p. 1129-1132
4 p.
|
artikel
|
| 7 |
Aqueous corrosion in static capsule tests representing multi-metal assemblies in the hydraulic circuit of Tore Supra
|
Lipa, M.
|
|
2008
|
96-97 |
7-9 |
p. 1063-1067
5 p.
|
artikel
|
| 8 |
A recent version of MELCOR for fusion safety applications
|
Merrill, Brad J.
|
|
2010
|
96-97 |
7-9 |
p. 1479-1483
5 p.
|
artikel
|
| 9 |
Assessment of EM loads on the EU HCPB TBM during plasma disruption and normal operating scenario including the ferromagnetic effect
|
Roccella, R.
|
|
2008
|
96-97 |
7-9 |
p. 1212-1216
5 p.
|
artikel
|
| 10 |
Assessment of the He-cooled Test Divertor Module for ITER
|
Widak, V.
|
|
2008
|
96-97 |
7-9 |
p. 1131-1136
6 p.
|
artikel
|
| 11 |
A stellarator reactor based on the optimization criteria of Wendelstein 7-X
|
Wolf, R.C.
|
|
2008
|
96-97 |
7-9 |
p. 990-996
7 p.
|
artikel
|
| 12 |
A strategic plan of Korea for developing fusion energy beyond ITER
|
Kwon, M.
|
|
2008
|
96-97 |
7-9 |
p. 883-888
6 p.
|
artikel
|
| 13 |
A study of the potential influence of frame coolant distribution on the radiation-induced damage of HCLL-TBM structural material
|
Chiovaro, P.
|
|
2008
|
96-97 |
7-9 |
p. 1273-1276
4 p.
|
artikel
|
| 14 |
A tritium diagnostic and trap for JUDITH—First results in disruption simulation experiments with neutron irradiated beryllium during cyclic electron beam testing
|
Schmidt, A.
|
|
2008
|
96-97 |
7-9 |
p. 1108-1113
6 p.
|
artikel
|
| 15 |
Author Index
|
|
|
2010
|
96-97 |
7-9 |
p. I-VIII
nvt p.
|
artikel
|
| 16 |
Author Index for 83/7-9
|
|
|
2008
|
96-97 |
7-9 |
p. 1348-1354
7 p.
|
artikel
|
| 17 |
Behavior of tritium accumulated on materials surface
|
Otsuka, Teppei
|
|
2010
|
96-97 |
7-9 |
p. 1437-1441
5 p.
|
artikel
|
| 18 |
Behaviour of melted tungsten plasma facing components under ITER-like transient heat loads
|
Bazylev, B.
|
|
2008
|
96-97 |
7-9 |
p. 1077-1081
5 p.
|
artikel
|
| 19 |
Blanket manufacturing technologies: Thermomechanical tests on helium cooled lithium lead (HCLL) blanket mocks up
|
Laffont, G.
|
|
2008
|
96-97 |
7-9 |
p. 1208-1211
4 p.
|
artikel
|
| 20 |
Carbon removal in stainless steel wall and graphite sheet by using oxygen glow discharge
|
Nomura, Takuya
|
|
2008
|
96-97 |
7-9 |
p. 1059-1062
4 p.
|
artikel
|
| 21 |
Characterization and improvement of water compatibility of γ-LiAlO2 ceramic breeders
|
Lin, Jiu
|
|
2010
|
96-97 |
7-9 |
p. 1162-1166
5 p.
|
artikel
|
| 22 |
Characterization of SiC based composite materials by the infiltration of ultra-fine SiC particles
|
Lee, J.K.
|
|
2010
|
96-97 |
7-9 |
p. 1376-1380
5 p.
|
artikel
|
| 23 |
Chemical stability of LiYO2 as an insulating material
|
Nagura, Masaru
|
|
2010
|
96-97 |
7-9 |
p. 1098-1101
4 p.
|
artikel
|
| 24 |
Codes and standards and regulation issues for design and construction of the ITER mechanical components
|
Barabash, V.
|
|
2010
|
96-97 |
7-9 |
p. 1290-1295
6 p.
|
artikel
|
| 25 |
Compatibility of atmospheric plasma sprayed Al2O3 coatings on CLAM with liquid LiPb
|
Guo, Zhihui
|
|
2010
|
96-97 |
7-9 |
p. 1469-1473
5 p.
|
artikel
|
| 26 |
Compatibility of PIP SiCf/SiC with LiPb at 700°C
|
Zhao, Shuang
|
|
2010
|
96-97 |
7-9 |
p. 1624-1626
3 p.
|
artikel
|
| 27 |
Completion of the KSTAR construction and its role as ITER pilot device
|
Oh, Yeong-Kook
|
|
2008
|
96-97 |
7-9 |
p. 804-809
6 p.
|
artikel
|
| 28 |
Computational thermo-fluid exploratory design analysis for complex ITER first wall/shield components
|
Youchison, Dennis L.
|
|
2008
|
96-97 |
7-9 |
p. 1025-1033
9 p.
|
artikel
|
| 29 |
Conceptual design of EAST flexible in-vessel inspection system
|
Peng, X.B.
|
|
2010
|
96-97 |
7-9 |
p. 1362-1365
4 p.
|
artikel
|
| 30 |
Configuration and operation of detritiation systems for ITER Tokamak Complex
|
Beloglazov, S.
|
|
2010
|
96-97 |
7-9 |
p. 1670-1674
5 p.
|
artikel
|
| 31 |
Construction of the plasma-wall experiment Magnum-PSI
|
Rapp, J.
|
|
2010
|
96-97 |
7-9 |
p. 1455-1459
5 p.
|
artikel
|
| 32 |
Corrosion of reduced activation ferritic martensitic steel JLF-1 in purified Flinak at static and flowing conditions
|
Kondo, Masatoshi
|
|
2010
|
96-97 |
7-9 |
p. 1430-1436
7 p.
|
artikel
|
| 33 |
Critical heat flux experiments using a screw tube under DEMO divertor-relevant cooling conditions
|
Ezato, K.
|
|
2008
|
96-97 |
7-9 |
p. 1097-1101
5 p.
|
artikel
|
| 34 |
Current status of design and analysis of Korean Helium-Cooled Solid Breeder Test Blanket Module
|
Cho, Seungyon
|
|
2008
|
96-97 |
7-9 |
p. 1163-1168
6 p.
|
artikel
|
| 35 |
Current status on the detailed design and development of fabrication techniques for the ITER blanket shield block in Korea
|
Kim, Duck-Hoi
|
|
2008
|
96-97 |
7-9 |
p. 1181-1187
7 p.
|
artikel
|
| 36 |
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
|
96-97 |
7-9 |
p. 1173-1180
8 p.
|
artikel
|
| 37 |
3D CFD analysis of subcooled flow boiling heat transfer with hypervapotron configurations for ITER first wall designs
|
Ying, A.
|
|
2010
|
96-97 |
7-9 |
p. 1348-1353
6 p.
|
artikel
|
| 38 |
DEMO development strategy based on China FPP program
|
Pan, C.H.
|
|
2008
|
96-97 |
7-9 |
p. 877-882
6 p.
|
artikel
|
| 39 |
DEMO relevance of the test blanket modules in ITER—Application to the European test blanket modules
|
Magnani, E.
|
|
2010
|
96-97 |
7-9 |
p. 1271-1278
8 p.
|
artikel
|
| 40 |
Densification of nano-SiC by ultra-high pressure effects of time, temperature and pressure
|
Mao-lin, Xie
|
|
2010
|
96-97 |
7-9 |
p. 964-968
5 p.
|
artikel
|
| 41 |
Design and preliminary safety analysis of a helium cooled molten lithium test blanket module for the ITER in Korea
|
Lee, Dong Won
|
|
2008
|
96-97 |
7-9 |
p. 1217-1221
5 p.
|
artikel
|
| 42 |
Detection efficiency of plastic scintillator for gaseous tritium sampling and measurement system
|
Uda, Tatsuhiko
|
|
2010
|
96-97 |
7-9 |
p. 1474-1478
5 p.
|
artikel
|
| 43 |
Deuterium retention and desorption behavior of lithium titanate
|
Hino, T.
|
|
2008
|
96-97 |
7-9 |
p. 1173-1175
3 p.
|
artikel
|
| 44 |
Development and application of SN Auto-Modeling Tool SNAM 2.1
|
Long, Pengcheng
|
|
2010
|
96-97 |
7-9 |
p. 1113-1116
4 p.
|
artikel
|
| 45 |
Development and testing of multigroup library with correction of self-shielding effects in fusion–fission hybrid reactor
|
Zou, Jun
|
|
2010
|
96-97 |
7-9 |
p. 1587-1590
4 p.
|
artikel
|
| 46 |
Development of advanced blanket performance under irradiation and system integration through JUPITER-II project
|
Abe, K.
|
|
2008
|
96-97 |
7-9 |
p. 842-849
8 p.
|
artikel
|
| 47 |
Development of anti-corrosion coating on low activation materials against fluoridation and oxidation in Flibe blanket environment
|
Nagasaka, Takuya
|
|
2010
|
96-97 |
7-9 |
p. 1261-1265
5 p.
|
artikel
|
| 48 |
Development of measurement technique for surface waves on high-speed liquid lithium jet for IFMIF target
|
Kondo, Hiroo
|
|
2010
|
96-97 |
7-9 |
p. 1102-1105
4 p.
|
artikel
|
| 49 |
Development of modular helium-cooled divertor for DEMO based on the multi-jet impingement (HEMJ) concept: Experimental validation of thermal performance
|
Weathers, J.B.
|
|
2008
|
96-97 |
7-9 |
p. 1120-1125
6 p.
|
artikel
|
| 50 |
Direct decomposition of methane using helium RF plasma
|
Katayama, Kazunari
|
|
2010
|
96-97 |
7-9 |
p. 1381-1385
5 p.
|
artikel
|
| 51 |
Direct numerical simulation of unstable stratified turbulent flow under a magnetic field
|
Satake, Shin-ichi
|
|
2010
|
96-97 |
7-9 |
p. 1326-1330
5 p.
|
artikel
|
| 52 |
Divertor conceptual designs for a fusion power plant
|
Norajitra, Prachai
|
|
2008
|
96-97 |
7-9 |
p. 893-902
10 p.
|
artikel
|
| 53 |
3D Monte Carlo vacuum modeling of the neutral beam injection system of ITER
|
Luo, X.
|
|
2010
|
96-97 |
7-9 |
p. 1446-1450
5 p.
|
artikel
|
| 54 |
DNS and k–ε model simulation of MHD turbulent channel flows with heat transfer
|
Yamamoto, Y.
|
|
2008
|
96-97 |
7-9 |
p. 1309-1312
4 p.
|
artikel
|
| 55 |
DNS of turbulent heat transfer under a uniform magnetic field at high Reynolds number
|
Satake, Shin-ichi
|
|
2008
|
96-97 |
7-9 |
p. 1092-1096
5 p.
|
artikel
|
| 56 |
2D SiC/SiC composite for flow channel insert (FCI) application
|
Yu, Haijiao
|
|
2010
|
96-97 |
7-9 |
p. 1693-1696
4 p.
|
artikel
|
| 57 |
Effect of high temperature corrosion in liquid lithium on mechanical properties of beryllium
|
Kupriyanov, I.B.
|
|
2010
|
96-97 |
7-9 |
p. 1702-1706
5 p.
|
artikel
|
| 58 |
Effect of oxygen on hydrogen retention in W deposition layers formed by hydrogen RF plasma
|
Fujiki, Toshiya
|
|
2010
|
96-97 |
7-9 |
p. 1094-1097
4 p.
|
artikel
|
| 59 |
Effect of surface water on tritium release behavior from Li4SiO4
|
Hanada, T.
|
|
2010
|
96-97 |
7-9 |
p. 998-1001
4 p.
|
artikel
|
| 60 |
Effect of Ta-doping on the ionic conductivity of lithium titanate
|
Wu, Xiangwei
|
|
2010
|
96-97 |
7-9 |
p. 1442-1445
4 p.
|
artikel
|
| 61 |
Effects of simultaneous transfer of heat and tritium through Li–Pb or Flibe blanket
|
Fukada, S.
|
|
2010
|
96-97 |
7-9 |
p. 1314-1319
6 p.
|
artikel
|
| 62 |
Electric flow coupling in the HCLL blanket concept
|
Mistrangelo, C.
|
|
2008
|
96-97 |
7-9 |
p. 1232-1237
6 p.
|
artikel
|
| 63 |
Electromagnetic analysis of transient disruption forces on the ITER shield modules
|
Kotulski, J.D.
|
|
2008
|
96-97 |
7-9 |
p. 1068-1071
4 p.
|
artikel
|
| 64 |
European DEMO design and maintenance strategy
|
Maisonnier, David
|
|
2008
|
96-97 |
7-9 |
p. 858-864
7 p.
|
artikel
|
| 65 |
Evaluation of deuterium permeation reduction factor of various coatings deposited on ferritic/martensitic steels for development of tritium permeation barrier
|
Nakamura, Hirofumi
|
|
2010
|
96-97 |
7-9 |
p. 1531-1536
6 p.
|
artikel
|
| 66 |
Evaluation of microstructure and mechanical properties of liquid phase diffusion bonded ODS steels
|
Noh, Sanghoon
|
|
2010
|
96-97 |
7-9 |
p. 1033-1037
5 p.
|
artikel
|
| 67 |
Examination of electrical insulating performance of Er2O3 ceramic coating under ion beam irradiation
|
Tanaka, T.
|
|
2008
|
96-97 |
7-9 |
p. 1300-1303
4 p.
|
artikel
|
| 68 |
Experimental estimate of tritium production parameters for RF test blanket module
|
Kapyshev, V.
|
|
2008
|
96-97 |
7-9 |
p. 1204-1207
4 p.
|
artikel
|
| 69 |
Experimental study of MHD effects on turbulent flow of Flibe simulant fluid in circular pipe
|
Takeuchi, Junichi
|
|
2008
|
96-97 |
7-9 |
p. 1082-1086
5 p.
|
artikel
|
| 70 |
Experimental tests and thermo-mechanical analyses on the HEXCALIBER mock-up
|
Di Maio, P.A.
|
|
2008
|
96-97 |
7-9 |
p. 1287-1293
7 p.
|
artikel
|
| 71 |
Explosive detection system using pulsed 14MeV neutron source
|
Sharma, Surender Kumar
|
|
2010
|
96-97 |
7-9 |
p. 1562-1564
3 p.
|
artikel
|
| 72 |
Ex-situ tritium removal from JET tiles using RF inductive heating
|
Bekris, N.
|
|
2008
|
96-97 |
7-9 |
p. 1137-1141
5 p.
|
artikel
|
| 73 |
Findings of the US research needs workshop on the topic of fusion power
|
Meier, W.R.
|
|
2010
|
96-97 |
7-9 |
p. 969-973
5 p.
|
artikel
|
| 74 |
First results on the effect of direct quenching on mechanical properties and anelastic relaxation in CLAM steel
|
Qiu, J.
|
|
2010
|
96-97 |
7-9 |
p. 1556-1561
6 p.
|
artikel
|
| 75 |
Fuel cycle design for ITER and its extrapolation to DEMO
|
Konishi, Satoshi
|
|
2008
|
96-97 |
7-9 |
p. 954-958
5 p.
|
artikel
|
| 76 |
Fusion–fission hybrids for nuclear waste transmutation: A synergistic step between Gen-IV fission and fusion reactors
|
Mehlhorn, T.A.
|
|
2008
|
96-97 |
7-9 |
p. 948-953
6 p.
|
artikel
|
| 77 |
Goals, challenges, and successes of managing fusion activated materials
|
El-Guebaly, L.
|
|
2008
|
96-97 |
7-9 |
p. 928-935
8 p.
|
artikel
|
| 78 |
Heat transfer enhancement in sphere-packed pipes under high Reynolds number conditions
|
Seto, Nao
|
|
2008
|
96-97 |
7-9 |
p. 1102-1107
6 p.
|
artikel
|
| 79 |
Heat transfer enhancement of free surface MHD-flow by a protrusion wall
|
Huang, Hulin
|
|
2010
|
96-97 |
7-9 |
p. 1496-1502
7 p.
|
artikel
|
| 80 |
Heat transfer in SiC compact heat exchanger
|
Takeuchi, Y.
|
|
2010
|
96-97 |
7-9 |
p. 1266-1270
5 p.
|
artikel
|
| 81 |
Heatup event analyses of the Water Cooled Solid Breeder Test Blanket Module
|
Tsuru, Daigo
|
|
2008
|
96-97 |
7-9 |
p. 1238-1243
6 p.
|
artikel
|
| 82 |
Helium-cooled lithium lead: Activation analysis of the test blanket module in ITER
|
Petrizzi, L.
|
|
2008
|
96-97 |
7-9 |
p. 1244-1248
5 p.
|
artikel
|
| 83 |
Helium-cooled pebble bed test blanket module: Alternative design and fabrication routes
|
Lux, Martin
|
|
2008
|
96-97 |
7-9 |
p. 1249-1252
4 p.
|
artikel
|
| 84 |
High heat flux test with HIP-bonded Cu/SS mock-ups for the ITER first wall
|
Lee, Dong Won
|
|
2008
|
96-97 |
7-9 |
p. 1038-1043
6 p.
|
artikel
|
| 85 |
Hydraulic analysis of the water-cooled blanket based on the sub-critical water condition
|
Liu, C.
|
|
2010
|
96-97 |
7-9 |
p. 979-982
4 p.
|
artikel
|
| 86 |
Hydrogen/dust explosion hazard in ITER: Effect of nitrogen dilution on explosion behavior of hydrogen/tungsten dust/air mixtures
|
Denkevits, A.
|
|
2010
|
96-97 |
7-9 |
p. 1059-1063
5 p.
|
artikel
|
| 87 |
IFMIF accelerators design
|
Mosnier, A.
|
|
2008
|
96-97 |
7-9 |
p. 1001-1006
6 p.
|
artikel
|
| 88 |
Impact of reflected neutrons on accuracy of tritium production rate prediction in blanket mock-ups for fusion reactors
|
Sato, S.
|
|
2008
|
96-97 |
7-9 |
p. 1304-1308
5 p.
|
artikel
|
| 89 |
Impact of various plasma instabilities on reliability and performance of tokamak fusion devices
|
Hassanein, A.
|
|
2010
|
96-97 |
7-9 |
p. 1331-1335
5 p.
|
artikel
|
| 90 |
Integration of IC/EC systems in ITER
|
Gassmann, T.
|
|
2010
|
96-97 |
7-9 |
p. 1245-1249
5 p.
|
artikel
|
| 91 |
Interfacial reaction and diffusion control between SiC and F82H steel
|
Zhong, Zhihong
|
|
2010
|
96-97 |
7-9 |
p. 992-997
6 p.
|
artikel
|
| 92 |
Investigation of alternative configurations of the LLCB TBM to increase neutronic and thermo-hydraulics performances
|
Kirillov, I.R.
|
|
2010
|
96-97 |
7-9 |
p. 1054-1058
5 p.
|
artikel
|
| 93 |
Investigation of coating CLAM steel substrates with erbium oxide by a magnetron sputtering method
|
Liu, Shuai
|
|
2010
|
96-97 |
7-9 |
p. 1401-1405
5 p.
|
artikel
|
| 94 |
Ion-beam assisted deposition of coating interlayers for the joining of Be/CuCrZr
|
Jung, Yang-Il
|
|
2010
|
96-97 |
7-9 |
p. 1689-1692
4 p.
|
artikel
|
| 95 |
Irradiation tests of a small-sized motor with radiation resistance
|
Nakamichi, M.
|
|
2008
|
96-97 |
7-9 |
p. 1321-1325
5 p.
|
artikel
|
| 96 |
Isotopic exchange between hydrogen and deuterium in the process of permeating through Li0.17Pb0.83
|
Edao, Y.
|
|
2010
|
96-97 |
7-9 |
p. 1225-1228
4 p.
|
artikel
|
| 97 |
ITER blanket module shield block design and analysis
|
Mitin, D.
|
|
2008
|
96-97 |
7-9 |
p. 1188-1198
11 p.
|
artikel
|
| 98 |
ITER vacuum vessel design and construction
|
Ioki, K.
|
|
2010
|
96-97 |
7-9 |
p. 1307-1313
7 p.
|
artikel
|
| 99 |
ITER vacuum vessel, in-vessel components and plasma facing materials
|
Ioki, K.
|
|
2008
|
96-97 |
7-9 |
p. 787-794
8 p.
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artikel
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Japanese perspective of fusion nuclear technology from ITER to DEMO
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Tanaka, Satoru
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2008
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96-97 |
7-9 |
p. 865-869
5 p.
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artikel
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| 101 |
JET operating experience: Global analysis of tritium plant failure
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Pinna, T.
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2010
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96-97 |
7-9 |
p. 1396-1400
5 p.
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artikel
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| 102 |
Latest design of liquid lithium target in IFMIF
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Nakamura, H.
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2008
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96-97 |
7-9 |
p. 1007-1014
8 p.
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artikel
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| 103 |
Liquid metal cooling issues for fusion and fission
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Horiike, H.
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2008
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96-97 |
7-9 |
p. 943-947
5 p.
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artikel
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| 104 |
Li2TiO3 pebble beds constitutive equations of using standard three-axial tests: Implementation of the model in an FEM code
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Zaccari, N.
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2008
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96-97 |
7-9 |
p. 1282-1286
5 p.
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artikel
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Manufacture of a shield prototype for primary wall modules
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Boudot, C.
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2008
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96-97 |
7-9 |
p. 1294-1299
6 p.
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artikel
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| 106 |
Manufacturing aspects in the design of the breeder unit for helium cooled pebble bed blankets
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Rey, J.
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2008
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96-97 |
7-9 |
p. 1258-1262
5 p.
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artikel
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Manufacturing experiment on a cooling plate for a blanket breeder unit
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von der Weth, A.
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2008
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96-97 |
7-9 |
p. 1263-1267
5 p.
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artikel
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Manufacturing of a HCLL cooling plate mock up
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Rigal, Emmanuel
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2008
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96-97 |
7-9 |
p. 1268-1272
5 p.
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artikel
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| 109 |
Manufacturing of U–10wt% Mo powder by hydride–dehydride processing
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Xiong, Yi-Fu
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2010
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96-97 |
7-9 |
p. 1492-1495
4 p.
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artikel
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| 110 |
Manufacturing studies of structural components for the ITER EC upper launcher
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Spaeh, Peter
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2010
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96-97 |
7-9 |
p. 1406-1409
4 p.
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artikel
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| 111 |
Measurement of TPR distribution in natural Li2TiO3/Be assembly with DT neutrons
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Kondo, Keitaro
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2010
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96-97 |
7-9 |
p. 1229-1233
5 p.
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artikel
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| 112 |
Measurement of tritium permeation in flibe (2LiF–BeF2)
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Calderoni, P.
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2008
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96-97 |
7-9 |
p. 1331-1334
4 p.
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artikel
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| 113 |
Mechanical design and first experimental results of an upgraded technical PERMCAT reactor for tritium recovery in the fuel cycle of a fusion machine
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Welte, S.
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2010
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96-97 |
7-9 |
p. 1320-1325
6 p.
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artikel
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Mechanical measurements in RFX-mod experiment
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Palma, M. Dalla
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2010
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96-97 |
7-9 |
p. 1279-1282
4 p.
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artikel
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| 115 |
MHD considerations for the DCLL inboard blanket and access ducts
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Smolentsev, Sergey
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2010
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96-97 |
7-9 |
p. 1007-1011
5 p.
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artikel
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MHD pressure drop characteristics in a three-surface-multi-layered channel under a strong magnetic field
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Aoyagi, M.
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2010
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96-97 |
7-9 |
p. 1181-1184
4 p.
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artikel
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MHD simulations of liquid metal flow through a toroidally oriented manifold
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Morley, N.B.
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2008
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96-97 |
7-9 |
p. 1335-1339
5 p.
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artikel
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| 118 |
MHD thermofluid issues of liquid-metal blankets: Phenomena and advances
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Smolentsev, Sergey
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2010
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96-97 |
7-9 |
p. 1196-1205
10 p.
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artikel
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| 119 |
Microstructure and mechanical property of 12Cr oxide dispersion strengthened ferritic steel for fusion application
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Li, Ming
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2010
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96-97 |
7-9 |
p. 1573-1576
4 p.
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artikel
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| 120 |
Microstructure and thermal property of tungsten coatings prepared by vacuum plasma spraying technology
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Niu, Yaran
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2010
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96-97 |
7-9 |
p. 1521-1526
6 p.
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artikel
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| 121 |
Microstructure control and deuterium permeability of erbium oxide coating on ferritic/martensitic steels by metal-organic decomposition
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Chikada, Takumi
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2010
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96-97 |
7-9 |
p. 1537-1541
5 p.
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artikel
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| 122 |
Modelling of wall and SOL processes and contamination of ITER plasma after impurity injection with the tokamak code TOKES
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Landman, I.S.
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2010
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96-97 |
7-9 |
p. 1366-1370
5 p.
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artikel
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| 123 |
Modification of a solid polymer electrolyte (SPE) electrolyser to ensure tritium compatibility
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Eichelhardt, F.
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2010
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96-97 |
7-9 |
p. 1211-1214
4 p.
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artikel
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| 124 |
Molecular dynamics and dynamic Monte Carlo studies of mixed materials and their impact on plasma wall interactions
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Ohya, K.
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2010
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96-97 |
7-9 |
p. 1167-1172
6 p.
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artikel
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| 125 |
Molecular dynamics simulation of low-energy atomic hydrogen on tungsten surface
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Yang, Zhongshi
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2010
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96-97 |
7-9 |
p. 1517-1520
4 p.
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artikel
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| 126 |
Monte Carlo based sensitivity and uncertainty analysis of the HCPB Test Blanket Module in ITER
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Fischer, U.
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2008
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96-97 |
7-9 |
p. 1222-1226
5 p.
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artikel
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| 127 |
Neutronic analysis of the HCPB TBM in ITER utilizing an advanced integral approach
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Pereslavtsev, P.
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2010
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96-97 |
7-9 |
p. 1653-1658
6 p.
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artikel
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| 128 |
Neutronics and nuclear data issues in ITER and their validation
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Batistoni, P.
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2008
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96-97 |
7-9 |
p. 834-841
8 p.
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artikel
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| 129 |
Neutronics assessment of the shielding and breeding requirements for FNSF (standard aspect ratio)
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Liu, Haibo
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2010
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96-97 |
7-9 |
p. 1296-1300
5 p.
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artikel
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| 130 |
Neutronics experiments on HCPB and HCLL TBM mock-ups in preparation of nuclear measurements in ITER
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Batistoni, P.
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2010
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96-97 |
7-9 |
p. 1675-1680
6 p.
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artikel
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| 131 |
Nitride-strengthened reduced activation ferritic/martensitic steels
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Hu, Ping
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2010
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96-97 |
7-9 |
p. 1632-1637
6 p.
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artikel
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Non-destructive examination with infrared thermography system for ITER divertor components
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Seki, Yohji
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2010
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96-97 |
7-9 |
p. 1451-1454
4 p.
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artikel
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| 133 |
Nuclear design analyses of the helium cooled lithium lead blanket for a fusion power demonstration reactor
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Fischer, U.
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2010
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96-97 |
7-9 |
p. 1133-1138
6 p.
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artikel
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| 134 |
Numerical analysis of heat transfer in the concentric recuperator for Chinese multifunctional experimental loop DRAGON-IV
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Wang, Wei-hua
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2010
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96-97 |
7-9 |
p. 1598-1602
5 p.
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artikel
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| 135 |
Numerical investigation of a brazed joint between W-1%La2O3 and ODS EUROFER components
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Reiser, J.
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2008
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96-97 |
7-9 |
p. 1126-1130
5 p.
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artikel
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| 136 |
Numerical Simulation of Nature Convection and Heat Transfer of the Liquid LiPb in Cubic Enclosure with a Magnetic Field
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Wang, H.Y.
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2010
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96-97 |
7-9 |
p. 1215-1219
5 p.
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artikel
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Numerical simulation of turbulent flow in microscopic pore scale of pebble bed by large-eddy simulation
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Ebara, S.
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2010
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96-97 |
7-9 |
p. 1638-1641
4 p.
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artikel
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| 138 |
Numerical simulation on bake-out of the ITER diagnostic upper port plug
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Pak, S.
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2010
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96-97 |
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p. 1627-1631
5 p.
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artikel
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| 139 |
On the hyperporous non-linear elasticity model for fusion-relevant pebble beds
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Di Maio, P.A.
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2010
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96-97 |
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p. 1234-1244
11 p.
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artikel
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Operating experiences from existing fusion facilities in view of ITER safety and reliability
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Pinna, T.
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2010
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96-97 |
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p. 1410-1415
6 p.
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artikel
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Out of pile tritium release behaviour and microscopic investigation of lithium metatitanate irradiated in the High Flux Reactor in Petten
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van Til, S.
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2010
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96-97 |
7-9 |
p. 1143-1146
4 p.
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artikel
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Overview of design and R&D of solid breeder TBM in China
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Feng, K.M.
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2008
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96-97 |
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p. 1149-1156
8 p.
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artikel
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Overview of liquid metal TBM concepts and programs
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Wong, C.P.C.
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2008
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96-97 |
7-9 |
p. 850-857
8 p.
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artikel
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| 144 |
Overview of the JET ITER-like Wall Project
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Philipps, V.
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2010
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96-97 |
7-9 |
p. 1581-1586
6 p.
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artikel
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| 145 |
Packing experiment of breeder pebbles into water cooled solid breeder test blanket module for ITER
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Hirose, Takanori
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2010
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96-97 |
7-9 |
p. 1426-1429
4 p.
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artikel
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| 146 |
Performances of inert gas glow discharges for reductions of fuel hydrogen retention and helium retention
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Hino, T.
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2010
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96-97 |
7-9 |
p. 974-978
5 p.
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artikel
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| 147 |
Plasma control systems relevant to ITER and fusion power plants
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Kurihara, K.
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2008
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96-97 |
7-9 |
p. 959-970
12 p.
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artikel
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Preliminary design of Indian Test Blanket Module for ITER
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Kumar, E. Rajendra
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2008
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96-97 |
7-9 |
p. 1169-1172
4 p.
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artikel
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| 149 |
Preliminary studies on MHD simulation and heat transfer analysis for LLCB TBM
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Goswami, K.S.
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2010
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96-97 |
7-9 |
p. 1371-1375
5 p.
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artikel
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| 150 |
Preparation of Mg and Al phosphate coatings on ferritic steel by wet-chemical method as tritium permeation barrier
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Zhang, Kun
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2010
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96-97 |
7-9 |
p. 1090-1093
4 p.
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artikel
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| 151 |
Preparing for ignition experiments on the National Ignition Facility
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Moses, Edward I.
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2008
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96-97 |
7-9 |
p. 997-1000
4 p.
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artikel
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| 152 |
Proceedings of the Eighth International Symposium on Fusion Nuclear Technology
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Janeschitz, G.
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2008
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96-97 |
7-9 |
p. 785-
1 p.
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artikel
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| 153 |
Proceedings of the Ninth International Symposium on Fusion Nuclear Technology
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Abdou, M.A.
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2010
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96-97 |
7-9 |
p. 963-
1 p.
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artikel
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| 154 |
Progress in technology and experiment of superconducting tokamaks in ASIPP
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Wan, Baonian
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2010
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96-97 |
7-9 |
p. 1048-1053
6 p.
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artikel
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| 155 |
Progress in the development of insulator coating for liquid lithium blankets
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Muroga, T.
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2010
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96-97 |
7-9 |
p. 1301-1306
6 p.
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artikel
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| 156 |
Progress in the development of reduced activation ferritic-martensitic steels and fabrication technologies in India
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Raj, Baldev
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2010
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96-97 |
7-9 |
p. 1460-1468
9 p.
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artikel
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| 157 |
Progress of conversion system from CAD data to MCNP geometry data in Japan
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Sato, S.
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2010
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96-97 |
7-9 |
p. 1546-1550
5 p.
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artikel
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| 158 |
Progress of design studies on an LHD-type steady state reactor
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Motojima, O.
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2008
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96-97 |
7-9 |
p. 983-989
7 p.
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artikel
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| 159 |
Progress on an integrated multi-physics simulation predictive capability for plasma chamber nuclear components
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Ying, A.
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2010
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96-97 |
7-9 |
p. 1681-1688
8 p.
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artikel
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RAMI Approach for ITER
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van Houtte, D.
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2010
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96-97 |
7-9 |
p. 1220-1224
5 p.
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artikel
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R&D activities on helium cooled solid breeder TBM in Korea
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Cho, S.
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2010
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96-97 |
7-9 |
p. 1608-1614
7 p.
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artikel
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| 162 |
R&D issues of W/Cu divertor for EAST
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Li, Q.
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2010
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96-97 |
7-9 |
p. 1106-1112
7 p.
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artikel
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| 163 |
R&D of atmosphere detritiation system for ITER in JAEA
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Hayashi, Takumi
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2010
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96-97 |
7-9 |
p. 1386-1390
5 p.
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artikel
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| 164 |
R&D of the key components for ITER magnet supports
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Lee, P.Y.
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2010
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96-97 |
7-9 |
p. 1603-1607
5 p.
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artikel
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| 165 |
R&D on major components of control system for ITER blanket maintenance equipment
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Takeda, Nobukazu
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2010
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96-97 |
7-9 |
p. 1190-1195
6 p.
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artikel
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| 166 |
Real-time dose assessment and visualization of radiation field for EAST tokamak
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Tang, Zhengdao
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2010
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96-97 |
7-9 |
p. 1591-1594
4 p.
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artikel
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| 167 |
Recent activities on tritium technologies of BA DEMO-R&D program in JAEA
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Yamanishi, Toshihiko
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2010
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96-97 |
7-9 |
p. 1002-1006
5 p.
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artikel
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| 168 |
Recent R&D results on polymeric materials for a SPE-type high-level tritiated water electrolyzer system
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Iwai, Yasunori
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2010
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96-97 |
7-9 |
p. 1421-1425
5 p.
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artikel
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| 169 |
Recent research and development for the dual-coolant blanket concept in the US
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Morley, N.B.
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2008
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96-97 |
7-9 |
p. 920-927
8 p.
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artikel
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| 170 |
Recovery of hydrogen from gas mixture by an intermediate-temperature type proton conductor
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Tanaka, M.
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2010
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96-97 |
7-9 |
p. 1038-1043
6 p.
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Removal rates of hydrogen isotope from liquid Li by HF-treated Y plate
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Wu, Y.
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2010
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96-97 |
7-9 |
p. 1484-1487
4 p.
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artikel
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| 172 |
Renewed first wall coating in plasma shots at the T-11M tokamak
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Buzhinskij, O.I.
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2010
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96-97 |
7-9 |
p. 1615-1617
3 p.
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artikel
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| 173 |
Requirements and proposals for control and monitoring measurements of the HCLL TBM
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Puma, A. Li
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2010
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96-97 |
7-9 |
p. 1642-1652
11 p.
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artikel
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| 174 |
Research Needs Workshop for Magnetic Fusion Energy Science
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Hazeltine, R.D.
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2010
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96-97 |
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p. 1016-1026
11 p.
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artikel
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| 175 |
Research on the preparation of ceramic tritium breeders in SICCAS
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Wen, Zhaoyin
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2010
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96-97 |
7-9 |
p. 1551-1555
5 p.
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artikel
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| 176 |
Results of acoustic monitoring of ITER divertor vertical target prototype
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Courtois, X.
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2010
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96-97 |
7-9 |
p. 1391-1395
5 p.
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artikel
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| 177 |
Review of blanket designs for advanced fusion reactors
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Ihli, T.
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2008
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96-97 |
7-9 |
p. 912-919
8 p.
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artikel
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| 178 |
Review of stellarator/heliotron design issues towards MFE DEMO
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Sagara, Akio
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2010
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96-97 |
7-9 |
p. 1336-1341
6 p.
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artikel
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| 179 |
Risk mitigation strategy for the ITER electron cyclotron upper port launcher
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Goede, A.P.H.
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2010
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96-97 |
7-9 |
p. 1117-1124
8 p.
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artikel
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Russian concept for a DEMO-S demonstration fusion power reactor
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Kolbasov, B.N.
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2008
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96-97 |
7-9 |
p. 870-876
7 p.
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Sc-doped CaZrO3 hydrogen sensor for liquid blanket system
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Kondo, Masatoshi
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2008
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96-97 |
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p. 1277-1281
5 p.
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Search for reality of solid breeder blanket for DEMO
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Tobita, K.
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2010
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96-97 |
7-9 |
p. 1342-1347
6 p.
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| 183 |
Selection of bounding events for ITER DFLL-TBM safety analysis
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Hu, Liqin
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2010
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96-97 |
7-9 |
p. 1577-1580
4 p.
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artikel
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Simulation of dust production in ITER transient events
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Pestchanyi, S.E.
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2008
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96-97 |
7-9 |
p. 1054-1058
5 p.
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artikel
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Simulation of tungsten armour cracking due to small ELMs in ITER
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Pestchanyi, S.
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2010
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96-97 |
7-9 |
p. 1697-1701
5 p.
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Simulation on the welding of CLAM steel
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Lei, Yu-cheng
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2010
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96-97 |
7-9 |
p. 1503-1507
5 p.
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artikel
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Sol–gel prepared Al2O3 coatings for the application as tritium permeation barrier
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Wang, Tianshi
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2010
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96-97 |
7-9 |
p. 1068-1072
5 p.
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State-of-the-art 3-D radiation transport methods for fusion energy systems
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Wilson, P.P.H.
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2008
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96-97 |
7-9 |
p. 824-833
10 p.
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| 189 |
Status of development of functional materials with perspective on beyond-ITER
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Shikama, T.
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2008
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96-97 |
7-9 |
p. 976-982
7 p.
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artikel
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| 190 |
Status of IFMIF Design and R&D
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Garin, Pascal
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2008
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96-97 |
7-9 |
p. 971-975
5 p.
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| 191 |
Status of JT-60SA tokamak under the EU-JA Broader Approach Agreement
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Matsukawa, M.
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2008
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96-97 |
7-9 |
p. 795-803
9 p.
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Status of R&D on fusion materials in institute of nuclear materials in USTB
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Chang-Chun, Ge
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2010
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96-97 |
7-9 |
p. 1080-1084
5 p.
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| 193 |
Status of the EU R&D programme on the blanket-shield modules for ITER
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Lorenzetto, P.
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2008
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96-97 |
7-9 |
p. 1015-1019
5 p.
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Steady state and transient thermal-hydraulic characterization of full-scale ITER divertor plasma facing components
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Tincani, A.
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2008
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96-97 |
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p. 1034-1037
4 p.
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Strategy for the Indian DEMO design
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Srinivasan, R.
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2008
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96-97 |
7-9 |
p. 889-892
4 p.
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| 196 |
Strength analysis results for the RF “modified” option of the shielding block for ITER blanket module
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Sviridenko, M.N.
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2010
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96-97 |
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p. 1354-1361
8 p.
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Structural material properties and dimensional stability of components in first wall components of a breeding blanket module
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Hirose, Takanori
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2008
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96-97 |
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p. 1176-1180
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| 198 |
Study of isotope exchange reactions on ceramic breeder materials deposited with noble metal
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Mochizuki, Kazuhiro
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2010
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p. 1185-1189
5 p.
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Study on the fuel balance of a DT reactor
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Nishikawa, Masabumi
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2010
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96-97 |
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p. 987-991
5 p.
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artikel
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Study on wall recycling behaviour in CPD spherical tokamak
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Bhattacharyay, R.
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2008
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96-97 |
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p. 1114-1119
6 p.
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artikel
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SVIP-N 1.0: An integrated visualization platform for neutronics analysis
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Luo, Yuetong
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2010
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96-97 |
7-9 |
p. 1527-1530
4 p.
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artikel
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Synergies in the design and development of fusion and generation IV fission reactors
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Bogusch, E.
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2008
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96-97 |
7-9 |
p. 936-942
7 p.
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artikel
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TechnoFusión, a relevant facility for fusion technologies: The remote handling area
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Ibarra, A.
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2010
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96-97 |
7-9 |
p. 1659-1663
5 p.
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artikel
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Temperature dependence of blistering and deuterium retention in tungsten exposed to high-flux and low-energy deuterium plasma
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Shu, W.M.
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2008
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96-97 |
7-9 |
p. 1044-1048
5 p.
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artikel
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The ancillary systems of the European test blanket modules: Configuration and integration in TIER
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Ricapito, I.
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2010
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96-97 |
7-9 |
p. 1154-1161
8 p.
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artikel
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The development of joining doped graphite to copper for first wall application in HT-7 tokamak
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Zhou, Zhangjian
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2010
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96-97 |
7-9 |
p. 1513-1516
4 p.
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artikel
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The first in-vessel cryopump for EAST divertor experiment
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Hu, Q.S.
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2010
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96-97 |
7-9 |
p. 1508-1512
5 p.
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artikel
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The HCLL Test Blanket Module system: Present reference design, system integration in ITER and R&D needs
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Salavy, J.-F.
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2008
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96-97 |
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p. 1157-1162
6 p.
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The impact of lithium wall coatings on NSTX discharges and the engineering of the Lithium Tokamak eXperiment (LTX)
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Majeski, R.
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2010
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96-97 |
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p. 1283-1289
7 p.
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artikel
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The integration of TBM systems in ITER
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Chuyanov, V.A.
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2008
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96-97 |
7-9 |
p. 817-823
7 p.
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The ITER remote maintenance system
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Tesini, A.
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2008
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96-97 |
7-9 |
p. 810-816
7 p.
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The MK III actively cooled duct liner for the JET neutral beam line: Thermo-mechanical performance and lifetime estimation
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Li-Puma, A.
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2008
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96-97 |
7-9 |
p. 1142-1148
7 p.
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The modified RF concept of CHC experimental module for testing on H–H iter phase
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Leshukov, A.Yu.
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2008
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96-97 |
7-9 |
p. 1199-1203
5 p.
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artikel
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The potential presence and minimisation of plutonium within the irradiated beryllium in fusion power plants
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Cambi, G.
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2010
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96-97 |
7-9 |
p. 1139-1142
4 p.
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artikel
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| 215 |
The radiation analyses of ITER lower ports
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Petrizzi, L.
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2010
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96-97 |
7-9 |
p. 1085-1089
5 p.
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artikel
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Thermal load testing of erosion-monitoring beryllium marker tile for the ITER-Like Wall Project at JET
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Hirai, T.
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2008
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96-97 |
7-9 |
p. 1072-1076
5 p.
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Thermal–mechanical and thermal–hydraulic integrated study of the Helium-Cooled Lithium Lead Test Blanket Module
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Chiovaro, P.
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2010
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96-97 |
7-9 |
p. 1147-1153
7 p.
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artikel
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Thermo-hydraulical and thermo-mechanical analysis of the HCLL-TBM breeding unit
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Aiello, G.
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2008
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96-97 |
7-9 |
p. 1227-1231
5 p.
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artikel
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Thermo-hydraulic and thermo-mechanical analysis of Korean helium cooled solid breeder TBM
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Ahn, Mu-Young
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2010
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96-97 |
7-9 |
p. 1664-1669
6 p.
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artikel
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Thermohydraulic experimental design for the European Helium-Cooled-Pebble-Bed Test Blanket Module
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Ilić, M.
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2008
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96-97 |
7-9 |
p. 1253-1257
5 p.
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artikel
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Thermo-hydraulic testing and integrity of ITER Test Blanket Module (TBM) First Wall mock-up in JAEA
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Ezato, K.
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2010
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96-97 |
7-9 |
p. 1255-1260
6 p.
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Thermo-mechanical analysis of pebble beds in HELICA mock-up experiments
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Gan, Yixiang
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2008
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96-97 |
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p. 1313-1316
4 p.
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artikel
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Thermo-mechanical design of the Plasma Driver Plate for the MITICA ion source
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Pavei, Mauro
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2010
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96-97 |
7-9 |
p. 1073-1079
7 p.
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The Sandia Plasma Materials Test Facility in 2007
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McDonald, J.M.
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2008
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96-97 |
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p. 1087-1091
5 p.
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Three-dimensional nuclear analysis for the US dual coolant lead lithium ITER test blanket module
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Sawan, M.E.
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2010
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96-97 |
7-9 |
p. 1027-1032
6 p.
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artikel
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| 226 |
Transient thermo-hydraulical/thermo-mechanical analysis of the HCLL-TBM for ITER
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Aiello, G.
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2010
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96-97 |
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p. 1565-1572
8 p.
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| 227 |
Transuranic transmutation efficiency of a small fusion–fission facility for spent uranium-oxide and inert matrix fuels
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Di Sanzo, Christian
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2010
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96-97 |
7-9 |
p. 1488-1491
4 p.
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Tritium analysis of fusion-based hydrogen production reactor FDS-III
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Song, Yong
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2010
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96-97 |
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p. 1044-1047
4 p.
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Tritium permeation barrier based on self-healing composite materials
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Gao, Jifeng
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2010
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96-97 |
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p. 1618-1623
6 p.
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Tritium permeation behavior in SiC/SiC composites
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Isobe, Kanetsugu
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2010
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96-97 |
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p. 1012-1015
4 p.
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Tritium release experiments with CATS and numerical simulation
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Munakata, Kenzo
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2010
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p. 1250-1254
5 p.
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Tritium release from lithium silicate pebbles produced from lithium hydroxide
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Munakata, Kenzo
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Tritium transfers and main operating parameters impact for demo lithium lead breeding blanket (HCLL)
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Gastaldi, Olivier
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2008
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8 p.
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Upgraded actively cooled high-field-side belt limiter and its preliminary results in HT-7
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Ruan, J.F.
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2010
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7-9 |
p. 1595-1597
3 p.
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Vacuum plasma sprayed FeAl/Al2O3 functionally graded coatings for fusion reactor applications
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Yan, Zilin
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2010
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7-9 |
p. 1542-1545
4 p.
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Vertical displacement events: A serious concern in future ITER operation
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Hassanein, A.
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2008
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Water vapor adsorption characteristics of honeycomb adsorbents
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Wajima, Takaaki
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2010
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p. 1064-1067
4 p.
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Wet scrubber technology for tritium confinement at ITER
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Perevezentsev, A.N.
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2010
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p. 1206-1210
5 p.
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X-ray tomography investigations on pebble bed structures
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Reimann, J.
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2008
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p. 1326-1330
5 p.
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artikel
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