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                             291 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 A bulk tungsten tile for JET: Heat flux tests in the MARION facility on the power-handling performance and validation of the thermal model Mertens, Ph.
2011
86 9-11 p. 1801-1804
4 p.
artikel
2 A comparison between a steady state and a pulsed fusion power plant Zollino, G.
2011
86 9-11 p. 2787-2790
4 p.
artikel
3 Activation, decay heat and waste analysis for a European HCLL DEMO concept Pohorecki, W.
2011
86 9-11 p. 2705-2708
4 p.
artikel
4 Advantage of redundancy in the controllability of remote handling manipulator Muhammad, Ali
2011
86 9-11 p. 1882-1885
4 p.
artikel
5 Alternative electro-chemically based processing routes for joining of plasma facing components Krauss, Wolfgang
2011
86 9-11 p. 1607-1610
4 p.
artikel
6 A method for enabling real-time structural deformation in remote handling control system by utilizing offline simulation results and 3D model morphing Kiviranta, Sauli
2011
86 9-11 p. 1958-1962
5 p.
artikel
7 An aerosol resuspension model for MELCOR for fusion Merrill, Brad J.
2011
86 9-11 p. 2686-2689
4 p.
artikel
8 Analysis of displacement damage in materials in nuclear fusion facilities (DEMO, IFMIF and TechnoFusion) Mota, F.
2011
86 9-11 p. 2425-2428
4 p.
artikel
9 Analysis of flow and MHD pressure drop in liquid metal LiPb duct with flow channel inserts Wang, Hongyan
2011
86 9-11 p. 2308-2311
4 p.
artikel
10 Analysis of in-pile operation and modeling of tritium transport in lead-lithium irradiation experiments Libretto 4/1, 4/2 and 5 Fedorov, Alexander V.
2011
86 9-11 p. 2370-2373
4 p.
artikel
11 Analysis of the KANT experiment on beryllium using TRIPOLI-4 Monte Carlo code Lee, Yi-Kang
2011
86 9-11 p. 2246-2249
4 p.
artikel
12 Analysis of the new architecture proposal for the CMM control system Heikkilä, L.
2011
86 9-11 p. 2071-2074
4 p.
artikel
13 A new approach to evaluate irradiation hardening of ion-irradiated ferritic alloys by nano-indentation techniques Kasada, Ryuta
2011
86 9-11 p. 2658-2661
4 p.
artikel
14 A new combination of membranes and membrane reactors for improved tritium management in breeder blanket of fusion machines Demange, D.
2011
86 9-11 p. 2312-2316
5 p.
artikel
15 Application of remote handling compatibility on ITER plant Sanders, S.
2011
86 9-11 p. 1989-1992
4 p.
artikel
16 A proposed method for foil set qualification for multiple foil activation measurements in the TBMs Rovni, Istvan
2011
86 9-11 p. 2330-2333
4 p.
artikel
17 A simulation model for transient response of a gas separation module using a hollow fiber membrane Sugiyama, Takahiko
2011
86 9-11 p. 2743-2746
4 p.
artikel
18 Assessment of radiation dose rate resulting from activated corrosion products in the PRIMA facility cooling loops D’Arienzo, M.
2011
86 9-11 p. 2758-2761
4 p.
artikel
19 Assessment of radiation maps during activated divertor moving in the ITER building Ying, Dongchuan
2011
86 9-11 p. 2087-2091
5 p.
artikel
20 ATLAS: Accelerated torus-like angular source for fusion neutronics applications Turner, Andrew
2011
86 9-11 p. 1825-1829
5 p.
artikel
21 Calculation of prompt doses induced by fusion experiments in Laser MegaJoule facility Baggio, Jacques
2011
86 9-11 p. 2762-2765
4 p.
artikel
22 Calibration and compensation of deflections and compliances in remote handling equipment configurations Kivelä, Tuomo
2011
86 9-11 p. 2043-2046
4 p.
artikel
23 Cask and plug handling system design in port cell Martins, Jean-Pierre
2011
86 9-11 p. 1886-1889
4 p.
artikel
24 Categorization of ITER remote handling operations Salminen, K.
2011
86 9-11 p. 2075-2077
3 p.
artikel
25 Characterisation of a multitube PERMCAT reactor in view of a technical facility for highly tritiated water processing at the Tritium Laboratory Karlsruhe Welte, S.
2011
86 9-11 p. 2237-2240
4 p.
artikel
26 Characterization of ceramic materials for electrochemical hydrogen sensors Serret, P.
2011
86 9-11 p. 2446-2449
4 p.
artikel
27 Command and Control application framework for interoperable heterogeneous ITER Remote Handling devices Tuominen, J.
2011
86 9-11 p. 2067-2070
4 p.
artikel
28 Compact tokamaks as convenient neutron sources for fusion reactors materials testing Bombarda, F.
2011
86 9-11 p. 2632-2634
3 p.
artikel
29 Comparative study of fusion relevant properties of Be12V and Be12Ti Kurinskiy, P.
2011
86 9-11 p. 2454-2457
4 p.
artikel
30 Comparison of global variance reduction techniques for Monte Carlo radiation transport simulations of ITER Davis, Andrew
2011
86 9-11 p. 2698-2700
3 p.
artikel
31 Comparison of hydrogen isotope retention and irradiation damage behaviors in tungsten and SS-316 with simultaneous C+–D2 + implantation Oya, Yasuhisa
2011
86 9-11 p. 1776-1779
4 p.
artikel
32 Compatibility of dip-coated Er2O3 coating by MOD method with liquid Li Zhang, Dongxun
2011
86 9-11 p. 2508-2511
4 p.
artikel
33 Compatibility of SiC with static liquid LiPb at 800°C Ling, Xinzhen
2011
86 9-11 p. 2655-2657
3 p.
artikel
34 Compressibility study during hydride reaction of ZrCo Yun, Sei-Hun
2011
86 9-11 p. 2282-2285
4 p.
artikel
35 Concept design of the cassette toroidal mover Mäkinen, H.
2011
86 9-11 p. 2092-2095
4 p.
artikel
36 Conceptual design of the hot cell facility universal docking station at ITER Dammann, A.
2011
86 9-11 p. 1890-1893
4 p.
artikel
37 Contact angle measurement of molten lead–lithium on silicon carbide surfaces Ueki, Yoshitaka
2011
86 9-11 p. 2297-2300
4 p.
artikel
38 Contact dose rates and relevant radioactive inventory in ITER TBM systems Zucchetti, M.
2011
86 9-11 p. 2690-2693
4 p.
artikel
39 Cooling scheme for W7-X divertor cryo-vacuum pumps Dhard, Chandra Prakash
2011
86 9-11 p. 2117-2120
4 p.
artikel
40 Corrosion behavior of CLAM steel in static and flowing LiPb at 480°C and 550°C Gao, Sheng
2011
86 9-11 p. 2627-2631
5 p.
artikel
41 Creep properties of V–4Cr–4Ti strengthened by cold working and aging Zheng, P.F.
2011
86 9-11 p. 2561-2564
4 p.
artikel
42 Current status of the engineering design of the test module interface heads in the IFMIF target and test cell Tian, Kuo
2011
86 9-11 p. 2382-2385
4 p.
artikel
43 Dependence of gamma-ray dose on annihilation processes of irradiation defects in Li2TiO3 Osuo, Junya
2011
86 9-11 p. 2362-2364
3 p.
artikel
44 Design analysis and manufacturing of the cooling lines of the in vessel components of WENDELSTEIN 7-X Mendelevitch, B.
2011
86 9-11 p. 1669-1672
4 p.
artikel
45 Design analysis of DRAGON-IV LiPb loop Zhu, Zhiqiang
2011
86 9-11 p. 2666-2669
4 p.
artikel
46 Design analysis of the hinge support for the ITER vacuum vessel Kim, B.Y.
2011
86 9-11 p. 2003-2007
5 p.
artikel
47 Design and application of GDC on EAST Tokamak Zhou, Zibo
2011
86 9-11 p. 1599-1602
4 p.
artikel
48 Design and fabrication of the KSTAR in-vessel cryo-pump Lee, H.J.
2011
86 9-11 p. 1993-1996
4 p.
artikel
49 Design and manufacturing of JT-60SA vacuum vessel Masaki, Kei
2011
86 9-11 p. 1872-1876
5 p.
artikel
50 Design and qualification of an on-line permeator for the recovery of tritium from lead–lithium eutectic breeding alloy Veredas, G.
2011
86 9-11 p. 2365-2369
5 p.
artikel
51 Design for high productivity remote handling Sykes, N.
2011
86 9-11 p. 1843-1846
4 p.
artikel
52 Design, manufacture and testing of the glow discharge electrodes for Wendelstein 7-X Spring, A.
2011
86 9-11 p. 1933-1936
4 p.
artikel
53 Design of gamma-ray and neutron area monitoring system for the IFMIF/EVEDA accelerator building Takahashi, Hiroki
2011
86 9-11 p. 2795-2798
4 p.
artikel
54 Design of JET ELM control coils for operation at 350°C Zatz, I.J.
2011
86 9-11 p. 1980-1983
4 p.
artikel
55 Design of Pd-based membrane reactor for gas detritiation Tosti, S.
2011
86 9-11 p. 2180-2183
4 p.
artikel
56 Design of purification loop and traps for the IFMIF/EVEDA Li Test Loop: Design of cold trap Kondo, H.
2011
86 9-11 p. 2437-2441
5 p.
artikel
57 Design progress for the ITER torus and neutral beam cryopumps Day, Chr.
2011
86 9-11 p. 2188-2191
4 p.
artikel
58 Design studies of innovatively small fusion reactor based on biomass-fusion hybrid concept: GNOME Ibano, K.
2011
86 9-11 p. 2779-2782
4 p.
artikel
59 Detailed benchmark test of JENDL-4.0 iron data for fusion applications Konno, Chikara
2011
86 9-11 p. 2682-2685
4 p.
artikel
60 Determination of flow distribution in a HCLL blanket mock-up through electric potential measurements Bühler, L.
2011
86 9-11 p. 2301-2303
3 p.
artikel
61 Deuterium permeation and thermal behaviors of amorphous silicon carbide coatings on steels Chikada, Takumi
2011
86 9-11 p. 2192-2195
4 p.
artikel
62 Deuterium retention in SiC coated graphite by D2 + implantation Li, Qiang
2011
86 9-11 p. 1689-1692
4 p.
artikel
63 Development and application of MC-SN coupled auto-modeling tool RCAM1.0 Zhang, Junjun
2011
86 9-11 p. 2783-2786
4 p.
artikel
64 Development and testing of 140GHz absorber coatings for the water baffle of W7-X cryopumps Floristán, Miriam
2011
86 9-11 p. 1847-1850
4 p.
artikel
65 Development of a filled resin system for the TF coils of ITER Canfer, Simon James
2011
86 9-11 p. 2504-2507
4 p.
artikel
66 Development of an experimental facility for a liquid breeder in Korea Yoon, Jae Sung
2011
86 9-11 p. 2212-2215
4 p.
artikel
67 Development of an instrumented indentation device for further characterization of irradiated steels at high temperature Sacksteder, I.
2011
86 9-11 p. 2565-2568
4 p.
artikel
68 Development of a thermo-hydraulic bypass leakage test method for the Wendelstein 7-X target element cooling structure Smirnow, M.
2011
86 9-11 p. 1732-1735
4 p.
artikel
69 Development of a two-dimensional nuclear-thermal-coupled analysis code for conceptual blanket design of fusion reactors Utoh, Hiroyasu
2011
86 9-11 p. 2378-2381
4 p.
artikel
70 Development of design options for the port plug components of the ITER core CXRS diagnostic Krasikov, Yu.
2011
86 9-11 p. 2055-2059
5 p.
artikel
71 Development of in situ cleaning techniques for diagnostic mirrors in ITER Litnovsky, A.
2011
86 9-11 p. 1780-1783
4 p.
artikel
72 Development of laser lock-in thermography for plasma facing component surface characterisation Courtois, X.
2011
86 9-11 p. 1714-1718
5 p.
artikel
73 Development of novel tungsten processing technologies for electro-chemical machining (ECM) of plasma facing components Holstein, Nils
2011
86 9-11 p. 1611-1615
5 p.
artikel
74 Development of numerical simulation code of membrane reactor for detritiation Munakata, Kenzo
2011
86 9-11 p. 2334-2337
4 p.
artikel
75 Development of oxide dispersion strengthened W alloys produced by hot isostatic pressing Martínez, J.
2011
86 9-11 p. 2534-2537
4 p.
artikel
76 Development of pellet fuelling system in HL-2A tokamak Zhu, G.L.
2011
86 9-11 p. 2286-2288
3 p.
artikel
77 Development of Pt/ASDBC catalyst for room temperature recombiner of atmosphere detritiation system Iwai, Yasunori
2011
86 9-11 p. 2164-2167
4 p.
artikel
78 Development of the armoring technique for ITER Divertor Dome Litunovsky, Nikolay
2011
86 9-11 p. 1749-1752
4 p.
artikel
79 Development of W coatings for fusion applications Ruset, C.
2011
86 9-11 p. 1677-1680
4 p.
artikel
80 Developments in remote metrology at JET Mindham, T.J.
2011
86 9-11 p. 1855-1858
4 p.
artikel
81 Diagnostics carried by a light multipurpose deployer for vacuum vessel interventions Houry, M.
2011
86 9-11 p. 1868-1871
4 p.
artikel
82 DTP2 control room operator and remote handing operation designer responsibilities and information available to them Aha, L.
2011
86 9-11 p. 2078-2081
4 p.
artikel
83 Dynamic response of the ITER tokamak during asymmetric VDEs Schioler, Tyge
2011
86 9-11 p. 1963-1966
4 p.
artikel
84 Effect of 16.3dpa neutron irradiation on fatigue lifetime of the RAFM steel EUROFER97 Materna-Morris, E.
2011
86 9-11 p. 2607-2610
4 p.
artikel
85 Effect of fringing magnetic field on magnetohydrodynamic flow in rectangular duct Zhou, Tao
2011
86 9-11 p. 2352-2357
6 p.
artikel
86 Effect of Li/Ti ratio on microstructure and thermal diffusivity of lithium titanate for solid breeding material Mukai, Keisuke
2011
86 9-11 p. 2643-2646
4 p.
artikel
87 Effect of post welding heat treatment of the HCPB TBM on Eurofer and lithium orthosilicate pebbles Abou-Sena, Ali
2011
86 9-11 p. 2254-2257
4 p.
artikel
88 Effects of specimen size on fracture toughness of phosphorous added F82H steels Kim, Byung Jun
2011
86 9-11 p. 2403-2408
6 p.
artikel
89 Effects of tube rolling and heat treatment on microstructure and mechanical properties of CLAM rectangular tube Huang, Bo
2011
86 9-11 p. 2602-2606
5 p.
artikel
90 Electromagnetic modeling and subsequent structural analysis for ITER core CXRS upper port plug diagnostic structure Panin, Anatoly
2011
86 9-11 p. 2016-2020
5 p.
artikel
91 Electromagnetic transients simulation using a shell approach for ITER cCXRS upper port plug due to plasma vertical displacement events Belov, Alexander
2011
86 9-11 p. 1920-1923
4 p.
artikel
92 Engineering studies for the installation of an axi-symmetric metallic divertor in Tore Supra Doceul, L.
2011
86 9-11 p. 1660-1664
5 p.
artikel
93 Enhanced fabrication process for lithium orthosilicate pebbles as breeding material Kolb, Matthias H.H.
2011
86 9-11 p. 2148-2151
4 p.
artikel
94 Enhancement of the remote handling strategy for the refurbishment of the backplate bayonet concept of IFMIF target system Miccichè, G.
2011
86 9-11 p. 2109-2112
4 p.
artikel
95 E2O3 layer forming on Er plate in high temperature liquid Li Nagura, Masaru
2011
86 9-11 p. 2670-2673
4 p.
artikel
96 Er2O3 coating synthesized with MOCVD process on the large interior surface of the metal tube Hishinuma, Yoshimitsu
2011
86 9-11 p. 2530-2533
4 p.
artikel
97 European preparations for the ITER VV sectors manufacture Jones, Lawrence
2011
86 9-11 p. 2096-2100
5 p.
artikel
98 European test blanket ancillary equipment unit development Ilkei, T.
2011
86 9-11 p. 2121-2124
4 p.
artikel
99 Evaluation of electromagnetic loads on various design options of the ITER diagnostic upper port plug during plasma disruptions Pak, Sunil
2011
86 9-11 p. 1877-1881
5 p.
artikel
100 Evaluations on reduction of the ITER TFC ripple generated by CN HCCB-TBM Chen, Yanjing
2011
86 9-11 p. 2273-2277
5 p.
artikel
101 Evolution of beryllium pebbles (HIDOBE) in long term, high flux irradiation in the high flux reactor van Til, S.
2011
86 9-11 p. 2258-2261
4 p.
artikel
102 Evolving the JET virtual reality system for delivering the JET EP2 shutdown remote handling tasks Williams, Adrian
2011
86 9-11 p. 1898-1902
5 p.
artikel
103 Experiments for the hydrogen combustion aspects of ITER LOVA scenarios Kuznetsov, Mike
2011
86 9-11 p. 2747-2752
6 p.
artikel
104 Exploration of reliability databases and comparison of former IFMIF's results Tapia, Carlos
2011
86 9-11 p. 2726-2729
4 p.
artikel
105 Extending Virtual Reality simulation of ITER maintenance operations with dynamic effects Heemskerk, C.J.M.
2011
86 9-11 p. 2082-2086
5 p.
artikel
106 Extraction residue analysis on F82H-BA07 heat and other reduced activation ferritic/martensitic steels Nagasaka, Takuya
2011
86 9-11 p. 2581-2584
4 p.
artikel
107 Fabrication and characterization of tungsten and graphite based PFC for divertor target elements of ITER like tokamak application Khirwadkar, S.S.
2011
86 9-11 p. 1736-1740
5 p.
artikel
108 Fabrication and high heat flux test of large mockups for ITER first wall semi-prototype Kim, Suk-Kwon
2011
86 9-11 p. 1766-1770
5 p.
artikel
109 Fabrication and high heat flux test with the first wall mockups for developing the KO TBM Lee, Dong Won
2011
86 9-11 p. 1697-1701
5 p.
artikel
110 Fabrication and installation of KSTAR in-vessel control coils Kim, H.K.
2011
86 9-11 p. 1975-1979
5 p.
artikel
111 Fabrication and test of thin double-layered annulus metal hydride bed Kang, Hyun-Goo
2011
86 9-11 p. 2196-2199
4 p.
artikel
112 Fabrication of a full-size mock-up for inboard 10° section of ITER vacuum vessel thermal shield Chung, W.
2011
86 9-11 p. 1928-1932
5 p.
artikel
113 Fabrication of nitrogen trapping test loop for IFMIF-EVEDA Yagi, Juro
2011
86 9-11 p. 2678-2681
4 p.
artikel
114 Fatigue lifetime of repaired high heat flux components for ITER divertor Richou, M.
2011
86 9-11 p. 1771-1775
5 p.
artikel
115 Feasibility of Upper Port Plug tube handling Koning, J.F.
2011
86 9-11 p. 2060-2063
4 p.
artikel
116 F4E R&D programme and results on in-vessel dust and tritium Le Guern, F.
2011
86 9-11 p. 2753-2757
5 p.
artikel
117 Ferroelectric materials and metamaterials for a new approach to ITER–ICRH loads Bottollier-Curtet, H.
2011
86 9-11 p. 2651-2654
4 p.
artikel
118 Flow accelerated corrosion and erosion–corrosion of RAFM steel in liquid breeders Kondo, Masatoshi
2011
86 9-11 p. 2500-2503
4 p.
artikel
119 Fluid dynamic and thermal analyses of a HCPB TBM Breeder Unit mock-up Hernández, Francisco
2011
86 9-11 p. 2278-2281
4 p.
artikel
120 Fundamental welding R&D results for manufacturing vacuum vessel of JT-60SA Asano, Shiro
2011
86 9-11 p. 1816-1820
5 p.
artikel
121 Fusion fuel gas recovery and delivery characteristics on a tray-type ZrCo bed Chung, Dongyou
2011
86 9-11 p. 2233-2236
4 p.
artikel
122 Fusion materials irradiations at MaRIE'S fission fusion facility Pitcher, Eric J.
2011
86 9-11 p. 2647-2650
4 p.
artikel
123 HCLL and HCPB coolant purification system: Design of the copper oxide bed Liger, K.
2011
86 9-11 p. 1859-1862
4 p.
artikel
124 HCLL TBM design status and development Aiello, G.
2011
86 9-11 p. 2129-2134
6 p.
artikel
125 HCPB TBM thermo mechanical design: Assessment with respect codes and standards and DEMO relevancy Cismondi, F.
2011
86 9-11 p. 2228-2232
5 p.
artikel
126 HETRA experiment for investigation of heat removal from the first wall of helium-cooled-pebble-bed test blanket module Ilic, Milica
2011
86 9-11 p. 2250-2253
4 p.
artikel
127 High-efficiency technology for lithium isotope separation using an ionic-liquid impregnated organic membrane Hoshino, Tsuyoshi
2011
86 9-11 p. 2168-2171
4 p.
artikel
128 High heat flux testing of beryllium components with improved diagnostics Thomser, C.
2011
86 9-11 p. 2409-2412
4 p.
artikel
129 High heat flux testing of mock-ups for a full tungsten ITER divertor Gavila, P.
2011
86 9-11 p. 1652-1655
4 p.
artikel
130 High level integration of remote handling control systems at JET Murcutt, Paul Douglas
2011
86 9-11 p. 1911-1914
4 p.
artikel
131 High resolution scanning transmission electron microscopy (HR STEM) analysis of re-deposited layer on ASDEX Upgrade tile Rasinski, M.
2011
86 9-11 p. 1753-1756
4 p.
artikel
132 High-temperature mechanical properties and microstructure of 9Cr oxide dispersion strengthened steel compared with RAFMs Li, Yanfen
2011
86 9-11 p. 2495-2499
5 p.
artikel
133 Hydraulic analysis on effects of back-plate deformation upon stability of high-speed free-surface lithium flow for IFMIF target design Ida, Mizuho
2011
86 9-11 p. 2478-2481
4 p.
artikel
134 Hydraulic characterization of the full scale divertor cassette prototype Tincani, A.
2011
86 9-11 p. 1673-1676
4 p.
artikel
135 Hydraulic numerical analyses of the IFMIF target performance Gordeev, S.
2011
86 9-11 p. 2545-2548
4 p.
artikel
136 Hydrogen incorporation in tungsten deposits growing by deuterium plasma sputtering Katayama, Kazunari
2011
86 9-11 p. 1702-1705
4 p.
artikel
137 Hydrogen permeability of beryllium films prepared by the thermionic vacuum arc method Nemanič, Vincenc
2011
86 9-11 p. 2421-2424
4 p.
artikel
138 Hydrogen retention in gallium samples exposed to ISTTOK plasmas Gomes, R.B.
2011
86 9-11 p. 2458-2461
4 p.
artikel
139 IFMIF accelerator: Database, FMEA, fault tree and RAM Tapia, Carlos
2011
86 9-11 p. 2722-2725
4 p.
artikel
140 Implementation of new techniques for the remote delivery of tooling and components at JET torus Belcher, Chris
2011
86 9-11 p. 1851-1854
4 p.
artikel
141 Increasing current drive efficiency in DEMO by induction of counter-rotation Kemp, R.
2011
86 9-11 p. 2709-2712
4 p.
artikel
142 Influence of CFC quality on the performance of TS limiter elements under cyclic heat loading Missirlian, M.
2011
86 9-11 p. 1579-1582
4 p.
artikel
143 Influence of different cooling rates on the microstructure of the HAZ and welding CCT diagram of CLAM steel Zheng, Shuhui
2011
86 9-11 p. 2616-2619
4 p.
artikel
144 Influence of Y2O3 and Fe2Y additions on the formation of nano-scale oxide particles and the mechanical properties of an ODS RAF steel Oksiuta, Z.
2011
86 9-11 p. 2417-2420
4 p.
artikel
145 Integral approach for neutronics analyses of the European test blanket modules in ITER Fischer, U.
2011
86 9-11 p. 2176-2179
4 p.
artikel
146 Investigation of accident cases for high pressure, high temperature experimental helium loop using RELAP5-3D code Jin, Xue Zhou
2011
86 9-11 p. 2739-2742
4 p.
artikel
147 Investigation of tungsten/EUROFER97 diffusion bonding using Nb interlayer Basuki, W.W.
2011
86 9-11 p. 2585-2588
4 p.
artikel
148 Investigation on the TPR prediction accuracy in blanket neutronics experiments with reflector at JAEA/FNS Kondo, Keitaro
2011
86 9-11 p. 2184-2187
4 p.
artikel
149 Is nuclear fusion a sustainable energy form? Bradshaw, A.M.
2011
86 9-11 p. 2770-2773
4 p.
artikel
150 ITER Cryostat—An overview and design progress Doshi, Bharat
2011
86 9-11 p. 1924-1927
4 p.
artikel
151 ITER – Earthing Perez, Albert
2011
86 9-11 p. 2694-2697
4 p.
artikel
152 ITER Equatorial Port plug engineering: Design and remote handling activities supported by Virtual Reality tools Keller, Delphine
2011
86 9-11 p. 2105-2108
4 p.
artikel
153 ITER Hot Cell process operability analysis using discrete event simulation tools Shuff, R.
2011
86 9-11 p. 1950-1953
4 p.
artikel
154 ITER In-Cryostat inspection and repair feasibility studies Reich, J.
2011
86 9-11 p. 1809-1811
3 p.
artikel
155 Iter in vessel viewing system design and assessment activities Neri, C.
2011
86 9-11 p. 1954-1957
4 p.
artikel
156 ITER lower port systems integration Levesy, B.
2011
86 9-11 p. 1812-1815
4 p.
artikel
157 ITER Port Plug Engineering Trainee Program: Design, manufacturing and integration of structural components (analysis of the attachment) Zeile, Christian
2011
86 9-11 p. 2029-2032
4 p.
artikel
158 ITER remote maintenance system configuration model overview Friconneau, J.P.
2011
86 9-11 p. 1903-1906
4 p.
artikel
159 ITER Remote Maintenance System (IRMS) lifecycle management Tesini, Alessandro
2011
86 9-11 p. 2113-2116
4 p.
artikel
160 ITER thermal shields at the starting phase of procurement Utin, Yu.
2011
86 9-11 p. 2051-2054
4 p.
artikel
161 ITER Upper Port Plug handling cask system assessment and design proposals Pustjens, J.-W.
2011
86 9-11 p. 1937-1940
4 p.
artikel
162 IWR-solution for the ITER vacuum vessel assembly Wu, H.
2011
86 9-11 p. 1834-1837
4 p.
artikel
163 Joining methods of Be/FMS and W/FMS for the ITER TBM first wall Jung, Yang-Il
2011
86 9-11 p. 2390-2393
4 p.
artikel
164 KIT induced activities to support fabrication, assembly and qualification of technology for the HCPB-TBM Neuberger, H.
2011
86 9-11 p. 2039-2042
4 p.
artikel
165 Latest progress on R&D of ITER DFLL-TBM in China Huang, Qunying
2011
86 9-11 p. 2611-2615
5 p.
artikel
166 LIBRETTO-4: Understanding and modeling tritium transport under irradiation Martínez, P.
2011
86 9-11 p. 2374-2377
4 p.
artikel
167 Limitation of tritium outgassing from fusion reactors waste drums: Theoretical aspects of hydrogen oxidation Lefebvre, X.
2011
86 9-11 p. 2398-2402
5 p.
artikel
168 Low temperature mechanical properties of 316L type stainless steel after hydrostatic extrusion Czarkowski, P.
2011
86 9-11 p. 2517-2521
5 p.
artikel
169 Magnetohydrodynamic pressure drops in geometric elements forming a HCLL blanket mock-up Mistrangelo, C.
2011
86 9-11 p. 2304-2307
4 p.
artikel
170 Maintenance concept for the SlimCS DEMO reactor Tobita, K.
2011
86 9-11 p. 2730-2734
5 p.
artikel
171 Manufacturing and characterization of porous SiC for flow channel inserts in dual-coolant blanket designs Bereciartu, Ainhoa
2011
86 9-11 p. 2526-2529
4 p.
artikel
172 Manufacturing of self-passivating W-Cr-Si alloys by mechanical alloying and HIP López-Ruiz, P.
2011
86 9-11 p. 1719-1723
5 p.
artikel
173 Manufacturing, testing and post-test examination of ITER divertor vertical target W small scale mock-ups Visca, Eliseo
2011
86 9-11 p. 1591-1594
4 p.
artikel
174 Markov Chain Monte Carlo (MCMC) methods for parameter estimation of a novel hybrid redundant robot Wang, Yongbo
2011
86 9-11 p. 1863-1867
5 p.
artikel
175 MAST upgrade closed pumped divertor design and analysis Katramados, I.
2011
86 9-11 p. 1595-1598
4 p.
artikel
176 Mechanical characterization of glass fibre–epoxy composite material for ITER pre-compression rings Crescenzi, Fabio
2011
86 9-11 p. 2553-2556
4 p.
artikel
177 Microstructural characterization of the ODS Eurofer 97 EU-batch Mateus, R.
2011
86 9-11 p. 2386-2389
4 p.
artikel
178 Microstructure and mechanical properties of an ODS RAF steel fabricated by hot extrusion or hot isostatic pressing Unifantowicz, P.
2011
86 9-11 p. 2413-2416
4 p.
artikel
179 Neutronic analysis of a dual He/LiPb coolant breeding blanket for DEMO Catalán, J.P.
2011
86 9-11 p. 2293-2296
4 p.
artikel
180 New linear plasma devices in the trilateral euregio cluster for an integrated approach to plasma surface interactions in fusion reactors Unterberg, B.
2011
86 9-11 p. 1797-1800
4 p.
artikel
181 Non-destructive methods for the defect detection in the ITER high heat flux components Roccella, S.
2011
86 9-11 p. 1791-1796
6 p.
artikel
182 Novel methods of tritium production rate measurements in HCLL TBM mock-up experiment with liquid scintillation technique Pohorecki, W.
2011
86 9-11 p. 2429-2432
4 p.
artikel
183 NSTX disruption simulations of detailed divertor and passive plate models by vector potential transfer from OPERA global analysis results Titus, P.H.
2011
86 9-11 p. 1784-1790
7 p.
artikel
184 Numerical benchmarks TRIPOLI−MCNP with use of MCAM on FNG ITER bulk shield and FNG HCLL TBM mock-up experiments Fausser, Clement
2011
86 9-11 p. 2135-2138
4 p.
artikel
185 Numerical estimates of the ITER first mirrors degradation due to atomic fluxes Kotov, V.
2011
86 9-11 p. 1583-1586
4 p.
artikel
186 Observations on the post-mortem investigation of electron beam welds and other micro-structural features of JET Hypervapotrons Olsson Robbie, Mikael Brian
2011
86 9-11 p. 2394-2397
4 p.
artikel
187 On design and development of additional End-Effectors for the Cassette Multifunctional Mover Valkama, Peetu
2011
86 9-11 p. 1946-1949
4 p.
artikel
188 On thermo-mechanical issues induced by irradiation swelling inside the back-plate of the IFMIF target assembly Di Maio, P.A.
2011
86 9-11 p. 2597-2601
5 p.
artikel
189 Operability of the ITER Hot Cell Facility Benchikhoune, M.
2011
86 9-11 p. 1894-1897
4 p.
artikel
190 Optimized trajectories of the transfer cask system in ITER Valente, Filipe
2011
86 9-11 p. 1967-1970
4 p.
artikel
191 Outgassing measurements for the ITER EC H&CD Upper Launcher Aiello, G.
2011
86 9-11 p. 2474-2477
4 p.
artikel
192 Overview: Free surface measurement with renewed nozzle of Osaka Li loop Yoshihashi-Suzuki, Sachiko
2011
86 9-11 p. 2577-2580
4 p.
artikel
193 Overview of liquid lithium lead breeder blanket program in China Wu, Yican
2011
86 9-11 p. 2343-2346
4 p.
artikel
194 Pellet injectors developed at PELIN for JET, TAE and HL-2A Vinyar, Igor
2011
86 9-11 p. 2208-2211
4 p.
artikel
195 Performance and statistical quality assessment of CFC tile bonding on the pre-series elements of the Wendelstein 7-X divertor Greuner, H.
2011
86 9-11 p. 1685-1688
4 p.
artikel
196 Plasma cleaning technique for the removal of mixed materials Vassallo, Espedito
2011
86 9-11 p. 1639-1641
3 p.
artikel
197 Potential common radiation problems for components and diagnostics in future magnetic and inertial confinement fusion devices Alvarez, J.
2011
86 9-11 p. 1762-1765
4 p.
artikel
198 Powder Injection Molding – An innovative manufacturing method for He-cooled DEMO divertor components Antusch, Steffen
2011
86 9-11 p. 1575-1578
4 p.
artikel
199 Power conversion systems based on Brayton cycles for fusion reactors Linares, J.I.
2011
86 9-11 p. 2735-2738
4 p.
artikel
200 Precipitation behavior in F82H during heat treatments of blanket fabrication Sakasegawa, Hideo
2011
86 9-11 p. 2541-2544
4 p.
artikel
201 Predicting the runtime reliability of ITER Remote Handling maintenance equipment Väyrynen, J.
2011
86 9-11 p. 2012-2015
4 p.
artikel
202 Preliminary definition of the remote handling system for the current IFMIF Test Facilities Queral, V.
2011
86 9-11 p. 1941-1945
5 p.
artikel
203 Preliminary results of the experimental study of PFCs exposure to ELMs-like transient loads followed by high heat flux thermal fatigue Riccardi, B.
2011
86 9-11 p. 1665-1668
4 p.
artikel
204 Preliminary studies of in-cell electrophoresis as 6Li enrichment technique Barrado, A.I.
2011
86 9-11 p. 2662-2665
4 p.
artikel
205 Pre-qualification of brazed plasma facing components of divertor target elements for ITER like tokamak application Singh, K.P.
2011
86 9-11 p. 1741-1744
4 p.
artikel
206 Present status of Japanese tasks for lithium target facility under IFMIF/EVEDA Nakamura, Kazuyuki
2011
86 9-11 p. 2491-2494
4 p.
artikel
207 Processing and characterization of a W–2Y material for fusion power reactors Veleva, Lyubomira
2011
86 9-11 p. 2450-2453
4 p.
artikel
208 Process simulation for fuel delivery from storage and delivery system in fusion power plant Chang, Min Ho
2011
86 9-11 p. 2200-2203
4 p.
artikel
209 Production of Cu/diamond composites for first-wall heat sinks Nunes, D.
2011
86 9-11 p. 2589-2592
4 p.
artikel
210 Progress of He-cooled divertor development for DEMO Norajitra, P.
2011
86 9-11 p. 1656-1659
4 p.
artikel
211 Qualification of MHD effects in dual-coolant DEMO blanket and approaches to their modelling Mas de les Valls, E.
2011
86 9-11 p. 2326-2329
4 p.
artikel
212 Quality assurance of Li-Pb eutectic alloy as nuclear material qualification of commercial and R&D material ingots Palomo, C.
2011
86 9-11 p. 2620-2623
4 p.
artikel
213 Radiation induced changes in electrical conductivity of chemical vapor deposited silicon carbides under fast neutron and gamma-ray irradiations Tsuchiya, Bun
2011
86 9-11 p. 2487-2490
4 p.
artikel
214 Radiation induced electrical and microstructural degradation at high temperature for HP SiC Hernández, T.
2011
86 9-11 p. 2442-2445
4 p.
artikel
215 Radiation testing of diagnostic window bondings for enhanced H isotope diffusion Moroño, A.
2011
86 9-11 p. 2466-2469
4 p.
artikel
216 Radioluminescence for in situ materials characterization: First results on SiC for fusion applications Malo, M.
2011
86 9-11 p. 2470-2473
4 p.
artikel
217 R&D status of key technologies for the development of KO TBM Cho, Seungyon
2011
86 9-11 p. 2223-2227
5 p.
artikel
218 Real-time markerless Augmented Reality for Remote Handling system in bad viewing conditions Ziaei, Z.
2011
86 9-11 p. 2033-2038
6 p.
artikel
219 Recent activities of R&D on effects of tritium water on confinement materials and tritiated water processing Yamanishi, T.
2011
86 9-11 p. 2152-2155
4 p.
artikel
220 Recent status of fabrication technology development of water cooled ceramic breeder test blanket module in Japan Hirose, Takanori
2011
86 9-11 p. 2265-2268
4 p.
artikel
221 Reflective metallic coatings for first mirrors on ITER Eren, Baran
2011
86 9-11 p. 2593-2596
4 p.
artikel
222 Remote handling concept for the neutral beam system Choi, Chang-Hwan
2011
86 9-11 p. 2025-2028
4 p.
artikel
223 Remote handling installation of diagnostics in the JET Tokamak Allan, P.
2011
86 9-11 p. 1821-1824
4 p.
artikel
224 Removal of in vessel Tokamak dust by laser techniques Vatry, A.
2011
86 9-11 p. 2717-2721
5 p.
artikel
225 Results of CMM standalone tests at DTP2 Saarinen, Hannu
2011
86 9-11 p. 1907-1910
4 p.
artikel
226 Robust control of Cassette Multi-functional Mover for ITER remote handling tasks Zhai, Likui
2011
86 9-11 p. 2008-2011
4 p.
artikel
227 Role of energetic tritium chemistry on developing thermonuclear fusion reactors Okuno, Kenji
2011
86 9-11 p. 2358-2361
4 p.
artikel
228 Safety concept of the IFMIF/EVEDA lithium test loop Furukawa, Tomohiro
2011
86 9-11 p. 2433-2436
4 p.
artikel
229 Seismic design of the ITER main Tokamak components Mazzone, G.
2011
86 9-11 p. 1984-1988
5 p.
artikel
230 Sensitivity and uncertainty analysis of nuclear responses in the EU HCLL TBM of ITER Leichtle, Dieter
2011
86 9-11 p. 2156-2159
4 p.
artikel
231 Shutdown dose rate analyses for the IFMIF HFTM Serikov, A.
2011
86 9-11 p. 2639-2642
4 p.
artikel
232 Simplification of blanket system for SlimCS fusion DEMO reactor Someya, Youji
2011
86 9-11 p. 2269-2272
4 p.
artikel
233 Simulation of residual thermostress in tungsten after repetitive ELM-like heat loads Pestchanyi, S.
2011
86 9-11 p. 1681-1684
4 p.
artikel
234 Simulations of the SOL plasma for FAST, a proposed ITER satellite tokamak Pericoli Ridolfini, V.
2011
86 9-11 p. 1757-1761
5 p.
artikel
235 Solid state bonding of CuCrZr to 316L stainless steel for ITER applications Goods, S.H.
2011
86 9-11 p. 1634-1638
5 p.
artikel
236 Some error studies for interface management in the HEBT of the IFMIF accelerator Shidara, Hiroyuki
2011
86 9-11 p. 2674-2677
4 p.
artikel
237 Specification of asymmetric VDE loads of the ITER tokamak Bachmann, C.
2011
86 9-11 p. 1915-1919
5 p.
artikel
238 Static stiffness modeling of a novel hybrid redundant robot machine Li, Ming
2011
86 9-11 p. 1838-1842
5 p.
artikel
239 Stress and fatigue in the magnets in DEMO in pulsed and steady-state operation using geometric scaling factors Kovari, Michael
2011
86 9-11 p. 2713-2716
4 p.
artikel
240 Structural analysis of alternative designs for the ITER vacuum vessel and support Hong, Yun-Seok
2011
86 9-11 p. 2021-2024
4 p.
artikel
241 Structural analysis of ITER sub-assembly tools Nam, K.O.
2011
86 9-11 p. 1805-1808
4 p.
artikel
242 Studies for the preparation of the Preliminary Safety Reports for the European test blanket systems Pinna, Tonio
2011
86 9-11 p. 2204-2207
4 p.
artikel
243 Studies on additional electrical heating of the HCLL TBM breeder zone Simon, H.
2011
86 9-11 p. 2216-2219
4 p.
artikel
244 Supervisory system for DTP2 remote handling operations Hahto, Antti
2011
86 9-11 p. 2047-2050
4 p.
artikel
245 Surface composition and morphology changes of JET tiles under plasma interactions Alves, L.C.
2011
86 9-11 p. 2557-2560
4 p.
artikel
246 Surface wave growth characteristics of the high speed liquid Li flow Sugiura, Hirokazu
2011
86 9-11 p. 2635-2638
4 p.
artikel
247 Swelling of CLAM steel irradiated by electron/helium to 17.5dpa with 10appm He/dpa Peng, Lei
2011
86 9-11 p. 2624-2626
3 p.
artikel
248 System engineering approach in the EU Test Blanket Systems Design Integration Panayotov, D.
2011
86 9-11 p. 2241-2245
5 p.
artikel
249 Systems approach for condition management design: JET neutral beam system—A fusion case study Khella, M.
2011
86 9-11 p. 2766-2769
4 p.
artikel
250 Technical issues related to the development of reduced-activation ferritic/martensitic steels as structural materials for a fusion blanket system Tanigawa, Hiroyasu
2011
86 9-11 p. 2549-2552
4 p.
artikel
251 Test Blanket Module Pipe Forest integration in ITER equatorial port Commin, L.
2011
86 9-11 p. 2143-2147
5 p.
artikel
252 Test facility for a neutron flux spectrometer system based on the foil activation technique for neutronics experiments with the ITER TBM Klix, A.
2011
86 9-11 p. 2322-2325
4 p.
artikel
253 The challenges in predicting the fatigue life of dissimilar brazed joints and initial finite element results for a tungsten to EUROFER97 steel brazed joint Hamilton, Niall Robert
2011
86 9-11 p. 1642-1645
4 p.
artikel
254 The design and application of the movable limiter in EAST Lei, Cao
2011
86 9-11 p. 1603-1606
4 p.
artikel
255 The development and prospect of fabrication of W based plasma facing component by atmospheric plasma spraying Zhou, Zhangjian
2011
86 9-11 p. 1625-1629
5 p.
artikel
256 The development of brazing filler for ITER thermal anchor attachment Lee, P.Y.
2011
86 9-11 p. 2569-2572
4 p.
artikel
257 The KSTAR plasma facing components for 2010 operation Kim, K.M.
2011
86 9-11 p. 1693-1696
4 p.
artikel
258 The loosing mechanism of screw bolts on the first wall graphite tiles in EAST Lei, Cao
2011
86 9-11 p. 1710-1713
4 p.
artikel
259 The materials production and processing facility at the Spanish National Centre for fusion technologies (TechnoFusión) Muñoz, A.
2011
86 9-11 p. 2538-2540
3 p.
artikel
260 Theoretical and experimental studies on molybdenum and stainless steel mirrors cleaning by high repetition rate laser beam Leontyev, A.
2011
86 9-11 p. 1728-1731
4 p.
artikel
261 The procurement and testing of the stainless steel in-vessel panels of the Wendelstein 7-X Stellarator Peacock, A.
2011
86 9-11 p. 1706-1709
4 p.
artikel
262 Thermal and mechanical analysis of Wendelstein 7-X thermal shield Nagel, M.
2011
86 9-11 p. 1830-1833
4 p.
artikel
263 Thermal effects and component cooling in Magnum-PSI Kruijt, O.G.
2011
86 9-11 p. 1724-1727
4 p.
artikel
264 Thermal fatigue of DEMO first wall due to pulsed operation Vizvary, Zsolt
2011
86 9-11 p. 1587-1590
4 p.
artikel
265 Thermal stress prediction in divertor cooling finger using the local heat transfer distribution Simonovski, Igor
2011
86 9-11 p. 1620-1624
5 p.
artikel
266 Thermo-hydraulic analysis on Korean helium cooled solid breeder TBM with updated back manifolds design Ahn, Mu-Young
2011
86 9-11 p. 2289-2292
4 p.
artikel
267 Thermo-hydraulic and structural analysis for finger-based concept of ITER blanket first wall Kim, Byoung-Yoon
2011
86 9-11 p. 1997-2002
6 p.
artikel
268 Thermo-hydraulic design verification of the neutral beam liner for the ITER vacuum vessel Ham, Jin-Ki
2011
86 9-11 p. 1971-1974
4 p.
artikel
269 Thermo-mechanical analysis of the Wendelstein 7-X divertor Ye, M.Y.
2011
86 9-11 p. 1630-1633
4 p.
artikel
270 Thermo-structural analysis of integrated back plate in IFMIF/EVEDA liquid lithium target Watanabe, Kazuyoshi
2011
86 9-11 p. 2482-2486
5 p.
artikel
271 The target for the new plasma/wall experiment Magnum-PSI van den Berg, M.A.
2011
86 9-11 p. 1745-1748
4 p.
artikel
272 The TBM-CA configuration management approach for the ITER test blanket module - application to the HCLL TBS Jourd’Heuil, L.
2011
86 9-11 p. 2317-2321
5 p.
artikel
273 Torsion test technique for interfacial shear evaluation of F82H RAFM HIP-joints Nozawa, Takashi
2011
86 9-11 p. 2512-2516
5 p.
artikel
274 Transfer cask system design activities: status and plan Locke, D.
2011
86 9-11 p. 2101-2104
4 p.
artikel
275 Trial fabrication of beryllides as advanced neutron multiplier Nakamichi, Masaru
2011
86 9-11 p. 2262-2264
3 p.
artikel
276 Trial fabrication tests of advanced tritium breeder pebbles using sol–gel method Hoshino, Tsuyoshi
2011
86 9-11 p. 2172-2175
4 p.
artikel
277 Tritium aging effects on hydrogen permeation through Pd8.5Y0.19Ru alloy membrane Guangda, Lu
2011
86 9-11 p. 2220-2222
3 p.
artikel
278 Tritium distribution and chemical forms in the irradiated beryllium pebbles before and after thermoannealing Pajuste, E.
2011
86 9-11 p. 2125-2128
4 p.
artikel
279 Tritium permeation, retention and release properties of beryllium pebbles Chakin, V.
2011
86 9-11 p. 2338-2342
5 p.
artikel
280 Tritium recovery from blanket sweep gas via ceramic proton conductor membrane Kawamura, Yoshinori
2011
86 9-11 p. 2160-2163
4 p.
artikel
281 Two-dimensional modeling of disruption mitigation by gas injection Landman, I.S.
2011
86 9-11 p. 1616-1619
4 p.
artikel
282 Unsteady vacuum gas flow in cylindrical tubes Lihnaropoulos, John
2011
86 9-11 p. 2139-2142
4 p.
artikel
283 Updated thermal-mechanical analysis of DFLL-TBM for ITER Liu, Songlin
2011
86 9-11 p. 2347-2351
5 p.
artikel
284 Upgrade of the material ion beam test facility MARION for enhanced requirements of JET and ITER Nicolai, D.
2011
86 9-11 p. 2791-2794
4 p.
artikel
285 Validation of a loss of vacuum accident (LOVA) Computational Fluid Dynamics (CFD) model Bellecci, C.
2011
86 9-11 p. 2774-2778
5 p.
artikel
286 Verifying elementary ITER maintenance actions with the MS2 benchmark product Heemskerk, C.J.M.
2011
86 9-11 p. 2064-2066
3 p.
artikel
287 Water radiolysis in fusion neutron environments Karditsas, Panagiotis J.
2011
86 9-11 p. 2701-2704
4 p.
artikel
288 Wave period of free-surface waves on high-speed liquid lithium jet for IFMIF target Kanemura, Takuji
2011
86 9-11 p. 2462-2465
4 p.
artikel
289 Workload foreseen for the IFMIF Post Irradiation Examination Facility Molla, J.
2011
86 9-11 p. 2522-2525
4 p.
artikel
290 W/steel joint fabrication using the pulse plasma sintering (PPS) method Rosiński, Marcin
2011
86 9-11 p. 2573-2576
4 p.
artikel
291 X-ray micro-tomography studies on carbon based composite materials for porosity network characterization Tiseanu, Ion
2011
86 9-11 p. 1646-1651
6 p.
artikel
                             291 gevonden resultaten
 
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