| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A conceptual design proposal for a blanket module in the neutral beam injector region of ITER
|
Furmanek, A.
|
|
2007
|
|
15-24 |
p. 1664-1670
7 p.
|
artikel
|
| 2 |
A constitutive model for the thermo-mechanical behaviour of fusion-relevant pebble beds and its application to the simulation of HELICA mock-up experimental results
|
Dell’Orco, G.
|
|
2007
|
|
15-24 |
p. 2366-2374
9 p.
|
artikel
|
| 3 |
Activation analysis of tritium breeder materials in the FDS-II fusion power reactor
|
Chen, M.
|
|
2007
|
|
15-24 |
p. 2641-2646
6 p.
|
artikel
|
| 4 |
Activation and clearance of vanadium alloys and beryllium multipliers in fusion reactors
|
Bartenev, S.A.
|
|
2007
|
|
15-24 |
p. 2885-2890
6 p.
|
artikel
|
| 5 |
Activation of the divertor region as a function of different designs and configurations
|
Taczanowski, S.
|
|
2007
|
|
15-24 |
p. 2089-2094
6 p.
|
artikel
|
| 6 |
Activation of the IFMIF lithium loop corrosion products
|
Cambi, G.
|
|
2007
|
|
15-24 |
p. 2734-2739
6 p.
|
artikel
|
| 7 |
Adaptation of the HCPB DEMO TBM as breeding blanket for ITER: Neutronic and thermal analyses
|
Aquaro, D.
|
|
2007
|
|
15-24 |
p. 2226-2232
7 p.
|
artikel
|
| 8 |
A 2D finite element modelling of tritium permeation for the HCLL DEMO blanket module
|
Gabriel, F.
|
|
2007
|
|
15-24 |
p. 2204-2211
8 p.
|
artikel
|
| 9 |
A dose rate experiment at JET for benchmarking the calculation direct one step method
|
Angelone, M.
|
|
2007
|
|
15-24 |
p. 2805-2811
7 p.
|
artikel
|
| 10 |
A mobile robot with parallel kinematics to meet the requirements for assembling and machining the ITER vacuum vessel
|
Pessi, Pekka
|
|
2007
|
|
15-24 |
p. 2047-2054
8 p.
|
artikel
|
| 11 |
An active vacuum general-purpose radiation test facility for assessment of ceramic insulators and diagnostic components
|
Ooms, H.
|
|
2007
|
|
15-24 |
p. 2531-2535
5 p.
|
artikel
|
| 12 |
Analysis and design of the beryllium tiles for the JET ITER-like wall project
|
Thompson, V.
|
|
2007
|
|
15-24 |
p. 1706-1712
7 p.
|
artikel
|
| 13 |
Analysis of three LOCAs for the European HCPB test blanket system
|
Boccaccini, L.V.
|
|
2007
|
|
15-24 |
p. 2335-2340
6 p.
|
artikel
|
| 14 |
A perspective on equipment design for fusion remote handling
|
Mills, Simon
|
|
2007
|
|
15-24 |
p. 1983-1988
6 p.
|
artikel
|
| 15 |
A perspective on fusion relevant remote handling techniques
|
Rolfe, A.C.
|
|
2007
|
|
15-24 |
p. 1917-1923
7 p.
|
artikel
|
| 16 |
Application of discrete element method to study mechanical behaviors of ceramic breeder pebble beds
|
An, Zhiyong
|
|
2007
|
|
15-24 |
p. 2233-2238
6 p.
|
artikel
|
| 17 |
A program to evaluate the erosion on the CFC tiles of the ITER divertor
|
D’Agata, E.
|
|
2007
|
|
15-24 |
p. 1739-1746
8 p.
|
artikel
|
| 18 |
Assessment of occupational radiation exposure (ORE) for hands-on assistance to the remote handling at ITER ports and waste treatment
|
Di Pace, L.
|
|
2007
|
|
15-24 |
p. 2758-2764
7 p.
|
artikel
|
| 19 |
Assessment of the structural integrity of a prototypical instrumented IFMIF high flux test module rig by fully 3D X-ray microtomography
|
Tiseanu, Ion
|
|
2007
|
|
15-24 |
p. 2608-2614
7 p.
|
artikel
|
| 20 |
A study of the potential influence of frame coolant on HCLL-TBM nuclear response
|
Chiovaro, P.
|
|
2007
|
|
15-24 |
p. 2359-2365
7 p.
|
artikel
|
| 21 |
Automatic generation and validation of an ITER neutronics model from CAD data
|
Tsige-Tamirat, H.
|
|
2007
|
|
15-24 |
p. 1956-1959
4 p.
|
artikel
|
| 22 |
Basic concepts of DEMO and a design of a helium-cooled molten lithium blanket for a testing in ITER
|
Hong, Bong Geun
|
|
2007
|
|
15-24 |
p. 2399-2405
7 p.
|
artikel
|
| 23 |
Basic study on self-healing of Er2O3 coating for vanadium–lithium blanket system
|
Chikada, Takumi
|
|
2007
|
|
15-24 |
p. 2572-2577
6 p.
|
artikel
|
| 24 |
Behaviour of molten beryllium with ITER reference CFC SEPCARB® NB31 under moisture
|
Lipa, M.
|
|
2007
|
|
15-24 |
p. 1688-1693
6 p.
|
artikel
|
| 25 |
Benchmarking of MCAM 4.0 with the ITER 3D model
|
Li, Y.
|
|
2007
|
|
15-24 |
p. 2861-2866
6 p.
|
artikel
|
| 26 |
Benchmarking of SNAM with the ITER 3D model
|
Hu, H.
|
|
2007
|
|
15-24 |
p. 2867-2871
5 p.
|
artikel
|
| 27 |
Burnup calculation of fusion–fission hybrid energy system with thorium cycle
|
Matsunaka, M.
|
|
2007
|
|
15-24 |
p. 2779-2785
7 p.
|
artikel
|
| 28 |
Chemical form of released tritium from solid breeder materials under the various purge gas conditions
|
Kinjyo, T.
|
|
2007
|
|
15-24 |
p. 2147-2151
5 p.
|
artikel
|
| 29 |
Commissioning of water detritiation and cryogenic distillation systems at TLK in view of ITER design
|
Cristescu, I.
|
|
2007
|
|
15-24 |
p. 2126-2132
7 p.
|
artikel
|
| 30 |
Comparison and analysis of expert and student views on the use of energy scenarios in communication on fusion research
|
Bombaerts, Gunter
|
|
2007
|
|
15-24 |
p. 2872-2878
7 p.
|
artikel
|
| 31 |
Conceptual design for a bulk tungsten divertor tile in JET
|
Mertens, Ph.
|
|
2007
|
|
15-24 |
p. 1833-1838
6 p.
|
artikel
|
| 32 |
Conceptual design of the cryogenic system for the helical-type fusion power plant FFHR
|
Yamada, S.
|
|
2007
|
|
15-24 |
p. 2817-2823
7 p.
|
artikel
|
| 33 |
Considerations in testing of ITER first wall mockups
|
Tanaka, T.J.
|
|
2007
|
|
15-24 |
p. 1884-1892
9 p.
|
artikel
|
| 34 |
Consolidation of HIP bonding technologies for the ITER first wall panels
|
Sherlock, P.
|
|
2007
|
|
15-24 |
p. 1806-1812
7 p.
|
artikel
|
| 35 |
Construction of the vacuum vessels and the magnet supporting structures of Wendelstein 7-X
|
Cardella, A.
|
|
2007
|
|
15-24 |
p. 1911-1916
6 p.
|
artikel
|
| 36 |
Corrosion and activation in fusion cooling loops—TRACT
|
Karditsas, Panos
|
|
2007
|
|
15-24 |
p. 2729-2733
5 p.
|
artikel
|
| 37 |
Corrosion experiment in the first liquid metal LiPb loop of China
|
Huang, Qunying
|
|
2007
|
|
15-24 |
p. 2655-2659
5 p.
|
artikel
|
| 38 |
Cryostat engineering design and manufacturing of the EAST superconducting Tokamak
|
Yu, J.
|
|
2007
|
|
15-24 |
p. 1929-1936
8 p.
|
artikel
|
| 39 |
Deliberating and communicating the potential of fusion power based on long-term foresight knowledge
|
Laes, Erik
|
|
2007
|
|
15-24 |
p. 2722-2728
7 p.
|
artikel
|
| 40 |
Demonstration tests for manufacturing the ITER vacuum vessel
|
Shimizu, Katsusuke
|
|
2007
|
|
15-24 |
p. 2081-2088
8 p.
|
artikel
|
| 41 |
Design analysis of the China dual-functional lithium lead (DFLL) test blanket module in ITER
|
Wu, Y.
|
|
2007
|
|
15-24 |
p. 1893-1903
11 p.
|
artikel
|
| 42 |
Design and testing of the Fusion Virtual Assembly System FVAS 1.0
|
Long, P.
|
|
2007
|
|
15-24 |
p. 2062-2066
5 p.
|
artikel
|
| 43 |
Design, fabrication and installation of the lower divertor for DIII-D
|
Anderson, P.M.
|
|
2007
|
|
15-24 |
p. 1756-1761
6 p.
|
artikel
|
| 44 |
Design for in-pile thermal fatigue of first wall mock-ups under ITER relevant conditions
|
Schmalz, F.
|
|
2007
|
|
15-24 |
p. 1820-1824
5 p.
|
artikel
|
| 45 |
Design of a lip seal-replaceable backwall for IFMIF liquid lithium target
|
Nakamura, H.
|
|
2007
|
|
15-24 |
p. 2671-2676
6 p.
|
artikel
|
| 46 |
Design of the ITER torus prototype cryopump
|
Hauer, V.
|
|
2007
|
|
15-24 |
p. 2113-2119
7 p.
|
artikel
|
| 47 |
Design progress of the ITER divertor cassette-to-vacuum vessel locking system
|
Komarov, V.
|
|
2007
|
|
15-24 |
p. 1866-1870
5 p.
|
artikel
|
| 48 |
Design progress of the ITER vacuum vessel sectors and port structures
|
Utin, Yu.
|
|
2007
|
|
15-24 |
p. 2040-2046
7 p.
|
artikel
|
| 49 |
Design study of plasma-facing components for JT-60SA
|
Sakurai, S.
|
|
2007
|
|
15-24 |
p. 1767-1773
7 p.
|
artikel
|
| 50 |
Detailed design and fabrication method of the upper and lower ports for the ITER vacuum vessel
|
Ahn, H.J.
|
|
2007
|
|
15-24 |
p. 1960-1968
9 p.
|
artikel
|
| 51 |
Detailed electromagnetic analysis for design optimization of a tungsten divertor plate for JET
|
Sadakov, S.
|
|
2007
|
|
15-24 |
p. 1825-1832
8 p.
|
artikel
|
| 52 |
Deuteron-induced activation data in EAF for IFMIF calculations
|
Forrest, R.A.
|
|
2007
|
|
15-24 |
p. 2478-2482
5 p.
|
artikel
|
| 53 |
Development of activation foils method for the IFMIF neutron flux characterization
|
Simakov, S.P.
|
|
2007
|
|
15-24 |
p. 2510-2517
8 p.
|
artikel
|
| 54 |
3D finite element electromagnetic and stress analyses of the JET LB-SRP divertor element (tungsten lamella design)
|
Borovkov, A.
|
|
2007
|
|
15-24 |
p. 1871-1877
7 p.
|
artikel
|
| 55 |
Displacement damage quantification in future fusion systems
|
O’Brien, M.H.
|
|
2007
|
|
15-24 |
p. 2536-2542
7 p.
|
artikel
|
| 56 |
3D numerical simulations of hypervapotron cooling concept
|
Pascal-Ribot, S.
|
|
2007
|
|
15-24 |
p. 1781-1785
5 p.
|
artikel
|
| 57 |
EASY-2005: Validation and new tools for data checking
|
Forrest, R.A.
|
|
2007
|
|
15-24 |
p. 2471-2477
7 p.
|
artikel
|
| 58 |
Economic assessment of fusion and fusion-driven subcritical systems based on internalization of external costs and benefits
|
Zhang, S.
|
|
2007
|
|
15-24 |
p. 2879-2884
6 p.
|
artikel
|
| 59 |
Effect of mechanical alloying on the mechanical and microstructural properties of ODS EUROFER 97
|
Ramar, A.
|
|
2007
|
|
15-24 |
p. 2543-2549
7 p.
|
artikel
|
| 60 |
Effects of addition of yttrium on properties and microstructure for China Low Activation Martensitic (CLAM) steel
|
Li, Yanfen
|
|
2007
|
|
15-24 |
p. 2683-2688
6 p.
|
artikel
|
| 61 |
Effects of implantation conditions on retention behavior of deuterrium in highly oriented pyrolytic graphite
|
Suda, Taichi
|
|
2007
|
|
15-24 |
p. 1762-1766
5 p.
|
artikel
|
| 62 |
Effects of repetitive ELM-like heat pulses on tungsten surface morphology
|
Ueda, Y.
|
|
2007
|
|
15-24 |
p. 1904-1910
7 p.
|
artikel
|
| 63 |
Energy storage system for a pulsed DEMO
|
Lucas, J.
|
|
2007
|
|
15-24 |
p. 2752-2757
6 p.
|
artikel
|
| 64 |
Engineering challenges in designing an attractive compact stellarator power plant
|
Raffray, A.R.
|
|
2007
|
|
15-24 |
p. 2696-2704
9 p.
|
artikel
|
| 65 |
Estimation and control of beryllium-7 behavior in liquid lithium loop of IFMIF
|
Ida, Mizuho
|
|
2007
|
|
15-24 |
p. 2490-2496
7 p.
|
artikel
|
| 66 |
EU fuel cycle development priorities for ITER
|
Murdoch, D.
|
|
2007
|
|
15-24 |
p. 2158-2163
6 p.
|
artikel
|
| 67 |
Evaluation of a three-dimensional discrete ordinates radiation transport tool for the support of ITER design
|
Pampin, R.
|
|
2007
|
|
15-24 |
p. 2008-2014
7 p.
|
artikel
|
| 68 |
Examination of Be//Cu joints in hipped Be tiles by using Ion Beam Analysis methods
|
De Vito, E.
|
|
2007
|
|
15-24 |
p. 1671-1680
10 p.
|
artikel
|
| 69 |
Experimental and simulation study on adsorption of hydrogen isotopes on MS5A at 77K
|
Munakata, K.
|
|
2007
|
|
15-24 |
p. 2303-2310
8 p.
|
artikel
|
| 70 |
Experimental investigation of liquid-metal flows through a sudden expansion at fusion-relevant Hartmann numbers
|
Bühler, L.
|
|
2007
|
|
15-24 |
p. 2239-2245
7 p.
|
artikel
|
| 71 |
Experimental validation of a method for performance monitoring of the impurity processing stage in the TEP system of ITER
|
Bornschein, B.
|
|
2007
|
|
15-24 |
p. 2133-2139
7 p.
|
artikel
|
| 72 |
Experimental validation of upgraded designs for PERMCAT reactors considering mechanical behaviour of Pd/Ag membranes under H2 atmosphere
|
Demange, D.
|
|
2007
|
|
15-24 |
p. 2383-2389
7 p.
|
artikel
|
| 73 |
Experimental verification of the axial and lateral stiffness of large W7-X rectangular bellows
|
Reich, J.
|
|
2007
|
|
15-24 |
p. 1924-1928
5 p.
|
artikel
|
| 74 |
Extreme hydrogen plasma fluxes at Pilot-PSI enter the ITER divertor regime
|
de Groot, B.
|
|
2007
|
|
15-24 |
p. 1861-1865
5 p.
|
artikel
|
| 75 |
Fast brazing development for the joining of the beryllium armour layer for the ITER first wall panels
|
Boudot, C.
|
|
2007
|
|
15-24 |
p. 1639-1644
6 p.
|
artikel
|
| 76 |
Fatigue life and cyclic softening behavior of JLF-1 steel
|
Li, Huailin
|
|
2007
|
|
15-24 |
p. 2595-2600
6 p.
|
artikel
|
| 77 |
Filtering of particulates by cracks in containment barriers
|
Han, W.E.
|
|
2007
|
|
15-24 |
p. 2829-2837
9 p.
|
artikel
|
| 78 |
Finite element based design optimization of WENDELSTEIN 7-X divertor components under high heat flux loading
|
Plankensteiner, A.
|
|
2007
|
|
15-24 |
p. 1813-1819
7 p.
|
artikel
|
| 79 |
Flexible small size radiofrequency plasma torch for Tokamak wall cleaning
|
Dinescu, G.
|
|
2007
|
|
15-24 |
p. 2311-2317
7 p.
|
artikel
|
| 80 |
Guidelines for remote handling maintenance of ITER neutral beam line components: Proposal of an alternate supporting system
|
Cordier, J.J.
|
|
2007
|
|
15-24 |
p. 2015-2020
6 p.
|
artikel
|
| 81 |
He-cooled divertor development for DEMO
|
Norajitra, P.
|
|
2007
|
|
15-24 |
p. 2740-2744
5 p.
|
artikel
|
| 82 |
Helium and hydrogen trapping in tungsten deposition layers formed by helium plasma sputtering
|
Katayama, K.
|
|
2007
|
|
15-24 |
p. 1645-1650
6 p.
|
artikel
|
| 83 |
Helium loop for the HCPB Test Blanket Module
|
Neuberger, H.
|
|
2007
|
|
15-24 |
p. 2288-2293
6 p.
|
artikel
|
| 84 |
High heat flux testing of a helium-cooled tungsten tube with porous foam
|
Youchison, D.L.
|
|
2007
|
|
15-24 |
p. 1854-1860
7 p.
|
artikel
|
| 85 |
High heat flux tests of the WENDELSTEIN 7-X pre-series target elements
|
Greuner, H.
|
|
2007
|
|
15-24 |
p. 1713-1719
7 p.
|
artikel
|
| 86 |
HIP joining of Be/CuCrZr for fabrication of ITER first wall
|
Park, Jeong-Yong
|
|
2007
|
|
15-24 |
p. 2497-2503
7 p.
|
artikel
|
| 87 |
Hydrogenic species transport model for ceramic alumina used in ITER ICRH H&CD & Diagnostics Systems
|
Moreno, C.
|
|
2007
|
|
15-24 |
p. 2647-2654
8 p.
|
artikel
|
| 88 |
Hydrogen permeation through membranes with cracks in protection layer
|
Pisarev, A.
|
|
2007
|
|
15-24 |
p. 2120-2125
6 p.
|
artikel
|
| 89 |
Hydrogen transport and trapping in ODS-EUROFER
|
Esteban, G.A.
|
|
2007
|
|
15-24 |
p. 2634-2640
7 p.
|
artikel
|
| 90 |
IFMIF high flux test module and test cell—Design and design validation
|
Heinzel, V.
|
|
2007
|
|
15-24 |
p. 2444-2450
7 p.
|
artikel
|
| 91 |
IFMIF lithium target backplate design integration and thermo-mechanical analysis
|
Riccardi, B.
|
|
2007
|
|
15-24 |
p. 2518-2523
6 p.
|
artikel
|
| 92 |
Impact of N-isotope composition control of ferritic steel on classification of radioactive materials from fusion reactor
|
Hayashi, T.
|
|
2007
|
|
15-24 |
p. 2850-2855
6 p.
|
artikel
|
| 93 |
Impact of risk analysis on ITER nuclear buildings layout
|
Sabathé, Laurent
|
|
2007
|
|
15-24 |
p. 2745-2751
7 p.
|
artikel
|
| 94 |
Improved CuCrZr/316L transition for plasma facing components
|
Tabernig, Bernhard
|
|
2007
|
|
15-24 |
p. 1793-1798
6 p.
|
artikel
|
| 95 |
Infrared images data merging for plasma-facing component inspection
|
Durocher, A.
|
|
2007
|
|
15-24 |
p. 1694-1699
6 p.
|
artikel
|
| 96 |
Infrared thermography inspection methods applied to the target elements of W7-X divertor
|
Missirlian, M.
|
|
2007
|
|
15-24 |
p. 1747-1755
9 p.
|
artikel
|
| 97 |
In-pile tritium permeation through F82H steel with and without a ceramic coating of Cr2O3–SiO2 including CrPO4
|
Nakamichi, M.
|
|
2007
|
|
15-24 |
p. 2246-2251
6 p.
|
artikel
|
| 98 |
In-pile tritium release behaviour of lithiummetatitanate produced by extrusion–spheroidisation–sintering process in EXOTIC-9/1 in the high flux reactor, Petten
|
Peeters, M.M.W.
|
|
2007
|
|
15-24 |
p. 2318-2325
8 p.
|
artikel
|
| 99 |
Installation of liquid phase catalytic exchange columns for the Wolsong tritium removal facility
|
Song, K.M.
|
|
2007
|
|
15-24 |
p. 2264-2268
5 p.
|
artikel
|
| 100 |
Integrated thermo-fluid analysis towards helium flow path design for an ITER solid breeder blanket module
|
Ying, A.
|
|
2007
|
|
15-24 |
p. 2217-2225
9 p.
|
artikel
|
| 101 |
Investigation of free-surface fluctuations of liquid lithium flow for IFMIF lithium target by using an electro-contact probe
|
Kanemura, T.
|
|
2007
|
|
15-24 |
p. 2550-2557
8 p.
|
artikel
|
| 102 |
Investigation of the susceptibility of EUROFER97 in lead–lithium to liquid metal embrittlement (LME)
|
Bosch, R.W.
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2007
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Investigation of tungsten and beryllium behaviour under short transient events
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2007
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Irradiation and testing of off-the-shelf seal materials for water hydraulic applications in ITER remote handling equipment
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2007
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15-24 |
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Kinetic Monte Carlo modelling of neutron irradiation damage in iron
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Gámez, L.
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2007
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15-24 |
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Large-eddy simulation of turbulent flow and heat transfer in a mildly expanded channel of IFMIF high flux test module
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Ebara, Shinji
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2007
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Manufacturing methods and characterisation of titanium beryllides
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Kurinskiy, P.
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2007
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Measurement and analysis of activation induced in lanthanum, tantalum, and erbium by fusion peak neutrons
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2007
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Measurement and analysis of neutron and gamma-ray flux spectra in a neutronics mock-up of the HCPB Test Blanket Module
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2007
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Measurement of free surface of liquid metal lithium jet for IFMIF target
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Kondo, H.
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2007
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Measurement of thermal expansion of Li2TiO3 pebble beds
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Tanigawa, Hisashi
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2007
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Mechanical characterization of Li2TiO3 and Li4SiO4 pebble beds: Experimental determination of the material properties and of the pebble bed effective values
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Zaccari, Nicola
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2007
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Mechanical response of oxide dispersion strengthened (ODS) EUROFER97 after neutron irradiation at 300°C
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2007
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Methods to determine the joint strength of C/C to copper joints
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2007
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Metrology for ITER assembly
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2007
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Mini-channel flow experiments and CFD validation analyses with the IFMIF thermo-hydraulic experimental facility (ITHEX)
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2007
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Modelling and computer simulation for the manufacture by powder HIPing of blanket shield components for ITER
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2007
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15-24 |
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Modelling irradiation effects in fusion materials
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2007
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Molecular Dynamics Simulation of surface vaporization in beryllium Plasma Facing Components
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2007
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Natural convection cooling of the IFMIF target and test cell
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2007
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Net shaping of tungsten components by micro powder injection moulding
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2007
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artikel
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Neutronics experiment on a helium cooled pebble bed (HCPB) breeder blanket mock-up
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2007
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10 p.
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New burnup calculation system for fusion–fission hybrid reactor
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2007
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Non-stoichiometory and vaporization characteristic of Li2.1TiO3.05 in hydrogen atmosphere
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Hoshino, Tsuyoshi
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2007
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p. 2269-2273
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Nuclear performance analyses for HCPB test blanket modules in ITER
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Fischer, U.
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2007
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Numerical investigation of liquid metal flows in rectangular sudden expansions
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Mistrangelo, C.
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2007
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Optimization of the JET beryllium tile profile for power handling
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Nunes, I.
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2007
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Overview of the last progresses for the European Test Blanket Modules projects
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Salavy, J.-F.
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2007
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Performance of modified pulse-operated piezoelectric valves for the gas inlet system of RFX
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Masiello, A.
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2007
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Plasma wall interaction study in the large helical device
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Hino, T.
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2007
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Power conversion cycles study for He-cooled reactor concepts for DEMO
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2007
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7 p.
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Power saving of large scaled helium compressor for fusion device using an adsorption chiller
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Noguchi, M.
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2007
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Pre-brazed casting and hot radial pressing: A reliable process for the manufacturing of CFC and W monoblock mock-ups
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Visca, Eliseo
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2007
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p. 1651-1656
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Pre-design of Magnum-PSI: A new plasma–wall interaction experiment
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van Eck, H.J.N.
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2007
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p. 1878-1883
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Preliminary design of lithium lead test blanket module for the Chinese Experimental Advanced Superconducting Tokamak
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Liu, Songlin
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2007
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Preliminary experimental study on Hot Isostatic Pressing diffusion bonding for CLAM/CLAM
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Li, C.
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Pressurizing behavior on ingress of coolant into pebble bed of blanket of Fusion DEMO reactor
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Tsuru, Daigo
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2007
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Qualification, commissioning and in situ monitoring of high heat flux plasma facing components
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Escourbiac, F.
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2007
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Quality management for WENDELSTEIN 7-X—Lessons learned
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Feist, J.-H.
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2007
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6 p.
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Radiation assessment of hydrogen-loaded aluminium-coated pure silica core fibres for ITER plasma diagnostic applications
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Brichard, B.
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2007
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5 p.
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Radiation effects on the optical and electrical properties of CVD diamond
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Moroño, A.
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2007
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Radiation induced ion currents in vacuum due to residual air, He, and H, and their expected effect on insulating surfaces
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Hodgson, E.R.
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2007
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R&D on full tungsten divertor and beryllium wall for JET ITER-like wall project
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Hirai, T.
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2007
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Recent developments toward the use of tungsten as armour material in plasma facing components
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Mitteau, R.
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2007
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Recent EU activities for IFMIF EVEDA in the framework of the broader approach
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Ibarra, A.
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2007
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Recent progress in DEMO fusion core engineering: Improved segmentation, maintenance and blanket concepts
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2007
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Reliability of the TJ-II power supply system: Collection and analysis of the operational experience data
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Izquierdo, Jesus
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2007
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Results from ITER vacuum vessel sector manufacturing development in Europe
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Jones, L.
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2007
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Results of the examinations of the W7-X pre-series target elements
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Boscary, J.
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2007
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Safety assessment of energy fluxes on in-vessel components with SAFALY
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2007
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5 p.
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Safety design of radiation shielding for JT-60SA
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Sukegawa, A.M.
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2007
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Sensitivity and uncertainty analyses of the tritium production in the HCPB breeder blanket mock-up experiment
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Leichtle, D.
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2007
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7 p.
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Simulation of cracks in tungsten under ITER specific transient heat loads
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Pestchanyi, S.E.
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2007
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7 p.
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Six-party qualification program of FW fabrication methods for ITER blanket module procurement
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Ioki, K.
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2007
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7 p.
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State of the art of fusion material recycling and remaining issues
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Massaut, V.
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2007
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6 p.
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Strategies in electro-chemical machining of tungsten for divertor application
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2007
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Structural analysis for an upper port of the ITER vacuum vessel
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Hong, Y.S.
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2007
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Structural and fracture mechanics analysis of ITER vacuum vessel
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Iguchi, Masahide
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2007
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Structural design of ferritic steel tiles for ripple reduction of toroidal magnetic field in JT-60U
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Kudo-Shibama, Yusuke
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2007
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9 p.
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Surface electrical degradation for low mass ion implanted SiO2: Dependence on ion mass, energy and dose rate
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Gonzalez de Vicente, S.M.
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2007
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5 p.
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Technological aspects of liquid lithium limiter experiment on FTU tokamak
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Vertkov, A.
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2007
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7 p.
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Temperature dependence of hydrogen isotope behaviors in non-He+ pre-implanted SiC and He+ pre-implanted SiC
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Oya, Yasuhisa
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2007
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6 p.
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The design and development of divertor remote handling equipment for ITER
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Palmer, J.
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2007
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6 p.
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The draining and drying experiments for the plasma vessel cooling pipes of the Wendelstein 7-X stellarator
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Dobosz, R.
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2007
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6 p.
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The effect of intense plasma pulse pre-treatment on wettability in ceramic–copper system
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Barlak, M.
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2007
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7 p.
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The EFF project status and the NEA nuclear data services
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Henriksson, H.
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2007
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The JET high frequency pellet injector project
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Geraud, Alain
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2007
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p. 2183-2188
6 p.
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The laser in vessel viewing system (IVVS) for iter: Test results on first wall and divertor samples and new developments
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Neri, C.
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2007
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The performance of a trickle-bed reactor packed with a Pt/SDBC catalyst mixture for the CECE process
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Paek, Seungwoo
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2007
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7 p.
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The plasma-facing components transporter (PFCT): A prototype system for PFC replacement on the new ITER 2001 cassette mock-up
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Miccichè, G.
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2007
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7 p.
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The production and delivery of inertial fusion energy power plant fuel: The cryogenic target
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Bozek, A.S.
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2007
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5 p.
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Thermal hydraulic analysis and control of the HELOKA water cooling system
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Marchese, V.
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2007
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9 p.
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Thermal–hydraulic analysis of the HCLL DEMO blanket
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Aiello, G.
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2007
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6 p.
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Thermo-mechanical analyses of large ceramic rings during brazing process
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Zaccaria, P.
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2007
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7 p.
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The test blanket modules project in Europe: From the strategy to the technical plan over next 10 years
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Poitevin, Y.
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2007
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The use of virtual prototyping and simulation in ITER maintenance device development
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Esqué, S.
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2007
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8 p.
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The value of modern decision-making support services to fusion projects
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Pascal, Claude
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2007
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9 p.
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Thin slit streaming experiment for ITER by using D-T neutron source
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Ochiai, K.
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2007
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5 p.
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Towards operations on Tore Supra of an ITER relevant inspection robot and associated processes
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Gargiulo, L.
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2007
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Treatment of ITER plasma facing components: Current status and remaining open issues before ITER implementation
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Grisolia, C.
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2007
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9 p.
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TRIEX facility: An experimental loop to test tritium extraction systems from lead lithium
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Aiello, A.
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2007
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p. 2294-2302
9 p.
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Tritium management in HCLL-PPCS model AB blanket
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Ricapito, I.
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2007
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9 p.
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Tritium release from breeding blanket materials in high magnetic field
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Vītiņš, A.
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2007
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p. 2341-2346
6 p.
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Validation of computational fluid dynamics (CFD) tools for the development of a helium-cooled divertor
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Kruessmann, R.
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2007
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5 p.
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Verification of back-plate sealing performance against Li-infiltration and corrosion-induced damage based on the bayonet back-plate concept
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Gillén, Peter
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2007
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p. 2601-2607
7 p.
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Verification of nuclear data for DT neutron induced charged-particle emission reaction of light nuclei
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Kondo, K.
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2007
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p. 2786-2793
8 p.
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Verification to recover tritium in neutron-irradiated Li by Y plate
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Fukada, Satoshi
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2007
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6 p.
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Water hydraulic polymer components under irradiation
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Hernández, Teresa
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2007
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Water leak localization and recovery in Tore Supra
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Martinez, A.
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2007
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7 p.
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W/Cu composites produced by pulse plasma sintering technique (PPS)
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Rosinski, M.
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2007
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p. 2621-2626
6 p.
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