| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A beam profile monitor for IFMIF
|
Surrey, E.
|
|
2008
|
96-97 |
10-12 |
p. 1559-1563
5 p.
|
artikel
|
| 2 |
Acceleration techniques for the direct use of CAD-based geometry in fusion neutronics analysis
|
Wilson, Paul P.H.
|
|
2010
|
96-97 |
10-12 |
p. 1759-1765
7 p.
|
artikel
|
| 3 |
Accuracy assessment of the in-bed calorimetry employed in ITER SDS
|
Lee, Eun-Seok
|
|
2008
|
96-97 |
10-12 |
p. 1424-1428
5 p.
|
artikel
|
| 4 |
A conceptual design and structural stabilities of in-pit assembly tools for the completion of final sector assembly at tokamak hall
|
Nam, K.O.
|
|
2010
|
96-97 |
10-12 |
p. 1716-1719
4 p.
|
artikel
|
| 5 |
A conceptual design of assembly strategy and dedicated tools for assembly of 40° sector
|
Park, H.K.
|
|
2010
|
96-97 |
10-12 |
p. 1981-1985
5 p.
|
artikel
|
| 6 |
A conceptual design of the ITER upper port plug structure and its cooling channels
|
Pak, S.I.
|
|
2008
|
96-97 |
10-12 |
p. 1594-1599
6 p.
|
artikel
|
| 7 |
Activation and afterheat analyses for the HCPB test blanket module in ITER
|
Pereslavtsev, P.
|
|
2008
|
96-97 |
10-12 |
p. 1742-1746
5 p.
|
artikel
|
| 8 |
Activation of the IFMIF prototype accelerator and beam dump by deuterons and protons
|
Simakov, S.P.
|
|
2008
|
96-97 |
10-12 |
p. 1543-1547
5 p.
|
artikel
|
| 9 |
A development of user-friendly graphical interface for a blanket simulator
|
Lee, Young-Seok
|
|
2010
|
96-97 |
10-12 |
p. 1957-1965
9 p.
|
artikel
|
| 10 |
Advanced electro-chemical processing of tungsten components for He-cooled divertor application
|
Krauss, W.
|
|
2010
|
96-97 |
10-12 |
p. 2257-2262
6 p.
|
artikel
|
| 11 |
Advanced fuelling system for ITER
|
Raman, Roger
|
|
2008
|
96-97 |
10-12 |
p. 1368-1374
7 p.
|
artikel
|
| 12 |
Analyses of fusion integral benchmark experiments at JAEA/FNS with FENDL-2.1 and other recent nuclear data libraries
|
Konno, Chikara
|
|
2008
|
96-97 |
10-12 |
p. 1774-1781
8 p.
|
artikel
|
| 13 |
Analysis of near-term fusion power plant designs from the material management stance
|
Pampin, R.
|
|
2008
|
96-97 |
10-12 |
p. 1419-1423
5 p.
|
artikel
|
| 14 |
An easy way to perform a radiation damage calculation in a complicated geometry
|
Hogenbirk, A.
|
|
2008
|
96-97 |
10-12 |
p. 1828-1831
4 p.
|
artikel
|
| 15 |
A new modular design concept for China's HCSB TBM in ITER
|
Zhang, G.
|
|
2010
|
96-97 |
10-12 |
p. 1819-1823
5 p.
|
artikel
|
| 16 |
An integrated approach to the back-end of the fusion materials cycle
|
Zucchetti, M.
|
|
2008
|
96-97 |
10-12 |
p. 1706-1709
4 p.
|
artikel
|
| 17 |
A proposal of ITER vacuum vessel fabrication specification and results of the full-scale partial mock-up test
|
Nakahira, M.
|
|
2008
|
96-97 |
10-12 |
p. 1578-1582
5 p.
|
artikel
|
| 18 |
Assessment of alternative vessel and blanket design on ITER operation
|
Cavinato, M.
|
|
2010
|
96-97 |
10-12 |
p. 2245-2250
6 p.
|
artikel
|
| 19 |
Assessment of a water hydraulic joint for remote handling operations in the divertor region
|
Dubus, G.
|
|
2008
|
96-97 |
10-12 |
p. 1845-1849
5 p.
|
artikel
|
| 20 |
Assessment of defects in EUROFER 97 first wall/blanket structures taking into account its viscoplastic behavior
|
Aktaa, J.
|
|
2010
|
96-97 |
10-12 |
p. 2065-2069
5 p.
|
artikel
|
| 21 |
Assessment of the activation, decay heat, and waste disposal of the US helium-cooled ceramic breeder test blanket module in ITER
|
Youssef, Mahmoud Z.
|
|
2008
|
96-97 |
10-12 |
p. 1764-1770
7 p.
|
artikel
|
| 22 |
A study on the thermal analyses of the ITER vacuum vessel thermal shield
|
Chung, W.
|
|
2008
|
96-97 |
10-12 |
p. 1588-1593
6 p.
|
artikel
|
| 23 |
Attachment systems for demo in-vessel components: Blanket, manifold and hot ring shield
|
Koehly, C.
|
|
2008
|
96-97 |
10-12 |
p. 1669-1673
5 p.
|
artikel
|
| 24 |
Author Index
|
|
|
2010
|
96-97 |
10-12 |
p. I-VII
nvt p.
|
artikel
|
| 25 |
Author Index
|
|
|
2008
|
96-97 |
10-12 |
p. 1896-1901
6 p.
|
artikel
|
| 26 |
Bend points of hydrogen partial pressure curves obtained by tritium removal simulation tests
|
Kawano, T.
|
|
2008
|
96-97 |
10-12 |
p. 1395-1399
5 p.
|
artikel
|
| 27 |
Biological hazard issues from potential releases of tritiated dust from ITER
|
Di Pace, L.
|
|
2008
|
96-97 |
10-12 |
p. 1729-1732
4 p.
|
artikel
|
| 28 |
Blanket mock-up experiment with a LiAlPb assembly irradiated with 14MeV neutrons in preparation of the HCLL-TBM neutronics experiment
|
Klix, A.
|
|
2008
|
96-97 |
10-12 |
p. 1813-1817
5 p.
|
artikel
|
| 29 |
Characteristics of honeycomb catalysts for oxidation of tritiated hydrogen and methane gases
|
Uda, T.
|
|
2008
|
96-97 |
10-12 |
p. 1715-1720
6 p.
|
artikel
|
| 30 |
Characterization of dusts and impurities from the interaction between the first wall materials and energetic laser beams
|
Xiao, Qingmei
|
|
2010
|
96-97 |
10-12 |
p. 2165-2170
6 p.
|
artikel
|
| 31 |
Code development and validation for analyzing liquid metal MHD flow in rectangular ducts
|
Zhou, Tao
|
|
2010
|
96-97 |
10-12 |
p. 1736-1741
6 p.
|
artikel
|
| 32 |
Comparison analysis of 1D/2D/3D neutronics modeling for a fusion reactor
|
Li, J.
|
|
2008
|
96-97 |
10-12 |
p. 1678-1682
5 p.
|
artikel
|
| 33 |
Computer simulation of packing structure in pebble beds
|
Gan, Yixiang
|
|
2010
|
96-97 |
10-12 |
p. 1782-1787
6 p.
|
artikel
|
| 34 |
Conceptual and preliminary engineering design of experimental helium loop for China HCCB TBM components test
|
Xiang, B.
|
|
2010
|
96-97 |
10-12 |
p. 2146-2149
4 p.
|
artikel
|
| 35 |
Conceptual design of a component test facility based on the spherical tokamak
|
Voss, G.M.
|
|
2008
|
96-97 |
10-12 |
p. 1648-1653
6 p.
|
artikel
|
| 36 |
Conceptual design of JT-60SA cryostat
|
Shibama, Y.K.
|
|
2008
|
96-97 |
10-12 |
p. 1605-1609
5 p.
|
artikel
|
| 37 |
Conceptual design of the China fusion power plant FDS-II
|
Wu, Y.
|
|
2008
|
96-97 |
10-12 |
p. 1683-1689
7 p.
|
artikel
|
| 38 |
Conceptual design on interface between ITER and tritium extraction system of Chinese helium-cooled solid breeder test blanket module
|
Zhang, Long
|
|
2010
|
96-97 |
10-12 |
p. 2213-2216
4 p.
|
artikel
|
| 39 |
Conceptual study for TBM-related activities in ITER Hot Cell Facility before TBM shipment back to owner
|
Bai, Yunqing
|
|
2010
|
96-97 |
10-12 |
p. 1913-1918
6 p.
|
artikel
|
| 40 |
Contamination of ITER core by impurities of tungsten and carbon
|
Landman, I.S.
|
|
2008
|
96-97 |
10-12 |
p. 1797-1800
4 p.
|
artikel
|
| 41 |
Corrosion analysis of CLAM steel in flowing liquid LiPb at 480°C
|
Chen, Yaping
|
|
2010
|
96-97 |
10-12 |
p. 1909-1912
4 p.
|
artikel
|
| 42 |
Corrosion characteristics of low activation ferritic steel, JLF-1, in liquid lithium in static and thermal convection conditions
|
Xu, Qi
|
|
2008
|
96-97 |
10-12 |
p. 1477-1483
7 p.
|
artikel
|
| 43 |
Coupled transient thermo-fluid/thermal-stress analysis approach in a VTBM setting
|
Ying, A.
|
|
2008
|
96-97 |
10-12 |
p. 1807-1812
6 p.
|
artikel
|
| 44 |
Current status of design and engineering analysis of Indian LLCB TBM
|
Chaudhuri, Paritosh
|
|
2010
|
96-97 |
10-12 |
p. 1966-1969
4 p.
|
artikel
|
| 45 |
Damage study for various materials at the first wall of a magnetic fusion reactor using protective liquid wall
|
Übeyli, Mustafa
|
|
2008
|
96-97 |
10-12 |
p. 1508-1511
4 p.
|
artikel
|
| 46 |
Data collection on component malfunctions and failures of JET ICRH system
|
Cambi, G.
|
|
2008
|
96-97 |
10-12 |
p. 1874-1877
4 p.
|
artikel
|
| 47 |
Deceleration in a traveling wave direct energy converter for advanced fusion
|
Takeno, H.
|
|
2008
|
96-97 |
10-12 |
p. 1696-1699
4 p.
|
artikel
|
| 48 |
DEMO maintenance scenarios: Scheme for time estimations and preliminary estimates for blankets arranged in multi-module segments
|
Nagy, D.
|
|
2008
|
96-97 |
10-12 |
p. 1870-1873
4 p.
|
artikel
|
| 49 |
Depletion analysis of a solid-type blanket design for ITER
|
Yun, Sunghwan
|
|
2008
|
96-97 |
10-12 |
p. 1654-1660
7 p.
|
artikel
|
| 50 |
Design and analyses of a one-dimensional CFC calorimeter for SPIDER beam characterisation
|
Rizzolo, Andrea
|
|
2010
|
96-97 |
10-12 |
p. 2268-2273
6 p.
|
artikel
|
| 51 |
Design, interface development and structural analyses of SPIDER vacuum vessel
|
Rigato, W.
|
|
2010
|
96-97 |
10-12 |
p. 2305-2311
7 p.
|
artikel
|
| 52 |
Design of a high-yield H2 + ion source for commissioning of the IFMIF accelerator using a one-dimensional plasma model
|
King, R.F.
|
|
2008
|
96-97 |
10-12 |
p. 1553-1558
6 p.
|
artikel
|
| 53 |
Design of lower divertor for JT-60SA
|
Sakurai, S.
|
|
2010
|
96-97 |
10-12 |
p. 2187-2191
5 p.
|
artikel
|
| 54 |
Design of the integration interface between the EU HCPB TBM and the ITER TBM port plug including operations for connection
|
Neuberger, H.
|
|
2008
|
96-97 |
10-12 |
p. 1861-1864
4 p.
|
artikel
|
| 55 |
Design of the ITER tokamak assembly tools
|
Park, Hyunki
|
|
2008
|
96-97 |
10-12 |
p. 1583-1587
5 p.
|
artikel
|
| 56 |
Design optimizations of IFMIF High Flux Test Module towards uniform specimen temperature distribution
|
Chen, Y.
|
|
2010
|
96-97 |
10-12 |
p. 1952-1956
5 p.
|
artikel
|
| 57 |
Design progress of the vacuum vessel sectors and ports towards the ITER construction
|
Utin, Yu.
|
|
2008
|
96-97 |
10-12 |
p. 1565-1570
6 p.
|
artikel
|
| 58 |
Design proposal of a connection system for ITER in-vessel magnetic sensors
|
Peruzzo, Simone
|
|
2010
|
96-97 |
10-12 |
p. 1707-1710
4 p.
|
artikel
|
| 59 |
Design study of JT-60SA divertor for high heat and particle controllability
|
Kawashima, H.
|
|
2008
|
96-97 |
10-12 |
p. 1643-1647
5 p.
|
artikel
|
| 60 |
Detail analysis of fusion neutronics benchmark experiment on beryllium
|
Konno, Chikara
|
|
2010
|
96-97 |
10-12 |
p. 2054-2058
5 p.
|
artikel
|
| 61 |
Detail design of the beam source for the SPIDER experiment
|
Marcuzzi, D.
|
|
2010
|
96-97 |
10-12 |
p. 1792-1797
6 p.
|
artikel
|
| 62 |
Detailed electromagnetic numerical evaluation of eddy currents induced by toroidal and poloidal magnetic field variation and halo currents
|
Roccella, M.
|
|
2008
|
96-97 |
10-12 |
p. 1625-1630
6 p.
|
artikel
|
| 63 |
Deterministic safety analysis of the reference accidental sequence for the European HCPB TBM system
|
Jin, X.
|
|
2008
|
96-97 |
10-12 |
p. 1759-1763
5 p.
|
artikel
|
| 64 |
Detritiation studies for JET decommissioning
|
Perevezentsev, A.N.
|
|
2008
|
96-97 |
10-12 |
p. 1364-1367
4 p.
|
artikel
|
| 65 |
Deuterium retention and desorption behavior of reduced activated ferritic steel with surface damage due to high energy helium ion irradiation
|
Yamauchi, Y.
|
|
2010
|
96-97 |
10-12 |
p. 1838-1840
3 p.
|
artikel
|
| 66 |
Development of advanced Al coating processes for future application as anti-corrosion and T-permeation barriers
|
Konys, J.
|
|
2010
|
96-97 |
10-12 |
p. 2141-2145
5 p.
|
artikel
|
| 67 |
Development of a IRSN code for dust mobilisation problems in ITER
|
García-Cascales, J.R.
|
|
2010
|
96-97 |
10-12 |
p. 2274-2281
8 p.
|
artikel
|
| 68 |
Development of a new detection system for monitoring high-level tritiated water
|
Matsuyama, Masao
|
|
2008
|
96-97 |
10-12 |
p. 1438-1441
4 p.
|
artikel
|
| 69 |
Development of an improved LPCE column for the TLK facility with the help of the channeling stage model
|
Sugiyama, T.
|
|
2008
|
96-97 |
10-12 |
p. 1442-1446
5 p.
|
artikel
|
| 70 |
Development of an ITER relevant inspection robot
|
Gargiulo, Laurent
|
|
2008
|
96-97 |
10-12 |
p. 1833-1836
4 p.
|
artikel
|
| 71 |
Development of a powder metallurgy process for tungsten components
|
Piotter, Volker
|
|
2008
|
96-97 |
10-12 |
p. 1517-1520
4 p.
|
artikel
|
| 72 |
Development of a tokamak reactor system code and its application for concept development of a demo reactor
|
Hong, Bong Guen
|
|
2008
|
96-97 |
10-12 |
p. 1615-1618
4 p.
|
artikel
|
| 73 |
Development of a virtual reality simulator for the ITER blanket remote handling system
|
Takeda, Nobukazu
|
|
2008
|
96-97 |
10-12 |
p. 1837-1840
4 p.
|
artikel
|
| 74 |
Development of in situ diagnostics and tools handled by a light multipurpose carrier for tokamak in-vessel interventions
|
Houry, M.
|
|
2010
|
96-97 |
10-12 |
p. 1947-1951
5 p.
|
artikel
|
| 75 |
Divertor modelling for conceptual studies of tokamak fusion reactor FDS-III
|
Chen, YiPing
|
|
2010
|
96-97 |
10-12 |
p. 1728-1731
4 p.
|
artikel
|
| 76 |
D-T neutron streaming experiment simulating narrow gaps in ITER equatorial port
|
Ochiai, K.
|
|
2008
|
96-97 |
10-12 |
p. 1725-1728
4 p.
|
artikel
|
| 77 |
Dust control in tokamak environment
|
Rosanvallon, S.
|
|
2008
|
96-97 |
10-12 |
p. 1701-1705
5 p.
|
artikel
|
| 78 |
Dust mobilization and transport modeling for loss of vacuum accidents
|
Humrickhouse, P.W.
|
|
2008
|
96-97 |
10-12 |
p. 1721-1724
4 p.
|
artikel
|
| 79 |
Dynamic test of the ITER blanket key and ceramic insulated pad
|
Khomyakov, S.
|
|
2010
|
96-97 |
10-12 |
p. 2334-2339
6 p.
|
artikel
|
| 80 |
Eddy current induced electromagnetic loads on shield blankets during plasma disruptions in ITER: A benchmark exercise
|
Kim, Duck-Hoi
|
|
2010
|
96-97 |
10-12 |
p. 1747-1758
12 p.
|
artikel
|
| 81 |
Effect of cooling rate on mechanical properties of aged ITER-grade CuCrZr
|
Park, Jeong-Yong
|
|
2008
|
96-97 |
10-12 |
p. 1503-1507
5 p.
|
artikel
|
| 82 |
Effect of Fe and C doping on the thermal release of helium from aluminum
|
Xiang, X.
|
|
2010
|
96-97 |
10-12 |
p. 2086-2089
4 p.
|
artikel
|
| 83 |
Effect of magnetic field on characteristics of divertor plasma and divertor erosion rate: PIC simulation
|
Sang, Chaofeng
|
|
2010
|
96-97 |
10-12 |
p. 1941-1946
6 p.
|
artikel
|
| 84 |
Effects of the gas–liquid ratio on the optimum catalyst quantity for the CECE process with a homogeneously packed LPCE column
|
Sugiyama, T.
|
|
2008
|
96-97 |
10-12 |
p. 1447-1450
4 p.
|
artikel
|
| 85 |
Electrical insulation test of alumina coating fabricated by sol–gel method in molten PbLi pool
|
Ueki, Yoshitaka
|
|
2010
|
96-97 |
10-12 |
p. 1824-1828
5 p.
|
artikel
|
| 86 |
Elucidation of annihilation processes of defects induced by γ-irradiation in Li2TiO3
|
Suzuki, Sachiko
|
|
2010
|
96-97 |
10-12 |
p. 2331-2333
3 p.
|
artikel
|
| 87 |
Engineering design and R&D of Impurity Influx Monitor (divertor) for ITER
|
Ogawa, Hiroaki
|
|
2008
|
96-97 |
10-12 |
p. 1405-1409
5 p.
|
artikel
|
| 88 |
Evaluation of electromagnetic forces on Chinese Dual Functional Lithium Lead Test Blanket Module in ITER
|
Liu, Songlin
|
|
2010
|
96-97 |
10-12 |
p. 2176-2180
5 p.
|
artikel
|
| 89 |
Evolution of ITER Tritium Confinement strategy and adaptation to Cadarache site conditions and French regulatory requirements
|
Murdoch, D.
|
|
2008
|
96-97 |
10-12 |
p. 1355-1358
4 p.
|
artikel
|
| 90 |
Experimental and numerical investigation in flow configurations related to the vacuum systems of fusion reactors
|
Varoutis, S.
|
|
2010
|
96-97 |
10-12 |
p. 1798-1802
5 p.
|
artikel
|
| 91 |
Experimental durability studies of electrolysis cell materials for a water detritiation system
|
Iwai, Yasunori
|
|
2008
|
96-97 |
10-12 |
p. 1410-1413
4 p.
|
artikel
|
| 92 |
Experimental study of detritiation system catalyst poisoning
|
Borgognoni, Fabio
|
|
2008
|
96-97 |
10-12 |
p. 1375-1379
5 p.
|
artikel
|
| 93 |
Experiment and analysis of hypervapotron mock-ups for preparing the 2nd qualification of the ITER blanket first wall
|
Lee, Dong Won
|
|
2010
|
96-97 |
10-12 |
p. 2155-2159
5 p.
|
artikel
|
| 94 |
Fabrication of thick W coatings by atmospheric plasma spraying and their transient high heat loading performance
|
Zhou, Zhangjian
|
|
2010
|
96-97 |
10-12 |
p. 1720-1723
4 p.
|
artikel
|
| 95 |
Fabrication study on the cooling module of the ITER neutral beam duct liner
|
Sa, J.W.
|
|
2010
|
96-97 |
10-12 |
p. 2207-2212
6 p.
|
artikel
|
| 96 |
Failure Mode and Effect Analysis for remote handling transfer systems of ITER
|
Pinna, T.
|
|
2008
|
96-97 |
10-12 |
p. 1710-1714
5 p.
|
artikel
|
| 97 |
Failure mode and effect analysis for the European test blanket modules
|
Pinna, T.
|
|
2008
|
96-97 |
10-12 |
p. 1733-1737
5 p.
|
artikel
|
| 98 |
Features and initial results of the EAST divertor plasma experiments
|
Wang, Dongsheng
|
|
2010
|
96-97 |
10-12 |
p. 1777-1781
5 p.
|
artikel
|
| 99 |
Features and optimization approaches of the entrance section cooling gas flow of the IFMIF High Flux Test Module
|
Arbeiter, F.
|
|
2008
|
96-97 |
10-12 |
p. 1536-1542
7 p.
|
artikel
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Fiber erosion of carbon fiber composite exposed to simulated ITER-relevant thermal impact by high-intensity pulsed ion beam
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Zhu, X.P.
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2010
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96-97 |
10-12 |
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6 p.
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artikel
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Final design and manufacturing of the Cryolegs of the W7-X-superconducting coil support system
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Jenzsch, H.
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2008
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96-97 |
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p. 1600-1604
5 p.
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Fusion-related work at the OECD Nuclear Energy Agency
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Henriksson, H.
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2008
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96-97 |
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p. 1801-1806
6 p.
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artikel
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Global depletion analysis of Korean helium cooled solid breeder TBM model for demo fusion reactor
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Yun, Sunghwan
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2010
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96-97 |
10-12 |
p. 2222-2226
5 p.
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artikel
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Heat analysis on the initial reference design of ZrCo hydride beds for ITER
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Shim, M.
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2008
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96-97 |
10-12 |
p. 1433-1437
5 p.
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artikel
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Heat loads and shape design of the ITER first wall
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Mitteau, R.
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2010
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96-97 |
10-12 |
p. 2049-2053
5 p.
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artikel
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Heat transfer characteristics of the first wall with graphite sheet interlayer
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Masaki, Kei
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2010
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96-97 |
10-12 |
p. 1732-1735
4 p.
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artikel
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Heavy water purification from tritium by CECE process
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2008
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96-97 |
10-12 |
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4 p.
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artikel
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He-cooled divertor for DEMO: Status of development and HHF tests
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Norajitra, Prachai
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2010
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96-97 |
10-12 |
p. 2251-2256
6 p.
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artikel
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Helium-cooled test blanket module box behaviour under accidental pressurisation
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Girard, Christian
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2008
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96-97 |
10-12 |
p. 1738-1741
4 p.
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artikel
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HELOKA facility: Thermo-hydrodynamic model and control
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Ghidersa, B.E.
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2008
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96-97 |
10-12 |
p. 1792-1796
5 p.
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artikel
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Hydrogen isotope separation capability of low temperature mordenite column for gas chromatograph
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Kawamura, Yoshinori
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2008
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96-97 |
10-12 |
p. 1384-1387
4 p.
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artikel
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Hydrogen transport in molten salt Flinak measured by solid electrolyte sensors with Pd electrode
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Ohshima, T.
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2010
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96-97 |
10-12 |
p. 1841-1846
6 p.
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artikel
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IFMIF High Flux Test Module—Recent progress in design and manufacturing
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Leichtle, D.
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2008
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96-97 |
10-12 |
p. 1484-1489
6 p.
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artikel
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IFMIF target and test cell—Conceptual designs, boundary condition definitions and current status of preliminary engineering design
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Tian, Kuo
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2010
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96-97 |
10-12 |
p. 2282-2287
6 p.
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artikel
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Implementation of gas targets on the LIL facility
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Di Nicola, P.
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2008
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96-97 |
10-12 |
p. 1893-1895
3 p.
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artikel
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Improved characteristics of hydrophobic polytetrafluoroethylene–platinum catalysts for tritium recovery from tritiated water
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Popescu, I.
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2008
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96-97 |
10-12 |
p. 1392-1394
3 p.
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Integrated simulation of tritium permeation in solid breeder blankets
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Zhang, Hongjie
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2010
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96-97 |
10-12 |
p. 1711-1715
5 p.
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artikel
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Interpretation of LEVI velocity signals in 3D MHD flows
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Bühler, L.
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2008
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96-97 |
10-12 |
p. 1822-1827
6 p.
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artikel
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Investigation of cascade-type falling liquid-film along first wall of laser-fusion reactor
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Kunugi, T.
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2008
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96-97 |
10-12 |
p. 1888-1892
5 p.
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artikel
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Investigation of liquid-film formation along first wall of laser-fusion reactor
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Kawara, Z.
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2010
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96-97 |
10-12 |
p. 2181-2186
6 p.
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ITER plasma-facing components
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Merola, Mario
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2010
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96-97 |
10-12 |
p. 2312-2322
11 p.
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artikel
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ITER Transfer Cask System: Status of design, issues and future developments
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Gutiérrez, C. González
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2010
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96-97 |
10-12 |
p. 2295-2299
5 p.
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ITER waste management
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Rosanvallon, S.
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2010
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96-97 |
10-12 |
p. 1788-1791
4 p.
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artikel
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Laboratory studies conducted for the development of a plant to concentrate the radioactive waste from tritiated water
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Bornea, Anisia
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2010
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96-97 |
10-12 |
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5 p.
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artikel
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| 125 |
Lifetime performance analysis of HCPB power plant in-vessel components using HERCULES
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Karditsas, Panos J.
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2008
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96-97 |
10-12 |
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5 p.
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artikel
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Long term characterization of unidirectional fiberglass for ITER pre-compression rings
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Nardi, Claudio
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2010
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96-97 |
10-12 |
p. 2241-2244
4 p.
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artikel
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| 127 |
Magnetohydrodynamic experimental design and program for Chinese liquid metal LiPb experimental loop DRAGON-IV
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Chen, Hongli
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2010
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96-97 |
10-12 |
p. 1742-1746
5 p.
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artikel
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Manufacture and test of mock-up for ITER thermal shield
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Noh, C.H.
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2010
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96-97 |
10-12 |
p. 1880-1884
5 p.
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artikel
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Manufacturing and testing of reference samples for the definition of acceptance criteria for the ITER divertor
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Visca, Eliseo
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2010
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96-97 |
10-12 |
p. 1986-1991
6 p.
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| 130 |
Measurement and analysis of neutron flux spectra in a neutronics mock-up of the HCLL test blanket module
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Klix, A.
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2010
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96-97 |
10-12 |
p. 1803-1806
4 p.
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Measurement of free-surface velocity of liquid lithium flow for IFMIF
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Kanemura, T.
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2008
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96-97 |
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p. 1529-1535
7 p.
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Mechanical experiments about pendulum support of vacuum vessel W7-X
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Missal, B.
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2008
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96-97 |
10-12 |
p. 1610-1613
4 p.
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MHD and heat transfer considerations for the US DCLL blanket for DEMO and ITER TBM
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Smolentsev, Sergey
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2008
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96-97 |
10-12 |
p. 1788-1791
4 p.
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Microstructure and mechanical properties of the TIG welded joints of fusion CLAM steel
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Jiang, Zhizhong
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2010
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96-97 |
10-12 |
p. 1903-1908
6 p.
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artikel
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| 135 |
Microstructure investigation of bronze/steel brazed joints proposed for HHF components of ITER manufacturing
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Kalinin, G.M.
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2008
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96-97 |
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p. 1521-1523
3 p.
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Mock-up testing facilities and qualification strategy for EU ITER TBMs
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Aiello, A.
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2010
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96-97 |
10-12 |
p. 2012-2021
10 p.
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artikel
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| 137 |
Modeling and analysis of alternative concept of ITER vacuum vessel primary heat transfer system
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Carbajo, Juan
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2010
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96-97 |
10-12 |
p. 1852-1858
7 p.
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Modeling of influence of lithium vacancy on thermal conductivity in lithium aluminate
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Tsuchihira, H.
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2010
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p. 1814-1818
5 p.
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Multi-component behaviors of hydrogen isotopes adsorbed on synthetic zeolites 4A and 5A at 77.4K and 87.3K
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Kotoh, K.
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2010
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96-97 |
10-12 |
p. 1928-1934
7 p.
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artikel
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| 140 |
Multi-scattering time-of-flight neutron spectrometer for deuterium to tritium fuel ratio measurement in fusion experimental reactors
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Asai, K.
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2008
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96-97 |
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p. 1818-1821
4 p.
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Must we use ferritic steel in TBM?
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Salavy, J.-F.
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2010
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96-97 |
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p. 1896-1902
7 p.
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artikel
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Neutronic calculations of a thorium-based fusion–fission hybrid reactor blanket
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Ma, X.B.
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2010
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p. 2227-2231
5 p.
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Neutronics analysis of the conceptual design of a component test facility based on the spherical tokamak
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Zheng, S.
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2010
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96-97 |
10-12 |
p. 2300-2304
5 p.
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Neutronics analysis of the international thermonuclear experimental reactor (ITER) MCNP “Benchmark CAD Model” with the ATTILA discrete ordinance code
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Youssef, Mahmoud Z.
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2008
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96-97 |
10-12 |
p. 1661-1668
8 p.
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| 145 |
Neutronics analysis of water-cooled energy production blanket for a fusion–fission hybrid reactor
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Jiang, Jieqiong
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2010
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96-97 |
10-12 |
p. 2115-2119
5 p.
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| 146 |
Neutronics performance evaluation of fast-fission fuel breeding blankets for a fusion–fission hybrid reactor
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Wang, Minghuang
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2010
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96-97 |
10-12 |
p. 2120-2124
5 p.
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| 147 |
Nuclear responses in IFMIF creep-fatigue testing machine
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Vladimirov, P.
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2008
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96-97 |
10-12 |
p. 1548-1552
5 p.
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Numerical analysis of a cooling system for high heat flux components in the neutral beam injection system
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Tao, Ling
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2010
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96-97 |
10-12 |
p. 2095-2099
5 p.
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| 149 |
Numerical analysis of free surface instabilities in the IFMIF lithium target
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Gordeev, S.
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2008
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96-97 |
10-12 |
p. 1524-1528
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Numerical analysis of MHD duct flow with a flow channel insert
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Zhang, Xiujie
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2010
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96-97 |
10-12 |
p. 2090-2094
5 p.
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Numerical hydraulic analysis of the turbulent contraction nozzle flow for IFMIF target application
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Gordeev, S.
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2010
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96-97 |
10-12 |
p. 1859-1865
7 p.
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Numerical study of MHD pressure drop in rectangular ducts with insulating coatings
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Yang, Zhiyi
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2010
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96-97 |
10-12 |
p. 2059-2064
6 p.
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Optimization activities on design studies of LHD-type reactor FFHR
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Sagara, A.
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2008
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96-97 |
10-12 |
p. 1690-1695
6 p.
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Optimization at the design phase of the potential impact of ITER on workers, the public and the environment
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Cortes, Pierre
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2010
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96-97 |
10-12 |
p. 2263-2267
5 p.
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artikel
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Overview of Fusion Nuclear Technology Activities at SWIP
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Liu, Yong
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2010
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96-97 |
10-12 |
p. 2125-2131
7 p.
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Overview of Korea heat load test facilities for plasma facing components
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Kim, Suk-Kwon
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2010
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96-97 |
10-12 |
p. 1834-1837
4 p.
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Overview of recent nuclear analyses for the Upper ECH launcher in ITER
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Serikov, A.
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2010
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96-97 |
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p. 1885-1895
11 p.
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Overview of the TBM R&D activities in Japan
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Akiba, Masato
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2010
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96-97 |
10-12 |
p. 1766-1771
6 p.
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Oxidation behavior of SiC/SiC composites for helium cooled solid breeder blanket
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Nogami, S.
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2008
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96-97 |
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p. 1490-1494
5 p.
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Performance of the electrochemical hydrogen pump of a proton-conducting oxide for the tritium monitor
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Tanaka, M.
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2008
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96-97 |
10-12 |
p. 1414-1418
5 p.
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Plasma facing components of EAST
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Song, Y.T.
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2010
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96-97 |
10-12 |
p. 2323-2327
5 p.
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Preliminary evaluations of electromagnetic impacts between CN HCSB-TBM and ITER
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Chen, Yanjing
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2010
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96-97 |
10-12 |
p. 2150-2154
5 p.
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Preliminary neutronics analysis and maintenance approach for final optical devices of fast ignition ICF reactor FALCON-D
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Someya, Youji
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2008
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96-97 |
10-12 |
p. 1884-1887
4 p.
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Preliminary safety analysis of Korea Helium Cooled Solid Breeder Test Blanket Module
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Ahn, Mu-Young
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2008
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96-97 |
10-12 |
p. 1753-1758
6 p.
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Preliminary thermal design and related DEMO relevancy of the EU-HCPB TBM in vertical arrangement
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Cismondi, F.
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2010
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96-97 |
10-12 |
p. 2040-2044
5 p.
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Preparation of interfaces in ITER for integrating the Test Blanket Systems
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Giancarli, L.
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2010
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96-97 |
10-12 |
p. 1829-1833
5 p.
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Processing test of an upgraded mechanical design for PERMCAT reactor
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Borgognoni, Fabio
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2010
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p. 2171-2175
5 p.
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Production and testing of HENDL-2.1/CG coarse-group cross-section library based on ENDF/B-VII.0
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Xu, Dezheng
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2010
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p. 2105-2110
6 p.
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Progress in development of fabrication of small TBMs for EAST and ITER
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Huang, Qunying
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2010
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96-97 |
10-12 |
p. 2192-2195
4 p.
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Progress in neutronics for the ITER ECRH launcher
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Serikov, Arkady
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2008
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96-97 |
10-12 |
p. 1631-1637
7 p.
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Progress of detailed design and supporting analysis of ITER thermal shield
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Nam, K.
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2010
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96-97 |
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p. 1866-1874
9 p.
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Progress of IFERC project in the Broader Approach Activities
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Araki, M.
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2010
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p. 2196-2202
7 p.
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Progress of R&D and design of blanket remote handling equipment for ITER
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Kakudate, S.
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2008
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96-97 |
10-12 |
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Progress on solid breeder TBM at SWIP
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Feng, K.M.
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2010
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p. 2132-2140
9 p.
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Radiation deep penetration calculations for the IFMIF test cell wall
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Simakov, S.P.
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2010
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96-97 |
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p. 1924-1927
4 p.
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Radiation dose due to tritium release from the ITER neutral beam injector
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D’Arienzo, Marco
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2010
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96-97 |
10-12 |
p. 2288-2291
4 p.
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Recent progress in safety assessments of Japanese water-cooled solid breeder test blanket module
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Tsuru, Daigo
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2008
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96-97 |
10-12 |
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6 p.
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Recent progress of ITER vacuum vessel related design activities in Korea
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Kim, B.C.
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2008
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10-12 |
p. 1571-1577
7 p.
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Recent results of R&D activities on tritium technologies for ITER and fusion reactors at TPL of JAEA
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Yamanishi, T.
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2008
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96-97 |
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p. 1359-1363
5 p.
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Release behavior of hydrogen isotopes thermally absorbed in lithium niobate
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Azuma, Kisaburo
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2010
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5 p.
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Remote handling dynamical modelling: Assessment of a new approach to enhance positioning accuracy with heavy load manipulation
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2008
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Retention behavior of hydrogen isotopes in boron film deposited on SS-316 for LHD first wall
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Okuno, Kenji
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2010
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p. 2328-2330
3 p.
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Safe handling experience of a tritium storage bed
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Hayashi, T.
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4 p.
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Safety issues and approach to meet the safety requirements in the tokamak cooling water system of ITER
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Flanagan, George
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2010
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p. 1847-1851
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Safety of fusion magnets: Pressure impact on arcing in model experiments to high-current arcs propagating along the busbars of large fusion magnet coils
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Klimenko, Dmitry
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2010
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96-97 |
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p. 1875-1879
5 p.
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Sensitivity and uncertainty analyses of the HCLL mock-up experiment
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Leichtle, D.
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2010
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p. 1724-1727
4 p.
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Sensitivity of a specially designed calorimeter for absolute evaluation of tritium concentration in water
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Matsuyama, Masao
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2010
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p. 2045-2048
4 p.
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Setting up and managing a remote maintenance operation for fusion
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Haist, Bernhard
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2008
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96-97 |
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4 p.
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Short-term tests on unidirectional fiberglass for ITER pre-compression rings
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Nardi, Claudio
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2008
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96-97 |
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p. 1495-1497
3 p.
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Status and prospect of the JT-60SA project
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Ishida, S.
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10 p.
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Status of ITER procurement activities in Korea
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Jung, K.J.
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2010
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96-97 |
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p. 2217-2221
5 p.
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Status of novel tools for estimation of activation dose
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Pampin, R.
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2010
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96-97 |
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6 p.
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Structuring of tungsten by pulsed ECM processes for He-cooled divertor application
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Holstein, N.
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2008
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Study on pump combinations for improving delivery rates of hydrogen
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Chang, Min Ho
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2010
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96-97 |
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p. 2022-2026
5 p.
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Study on the technology of CECE–GC system for water detritiation
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Ying, Sun
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2008
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p. 1400-1404
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Synthesis and characterization of proton conductive CaZr0.90In0.10O3−δ by a citric acid complexation method
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Han, Jinduo
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2010
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p. 2100-2104
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System requirements and design challenges of the gas injection system of ITER
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Yang, Y.
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2010
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p. 2292-2294
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TBM Program implementation in ITER
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Chuyanov, V.A.
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2010
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Technical issues of reduced activation ferritic/martensitic steels for fabrication of ITER test blanket modules
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Tanigawa, H.
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2008
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Test blanket module maintenance operations between port plug and ancillary equipment unit in ITER
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2008
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96-97 |
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5 p.
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artikel
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The conceptual alternative design for ITER magnet gravity support using clamp bolt
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Hou, B.L.
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2010
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96-97 |
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5 p.
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artikel
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The coolant purification system of the European test blanket modules: Preliminary design
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Ciampichetti, A.
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2010
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96-97 |
10-12 |
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7 p.
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artikel
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The design decisions of breeding zone sub-module for testing in ITER in order to validate the CHC TBM concept
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Leshukov, A.Yu.
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2010
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96-97 |
10-12 |
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7 p.
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artikel
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The development of standard operating procedures for the SDS of the ITER tritium plant
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Song, Kyu-Min
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2008
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96-97 |
10-12 |
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4 p.
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artikel
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The effect of isotope on the interaction between hydrogen and irradiation defect in pure iron
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Huang, Yina
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2010
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96-97 |
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4 p.
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artikel
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| 206 |
The effects of helium on the embrittlement and hardening of boron doped EUROFER97 steels
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Gaganidze, E.
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2008
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96-97 |
10-12 |
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5 p.
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artikel
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The heat flux pattern on HT-7 lower toroidal limiter
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Chen, H.
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2010
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96-97 |
10-12 |
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4 p.
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artikel
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The ITER TF coil ripple: Evaluation of ripple attenuation using Fe insert and of ripple enhancement produced by TBM
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Portone, A.
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2008
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96-97 |
10-12 |
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Theoretical calculation and analysis modeling for the effective thermal conductivity of Li4SiO4 pebble bed
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Zhao, Zhou
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2010
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96-97 |
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6 p.
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artikel
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Thermal conductivity and thermal expansion coefficient of diamond/5wt%Si–Cu composite by vacuum hot pressing
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Shen, Weiping
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2010
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96-97 |
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4 p.
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artikel
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Thermal-hydraulics design and analysis on a helium-cooled high power density blanket for a fusion–fission hybrid reactor
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Jin, Ming
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2010
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96-97 |
10-12 |
p. 2232-2236
5 p.
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artikel
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Thermal hydraulic test with 6MPa nitrogen gas loop for developing the Korean He cooled test blanket
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Lee, Dong Won
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2010
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96-97 |
10-12 |
p. 2160-2164
5 p.
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artikel
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Three-dimensional nuclear analysis of the final optics of a laser driven fusion power plant
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2008
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96-97 |
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artikel
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Tritium breeder blankets design and technologies in Europe: Development status of ITER Test Blanket Modules, test & qualification strategy and roadmap towards DEMO
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Poitevin, Y.
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2010
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96-97 |
10-12 |
p. 2340-2347
8 p.
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Tritium processing systems for the helium cooled pebble bed test blanket module
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Ricapito, I.
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2008
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96-97 |
10-12 |
p. 1461-1465
5 p.
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Tritium safety consideration in the design of tritium systems for China HCSB and DFLL TBMs
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Chen, C.A.
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2008
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96-97 |
10-12 |
p. 1455-1460
6 p.
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artikel
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Tritium sorption and desorption from JET beryllium tiles under temperature, electron radiation and magnetic field
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Tīliks, Juris
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2008
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96-97 |
10-12 |
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4 p.
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Use of McCad for the conversion of ITER CAD data to MCNP geometry
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2008
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96-97 |
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3 p.
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artikel
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Validation of shutdown dose rate Monte Carlo calculations through a benchmark experiment at JET
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Villari, R.
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2008
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96-97 |
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Verification of a dust transport model against theoretical solutions in multidimensional advection diffusion problems
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2010
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96-97 |
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6 p.
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artikel
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| 221 |
Verification of hydrogen isotope separation/enrichment by pressure swing adsorption process: Successive enrichment of deuterium using SZ-5A column
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Kotoh, K.
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2010
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96-97 |
10-12 |
p. 1992-1998
7 p.
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| 222 |
Verification of KERMA factor for beryllium at neutron energy of 14.2MeV based on charged-particle measurement
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Kondo, Keitaro
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p. 1674-1677
4 p.
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artikel
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| 223 |
Vibration control of an IVVS long-reach deployer using unknown visual features from inside the ITER vessel
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Dubus, G.
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2010
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96-97 |
10-12 |
p. 2027-2032
6 p.
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artikel
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| 224 |
16-8-2 weld metal design data for 316L(N) steel
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Tavassoli, A.-A.F.
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2008
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p. 1467-1470
4 p.
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