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                             109 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 An inverse method based on finite element model to derive the plastic flow properties from non-standard tensile specimens of Eurofer97 steel Knitel, S.
2016
9 C p. 311-316
6 p.
artikel
2 Annealing effects on deuterium retention behavior in damaged tungsten Sakurada, S.
2016
9 C p. 141-144
4 p.
artikel
3 ANSYS Creep-Fatigue Assessment tool for EUROFER97 components Mahler, M.
2016
9 C p. 535-538
4 p.
artikel
4 Application of optical reflectivity measurements to diagnostics for plasma facing materials Miyamoto, M.
2016
9 C p. 132-136
5 p.
artikel
5 Arc erosion of full metal plasma facing components at the inner baffle region of ASDEX Upgrade Rohde, V.
2016
9 C p. 36-39
4 p.
artikel
6 Atomistic simulations of deuterium irradiation on iron-based alloys in future fusion reactors Safi, E.
2016
9 C p. 571-575
5 p.
artikel
7 Behavior and microstructural changes in different tungsten-based materials under pulsed plasma loading Vilémová, M.
2016
9 C p. 123-127
5 p.
artikel
8 Behavior of a self-interstitial-atom type dislocation loop in the periphery of an edge dislocation in BCC-Fe Hayakawa, Sho
2016
9 C p. 592-597
6 p.
artikel
9 Behavior of tungsten fiber-reinforced tungsten based on single fiber push-out study Jasper, B.
2016
9 C p. 416-421
6 p.
artikel
10 Behavior of W-based materials in hot helium gas Matějíček, J.
2016
9 C p. 405-410
6 p.
artikel
11 Brazing of Be with CuCrZr-bronze using copper-based filler metal STEMET Kalin, B.A.
2016
9 C p. 388-393
6 p.
artikel
12 Characteristic of a pdCu membrane as atomic hydrogen probe for QUEST Onaka, Masayuki
2016
9 C p. 104-108
5 p.
artikel
13 Chemically deposited tungsten fibre-reinforced tungsten – The way to a mock-up for divertor applications Riesch, J.
2016
9 C p. 75-83
9 p.
artikel
14 CO2 absorption characteristics of a blanket candidate material Li2TiO3 under exposure to different gas mixture Furuyama, Yuichi
2016
9 C p. 227-232
6 p.
artikel
15 Comparative small angle neutron scattering (SANS) study of Eurofer97 steel neutron irradiated in mixed (HFR) and fast spectra (BOR60) reactors Coppola, R.
2016
9 C p. 189-193
5 p.
artikel
16 Comparison of passivation behavior of SS316L with that of SS304 in tritiated water solution Oyaidzu, M.
2016
9 C p. 508-511
4 p.
artikel
17 Corrosion resistance of Al-based coatings in flowing Pb–15.7Li produced by aluminum electrodeposition from ionic liquids Wulf, Sven-Erik
2016
9 C p. 519-523
5 p.
artikel
18 Cracking behavior of tungsten armor under ELM-like thermal shockloads II: A revised prediction for crack appearance map Li, Muyuan
2016
9 C p. 598-603
6 p.
artikel
19 Crystallization and deuterium permeation behaviors of yttrium oxide coating prepared by metal organic decomposition Chikada, Takumi
2016
9 C p. 529-534
6 p.
artikel
20 Damage production in atomic displacement cascades in beryllium Borodin, V.A.
2016
9 C p. 216-220
5 p.
artikel
21 Damaging of tungsten and tungsten–tantalum alloy exposed in ITER ELM-like conditions Makhlai, V.A.
2016
9 C p. 116-122
7 p.
artikel
22 Defects annihilation behavior of neutron-irradiated SiC ceramics densified by liquid-phase-assisted method after post-irradiation annealing Idris, Mohd Idzat
2016
9 C p. 199-206
8 p.
artikel
23 Design description and validation results for the IFMIF High Flux Test Module as outcome of the EVEDA phase Arbeiter, F.
2016
9 C p. 59-65
7 p.
artikel
24 Detection of deuterium trapping sites in tungsten by thermal desorption spectroscopy and positron annihilation spectroscopy Sato, K.
2016
9 C p. 554-559
6 p.
artikel
25 Deuterium retention in tungsten under combined high cycle ELM-like heat loads and steady-state plasma exposure Huber, A.
2016
9 C p. 157-164
8 p.
artikel
26 Deuterium retention in W and W-Re alloy irradiated with high energy Fe and W ions: Effects of irradiation temperature Hatano, Y.
2016
9 C p. 93-97
5 p.
artikel
27 Development of a dispersion strengthened copper alloy using a MA-HIP method Yamada, T.
2016
9 C p. 455-458
4 p.
artikel
28 Development of high strength W/V/Au/ODS-Cu joint using HIP process Noto, Hiroyuki
2016
9 C p. 411-415
5 p.
artikel
29 Development of hydrophobic platinum catalyst for oxidation of tritium in JAEA Iwai, Yasunori
2016
9 C p. 267-272
6 p.
artikel
30 Development of quantitative analysis method for tritium using by hydrophobic platinum catalyst Edao, Yuki
2016
9 C p. 273-277
5 p.
artikel
31 Development of yttrium-containing self-passivating tungsten alloys for future fusion power plants Wegener, T.
2016
9 C p. 394-398
5 p.
artikel
32 Dissolution behavior of lithium compounds in ethanol Furukawa, Tomohiro
2016
9 C p. 286-291
6 p.
artikel
33 Dose dependence of irradiation hardening of neutron irradiated vanadium alloys by using temperature control rig in JMTR Fukumoto, Ken-ichi
2016
9 C p. 441-446
6 p.
artikel
34 Editorial Board 2016
9 C p. 624-
1 p.
artikel
35 Editorial for Proceedings of ICFRM-17 Edmondson, Philip D
2016
9 C p. 40-
1 p.
artikel
36 Effect of Cr/Al contents on the 475ºC age-hardening in oxide dispersion strengthened ferritic steels Han, Wentuo
2016
9 C p. 610-615
6 p.
artikel
37 Effect of design geometry of the demo first wall on the plasma heat load Igitkhanov, Yu.
2016
9 C p. 560-564
5 p.
artikel
38 Effect of dissolved gas on mechanical property of sheath material of mineral insulated cables under high temperature and pressure water Takeuchi, T.
2016
9 C p. 451-454
4 p.
artikel
39 Effect of impurity deposition layer formation on D retention in LHD plasma exposed W Oya, Y.
2016
9 C p. 84-88
5 p.
artikel
40 Effect of neutron irradiation on the microstructure of tungsten Klimenkov, M.
2016
9 C p. 480-483
4 p.
artikel
41 Effect of post-weld heat treatment on microstructure, hardness and low-temperature impact toughness of electron beam welds of NIFS-HEAT-2 and CEA-J57 heats of V–4Ti–4Cr alloy Tsisar, V.
2016
9 C p. 436-440
5 p.
artikel
42 Effect of second-phase particles on the properties of W-based materials under high-heat loading Tan, Xiao–Yue
2016
9 C p. 399-404
6 p.
artikel
43 Effect of self-ion irradiation on hardening and microstructure of tungsten Hwang, T.
2016
9 C p. 430-435
6 p.
artikel
44 Effect of thermo-mechanical treatments on nano-structure of 9Cr-ODS steel Oka, Hiroshi
2016
9 C p. 346-352
7 p.
artikel
45 Effects of stacking fault energies on the interaction between an edge dislocation and an 8.0-nm-diameter Frank loop of self-interstitial atoms Hayakawa, S.
2016
9 C p. 581-586
6 p.
artikel
46 Engineering validation for lithium target facility of the IFMIF under IFMIF/EVEDA project Wakai, E.
2016
9 C p. 278-285
8 p.
artikel
47 Er2O3 coating by reactive magnetron sputtering: Effect of oxygen supply and erbium pre-layer deposition Rayjada, P.A.
2016
9 C p. 256-260
5 p.
artikel
48 Erosion corrosion of CuCrZr specimens exposed for simulated ITER operational conditions Obitz, C.
2016
9 C p. 261-266
6 p.
artikel
49 European DEMO divertor target: Operational requirements and material-design interface You, J.H.
2016
9 C p. 171-176
6 p.
artikel
50 Evaluation of helium effect on ion-irradiation hardening in pure tungsten by nano-indentation method Zhang, Zhexian
2016
9 C p. 539-546
8 p.
artikel
51 Evaluation of the cool-down behaviour of ITER FW beryllium tiles for an early failure detection Weber, Thomas
2016
9 C p. 109-115
7 p.
artikel
52 Experimental investigation of high He/dpa microstructural effects in neutron irradiated B-alloyed Eurofer97 steel by means of small angle neutron scattering (SANS) and electron microscopy Coppola, R.
2016
9 C p. 194-198
5 p.
artikel
53 Fabrication and characterization of advanced neutron multipliers for DEMO blanket Nakamichi, Masaru
2016
9 C p. 55-58
4 p.
artikel
54 Fe+ ion irradiation induced changes in structural and magnetic properties of iron films Papamihail, K.
2016
9 C p. 459-464
6 p.
artikel
55 Grain boundary sliding associated with low strain rate at 1000°C in recrystallized ODS ferritic steel Kamikawa, R.
2016
9 C p. 338-341
4 p.
artikel
56 High heat flux testing of first wall mock-ups with and without neutron irradiation Pintsuk, G.
2016
9 C p. 41-45
5 p.
artikel
57 Hydrogen retention behavior of beryllides as advanced neutron multipliers Fujii, Y.
2016
9 C p. 233-236
4 p.
artikel
58 IFMIF, the European–Japanese efforts under the Broader Approach agreement towards a Li(d,xn) neutron source: Current status and future options Knaster, J.
2016
9 C p. 46-54
9 p.
artikel
59 Improved ERO modelling for spectroscopy of physically and chemically assisted eroded beryllium from the JET-ILW Borodin, D.
2016
9 C p. 604-609
6 p.
artikel
60 Improved fracture behavior and microstructural characterization of thin tungsten foils Nikolic, Vladica
2016
9 C p. 181-188
8 p.
artikel
61 Influence of an external magnetic field on damage by self-ion irradiation in Fe90Cr10 alloy Sánchez, Fernando José
2016
9 C p. 476-479
4 p.
artikel
62 Influence of friction stir welding conditions on joinability of oxide dispersion strengthened steel / F82H ferritic/martensitic steel joint Serizawa, Hisashi
2016
9 C p. 367-371
5 p.
artikel
63 Influence of helium induced nanostructures on the thermal shock performance of tungsten Wirtz, M.
2016
9 C p. 177-180
4 p.
artikel
64 Influence of stacking fault energies on the size distribution and character of defect clusters formed by collision cascades in face-centered cubic metals Yang, Y.
2016
9 C p. 587-591
5 p.
artikel
65 Influence of the C content on the permeation of hydrogen in Fe alloys with low contents of C Peñalva, I.
2016
9 C p. 306-310
5 p.
artikel
66 Instrumented indentation at elevated temperatures for determination of material properties of fusion relevant materials Bredl, Julian
2016
9 C p. 502-507
6 p.
artikel
67 Investigation of damages induced by ITER-relevant heat loads during massive gas injections on Beryllium Spilker, B.
2016
9 C p. 145-152
8 p.
artikel
68 Irradiation performance of rare earth and nanoparticle enhanced high temperature superconducting films based on YBCO Leonard, K.J.
2016
9 C p. 251-255
5 p.
artikel
69 Laser re-melting of tungsten damaged by transient heat loads Loewenhoff, Th.
2016
9 C p. 165-170
6 p.
artikel
70 Liquid surfaces for fusion plasma facing components—A critical review. Part I: Physics and PSI Nygren, R.E.
2016
9 C p. 6-21
16 p.
artikel
71 Long-term corrosion behavior of ODS-Eurofer in flowing Pb-15.7Li at 550°C Krauss, W.
2016
9 C p. 512-518
7 p.
artikel
72 Low-temperature embrittlement and fracture of metals with different crystal lattices – Dislocation mechanisms Chernov, V.M.
2016
9 C p. 496-501
6 p.
artikel
73 Manufacturing and testing of self-passivating tungsten alloys of different composition Calvo, A.
2016
9 C p. 422-429
8 p.
artikel
74 Mechanics of binary crushable granular assembly through discrete element method Desu, Raghuram Karthik
2016
9 C p. 237-241
5 p.
artikel
75 Melt-layer formation on PFMs and the consequences for the material performance Steudel, I.
2016
9 C p. 153-156
4 p.
artikel
76 Microstructural changes of Y-doped V-4Cr-4Ti alloys after ion and neutron irradiation Watanabe, H.
2016
9 C p. 447-450
4 p.
artikel
77 Microstructural defects in EUROFER 97 after different neutron irradiation conditions Dethloff, Christian
2016
9 C p. 471-475
5 p.
artikel
78 Microstructural stability of ODS Fe–14Cr (–2W–0.3Ti) steels after simultaneous triple irradiation Šćepanović, M.
2016
9 C p. 490-495
6 p.
artikel
79 Microstructure and mechanical property in heat affected zone (HAZ) in F82H jointed with SUS316L by fiber laser welding Kano, S.
2016
9 C p. 300-305
6 p.
artikel
80 Microstructure and tensile properties of ODS ferritic steels mechanically alloyed with Fe2Y Macías-Delgado, J.
2016
9 C p. 372-377
6 p.
artikel
81 Multiscale modelling of hydrogen behaviour on beryllium (0001) surface Stihl, Ch.
2016
9 C p. 547-553
7 p.
artikel
82 Nanostructure evolution in ODS steels under ion irradiation Rogozhkin, S.
2016
9 C p. 66-74
9 p.
artikel
83 ODS-materials for high temperature applications in advanced nuclear systems Eiselt, C.C.
2016
9 C p. 22-28
7 p.
artikel
84 Optimization of mechanical alloying and spark-plasma sintering regimes to obtain ferrite–martensitic ODS steel Staltsov, M.S.
2016
9 C p. 360-366
7 p.
artikel
85 Overview on the welding technologies of CLAM steel and the DFLL TBM fabrication Zhang, Junyu
2016
9 C p. 317-323
7 p.
artikel
86 Oxide particle coarsening at temperature over 1473K in 9CrODS steel Oono, N.
2016
9 C p. 342-345
4 p.
artikel
87 Oxide particle–dislocation interaction in 9Cr-ODS steel Ijiri, Yuta
2016
9 C p. 378-382
5 p.
artikel
88 Pebble fabrication of super advanced tritium breeders using a solid solution of Li2+ x TiO3+ y with Li2ZrO3 Hoshino, Tsuyoshi
2016
9 C p. 221-226
6 p.
artikel
89 Pebble structure change of Li2TiO3 with excess Li in water vapor atmosphere at elevated temperatures Katayama, K.
2016
9 C p. 242-246
5 p.
artikel
90 Physisorption of ammonia on AISI 304L stainless steel at different surface temperature under high vacuum conditions de Castro, A.
2016
9 C p. 1-5
5 p.
artikel
91 PKA distributions: Contributions from transmutation products and from radioactive decay Gilbert, M.R.
2016
9 C p. 576-580
5 p.
artikel
92 Plasma etching to enhance the surface insulating stability of alumina for fusion applications Malo, M.
2016
9 C p. 247-250
4 p.
artikel
93 Post mortem analysis of a tungsten coated tile from the outer divertor strike point region of ASDEX upgrade Fortuna-Zalesna, E.
2016
9 C p. 128-131
4 p.
artikel
94 Precipitation of carbides in F82H steels and its impact on mechanical strength Kano, S.
2016
9 C p. 331-337
7 p.
artikel
95 Retention in tungsten resulting from extremely high fluence plasma exposure Doerner, R.P.
2016
9 C p. 89-92
4 p.
artikel
96 Simulation of Be armour cracking under ITER-like transient heat loads Pestchanyi, S.
2016
9 C p. 98-103
6 p.
artikel
97 Simulation of nanostructural evolution under irradiation in Fe-9%CrC alloys: An object kinetic Monte Carlo study of the effect of temperature and dose-rate Chiapetto, M.
2016
9 C p. 565-570
6 p.
artikel
98 Simulation of neutron irradiation damage in tungsten using higher energy protons Rayaprolu, R.
2016
9 C p. 29-35
7 p.
artikel
99 Strength anisotropy of rolled 11Cr-ODS steel Tanno, Takashi
2016
9 C p. 353-359
7 p.
artikel
100 Study of the wettability of fusion relevant steels by the sodium potassium eutectic alloy NaK-78 Abou-Sena, Ali
2016
9 C p. 292-299
8 p.
artikel
101 TEM analysis of recrystallized double forged tungsten after exposure in JUDITH 1 and JUDITH 2 Van Renterghem, W.
2016
9 C p. 484-489
6 p.
artikel
102 Tensile properties and hardness of two types of 11Cr-ferritic/martensitic steel after aging up to 45,000 h Yano, Y.
2016
9 C p. 324-330
7 p.
artikel
103 The influence of carbon on the resistivity recovery of proton irradiated Fe–11at.% Cr alloys Apostolopoulos, G.
2016
9 C p. 465-470
6 p.
artikel
104 17th International Conference on Fusion Reactor Materials 2016
9 C p. 623-
1 p.
artikel
105 Trapping and thermal diffusion for energetic deuterium implanted into SiC Sánchez, F.J.
2016
9 C p. 383-387
5 p.
artikel
106 Tritium and helium release from beryllium pebbles neutron-irradiated up to 230appm tritium and 3000appm helium Chakin, Vladimir
2016
9 C p. 207-215
9 p.
artikel
107 Tritium permeation behavior through pyrolytic carbon in tritium production using high-temperature gas-cooled reactor for fusion reactors Ushida, H.
2016
9 C p. 524-528
5 p.
artikel
108 Tungsten coatings for application in WEST project Grigore, E.
2016
9 C p. 137-140
4 p.
artikel
109 Use of tungsten material for the ITER divertor Hirai, T.
2016
9 C p. 616-622
7 p.
artikel
                             109 gevonden resultaten
 
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