| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Ablation of hydrogen-implanted graphite target using pulsed laser beam
|
Sakawa, Youichi
|
|
2006
|
|
1-7 |
p. 381-386
6 p.
|
artikel
|
| 2 |
Acceptance criteria for the ITER divertor vertical target
|
Fouquet, S.
|
|
2006
|
|
1-7 |
p. 265-268
4 p.
|
artikel
|
| 3 |
A design study for tritium recovery system from cooling water of a fusion power plant
|
Yamanishi, Toshihiko
|
|
2006
|
|
1-7 |
p. 797-802
6 p.
|
artikel
|
| 4 |
Aging effects in uranium tritide
|
Li, Rong
|
|
2006
|
|
1-7 |
p. 859-862
4 p.
|
artikel
|
| 5 |
Analyses of metallic first mirror samples after long term plasma exposure in Tore Supra
|
Lipa, M.
|
|
2006
|
|
1-7 |
p. 221-225
5 p.
|
artikel
|
| 6 |
Analysis on fuel cycle schemes in the dual-cooled waste transmutation blanket for the FDS-I
|
Zhu, X.
|
|
2006
|
|
1-7 |
p. 851-857
7 p.
|
artikel
|
| 7 |
A neutronic feasibility study on Be-free He-cooled solid breeder blanket
|
Han, Beomseok
|
|
2006
|
|
1-7 |
p. 725-728
4 p.
|
artikel
|
| 8 |
An overview of dual coolant Pb–17Li breeder first wall and blanket concept development for the US ITER-TBM design
|
Wong, C.P.C.
|
|
2006
|
|
1-7 |
p. 461-467
7 p.
|
artikel
|
| 9 |
An overview of US ITER test blanket module program
|
Ying, A.
|
|
2006
|
|
1-7 |
p. 433-441
9 p.
|
artikel
|
| 10 |
Applicability of β-ray-induced X-ray spectrometry to in situ measurements of tritium retention in plasma-facing materials in ITER
|
Matsuyama, M.
|
|
2006
|
|
1-7 |
p. 163-168
6 p.
|
artikel
|
| 11 |
Author Index of Volume 81, Issues 1–7
|
|
|
2006
|
|
1-7 |
p. e1-e10
nvt p.
|
artikel
|
| 12 |
Behavior of actively cooled mock-ups with plasma sprayed tungsten coating under high heat flux conditions
|
Tokunaga, K.
|
|
2006
|
|
1-7 |
p. 133-138
6 p.
|
artikel
|
| 13 |
Breeder foam: an innovative low porosity solid breeder material
|
Sharafat, S.
|
|
2006
|
|
1-7 |
p. 455-460
6 p.
|
artikel
|
| 14 |
Breeding blanket design and systems integration for a helium-cooled lithium–lead fusion power plant
|
Li Puma, A.
|
|
2006
|
|
1-7 |
p. 469-476
8 p.
|
artikel
|
| 15 |
Breeding Blanket Modules testing in ITER: An international program on the way to DEMO
|
Giancarli, L.
|
|
2006
|
|
1-7 |
p. 393-405
13 p.
|
artikel
|
| 16 |
Carbon impurity behavior on plasma facing surface of tungsten
|
Ueda, Y.
|
|
2006
|
|
1-7 |
p. 233-239
7 p.
|
artikel
|
| 17 |
Characterization of JT-60U exhaust gas during experimental operation
|
Isobe, K.
|
|
2006
|
|
1-7 |
p. 827-832
6 p.
|
artikel
|
| 18 |
Chemical behavior of energetic deuterium implanted into tungsten carbide
|
Kimura, H.
|
|
2006
|
|
1-7 |
p. 295-299
5 p.
|
artikel
|
| 19 |
Control of nitrogen concentration in liquid lithium by iron–titanium alloy
|
Hirakane, Shinji
|
|
2006
|
|
1-7 |
p. 665-670
6 p.
|
artikel
|
| 20 |
Control of tritium in FFHR-2 self-cooled Flibe blanket
|
Fukada, Satoshi
|
|
2006
|
|
1-7 |
p. 477-483
7 p.
|
artikel
|
| 21 |
Correlation between annihilation of irradiation defects and tritium release in neutron-irradiated lithium zirconate
|
Oyaidzu, M.
|
|
2006
|
|
1-7 |
p. 583-588
6 p.
|
artikel
|
| 22 |
Critical heat flux loading experiments on CVD-W coating in the TEXTOR tokamak
|
Hirai, T.
|
|
2006
|
|
1-7 |
p. 175-180
6 p.
|
artikel
|
| 23 |
Design and development of EC H&CD antenna mirrors for ITER
|
Takahashi, K.
|
|
2006
|
|
1-7 |
p. 281-287
7 p.
|
artikel
|
| 24 |
Design approach for the main ITER test blanket modules for the EU helium cooled lithium–lead blankets
|
Rampal, G.
|
|
2006
|
|
1-7 |
p. 695-700
6 p.
|
artikel
|
| 25 |
Design of auxiliary system for the dual functional lithium–lead test blanket module in ITER
|
Zhang, Maolian
|
|
2006
|
|
1-7 |
p. 671-675
5 p.
|
artikel
|
| 26 |
Determination of hydrogen solubility in lead lithium using sole device
|
Aiello, A.
|
|
2006
|
|
1-7 |
p. 639-644
6 p.
|
artikel
|
| 27 |
Deuterium retention and desorption behavior of boron–titanium as first wall material of fusion experimental device
|
Hino, T.
|
|
2006
|
|
1-7 |
p. 127-131
5 p.
|
artikel
|
| 28 |
Deuterium retention of low activation ferritic steel and boronized wall in JFT-2M
|
Yamauchi, Y.
|
|
2006
|
|
1-7 |
p. 315-319
5 p.
|
artikel
|
| 29 |
Development of a tritium separation process using SDGC
|
Morimoto, Y.
|
|
2006
|
|
1-7 |
p. 821-826
6 p.
|
artikel
|
| 30 |
Development of tritium production measurement method for in-pile tests of fusion blanket in the JMTR
|
Nagao, Y.
|
|
2006
|
|
1-7 |
p. 619-623
5 p.
|
artikel
|
| 31 |
Direct numerical simulation of MHD flow with electrically conducting wall
|
Satake, S.
|
|
2006
|
|
1-7 |
p. 367-374
8 p.
|
artikel
|
| 32 |
Distinctive radiation durability of an ion exchange membrane in the SPE water electrolyzer for the ITER water detritiation system
|
Iwai, Yasunori
|
|
2006
|
|
1-7 |
p. 815-820
6 p.
|
artikel
|
| 33 |
Dynamic amplification of reaction forces in the blanket module attachment during plasma disruption of ITER
|
Khomyakov, S.
|
|
2006
|
|
1-7 |
p. 485-490
6 p.
|
artikel
|
| 34 |
Dynamic erosion and deposition on carbon and tungsten due to simultaneous bombardment with deuterium and beryllium ions in plasmas
|
Ebisu, Shinji
|
|
2006
|
|
1-7 |
p. 253-258
6 p.
|
artikel
|
| 35 |
Effect of low energy helium irradiation on mechanical properties of 304 stainless steel
|
Kawakami, T.
|
|
2006
|
|
1-7 |
p. 335-340
6 p.
|
artikel
|
| 36 |
Erosion of carbon deposition layer by hydrogen RF plasma
|
Katayama, K.
|
|
2006
|
|
1-7 |
p. 247-252
6 p.
|
artikel
|
| 37 |
EU activities in preparation of the procurement of the ITER divertor
|
Merola, M.
|
|
2006
|
|
1-7 |
p. 105-112
8 p.
|
artikel
|
| 38 |
EU R&D on the ITER First Wall
|
Lorenzetto, P.
|
|
2006
|
|
1-7 |
p. 355-360
6 p.
|
artikel
|
| 39 |
Experimental and numerical analysis on pebble beds used in an ITER Test Module Blanket
|
Aquaro, Donato
|
|
2006
|
|
1-7 |
p. 707-712
6 p.
|
artikel
|
| 40 |
Experimental examination of heat removal limitation of screw cooling tube at high pressure and temperature conditions
|
Ezato, Koichiro
|
|
2006
|
|
1-7 |
p. 347-354
8 p.
|
artikel
|
| 41 |
Experimental study of lithium free-surface flow for IFMIF target design
|
Kondo, H.
|
|
2006
|
|
1-7 |
p. 687-693
7 p.
|
artikel
|
| 42 |
Experimental study of the interaction of ceramic breeder pebble beds with structural materials under thermo-mechanical loads
|
Calderoni, P.
|
|
2006
|
|
1-7 |
p. 607-612
6 p.
|
artikel
|
| 43 |
Experimental study of tritium recovery from liquid lithium by yttrium
|
Kinoshita, Mika
|
|
2006
|
|
1-7 |
p. 567-571
5 p.
|
artikel
|
| 44 |
Experiments on deuterium trapping in helium-irradiated copper
|
Takagi, I.
|
|
2006
|
|
1-7 |
p. 785-789
5 p.
|
artikel
|
| 45 |
Feasibility study on the blanket tritium recovery system using the palladium membrane diffuser
|
Kawamura, Yoshinori
|
|
2006
|
|
1-7 |
p. 809-814
6 p.
|
artikel
|
| 46 |
First wall and divertor engineering research for power plant in JAERI
|
Suzuki, S.
|
|
2006
|
|
1-7 |
p. 93-103
11 p.
|
artikel
|
| 47 |
He-cooled divertor for DEMO: Experimental verification of the conceptual modular design
|
Norajitra, P.
|
|
2006
|
|
1-7 |
p. 341-346
6 p.
|
artikel
|
| 48 |
Helium irradiation effects for deuterium retention in boron coating films
|
Takeda, T.
|
|
2006
|
|
1-7 |
p. 301-306
6 p.
|
artikel
|
| 49 |
Helium thermal desorption and retention properties of V–4Cr–4Ti alloy used for first wall of breeding blanket
|
Hirohata, Yuko
|
|
2006
|
|
1-7 |
p. 193-198
6 p.
|
artikel
|
| 50 |
High flux ion beam acceleration at the 100-eV level for fusion plasma facing material studies
|
Yoshida, H.
|
|
2006
|
|
1-7 |
p. 361-366
6 p.
|
artikel
|
| 51 |
Hydrogen inventories in the vacuum pumping systems of ITER
|
Day, Christian
|
|
2006
|
|
1-7 |
p. 777-784
8 p.
|
artikel
|
| 52 |
Hydrogen permeability and erosion behavior of W–Pd bimetallic systems
|
Glazunov, G.P.
|
|
2006
|
|
1-7 |
p. 375-380
6 p.
|
artikel
|
| 53 |
Hydrogen retention and depth profile in divertor tiles of Jt-60 exposed to hydrogen discharges
|
Yoshikawa, A.
|
|
2006
|
|
1-7 |
p. 289-294
6 p.
|
artikel
|
| 54 |
Improvement of the CFC structure to withstand high heat flux
|
Pestchanyi, S.
|
|
2006
|
|
1-7 |
p. 275-279
5 p.
|
artikel
|
| 55 |
Influence of oxygen and carbon on performance of superpermeable membranes
|
Hatano, Y.
|
|
2006
|
|
1-7 |
p. 771-776
6 p.
|
artikel
|
| 56 |
Integration of an advanced He-cooled divertor in a DEMO-relevant tokamak geometry
|
Ihli, T.
|
|
2006
|
|
1-7 |
p. 121-126
6 p.
|
artikel
|
| 57 |
Integration of the EU HCPB Test Blanket Module system in ITER
|
Neuberger, H.
|
|
2006
|
|
1-7 |
p. 499-503
5 p.
|
artikel
|
| 58 |
Interactions between molten Flibe and metallic Be
|
Hara, M.
|
|
2006
|
|
1-7 |
p. 561-566
6 p.
|
artikel
|
| 59 |
Introduction of tritium transfer step at surface layer of breeder grain for modeling of tritium release behavior from solid breeder materials
|
Kinjyo, T.
|
|
2006
|
|
1-7 |
p. 573-577
5 p.
|
artikel
|
| 60 |
Investigation of hydrogen isotope permeation through F82H steel with and without a ceramic coating of Cr2O3–SiO2 including CrPO4 (out-of-pile tests)
|
Kulsartov, T.V.
|
|
2006
|
|
1-7 |
p. 701-705
5 p.
|
artikel
|
| 61 |
Investigation of the dynamic behavior of the ITER tokamak assembly using a 1/5.8-scale model
|
Onozuka, M.
|
|
2006
|
|
1-7 |
p. 155-161
7 p.
|
artikel
|
| 62 |
Investigation of the impact of fabrication methods on the microstructure features of W-components of a He-cooled divertor
|
Krauss, W.
|
|
2006
|
|
1-7 |
p. 259-264
6 p.
|
artikel
|
| 63 |
Ion and neutron beam analyses of hydrogen isotopes
|
Kubota, N.
|
|
2006
|
|
1-7 |
p. 227-231
5 p.
|
artikel
|
| 64 |
ITER first wall Module 18—The US effort
|
Nygren, R.E.
|
|
2006
|
|
1-7 |
p. 387-392
6 p.
|
artikel
|
| 65 |
ITER fuel cycle R&D: Consequences for the design
|
Glugla, M.
|
|
2006
|
|
1-7 |
p. 733-744
12 p.
|
artikel
|
| 66 |
Japanese activities in ITER transitional arrangements
|
Mori, M.
|
|
2006
|
|
1-7 |
p. 69-77
9 p.
|
artikel
|
| 67 |
JET contributions to ITER technology issues
|
Grisolia, C.
|
|
2006
|
|
1-7 |
p. 149-154
6 p.
|
artikel
|
| 68 |
Joining technologies of reduced activation ferritic/martensitic steel for blanket fabrication
|
Hirose, T.
|
|
2006
|
|
1-7 |
p. 645-651
7 p.
|
artikel
|
| 69 |
Lithium compatibility of insulator coatings fabricated by RF sputtering method
|
Sawada, Akihiko
|
|
2006
|
|
1-7 |
p. 579-582
4 p.
|
artikel
|
| 70 |
Long term performances assessment of a water detritiation system components
|
Cristescu, I.
|
|
2006
|
|
1-7 |
p. 839-844
6 p.
|
artikel
|
| 71 |
Low cycle fatigue behavior of JLF-1 steel at elevated temperatures
|
Li, Huailin
|
|
2006
|
|
1-7 |
p. 241-245
5 p.
|
artikel
|
| 72 |
Magneto-hydrodynamic issues of the HCLL blanket
|
Reimann, J.
|
|
2006
|
|
1-7 |
p. 625-629
5 p.
|
artikel
|
| 73 |
Material probe analysis of boronized wall in LHD
|
Nobuta, Y.
|
|
2006
|
|
1-7 |
p. 187-192
6 p.
|
artikel
|
| 74 |
Model calculation of tritium release behavior from lithium titanate
|
Yamaki, Daiju
|
|
2006
|
|
1-7 |
p. 589-593
5 p.
|
artikel
|
| 75 |
Moderate tritium properties in lithium–tin alloy as a liquid breeder/coolant
|
Kang, Yi
|
|
2006
|
|
1-7 |
p. 519-523
5 p.
|
artikel
|
| 76 |
Monitoring of tritium in diluted gases by detecting bremsstrahlung X-rays
|
Shu, W.M.
|
|
2006
|
|
1-7 |
p. 803-808
6 p.
|
artikel
|
| 77 |
Neutron irradiation effect on mechanical properties of SS/SS hip joint materials for ITER shielding blankets
|
Yamada, Hirokazu
|
|
2006
|
|
1-7 |
p. 631-637
7 p.
|
artikel
|
| 78 |
Notch toughness evaluation of diffusion-bonded joint of alumina dispersion-strengthened copper to stainless steel
|
Nishi, H.
|
|
2006
|
|
1-7 |
p. 269-274
6 p.
|
artikel
|
| 79 |
Numerical analysis of MHD flow and heat transfer in a poloidal channel of the DCLL blanket with a SiCf/SiC flow channel insert
|
Smolentsev, S.
|
|
2006
|
|
1-7 |
p. 549-553
5 p.
|
artikel
|
| 80 |
Numerical analysis of MHD flow structure behind a square rod
|
Satake, M.
|
|
2006
|
|
1-7 |
p. 525-532
8 p.
|
artikel
|
| 81 |
Numerical research on heat transfer enhancement for high Prandtl-number fluid
|
Chiba, Shin-Ya
|
|
2006
|
|
1-7 |
p. 513-517
5 p.
|
artikel
|
| 82 |
On the influence of the supporting frame on the nuclear response of the Helium-Cooled Lithium Lead Test Blanket Module for ITER
|
Chiovaro, P.
|
|
2006
|
|
1-7 |
p. 677-686
10 p.
|
artikel
|
| 83 |
On the possibility of ITER starting with full carbon
|
Tanabe, Tetsuo
|
|
2006
|
|
1-7 |
p. 139-147
9 p.
|
artikel
|
| 84 |
Optimal configuration of neutron reflector in He-cooled molten Li blanket
|
Han, Beomseok
|
|
2006
|
|
1-7 |
p. 729-732
4 p.
|
artikel
|
| 85 |
Overview of comprehensive characterisation of erosion zones on plasma facing components
|
Rubel, M.J.
|
|
2006
|
|
1-7 |
p. 211-219
9 p.
|
artikel
|
| 86 |
Overview of design and R&D of test blankets in Japan
|
Enoeda, Mikio
|
|
2006
|
|
1-7 |
p. 415-424
10 p.
|
artikel
|
| 87 |
Overview of fusion nuclear technology in the US
|
Morley, N.B.
|
|
2006
|
|
1-7 |
p. 33-43
11 p.
|
artikel
|
| 88 |
Overview of research and development activities on fusion nuclear technologies in Japan
|
Tanaka, Satoru
|
|
2006
|
|
1-7 |
p. 13-24
12 p.
|
artikel
|
| 89 |
Overview of the European Union fusion nuclear technologies development and essential elements on the way to DEMO
|
Andreani, R.
|
|
2006
|
|
1-7 |
p. 25-32
8 p.
|
artikel
|
| 90 |
Preparation of ITER construction and operation
|
Shimomura, Y.
|
|
2006
|
|
1-7 |
p. 3-11
9 p.
|
artikel
|
| 91 |
Preparations for ITER construction in the European Union
|
Di Pietro, E.
|
|
2006
|
|
1-7 |
p. 59-67
9 p.
|
artikel
|
| 92 |
Present status of hydrogen isotope separation by CECE process at the NIFS
|
Sugiyama, T.
|
|
2006
|
|
1-7 |
p. 833-838
6 p.
|
artikel
|
| 93 |
Proceedings of the Seventh International Symposium on Fusion Nuclear Technology
|
Seki, Masahiro
|
|
2006
|
|
1-7 |
p. 1-2
2 p.
|
artikel
|
| 94 |
Progress in the benchmark exercise for analyzing the lithiate breeder pebble bed thermo-mechanical behaviour
|
Dell’Orco, G.
|
|
2006
|
|
1-7 |
p. 169-174
6 p.
|
artikel
|
| 95 |
Progress of plasma surface interaction study on low activation materials
|
Hino, T.
|
|
2006
|
|
1-7 |
p. 181-186
6 p.
|
artikel
|
| 96 |
Quantitative measurement of beryllium-controlled redox of hydrogen fluoride in molten Flibe
|
Simpson, Michael F.
|
|
2006
|
|
1-7 |
p. 541-547
7 p.
|
artikel
|
| 97 |
Reactivity of H2O gas with the surface of polycrystalline Li2O pellet
|
Oda, Takuji
|
|
2006
|
|
1-7 |
p. 613-618
6 p.
|
artikel
|
| 98 |
Recent progress of ITER FW/blanket design and preparations for fabrication
|
Ioki, K.
|
|
2006
|
|
1-7 |
p. 443-448
6 p.
|
artikel
|
| 99 |
Review of the activity in Russia in the area of fusion nuclear technology
|
Strebkov, Y.
|
|
2006
|
|
1-7 |
p. 45-58
14 p.
|
artikel
|
| 100 |
RF TBMs for ITER tests
|
Kirillov, I.R.
|
|
2006
|
|
1-7 |
p. 425-432
8 p.
|
artikel
|
| 101 |
RF test blanket sub-module with ceramic breeder and helium cooling for test in ITER
|
Kovalenko, V.
|
|
2006
|
|
1-7 |
p. 199-203
5 p.
|
artikel
|
| 102 |
Russian Federation contribution to the ITER project
|
Belyakov, V.A.
|
|
2006
|
|
1-7 |
p. 79-86
8 p.
|
artikel
|
| 103 |
Simulation of redeposition patterns of hydrocarbons released from carbon target in divertors
|
Ohya, Kaoru
|
|
2006
|
|
1-7 |
p. 205-210
6 p.
|
artikel
|
| 104 |
Solid breeder test blanket module design and analysis
|
Ying, A.
|
|
2006
|
|
1-7 |
p. 659-664
6 p.
|
artikel
|
| 105 |
Structural concept of Japanese solid breeder test blanket modules for ITER
|
Nomoto, Yasunobu
|
|
2006
|
|
1-7 |
p. 719-724
6 p.
|
artikel
|
| 106 |
Study of heat transfer enhancement/suppression for molten salt flows in a large diameter circular pipe
|
Takeuchi, J.
|
|
2006
|
|
1-7 |
p. 601-606
6 p.
|
artikel
|
| 107 |
Study of poisoning effects with the ITER model pump during relevant operation cycles
|
Haas, H.
|
|
2006
|
|
1-7 |
p. 845-850
6 p.
|
artikel
|
| 108 |
Study of surface and bulk instabilities in MHD duct flow with imitation of insulator coating imperfections
|
Xu, Zengyu
|
|
2006
|
|
1-7 |
p. 491-497
7 p.
|
artikel
|
| 109 |
Study of tritium migration in liquid Li2BeF4 with ab initio molecular dynamics
|
Klix, A.
|
|
2006
|
|
1-7 |
p. 713-717
5 p.
|
artikel
|
| 110 |
Study on tritium accountancy in fusion DEMO plant at JAERI
|
Nishi, Masataka
|
|
2006
|
|
1-7 |
p. 745-751
7 p.
|
artikel
|
| 111 |
Tensile property of low activation vanadium alloy after liquid lithium exposure
|
Nagasaka, Takuya
|
|
2006
|
|
1-7 |
p. 307-313
7 p.
|
artikel
|
| 112 |
The cascading pebble divertor for the spherical tokamak power plant
|
Voss, G.M.
|
|
2006
|
|
1-7 |
p. 327-333
7 p.
|
artikel
|
| 113 |
The European test blanket module systems: Design and integration in ITER
|
Boccaccini, L.V.
|
|
2006
|
|
1-7 |
p. 407-414
8 p.
|
artikel
|
| 114 |
The RF concept of experimental breeding module for testing in ITER
|
Leshukov, A.Yu.
|
|
2006
|
|
1-7 |
p. 533-539
7 p.
|
artikel
|
| 115 |
Thermal conductivity of ceramics during irradiation
|
Akiyoshi, M.
|
|
2006
|
|
1-7 |
p. 321-325
5 p.
|
artikel
|
| 116 |
Thermal conductivity of compressed beryllium pebble beds
|
Reimann, J.
|
|
2006
|
|
1-7 |
p. 449-454
6 p.
|
artikel
|
| 117 |
The tests of liquid metals (Ga, Li) as plasma facing components in T-3M and T-11M tokamaks
|
Mirnov, S.V.
|
|
2006
|
|
1-7 |
p. 113-119
7 p.
|
artikel
|
| 118 |
Three-dimensional neutronics assessment of dual coolant molten salt blankets with comparison to one-dimensional results
|
Sawan, M.E.
|
|
2006
|
|
1-7 |
p. 505-511
7 p.
|
artikel
|
| 119 |
Topology of compressed pebble beds
|
Reimann, J.
|
|
2006
|
|
1-7 |
p. 653-658
6 p.
|
artikel
|
| 120 |
Tritium control modelling for a helium cooled lithium–lead blanket of a fusion power reactor
|
Farabolini, W.
|
|
2006
|
|
1-7 |
p. 753-762
10 p.
|
artikel
|
| 121 |
Tritium inventory assessment for ITER using TRIMO
|
Cristescu, Ioana-R.
|
|
2006
|
|
1-7 |
p. 763-769
7 p.
|
artikel
|
| 122 |
Tritium release from neutron-irradiated Li2O: Transport in porous sintered pellets
|
Tanifuji, Takaaki
|
|
2006
|
|
1-7 |
p. 595-600
6 p.
|
artikel
|
| 123 |
U.S. contributions to ITER
|
Sauthoff, Ned R.
|
|
2006
|
|
1-7 |
p. 87-92
6 p.
|
artikel
|
| 124 |
Vapor species evolved from Li2TiO3 heated at high temperature under various conditions
|
Hoshino, T.
|
|
2006
|
|
1-7 |
p. 555-559
5 p.
|
artikel
|
| 125 |
Water vapor decomposition reaction on ZrNi alloy
|
Kawano, Takao
|
|
2006
|
|
1-7 |
p. 791-796
6 p.
|
artikel
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