Tensile and fatigue properties of two titanium alloys as candidate materials for fusion reactors (Unbekannt)
- Neue Suche nach: Marmy, P.
- Neue Suche nach: Marmy, P.
- Neue Suche nach: Leguey, T.
- Neue Suche nach: Belianov, I.
- Neue Suche nach: Victoria, M.
In:
Journal of nuclear materials
;
283
, 1
; 602-606
;
2000
-
ISSN:
- Aufsatz (Zeitschrift) / Print
-
Titel:Tensile and fatigue properties of two titanium alloys as candidate materials for fusion reactors
-
Beteiligte:
-
Erschienen in:Journal of nuclear materials ; 283, 1 ; 602-606
-
Verlag:
- Neue Suche nach: North Holland Publ. Co.
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Erscheinungsort:Amsterdam
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Erscheinungsdatum:2000
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ISSN:
-
ZDBID:
-
Medientyp:Aufsatz (Zeitschrift)
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Format:Print
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Sprache:Unbekannt
- Neue Suche nach: 52.55 / 51.40 / 33.81 / 33.80
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Schlagwörter:
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Datenquelle:
Inhaltsverzeichnis – Band 283, Ausgabe 1
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- 1
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Advances in fusion technologyBaker, Charles C. et al. | 2000
- 10
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Assessment and selection of materials for ITER in-vessel componentsKalinin, G. et al. | 2000
- 20
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Interactions between fusion materials R&D and other technologiesKohyama, A. et al. | 2000
- 28
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The impact of materials selection on long-term activation in fusion power plantsTaylor, N.P. et al. | 2000
- 35
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Evaluation of hot isostatic pressing for joining of fusion reactor structural componentsIvanov, A.D. et al. | 2000
- 43
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The status of beryllium technology for fusionScaffidi-Argentina, F. et al. | 2000
- 52
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Progress and critical issues of reduced activation ferritic-martensitic steel developmentvan der Schaaf, B. et al. | 2000
- 60
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Impact of irradiation effects on design solutions for ITER diagnosticsYamamoto, S. et al. | 2000
- 70
-
Critical issues and current status of vanadium alloys for fusion energy applicationsKurtz, R.J. et al. | 2000
- 79
-
International strategy for fusion materials developmentEhrlich, Karl et al. | 2000
- 89
-
Progress in modelling the microstructural evolution in metals under cascade damage conditionsTrinkaus, H. et al. | 2000
- 99
-
Ceramic breeder research and development: progress and focusvan der Laan, J.G. et al. | 2000
- 110
-
Critical plasma-wall interaction issues for plasma-facing materials and components in near-term fusion devicesFederici, G. et al. | 2000
- 120
-
A cleavage toughness master curve modelOdette, G.R. et al. | 2000
- 128
-
Critical issues and current status of SiC-SiC composites for fusionHasegawa, A. et al. | 2000
- 138
-
Neutron irradiation effects on plasma facing materialsBarabash, V. et al. | 2000
- 147
-
Radiation-induced inter-granular segregation in first wall fusion reactor materialsFaulkner, R.G. et al. | 2000
- 152
-
Sink effect of grain boundary on radiation-induced segregation in austenitic stainless steelWatanabe, S. et al. | 2000
- 157
-
Influence of cold work to increase swelling of pure iron irradiated in the BR-10 reactor to ~6 and ~25 dpa at ~400(degree)CDvoriashin, A.M. et al. | 2000
- 161
-
Synergistic effect of hydrogen and impurity segregations on the grain boundary embrittlement in NbIlyin, A.M. et al. | 2000
- 164
-
Compositional and temperature dependence of void swelling in model Fe-Cr base alloys irradiated in the EBR-II fast reactorSencer, B.H. et al. | 2000
- 169
-
Effect of temperature gradients on void formation in modified 316 stainless steel claddingAkasaka, N. et al. | 2000
- 174
-
Recovery of electrical resistivity of high-purity iron irradiated with 30 MeV electrons at 77 KAbe, Hironobu et al. | 2000
- 179
-
Correlation between defect structures and hardness in tantalum irradiated by heavy ionsYasunaga, K. et al. | 2000
- 183
-
Study of He-bubble growth in a-particle implanted F82H-mod martensitic steelCoppola, R. et al. | 2000
- 188
-
Modeling of microstructure evolution and mechanical property change of reduced-activation martensitic steel during varying-temperature irradiationKasada, R. et al. | 2000
- 193
-
Influence of neutron irradiation on CuNiCrSi alloy pre-implanted with heliumKozlov, A.V. et al. | 2000
- 198
-
Effects of grain boundary misorientation on solute segregation in thermally sensitized and proton-irradiated 304 stainless steelDuh, T.S. et al. | 2000
- 205
-
Correlation of simulated TEM images with irradiation induced damageSchäublin, R. et al. | 2000
- 210
-
Formation and migration of helium bubbles in Fe-16Cr-17Ni austenitic alloy at high temperatureOno, K. et al. | 2000
- 215
-
The effect of transmutation and displacement in irradiated copper for heat-sink materialsIshino, Shiori et al. | 2000
- 220
-
Effects of dose rate on microsturctural evolution and swelling in austenitic steels under irradiationOkita, T. et al. | 2000
- 224
-
Synergistic effects of hydrogen and helium on microstructural evolution in vanadium alloys by triple ion beam irradiationSekimura, N. et al. | 2000
- 229
-
The effect of alloying elements on the defect structural evolution in neutron irradiated Ni alloysYoshiie, T. et al. | 2000
- 234
-
Study of point defect behaviors in vanadium and its alloys by using HVEMHayashi, T. et al. | 2000
- 239
-
Void swelling and irradiation creep of two high-nickel steels after irradiation at 400-410(degree)C to 84-91 dpa in the BN-350 fast reactorPorollo, S.I. et al. | 2000
- 244
-
Radiation-induced segregation in model alloysEzawa, T. et al. | 2000
- 249
-
Development of vacancy clusters in neutron-irradiated copper at high temperatureShimomura, Y. et al. | 2000
- 255
-
Application of the internal friction method to studying microstructural effects in fusion materialsTähtinen, S. et al. | 2000
- 259
-
Microstructural changes in a low-activation Fe-Cr-Mn alloy irradiated with 92 MeV Ar ions at 450(degree)CZhang, Chonghong et al. | 2000
- 263
-
Microstructural changes of austenitic steels caused by proton irradiation under various conditionsFukuda, T. et al. | 2000
- 268
-
Effect of dual-beam-irradiation by helium and carbon ions on microstructure development of SiC-SiC compositesNogami, S. et al. | 2000
- 273
-
Microstructures in Ti-Al intermetallic compounds irradiated at 673 K in HFIRMiwa, Y. et al. | 2000
- 278
-
Role of a2-g and g-g phase boundaries in cavity formation in a TiAl intermetallic compound irradiated with He-ionsNakata, K. et al. | 2000
- 282
-
Defect structures introduced in iron under varying temperature neutron irradiationHoriki, M. et al. | 2000
- 286
-
Microstructure of vanadium alloys during ion irradiation with stepwise change of temperatureWatanabe, H. et al. | 2000
- 291
-
Effects of temperature change on the microstructural evolution of vanadium alloys under ion irradiationNita, N. et al. | 2000
- 297
-
Computer simulations of the effects of temperature change on defect accumulation in copper during neutron irradiationXu, Q. et al. | 2000
- 302
-
Microstructure in pure copper irradiated by simultaneous multi-ion beam of hydrogen, helium and self ionsMukouda, I. et al. | 2000
- 306
-
Microstructure of Cu-Ni alloys neutron irradiated at 210(degree)C and 420(degree)C to 14 dpaZinkle, S.J. et al. | 2000
- 313
-
Simulating the influence of radiation temperature variations on microstructural evolutionKatoh, Y. et al. | 2000
- 319
-
Influence of variable temperatures irradiation on microstructural evolution in phosphorus doped Fe-Cr-Ni alloysHamaguchi, D. et al. | 2000
- 324
-
Microstructural evolution of Alloy 718 at high helium and hydrogen generation rates during irradiation with 600-800 MeV protonsSencer, B.H. et al. | 2000
- 329
-
Microstructural changes induced by post-irradiation annealing of neutron-irradiated austenitic stainless steelsCole, J.I. et al. | 2000
- 334
-
Swelling of F82H irradiated at 673 K up to 51 dpa in HFIRMiwa, Y. et al. | 2000
- 339
-
Differences in the microstructure of the F82H ferritic-martensitic steel after proton and neutron irradiationSchäublin, R. et al. | 2000
- 344
-
Microstructural examination of V-(3-6%)Cr-(3-5%)Ti irradiated in the ATR-A1 experimentGelles, D.S. et al. | 2000
- 349
-
On the relationship between uniaxial yield strength and resolved shear stress in polycrystalline materialsStoller, R.E. et al. | 2000
- 353
-
Mechanical behavior of reduced-activation and conventional martensitic steels after neutron irradiation in the range 250-450(degree)CAlamo, A. et al. | 2000
- 358
-
Tensile behavior of F82H with and without spectral tailoringShiba, K. et al. | 2000
- 362
-
Effects of low-temperature neutron irradiation on mechanical properties of vanadium-base alloysTsai, H. et al. | 2000
- 367
-
Improvement in post-irradiation ductility of neutron irradiated V-Ti-Cr-Si-Al-Y alloy and the role of interstitial impuritiesSatou, M. et al. | 2000
- 372
-
Irradiation creep of advanced silicon carbide fibersScholz, R. et al. | 2000
- 376
-
The effect of neutron-irradiation on the shear properties of SiC-SiC composites with varied interfaceHinoki, T. et al. | 2000
- 380
-
Swelling, irradiation creep and growth of pure rhenium irradiated with fast neutrons at 1030-1330(degree)CGarner, F.A. et al. | 2000
- 386
-
In-pile and post-irradiation creep of type 304 stainless steel under different neutron spectraKurata, Y. et al. | 2000
- 391
-
Irradiation creep at 60(degree)C in SUS 316 and its impact on fatigue fractureNagakawa, Johsei et al. | 2000
- 396
-
Irradiation creep of 11Cr-0.5Mo-2W,V,Nb ferritic-martensitic, modified 316, and 15Cr-20Ni austenitic S.S. irradiated in FFTF to 103-206 dpaUehira, A. et al. | 2000
- 400
-
Effects of helium implantation on creep rupture properties of low activation ferritic steel F82H IEA heatYamamoto, Norikazu et al. | 2000
- 404
-
Effect of neutron dose and irradiation temperature on the mechanical properties and structure of dispersion strengthened copper alloysPokrovsky, A.S. et al. | 2000
- 409
-
Application of generalized deformation theory to irradiation creep of fcc and bcc stainless steelsToloczko, M.B. et al. | 2000
- 414
-
Proton irradiation creep of Inconel 718 at 300(degree)CScholz, R. et al. | 2000
- 418
-
Shear punch and tensile measurements of mechanical property changes induced in various austenitic alloys by high-energy mixed proton and neutron irradiation at low temperaturesHamilton, M.L. et al. | 2000
- 423
-
The contribution of various defects to irradiation-induced hardening in an austenitic model alloyAndo, M. et al. | 2000
- 428
-
Tensile and low-cycle fatigue properties of solution annealed type 316L stainless steel plate and TIG-weld exposed to 5 dpa at low-temperature (42(degree)C)Puzzolante, J.-L. et al. | 2000
- 435
-
Tensile properties and damage microstructures in ORR-HFIR-irradiated austenitic stainless steelsWakai, E. et al. | 2000
- 440
-
Effect of helium to dpa ratio on fatigue behavior of austenitic stainless steel irradiated to 2 dpaIoka, I. et al. | 2000
- 446
-
The effects of irradiation and testing temperature on tensile behaviour of stainless steelsBailat, C. et al. | 2000
- 451
-
Mechanical properties of hot isostatic pressed type 316LN steel after irradiationLind, A. et al. | 2000
- 455
-
Analysis of tensile and fracture toughness results on irradiated molybdenum alloys, TZM and Mo-5%ReScibetta, M. et al. | 2000
- 461
-
Thermal fatigue crack nucleation in ferritic-martensitic steels before and after neutron irradiationBelyaeva, L.A. et al. | 2000
- 465
-
Effect of heat treatment and irradiation temperature on mechanical properties and structure of reduced-activation Cr-W-V steels of bainitic, martensitic, and martensitic-ferritic classesGorynin, I.V. et al. | 2000
- 470
-
Effects of helium implantation on hardness of pure iron and a reduced activation ferritic-martensitic steelTanigawa, Hiroyasu et al. | 2000
- 474
-
Low-temperature irradiation effects on tensile and Charpy properties of low-activation ferritic steelsShiba, Kiyoyuki et al. | 2000
- 478
-
Embrittlement of reduced-activation ferritic-martensitic steels irradiated in HFIR at 300(degree)C and 400(degree)CKlueh, R.L. et al. | 2000
- 483
-
Tensile properties and microstructure of 590 MeV proton-irradiated pure Fe and a Fe-Cr alloyLuppo, M.I. et al. | 2000
- 488
-
Effect of low temperature irradiation on the mechanical properties of ternary V-Cr-Ti alloys as determined by tensile tests and shear punch testsHamilton, M.L. et al. | 2000
- 492
-
Mechanical behavior and microstructural evolution of vanadium alloys irradiated in ATR-A1Fukumoto, K.-i. et al. | 2000
- 498
-
V-alloy embrittlement by irradiation in a cooling gas environmentRöhrig, H.D. et al. | 2000
- 503
-
Defect microstructure and deformation behavior of V-Ti-Cr-Si-Al-Y alloy irradiated in ATRChuto, Toshinori et al. | 2000
- 508
-
Effect of strain rate on the tensile properties of unirradiated and irradiated V-4Cr-4TiRowcliffe, A.F. et al. | 2000
- 513
-
Mechanical properties and microstructure in low-activation martensitic steels F82H and Optimax after 800-MeV proton irradiationDai, Y. et al. | 2000
- 518
-
On the mechanisms and mechanics of fracture toughness of a V-4Cr-4Ti alloyDonahue, E.G. et al. | 2000
- 523
-
Effect of high-dose neutron irradiation on the mechanical properties and structure of copper alloys and Cu-SS joints for ITER applicationsFabritsiev, S.A. et al. | 2000
- 528
-
Deformation mechanisms in 316 stainless steel irradiated at 60(degree)C and 330(degree)CHashimoto, N. et al. | 2000
- 535
-
Radiation-induced precipitation in V-(Cr,Fe)-Ti alloys irradiated at low temperature with low dose during neutron or ion irradiationFukumoto, Ken-ichi et al. | 2000
- 540
-
Diffusion and permeation of hydrogen in low-activation martensitic stainless steel - effect of irradiationSchliefer, F. et al. | 2000
- 545
-
In situ thermal conductivity measurement of ceramics in a fast neutron environmentSnead, L.L. et al. | 2000
- 551
-
Evaluation of neutron irradiated near-stoichiometric silicon carbide fiber compositesSnead, L.L. et al. | 2000
- 556
-
SYLRAMIC(TM) SiC fibers for CMC reinforcementJones, Richard E. et al. | 2000
- 560
-
Room and high-temperature mechanical and thermal properties of SiC fiber-reinforced SiC composite sintered under pressureYoshida, K. et al. | 2000
- 565
-
High-performance SiC-SiC composites by improved PIP processing with new precursor polymersKohyama, A. et al. | 2000
- 570
-
High thermal conductivity SiC-SiC composites for fusion applicationsKowbel, W. et al. | 2000
- 574
-
Mechanical and thermal properties of 2D and 3D SiC-SiC compositesYamada, R. et al. | 2000
- 579
-
New evaluation method of crack growth in SiC-SiC composites using interface elementsSerizawa, H. et al. | 2000
- 584
-
Time-dependent failure mechanisms in silicon carbide composites for fusion energy applicationsLewinsohn, C.A. et al. | 2000
- 588
-
Neutron wall loading of Tokamak reactorsWong, C.P.C. et al. | 2000
- 593
-
Characterization of non-magnetic Mn-Cr steel as a low induced activation material for vacuum vesselsSaito, S. et al. | 2000
- 597
-
Thermomechanical characteristics of the low activation materials chromium and Cr.5Fe.1Y2O3 alloyStamm, H. et al. | 2000
- 602
-
Tensile and fatigue properties of two titanium alloys as candidate materials for fusion reactorsMarmy, P. et al. | 2000
- 607
-
Uses of zirconium alloys in fusion applicationsForty, C.B.A. et al. | 2000
- 611
-
Microstructure control to improve mechanical properties of vanadium alloys for fusion applicationsKuwabara, T. et al. | 2000
- 616
-
Solute interactions in pure vanadium and V-4Cr-4Ti alloyHoelzer, D.T. et al. | 2000
- 622
-
Performance of V-4Cr-4Ti alloy exposed to the JFT-2M tokamak environmentJohnson, W.R. et al. | 2000
- 628
-
Biaxial thermal creep of V-4Cr-4Ti at 700(degree)C and 800(degree)CKurtz, R.J. et al. | 2000
- 633
-
Tensile and impact properties of V-4Cr-4Ti alloy heats 832665 and 832864Bray, T.S. et al. | 2000
- 637
-
A physically based constitutive model for a V-4Cr-4Ti alloyDonahue, E.G. et al. | 2000
- 642
-
Development of an oxide dispersion strengthened, reduced-activation steel for fusion energyRomanoski, G.R. et al. | 2000
- 647
-
Effect of mechanical alloying parameters on irradiation damage in oxide dispersion strengthened ferritic steelsYamashita, S. et al. | 2000
- 652
-
Material science and manufacturing of heat-resistant reduced-activation ferritic-martensitic steels for fusionIoltukhovskiy, A.G. et al. | 2000
- 657
-
Microstructure of welded and thermal-aged low activation steel F82H IEA heatSawai, T. et al. | 2000
- 662
-
Chemical segregation behavior under thermal aging of the low-activation F82H-modified steelLapeña, J. et al. | 2000
- 667
-
Mechanical properties of 8Cr-2WVTa steel aged for 30000 hTamura, M. et al. | 2000
- 672
-
Effect of thermal aging on the microstructure and mechanical properties of 7-11 CrW steelsde Carlan, Y. et al. | 2000
- 677
-
Low cycle fatigue properties of a low activation ferritic steel (JLF-1) at room temperatureNishimura, A. et al. | 2000
- 681
-
Ripple reduction and surface coating tests with ferritic steel on JFT-2MTsuzuki, K. et al. | 2000
- 685
-
High heat flux test of a HIP-bonded first wall panel of reduced activation ferritic steel F-82HHatano, T. et al. | 2000
- 689
-
Phenomenological aspects of fatigue cracking in as-received and hardened F82H modified steel exposed to lithiated water with dissolved hydrogen at 240(degree)CMaday, Marie-Françoise et al. | 2000
- 694
-
Influence of combined thermomechanical treatment on impurity segregation in ferritic-martensitic and austenitic stainless steelsIlyin, A.M. et al. | 2000
- 697
-
A potential new ferritic-martensitic steel for fusion applicationsKlueh, R.L. et al. | 2000
- 702
-
Tube manufacturing and characterization of oxide dispersion strengthened ferritic steelsUkai, Shigeharu et al. | 2000
- 707
-
Tensile and impact behavior of the reduced-activation steels OPTIFER and F82H modSchäfer, L. et al. | 2000
- 711
-
NIFS program for large ingot production of a V-Cr-Ti alloyMuroga, T. et al. | 2000
- 716
-
Performance limits for fusion first-wall structural materialsSmith, D.L. et al. | 2000
- 721
-
Constitutive behavior and fracture toughness properties of the F82H ferritic-martensitic steelSpätig, P. et al. | 2000
- 727
-
Features of radiation damage of vanadium and its alloys at a temperature of 330-340(degree)CKazakov, V.A. et al. | 2000
- 731
-
The mechanical properties and microstructure of the OPTIMAX series of low activation ferritic-martensitic steelsBaluc, N. et al. | 2000
- 737
-
The effects of one-dimensional glide on the reaction kinetics of interstitial clustersHeinisch, H.L. et al. | 2000
- 741
-
3D dislocation dynamics study of plastic instability in irradiated copperSun, L.Z. et al. | 2000
- 746
-
Statistical analysis of a library of molecular dynamics cascade simulations in iron at 100 KStoller, R.E. et al. | 2000
- 753
-
A molecular dynamics simulation study of small cluster formation and migration in metalsMorishita, K. et al. | 2000
- 758
-
Modeling of cascade damage interactions by Monte-Carlo methodSekimura, N. et al. | 2000
- 763
-
Interstitial cluster motion in displacement cascadesDoan, N.V. et al. | 2000
- 768
-
Comparative study of damage accumulation in iron under magnetic and inertial fusion conditionsAlonso, E. et al. | 2000
- 773
-
Atomistic simulation of stacking fault tetrahedra formation in CuWirth, B.D. et al. | 2000
- 778
-
Computer simulation of defects interacting with a dislocation in Fe and NiKuramoto, E. et al. | 2000
- 784
-
Study of loop-loop and loop-edge dislocation interactions in bcc ironOsetsky, Yu N. et al. | 2000
- 789
-
Comparison of a microstructure evolution model with experiments on irradiated vanadiumSharafat, S. et al. | 2000
- 794
-
Molecular dynamics simulation of defect production in irradiated b-SiCMalerba, L. et al. | 2000
- 799
-
Effect of helium production on swelling of F82H irradiated in HFIRWakai, E. et al. | 2000
- 806
-
A comparison of defects in helium implanted a- and b-SiCJung, P. et al. | 2000
- 811
-
Study of helium effects in SiC-SiC composites under fusion reactor environmentHasegawa, A. et al. | 2000
- 816
-
Recovery and recrystallization behavior of vanadium at various controlled nitrogen and oxygen levelsNagasaka, T. et al. | 2000
- 822
-
Effect of oxygen on the crack growth behavior of V-4Cr-4Ti at 600(degree)CKurtz, Richard J. et al. | 2000
- 827
-
Annealing behavior of irradiation hardening and microstructure in helium-implanted reduced activation martensitic steelKimura, A. et al. | 2000
- 832
-
Fatigue behavior and development of microcracks in F82H after helium implantation at 200(degree)CBertsch, J. et al. | 2000
- 838
-
On quantification of helium embrittlement in ferritic-martensitic steelsGelles, D.S. et al. | 2000
- 841
-
Effects of oxygen and hydrogen at low pressure on the mechanical properties of V-Cr-Ti alloysDistefano, J.R. et al. | 2000
- 846
-
Hydrogen-irradiated steel interaction during alternating hydrogenation and annealingKrasikov, E.A. et al. | 2000
- 849
-
The interaction of deuterium and tritium with radiation and other defects in austenitic steel and nickelArbuzov, V.L. et al. | 2000
- 854
-
Heavy hydrogen isotopes penetration through austenitic and martensitic steelsDolinski, Yu et al. | 2000
- 858
-
Positron-lifetime study of electrically hydrogen charged Ni, austenitic stainless steel and FeOhkubo, H. et al. | 2000
- 863
-
The effect of electrical hydrogen charging on the strength of 316 stainless steelSugiyama, S. et al. | 2000
- 868
-
Permeation of hydrogen through vanadium under helium ion irradiationHatano, Yuji et al. | 2000
- 872
-
Hydrogen permeation through vanadium alloy V-4Cr-4Ti 'in situ' of reactor irradiationKulsartov, T.V. et al. | 2000
- 876
-
Effect of hydrogen accumulation on mechanical property and microstructure of V-Cr-Ti alloysAoyagi, K. et al. | 2000
- 880
-
An initial model for the RIED effectHodgson, E.R. et al. | 2000
- 885
-
Significance of sample thickness and surface segregation on the electrical conductivity of Wesgo AL995 alumina under ITER environmentsHowlader, M.M.R. et al. | 2000
- 890
-
KU1 quartz glass for remote handling and LIDAR diagnostic optical transmission systemsGarcia-Matos, M. et al. | 2000
- 894
-
Radiation effects on laser damage in KU1 quartz glassMartin, P. et al. | 2000
- 898
-
Study on the damaging process of silica by in-reactor luminescenceIi, Tatsuya et al. | 2000
- 903
-
In-beam dielectric properties of alumina at low frequenciesVila, R. et al. | 2000
- 907
-
Radiation-induced conductivity of doped silicon in response to photon, proton and neutron irradiationKishimoto, N. et al. | 2000
- 912
-
Current-voltage characteristic of alumina and aluminum nitride with or without electron irradiationShiiyama, K. et al. | 2000
- 917
-
Temperature effect of electron-irradiation-induced structural modification in graphiteMuto, Shunsuke et al. | 2000
- 922
-
Positron lifetime calculation for defects and defect clusters in graphiteOnitsuka, T. et al. | 2000
- 927
-
Neutron irradiation effects in magnesium-aluminate spinel doped with transition metalsGritsyna, V.T. et al. | 2000
- 932
-
Radiation-induced processes and their influence on the functional properties of dielectrics for different types of irradiationStepanov, V.A. et al. | 2000
- 937
-
Thermal stability and kinetics of defects in magnesium aluminate spinel irradiated with fast neutronsYasuda, Kazuhiro et al. | 2000
- 942
-
Effects of co-implanted oxygen or aluminum atoms on hydrogen migration and damage structure in multiple-beam irradiated Al2O3Katano, Y. et al. | 2000
- 947
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Neutron irradiation damage in aluminum oxide and nitride ceramics up to a fluence of 4.2x1026n-m2Yano, T. et al. | 2000
- 952
-
Cation disordering in magnesium aluminate spinel crystals induced by electron or ion irradiationSoeda, Takeshi et al. | 2000
- 957
-
Design and fabrication methods of FW-blanket, divertor and vacuum vessel for ITERIoki, K. et al. | 2000
- 962
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Status of international collaborative efforts on selected ITER materialsBelyakov, V.A. et al. | 2000
- 968
-
Russian superconducting materials for magnet systems of fusion reactorsShikov, A. et al. | 2000
- 973
-
Mechanical properties of the ITER central solenoid model coil insulation under static and dynamic load after reactor irradiationHumer, K. et al. | 2000
- 977
-
Fracture behavior of high-strength, high-conductivity copper alloysLi, M. et al. | 2000
- 982
-
Evaluation of the deformation fields and bond integrity of Cu-SS jointsStubbins, J.F. et al. | 2000
- 987
-
Ductility correlations between shear punch and uniaxial tensile test dataToloczko, M.B. et al. | 2000
- 992
-
Confocal microscopy-fracture reconstruction and finite element modeling characterization of local cleavage toughness in a ferritic-martensitic steel in subsized Charpy V-notch impact testsYamamoto, T. et al. | 2000
- 997
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Irradiation-coupling techniques using JMTR and another facilityMatsui, Y. et al. | 2000
- 1001
-
How to improve the irradiation conditions for the International Fusion Materials Irradiation FacilityDaum, Eric et al. | 2000
- 1006
-
High-sensitivity quadrupole mass spectometry system for the determination of hydrogen in irradiated materialsOliver, B.M. et al. | 2000
- 1011
-
Neutron irradiation hardening of ODS alloy tested by miniature disk bend test methodChen, C.Q. et al. | 2000
- 1014
-
Specimen size effects on the tensile properties of JPCA and JFMSKohno, Yutaka et al. | 2000
- 1018
-
Effect of specimen size on fatigue properties of reduced activation ferritic-martensitic steelsHirose, T. et al. | 2000
- 1023
-
Development of a small specimen test machine to evaluate irradiation embrittlement of fusion reactor materialsIshii, T. et al. | 2000
- 1028
-
Damage mechanisms and fracture toughness of GlidCop(R) CuAl25 IG0 copper alloyTähtinen, S. et al. | 2000
- 1033
-
Hydrogen and deuterium transport and inventory parameters through W and W-alloys for fusion reactor applicationsBenamati, G. et al. | 2000
- 1038
-
Deuterium retention in tungsten and molybdenumNagata, S. et al. | 2000
- 1043
-
Tritium permeation experiment using a tungsten armored divertor-simulating moduleNakamura, H. et al. | 2000
- 1048
-
Depth profile of tritium in plasma exposed CX-2002UTadokoro, T. et al. | 2000
- 1053
-
Hydrogen absorption process into graphite and carbon materialsAtsumi, H. et al. | 2000
- 1057
-
Removal of deuterium from co-deposited carbon-silicon layersBalden, M. et al. | 2000
- 1062
-
Effect of carbon pre-implantation on deuterium retention in tungstenPoon, M. et al. | 2000
- 1068
-
Manufacturing and testing of a prototypical divertor vertical target for ITERMerola, M. et al. | 2000
- 1073
-
Tungsten filament mock-ups for gas box linerCazzola, C. et al. | 2000
- 1077
-
The behavior of coatings and SiCf-SiC composites under thermal shockYu, Jinnan et al. | 2000
- 1081
-
Infrared characterization and high heat flux testing of plasma sprayed layersChappuis, Ph et al. | 2000
- 1085
-
The removal of ion implanted deuterium from tungsten and stainless steel by transferred-arc cleaningHollis, K.J. et al. | 2000
- 1089
-
Graphite-tungsten twin limiters in studies of material mixing processes on high heat flux componentsRubel, M. et al. | 2000
- 1094
-
Codeposition of deuterium ions with beryllium oxide at elevated temperaturesMarkin, A.V. et al. | 2000
- 1100
-
Sputtering studies of beryllium with helium and deuterium using molecular dynamics approachUeda, Shuzo et al. | 2000
- 1105
-
Effects of plasma disruption events on ITER first wall materialsCardella, A. et al. | 2000
- 1111
-
Erosion mechanisms and products in graphite targets under simulated disruption conditionsScaffidi-Argentina, F. et al. | 2000
- 1116
-
Development of functionally graded plasma-facing materialsGe, Chang-Chun et al. | 2000
- 1121
-
Changes of composition and microstructure of joint interface of tungsten coated carbon by high heat fluxTokunaga, K. et al. | 2000
- 1128
-
Application of tungsten for plasma limiters in TEXTORTanabe, T. et al. | 2000
- 1134
-
Microstructure evolution in tungsten during low-energy helium ion irradiationIwakiri, H. et al. | 2000
- 1139
-
TEM study on deuterium-irradiation-induced defects in tungsten and molybdenumMatsui, Tsuyoshi et al. | 2000
- 1144
-
Microstructural development of neutron irradiated W-Re alloysNemoto, Yoshiyuki et al. | 2000
- 1148
-
Effect of neutron irradiation on thermal diffusivity of tungsten-rhenium alloysFujitsuka, M. et al. | 2000
- 1152
-
High heat flux simulation experiments with improved electron beam diagnosticsLinke, J. et al. | 2000
- 1157
-
Erosion characteristics of neutron-irradiated carbon-based materials under simulated disruption heat loadsSato, K. et al. | 2000
- 1161
-
Neutron-irradiation effects on high heat flux components - examination of plasma-facing materials and their jointsRödig, M. et al. | 2000
- 1166
-
Effect of ITER components manufacturing cycle on the irradiation behaviour of 316L(N)-IG steelRodchenkov, B.S. et al. | 2000
- 1171
-
Hydrodynamic effects of eroded materials of plasma-facing component during a Tokamak disruptionHassanein, A. et al. | 2000
- 1177
-
Structure of materials deposited on the plasma facing surface in TRIAM-1M tokamak and the effect on hydrogen recyclingHirai, T. et al. | 2000
- 1182
-
Simulation study of carbon and tungsten deposition on W-C twin test limiter in TEXTOR-94Ohya, K. et al. | 2000
- 1187
-
Characterization of low-activation ferritic steel (JLF-1) weld joint by simulated heat-treatmentsInoue, N. et al. | 2000
- 1192
-
Effects of thermal aging on the mechanical behavior of F82H weldmentsAlamo, A. et al. | 2000
- 1196
-
Diffusion welding parameters and mechanical properties of martensitic chromium steelsSchleisiek, K. et al. | 2000
- 1201
-
Post-irradiation mechanical tests on F82H EB and TIG weldsRensman, J. et al. | 2000
- 1206
-
The effect of laser welding process parameters on the mechanical and microstructural properties of V-4Cr-4Ti structural materialsReed, C.B. et al. | 2000
- 1210
-
Re-weldability tests of irradiated austenitic stainless steel by a TIG welding methodTsuchiya, Kunihiko et al. | 2000
- 1215
-
Radiation resistance of weld joints of type 316 stainless steel containing about 10 appm HeFabritsiev, S.A. et al. | 2000
- 1220
-
Effect of weld thermal cycle and restraint stress on helium bubble formation in stainless steelsKawano, S. et al. | 2000
- 1224
-
Furnace brazing type 304 stainless steel to vanadium alloy (V-5Cr-5Ti)Steward, R.V. et al. | 2000
- 1229
-
Effects of heat treatments on microstructure changes in the interface of Cu-SS316L joint materialsXu, Q. et al. | 2000
- 1234
-
Low cycle fatigue strength of diffusion bonded joints of alumina dispersion-strengthened copper to stainless steelNishi, H. et al. | 2000
- 1238
-
Effect of neutron irradiation on mechanical properties of Cu-SS joints after single and multiple HIP cyclesTähtinen, S. et al. | 2000
- 1243
-
High temperature residual strain measurements in a brazed sample for NET-ITERCoppola, R. et al. | 2000
- 1248
-
Armor and heat sink materials joining technologies development for ITER plasma facing componentsBarabash, V. et al. | 2000
- 1253
-
Refractory metal joining for first wall applicationsCadden, C.H. et al. | 2000
- 1258
-
Joining of silicon carbide composites for fusion energy applicationsLewinsohn, C.A. et al. | 2000
- 1262
-
Microstructure and mechanical properties of low-activation glass-ceramic joining and coating for SiC-SiC compositesKatoh, Yutai et al. | 2000
- 1267
-
Magnetic field effect on deposition of corrosion products in liquid Pb-17LiBarbier, F. et al. | 2000
- 1272
-
The hydrogen permeation behaviour of aluminised coated martensitic steels under gaseous hydrogen, liquid Pb-17Li-hydrogen and cyclic tensile loadSample, T. et al. | 2000
- 1277
-
Development of electrically insulating coatings for service in a lithium environmentNatesan, K. et al. | 2000
- 1282
-
Corrosion of V-Ti-Cr alloys in liquid lithium: influence of alloy composition and concentration of nitrogen in lithiumEliseeva, O.I. et al. | 2000
- 1287
-
The permeation of tritium through 316L stainless steel with multiple coatingsYao, Zhenyu et al. | 2000
- 1292
-
The oxidation kinetics of Incoloy 800 and its deuterium permeation behaviorPerujo, A. et al. | 2000
- 1297
-
Effects of thin films on inventory, permeation and re-emission of energetic hydrogenOhyabu, N. et al. | 2000
- 1302
-
Scale structure of aluminised Manet steel after HIP treatmentGlasbrenner, H. et al. | 2000
- 1306
-
A microstructural study of the oxide scale formation on ODS Fe-13Cr steelHoelzer, D.T. et al. | 2000
- 1311
-
Oxidation and hardness profile of V-Ti-Cr-Si-Al-Y alloysFujiwara, Mitsuhiro et al. | 2000
- 1316
-
Performance of V-Cr-Ti alloys in a hydrogen environmentNatesan, K. et al. | 2000
- 1322
-
Compatibility of AlN with liquid lithiumTerai, T. et al. | 2000
- 1326
-
Compatibility of structural candidate materials with LiF-BeF2 molten salt mixtureNishimura, H. et al. | 2000
- 1332
-
Corrosion of ferritic-martensitic steels in the eutectic Pb-17LiGlasbrenner, H. et al. | 2000
- 1336
-
Liquid metal embrittlement (LME) susceptibility of the 8-9% Cr martensitic steels F82H-mod., OPTIFER IVb and their simulated welded structures in liquid Pb-17LiSample, T. et al. | 2000
- 1341
-
Water corrosion of F82H-modified in simulated irradiation conditions by heat treatmentLapeña, J. et al. | 2000
- 1346
-
Copper corrosion and activation in water cooling loops under fusion irradiation conditionsKarditsas, P.J. et al. | 2000
- 1351
-
In-pile tritium-permeation measurements on T91 tubes with double walls or a Fe-Al-Al2O3 coatingConrad, R. et al. | 2000
- 1356
-
Impurity effects on gas tungsten arc welds in V-Cr-Ti alloysGrossbeck, M.L. et al. | 2000
- 1361
-
Behaviour of Li2ZrO3 and Li2TiO3 pebbles relevant to their utilization as ceramic breeder for the HCPB blanketLulewicz, J.D. et al. | 2000
- 1366
-
Study of the tritium behavior on the surface of Li2O by means of work function measurementYokota, Toshihiko et al. | 2000
- 1370
-
Multiplier, moderator, and reflector materials for advanced lithium-vanadium fusion blanketsGohar, Y. et al. | 2000
- 1375
-
On the use of tin-lithium alloys as breeder material for blankets of fusion power plantsFütterer, M.A. et al. | 2000
- 1380
-
Development of wet process with substitution reaction for the mass production of Li2TiO3 pebblesTsuchiya, Kunihiko et al. | 2000
- 1385
-
Chemical reactivity of SiC fibre-reinforced SiC with beryllium and lithium ceramic breeder materialsKleykamp, H. et al. | 2000
- 1390
-
On the mechanisms associated with the chemical reactivity of Be in steamPetti, D.A. et al. | 2000
- 1396
-
Post-irradiation examinations of Li4SiO4 pebbles irradiated in the EXOTIC-7 experimentPiazza, G. et al. | 2000
- 1401
-
Effects of helium production and radiation damage on tritium release behavior of neutron-irradiated beryllium pebblesIshitsuka, E. et al. | 2000
- 1405
-
XPS and UPS studies on electronic structure of Li2OTanaka, Satoru et al. | 2000
- 1409
-
Development of materials and fabrication of porous and pebble bed beryllium multipliersDavydov, D.A. et al. | 2000
- 1414
-
Improvement of the model for surface process of tritium release from lithium oxideYamaki, Daiju et al. | 2000
- 1419
-
Tritium release from neutron-irradiated Li2O sintered pellets: porosity dependenceTanifuji, Takaaki et al. | 2000
- 1424
-
ITER structural design criteria and their extension to advanced reactor blanketsMajumdar, S. et al. | 2000
- 1429
-
Materials and fabrication technology of modules intended for irradiation tests of blanket tritium-breeding zones in Russian fusion reactor projectsKapychev, V. et al. | 2000
- 1434
-
Measurement and analysis of radioactivity induced in steels and a vanadium alloy by 14-MeV neutronsRichter, D. et al. | 2000
- 1438
-
Accelerated helium and hydrogen production in 54Fe doped alloys - measurements and calculations for the FIST experimentGreenwood, L.R. et al. | 2000
- 1443
-
Compositional optimisation of silicon carbide for various fusion blanket designsForty, C.B.A. et al. | 2000
- 1448
-
Experimental study on beryllium-7 production via sequential reactions in lithium-containing compounds irradiated by 14 MeV neutronsMaekawa, F. et al. | 2000
- 1453
-
Material composition and nuclear data libraries' influence on nickel-chromium alloys activation evaluation: a comparison with decay heat experimentsCepraga, D.G. et al. | 2000
- 1458
-
Oxidation and volatilization of TZM alloy in airSmolik, G.R. et al. | 2000
- 1463
-
Steam chemical reactivity of Be pebbles and Be powderAnderl, R.A. et al. | 2000
- 1468
-
Present status and future prospect of the Russian program for fusion low-activation materialsSolonin, M.I. et al. | 2000
- 1473
-
Waste management for different fusion reactor designsRocco, Paolo et al. | 2000