Atomistic simulation of stacking fault tetrahedra formation in Cu (Unknown)
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In:
Journal of nuclear materials
;
283
, 1
; 773-777
;
2000
-
ISSN:
- Article (Journal) / Print
-
Title:Atomistic simulation of stacking fault tetrahedra formation in Cu
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Contributors:
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Published in:Journal of nuclear materials ; 283, 1 ; 773-777
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Publisher:
- New search for: North Holland Publ. Co.
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Place of publication:Amsterdam
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Publication date:2000
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ISSN:
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ZDBID:
-
Type of media:Article (Journal)
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Type of material:Print
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Language:Unknown
- New search for: 52.55 / 51.40 / 33.81 / 33.80
- Further information on Basic classification
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Keywords:
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Source:
Table of contents – Volume 283, Issue 1
The tables of contents are generated automatically and are based on the data records of the individual contributions available in the index of the TIB portal. The display of the Tables of Contents may therefore be incomplete.
- 1
-
Advances in fusion technologyBaker, Charles C. et al. | 2000
- 10
-
Assessment and selection of materials for ITER in-vessel componentsKalinin, G. et al. | 2000
- 20
-
Interactions between fusion materials R&D and other technologiesKohyama, A. et al. | 2000
- 28
-
The impact of materials selection on long-term activation in fusion power plantsTaylor, N.P. et al. | 2000
- 35
-
Evaluation of hot isostatic pressing for joining of fusion reactor structural componentsIvanov, A.D. et al. | 2000
- 43
-
The status of beryllium technology for fusionScaffidi-Argentina, F. et al. | 2000
- 52
-
Progress and critical issues of reduced activation ferritic-martensitic steel developmentvan der Schaaf, B. et al. | 2000
- 60
-
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
-
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
-
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
-
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