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                             97 results found
no title author magazine year volume issue page(s) type
1 Absorption and desorption of hydrogen from inert gas mixtures with a Zr3Al2 particle bed Mitsuishi, Nobuo
 1995
 28 C p. 362-366
5 p.
 article
2 Activation analyses for the different options considered in the US ITER blanket trade-off study Khater, Hesham Y
 1995
 28 C p. 589-595
7 p.
 article
3 Analysis of tritium behaviour and recovery from a water-cooled Pb17Li blanket Malara, C
 1995
 28 C p. 299-312
14 p.
 article
4 Analysis of tritium extraction from liquid lithium by permeation window and solid gettering processes Takeda, Tetsuaki
 1995
 28 C p. 278-285
8 p.
 article
5 Analysis of tritium transport in irradiated beryllium Cho, Seungyon
 1995
 28 C p. 265-270
6 p.
 article
6 Analytical formulae for estimating damage rate in the final mirrors of laser inertial fusion energy reactors based on the uncollided neutron flux Youssef, Mahmoud Z
 1995
 28 C p. 648-657
10 p.
 article
7 An assessment of disruption erosion in the ITER environment Hassanein, A
 1995
 28 C p. 27-33
7 p.
 article
8 Application of amorphous filler metals in production of fusion reactor high heat flux components Kahn, B.A
 1995
 28 C p. 119-124
6 p.
 article
9 Assessing braze quality in the actively cooled Tore Supra phase III outboard pump limiter Nygren, R.E
 1995
 28 C p. 113-118
6 p.
 article
10 Author index of volume 28 1995
 28 C p. 777-784
8 p.
 article
11 Benchmark analyses of the ENDF/B-VI, EFF-1 and EFF-2 beryllium data evaluations for neutron transport calculations Fischer, U
 1995
 28 C p. 624-635
12 p.
 article
12 Benchmark experiment on copper with D-T neutrons for verification of neutron transport and related nuclear data of JENDL-3.1 Konno, Chikara
 1995
 28 C p. 745-752
8 p.
 article
13 Benchmark experiment on copper with D-T neutrons for verification of secondary gamma-ray data in JENDL-3.1 Maekawa, F
 1995
 28 C p. 753-761
9 p.
 article
14 Calorimetric measurements of nuclear heating in small probes of plasma-facing materials Kumar, A
 1995
 28 C p. 699-707
9 p.
 article
15 Changes in the microstructure and density of Li2O during irradiation in BEATRIX-II, phase I Takahashi, T
 1995
 28 C p. 271-277
7 p.
 article
16 Characterization of nuclear transmutations in materials irradiation test facilities Gomes, Itacil C
 1995
 28 C p. 610-617
8 p.
 article
17 Characterization of TFTR shielding penetrations of ITER relevance in D-T neutron field Kumar, Anil
 1995
 28 C p. 492-503
12 p.
 article
18 Characterization of the source neutrons produced by the Frascati Neutron Generator Pillon, M
 1995
 28 C p. 683-688
6 p.
 article
19 Coating effect on plasma-driven permeation of hydrogen in iron Shu, W.M
 1995
 28 C p. 131-135
5 p.
 article
20 Comparison of three-dimensional neutronics calculations for a fusion breeder with large channels Huang, J.H
 1995
 28 C p. 618-623
6 p.
 article
21 Conceptual design of neutron diagnostic systems for fusion experimental reactor Iguchi, T
 1995
 28 C p. 689-698
10 p.
 article
22 Conceptual study of the cryocascade for pumping, separation and recycling of ITER torus exhaust Mack, A
 1995
 28 C p. 319-323
5 p.
 article
23 Cost-effectiveness of new polynated materials for shielding against fusion neutrons Karni, Yonathan
 1995
 28 C p. 559-565
7 p.
 article
24 Critical heat flux multiplier of subcooled flow boiling for non-uniform heating conditions in a swirl tube Inasaka, Fujio
 1995
 28 C p. 53-58
6 p.
 article
25 Design, fabrication and testing of a helium cooled module Baxi, C.B
 1995
 28 C p. 22-26
5 p.
 article
26 Design, materials and R&D issues of innovative thermal contact joints for high heat flux applications Federici, G
 1995
 28 C p. 34-43
10 p.
 article
27 Detection of subcooled boiling heat transfer regimes up to critical heat flux by accelerometric equipment Celata, G.P
 1995
 28 C p. 44-52
9 p.
 article
28 Development of fusion fuel cycle technology at the Tritium Laboratory Karlsruhe: the experiment CAPRICE Glugla, M
 1995
 28 C p. 348-356
9 p.
 article
29 Effect of selection of calculation parameters in discrete ordinate code DOT3.5 for analyses of fusion blanket integral experiments in JAERI-USDOE collaborative program Oyama, Y
 1995
 28 C p. 636-641
6 p.
 article
30 Efficient HTO reduction using a ZrFeMn alloy Ghezzi, F
 1995
 28 C p. 367-372
6 p.
 article
31 Erosion yield of graphite and B4C irradiated by high flux deuterium beams Isobe, M
 1995
 28 C p. 170-175
6 p.
 article
32 Estimates of the effect of a plasma momentum flux on the free surface of a thin film of liquid metal Morley, Neil B
 1995
 28 C p. 176-180
5 p.
 article
33 Estimation of the tritium production and inventory in beryllium Shimakawa, Satoshi
 1995
 28 C p. 215-219
5 p.
 article
34 Evaluation of cooling concepts and specimen geometries for high heat flux tests on neutron irradiated divertor elements Linke, J
 1995
 28 C p. 72-80
9 p.
 article
35 Evaluation of the prediction uncertainty in tritium production based on results from experiments on an Li2O annular blanket surrounding a 14 MeV simulated line source Youssef, M.Z
 1995
 28 C p. 673-682
10 p.
 article
36 Experimental investigation of neutron and photon penetration and streaming through iron assemblies Freiesleben, H
 1995
 28 C p. 545-550
6 p.
 article
37 Experimental simulation of plasma high heat flux-materials interaction during ITER disruption Kozhevin, V.M
 1995
 28 C p. 157-161
5 p.
 article
38 Experiment and analysis of induced radioactivity in large SS-316 stainless steel shielding material bombarded with 14 MeV neutrons Ikeda, Y
 1995
 28 C p. 449-456
8 p.
 article
39 FENDL data testing for beryllium, lead, iron and copper Fischer, U
 1995
 28 C p. 437-445
9 p.
 article
40 Fuel cycle design for SEAFP project Murdoch, D.K
 1995
 28 C p. 341-347
7 p.
 article
41 High quality actively cooled plasma-facing components for fusion Nygren, R.E
 1995
 28 C p. 3-12
10 p.
 article
42 High Z limiter test in TEXTOR: thermal response and post-mortem analysis Tanabe, T
 1995
 28 C p. 13-21
9 p.
 article
43 Impact of surface phenomena in metals on hydrogen isotope permeation Yamawaki, M
 1995
 28 C p. 125-130
6 p.
 article
44 Integral experiment on effects of large opening in fusion reactor blanket on tritium breeding using annular geometry Konno, Chikara
 1995
 28 C p. 708-715
8 p.
 article
45 Integral test of Kerma data for SS-304 stainless steel in the D-T fusion neutron environment Ikeda, Y
 1995
 28 C p. 769-775
7 p.
 article
46 Luminescence observation from lithium oxide under neutron irradiation Tanaka, Satoru
 1995
 28 C p. 292-298
7 p.
 article
47 Measurements of D—T neutron induced radioactivity in plasma-facing materials and their role in qualification of activation cross-section libraries and codes Kumar, A
 1995
 28 C p. 596-609
14 p.
 article
48 Measurements of 14 MeV neutron multiplication in spherical beryllium shells von Möllendorff, U
 1995
 28 C p. 737-744
8 p.
 article
49 Measurements of tokamak fusion test reactor D-T radiation shielding efficiency Kugel, H.W
 1995
 28 C p. 534-544
11 p.
 article
50 Measurement techniques for fusion blanket neutronics experiments Oyama, Y
 1995
 28 C p. 716-723
8 p.
 article
51 Mechanisms for extreme heat transfer conditions in water-cooling of fusion reactor components Lekakh, B.M
 1995
 28 C p. 59-62
4 p.
 article
52 Membrane pumping technology for helium and hydrogen isotope separation in the fusion reactor Pistunovich, V.I
 1995
 28 C p. 336-340
5 p.
 article
53 Modeling of surface reaction in tritium release from lithium ceramics and its comparison with transient experiments Yamaki, Daiju
 1995
 28 C p. 286-291
6 p.
 article
54 Neutronic performance of two European breeder-inside-tube (BIT) blankets for DEMO: the helium-cooled ceramic LiAlO2 with Be multiplier and the water-cooled liquid Li17Pb Petrizzi, L
 1995
 28 C p. 642-647
6 p.
 article
55 Neutronics and shielding results of the US International Thermonuclear Experimental Reactor blanket trade-off study Sawan, M.E
 1995
 28 C p. 551-558
8 p.
 article
56 Neutronics assessment for the ARIES advanced reactor studies El-Guebaly, L.A
 1995
 28 C p. 658-664
7 p.
 article
57 Neutronics of a D-Li neutron source. An overview Gomes, Itacil C
 1995
 28 C p. 724-729
6 p.
 article
58 Nuclear analysis for the inertially confined direct drive laser fusion power reactor SIRIUS-P Sawan, M.E
 1995
 28 C p. 665-672
8 p.
 article
59 Nuclear data for fusion: a view from two meetings Mann, Frederick M
 1995
 28 C p. 446-448
3 p.
 article
60 Numerical simulation of heat transfer and fluid flow of a non-equilibrium argon plasma jet with confined wall Kunugi, T
 1995
 28 C p. 63-71
9 p.
 article
61 Numerical simulation of strong evaporation and condensation for plasma-facing materials Kunugi, Tomoaki
 1995
 28 C p. 162-169
8 p.
 article
62 On order reduction in hydrogen isotope distillation models Sarigiannis, D.A
 1995
 28 C p. 406-412
7 p.
 article
63 Operation of a simulated non-steady tokamak fuel loop using the tritium systems test assembly Konishi, S
 1995
 28 C p. 258-264
7 p.
 article
64 Operation of the tokamak fusion test reactor tritium systems during initial tritium experiments Anderson, J.L
 1995
 28 C p. 209-214
6 p.
 article
65 Performance of a palladium membrane reactor using an Ni catalyst for fusion fuel impurities processing Willms, R.Scott
 1995
 28 C p. 397-405
9 p.
 article
66 Practical-scale tests of cryogenic molecular sieve for separating low-concentration hydrogen isotopes from helium Willms, R.Scott
 1995
 28 C p. 386-391
6 p.
 article
67 Pre-evaluation of fusion shielding benchmark experiment Hayashi, Katsumi
 1995
 28 C p. 525-533
9 p.
 article
68 Progress in tritium retention and release modeling for ceramic breeders Raffray, A.R
 1995
 28 C p. 240-251
12 p.
 article
69 Pulsed activation analyses of the ITER blanket design options considered in the blanket trade-off study Wang, Q
 1995
 28 C p. 579-588
10 p.
 article
70 Quantification of design margins and safety factors based on the prediction uncertainty in tritium production rate from fusion integral experiments of the USDOE/JAERI collaborative program on fusion blanket neutronics Youssef, M.Z
 1995
 28 C p. 457-478
22 p.
 article
71 Radiation shielding analysis of a large helical device Handa, Hiroyuki
 1995
 28 C p. 515-524
10 p.
 article
72 Radioactivity computation of steady state and pulsed fusion reactor operation Attaya, Hosny
 1995
 28 C p. 571-578
8 p.
 article
73 Radioactivity measurements of ITER materials using the TFTR D-T neutron field Kumar, Anil
 1995
 28 C p. 415-428
14 p.
 article
74 Radiological dose calculations for the particle beam fusion accelerator upgrade (PBFA-U) Khater, H.Y
 1995
 28 C p. 730-736
7 p.
 article
75 Shielding analysis for the ITER divertor and vacuum-pumping ducts Sawan, M.E
 1995
 28 C p. 429-436
8 p.
 article
76 Sorbent materials for fusion reactor tritium processing Toci, F
 1995
 28 C p. 373-377
5 p.
 article
77 Study of fusion shielding neutronics in experiments with an assembly containing voids Konakov, S.A
 1995
 28 C p. 566-570
5 p.
 article
78 Summary of experiments and analyses from the JAERI/USDOE Collaborative Program on Fusion Blanket Neutronics Maekawa, Hiroshi
 1995
 28 C p. 479-491
13 p.
 article
79 The analytical glove-box in the tritium magazine of ETHEL Engelmann, U
 1995
 28 C p. 324-328
5 p.
 article
80 The bulk shielding benchmark experiment at the Frascati Neutron Generator (FNG) Batistoni, P
 1995
 28 C p. 504-514
11 p.
 article
81 Thermal cycling and isothermal tests on black-coated specimens Windelband, B
 1995
 28 C p. 90-96
7 p.
 article
82 Thermomechanical investigation on divertor supports for fusion experimental reactor: hydraulic experimental results Arai, T
 1995
 28 C p. 103-112
10 p.
 article
83 Thermomechanical study of a new concept for a beryllium-protected high heat flux component Merola, M
 1995
 28 C p. 97-102
6 p.
 article
84 The role of sidestream recycle in hydrogen isotope separation and column cascade design Sherman, Robert H
 1995
 28 C p. 392-396
5 p.
 article
85 TIARA analysis of tritium inventory in Li2O Billone, Michael C
 1995
 28 C p. 313-318
6 p.
 article
86 Time-dependent tritium inventories and flow rates in fuel cycle components of a tokamak fusion reactor Kuan, W
 1995
 28 C p. 329-335
7 p.
 article
87 Tritium evacuation performance of a large oil-free reciprocating pump Hayashi, T
 1995
 28 C p. 357-361
5 p.
 article
88 Tritium handling and processing experience at the Tritium Systems Test Assembly Anderson, J.L
 1995
 28 C p. 183-189
7 p.
 article
89 Tritium/hydrogen barrier development Hollenberg, G.W
 1995
 28 C p. 190-208
19 p.
 article
90 Tritium permeation barriers for fusion technology Perujo, A
 1995
 28 C p. 252-257
6 p.
 article
91 Tritium recovery from liquid metals Moriyama, H
 1995
 28 C p. 226-239
14 p.
 article
92 Tritium recovery from lithium, based on a cold trap Sze, Dai-Kai
 1995
 28 C p. 220-225
6 p.
 article
93 Tritium retention in candidate next-step protection materials: engineering key issues and research requirements Federici, G
 1995
 28 C p. 136-148
13 p.
 article
94 Tritium sorption by cement and subsequent release Ono, Futaba
 1995
 28 C p. 378-385
8 p.
 article
95 Two-dimensional impinging jet cooling of high heat flux surfaces in magnetic confinement fusion reactors Inoue, A
 1995
 28 C p. 81-89
9 p.
 article
96 Vacuum UV spectroscopy of armor erosion from plasma gun disruption simulation experiments Rockett, P.D
 1995
 28 C p. 149-156
8 p.
 article
97 Validation and improvement of Fe, Cr, Ni nuclear data in bulk shield benchmark experiments Santamarina, A
 1995
 28 C p. 762-768
7 p.
 article
                             97 results found
 
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