nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('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. |
artikel |
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. |
artikel |
3 |
Analysis of tritium behaviour and recovery from a water-cooled Pb17Li blanket
|
Malara, C |
|
1995 |
28 |
C |
p. 299-312 14 p. |
artikel |
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. |
artikel |
5 |
Analysis of tritium transport in irradiated beryllium
|
Cho, Seungyon |
|
1995 |
28 |
C |
p. 265-270 6 p. |
artikel |
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. |
artikel |
7 |
An assessment of disruption erosion in the ITER environment
|
Hassanein, A |
|
1995 |
28 |
C |
p. 27-33 7 p. |
artikel |
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. |
artikel |
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. |
artikel |
10 |
Author index of volume 28
|
|
|
1995 |
28 |
C |
p. 777-784 8 p. |
artikel |
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. |
artikel |
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. |
artikel |
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. |
artikel |
14 |
Calorimetric measurements of nuclear heating in small probes of plasma-facing materials
|
Kumar, A |
|
1995 |
28 |
C |
p. 699-707 9 p. |
artikel |
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. |
artikel |
16 |
Characterization of nuclear transmutations in materials irradiation test facilities
|
Gomes, Itacil C |
|
1995 |
28 |
C |
p. 610-617 8 p. |
artikel |
17 |
Characterization of TFTR shielding penetrations of ITER relevance in D-T neutron field
|
Kumar, Anil |
|
1995 |
28 |
C |
p. 492-503 12 p. |
artikel |
18 |
Characterization of the source neutrons produced by the Frascati Neutron Generator
|
Pillon, M |
|
1995 |
28 |
C |
p. 683-688 6 p. |
artikel |
19 |
Coating effect on plasma-driven permeation of hydrogen in iron
|
Shu, W.M |
|
1995 |
28 |
C |
p. 131-135 5 p. |
artikel |
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. |
artikel |
21 |
Conceptual design of neutron diagnostic systems for fusion experimental reactor
|
Iguchi, T |
|
1995 |
28 |
C |
p. 689-698 10 p. |
artikel |
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. |
artikel |
23 |
Cost-effectiveness of new polynated materials for shielding against fusion neutrons
|
Karni, Yonathan |
|
1995 |
28 |
C |
p. 559-565 7 p. |
artikel |
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. |
artikel |
25 |
Design, fabrication and testing of a helium cooled module
|
Baxi, C.B |
|
1995 |
28 |
C |
p. 22-26 5 p. |
artikel |
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. |
artikel |
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. |
artikel |
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. |
artikel |
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. |
artikel |
30 |
Efficient HTO reduction using a ZrFeMn alloy
|
Ghezzi, F |
|
1995 |
28 |
C |
p. 367-372 6 p. |
artikel |
31 |
Erosion yield of graphite and B4C irradiated by high flux deuterium beams
|
Isobe, M |
|
1995 |
28 |
C |
p. 170-175 6 p. |
artikel |
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. |
artikel |
33 |
Estimation of the tritium production and inventory in beryllium
|
Shimakawa, Satoshi |
|
1995 |
28 |
C |
p. 215-219 5 p. |
artikel |
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. |
artikel |
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. |
artikel |
36 |
Experimental investigation of neutron and photon penetration and streaming through iron assemblies
|
Freiesleben, H |
|
1995 |
28 |
C |
p. 545-550 6 p. |
artikel |
37 |
Experimental simulation of plasma high heat flux-materials interaction during ITER disruption
|
Kozhevin, V.M |
|
1995 |
28 |
C |
p. 157-161 5 p. |
artikel |
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. |
artikel |
39 |
FENDL data testing for beryllium, lead, iron and copper
|
Fischer, U |
|
1995 |
28 |
C |
p. 437-445 9 p. |
artikel |
40 |
Fuel cycle design for SEAFP project
|
Murdoch, D.K |
|
1995 |
28 |
C |
p. 341-347 7 p. |
artikel |
41 |
High quality actively cooled plasma-facing components for fusion
|
Nygren, R.E |
|
1995 |
28 |
C |
p. 3-12 10 p. |
artikel |
42 |
High Z limiter test in TEXTOR: thermal response and post-mortem analysis
|
Tanabe, T |
|
1995 |
28 |
C |
p. 13-21 9 p. |
artikel |
43 |
Impact of surface phenomena in metals on hydrogen isotope permeation
|
Yamawaki, M |
|
1995 |
28 |
C |
p. 125-130 6 p. |
artikel |
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. |
artikel |
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. |
artikel |
46 |
Luminescence observation from lithium oxide under neutron irradiation
|
Tanaka, Satoru |
|
1995 |
28 |
C |
p. 292-298 7 p. |
artikel |
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. |
artikel |
48 |
Measurements of 14 MeV neutron multiplication in spherical beryllium shells
|
von Möllendorff, U |
|
1995 |
28 |
C |
p. 737-744 8 p. |
artikel |
49 |
Measurements of tokamak fusion test reactor D-T radiation shielding efficiency
|
Kugel, H.W |
|
1995 |
28 |
C |
p. 534-544 11 p. |
artikel |
50 |
Measurement techniques for fusion blanket neutronics experiments
|
Oyama, Y |
|
1995 |
28 |
C |
p. 716-723 8 p. |
artikel |
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. |
artikel |
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. |
artikel |
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. |
artikel |
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. |
artikel |
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. |
artikel |
56 |
Neutronics assessment for the ARIES advanced reactor studies
|
El-Guebaly, L.A |
|
1995 |
28 |
C |
p. 658-664 7 p. |
artikel |
57 |
Neutronics of a D-Li neutron source. An overview
|
Gomes, Itacil C |
|
1995 |
28 |
C |
p. 724-729 6 p. |
artikel |
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. |
artikel |
59 |
Nuclear data for fusion: a view from two meetings
|
Mann, Frederick M |
|
1995 |
28 |
C |
p. 446-448 3 p. |
artikel |
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. |
artikel |
61 |
Numerical simulation of strong evaporation and condensation for plasma-facing materials
|
Kunugi, Tomoaki |
|
1995 |
28 |
C |
p. 162-169 8 p. |
artikel |
62 |
On order reduction in hydrogen isotope distillation models
|
Sarigiannis, D.A |
|
1995 |
28 |
C |
p. 406-412 7 p. |
artikel |
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. |
artikel |
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. |
artikel |
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. |
artikel |
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. |
artikel |
67 |
Pre-evaluation of fusion shielding benchmark experiment
|
Hayashi, Katsumi |
|
1995 |
28 |
C |
p. 525-533 9 p. |
artikel |
68 |
Progress in tritium retention and release modeling for ceramic breeders
|
Raffray, A.R |
|
1995 |
28 |
C |
p. 240-251 12 p. |
artikel |
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. |
artikel |
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. |
artikel |
71 |
Radiation shielding analysis of a large helical device
|
Handa, Hiroyuki |
|
1995 |
28 |
C |
p. 515-524 10 p. |
artikel |
72 |
Radioactivity computation of steady state and pulsed fusion reactor operation
|
Attaya, Hosny |
|
1995 |
28 |
C |
p. 571-578 8 p. |
artikel |
73 |
Radioactivity measurements of ITER materials using the TFTR D-T neutron field
|
Kumar, Anil |
|
1995 |
28 |
C |
p. 415-428 14 p. |
artikel |
74 |
Radiological dose calculations for the particle beam fusion accelerator upgrade (PBFA-U)
|
Khater, H.Y |
|
1995 |
28 |
C |
p. 730-736 7 p. |
artikel |
75 |
Shielding analysis for the ITER divertor and vacuum-pumping ducts
|
Sawan, M.E |
|
1995 |
28 |
C |
p. 429-436 8 p. |
artikel |
76 |
Sorbent materials for fusion reactor tritium processing
|
Toci, F |
|
1995 |
28 |
C |
p. 373-377 5 p. |
artikel |
77 |
Study of fusion shielding neutronics in experiments with an assembly containing voids
|
Konakov, S.A |
|
1995 |
28 |
C |
p. 566-570 5 p. |
artikel |
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. |
artikel |
79 |
The analytical glove-box in the tritium magazine of ETHEL
|
Engelmann, U |
|
1995 |
28 |
C |
p. 324-328 5 p. |
artikel |
80 |
The bulk shielding benchmark experiment at the Frascati Neutron Generator (FNG)
|
Batistoni, P |
|
1995 |
28 |
C |
p. 504-514 11 p. |
artikel |
81 |
Thermal cycling and isothermal tests on black-coated specimens
|
Windelband, B |
|
1995 |
28 |
C |
p. 90-96 7 p. |
artikel |
82 |
Thermomechanical investigation on divertor supports for fusion experimental reactor: hydraulic experimental results
|
Arai, T |
|
1995 |
28 |
C |
p. 103-112 10 p. |
artikel |
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. |
artikel |
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. |
artikel |
85 |
TIARA analysis of tritium inventory in Li2O
|
Billone, Michael C |
|
1995 |
28 |
C |
p. 313-318 6 p. |
artikel |
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. |
artikel |
87 |
Tritium evacuation performance of a large oil-free reciprocating pump
|
Hayashi, T |
|
1995 |
28 |
C |
p. 357-361 5 p. |
artikel |
88 |
Tritium handling and processing experience at the Tritium Systems Test Assembly
|
Anderson, J.L |
|
1995 |
28 |
C |
p. 183-189 7 p. |
artikel |
89 |
Tritium/hydrogen barrier development
|
Hollenberg, G.W |
|
1995 |
28 |
C |
p. 190-208 19 p. |
artikel |
90 |
Tritium permeation barriers for fusion technology
|
Perujo, A |
|
1995 |
28 |
C |
p. 252-257 6 p. |
artikel |
91 |
Tritium recovery from liquid metals
|
Moriyama, H |
|
1995 |
28 |
C |
p. 226-239 14 p. |
artikel |
92 |
Tritium recovery from lithium, based on a cold trap
|
Sze, Dai-Kai |
|
1995 |
28 |
C |
p. 220-225 6 p. |
artikel |
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. |
artikel |
94 |
Tritium sorption by cement and subsequent release
|
Ono, Futaba |
|
1995 |
28 |
C |
p. 378-385 8 p. |
artikel |
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. |
artikel |
96 |
Vacuum UV spectroscopy of armor erosion from plasma gun disruption simulation experiments
|
Rockett, P.D |
|
1995 |
28 |
C |
p. 149-156 8 p. |
artikel |
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. |
artikel |