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A. V. Beznosov D. V. Davydov A. G. Meluzov D. I. Khokhlov Yu. I. Orlov Yu. D. Levchenko 《Atomic Energy》2000,89(5):863-867
The hydrodynamics of the flow part of variants of a water-based design of a liquid-metal target is investigated from the standpoint of its meeting the requirements. Investigations of the measurement of the velocity fields in the region of heat release of the liquid-metal target and also of the effect of variations of certain geometric characteristics of the target on the hydrodynamics in this region are performed. The optimal values of the individual geometric parameters of the target were determined from the results of this work and conclusions are drawn concerning whether or not the target structure meets the requirements as a whole. 5 figures. 相似文献
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157.
V. A. Gorokhov N. S. Gryaznov D. A. Davydov A. G. Ioltukhovskii Yu. I. Kazennov V. K. Kapyshev E. A. Medvedeva A. V. Minaev V. N. Tebus V. N. Frolov A. K. Shikov N. V. Shishkov V. G. Kovalenko A. V. Marachev Yu. S. Strebkov 《Atomic Energy》2000,89(2):638-645
The development, performed in the 1980s–1990s, of models of tritium breeding zones for blankets of thermonuclear reactors, based on the use of ceramic lithium-containing materials, is described. 5 figures, 1 table. 相似文献
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159.
Takahashi H. Yokoi K. Yano K. Fukuda D. Nakazawa M. Kishimoto S. Hasegawa K. 《IEEE transactions on nuclear science》2001,48(6):2317-2320
Conventional microstrip gas chambers (MSGCs) have encountered many difficulties, such as limited gas gain and sparking damages. We propose a new multigrid-type MSGC (M-MSGC) to overcome some of these difficulties. Additional grid strips are inserted between the anode and the cathode in this new type of MSGC. Gaps between these strips are chosen to be as small as 10 μm where one can expect an efficient removal of the surface charge. With the existence of other strips with lower potentials than the anode, the field strength around the neighboring grid to the anode strip is not as high as the conventional small-gap MSGCs. The contribution of the surface streamer to the damage is greatly suppressed because the electric field parallel to the surface is screened by the intermediate grid electrodes. However, additional electrodes also screen all the electric field of the upper part of the substrate, and we cannot observe induced signals from the backside of the substrate. To overcome that difficulty, we propose another signal readout method using a patterning approach. Floating pads are placed close to the cathode strip on the surface of the M-MSGC, and the induced charges are read out via the pads. If the area of the pads is sufficiently large and the positive charges are moving toward the pads, the backside electrodes can sense the induced charge. Collected charges on the pads are leaked through the surface resistance. The backside signal through 2.3-mm-thick glass readout of the position along the cathode strips is successfully confirmed through experimental results 相似文献
160.
P. Cousinou C. Lavarenne D. Biron M. Douchet J. P. Grouiller N. Thiollay E. Guillou 《Nuclear Engineering and Design》2001,208(2)
As enrichment of the fuel has become higher than the limits used at the designing stages, it seemed necessary to consider fuel depletion during irradiation to guarantee the criticality safety for relatively high enriched fuels transportation, storage or reprocessing. This burnup credit will make it possible to use the devices for spent fuels which are initially relatively high enriched. For that purpose, a method was developed considering: (i) partial Uranium-and-Plutonium burnup credit in the criticality studies, and (ii) a conservative assumption concerning the axial profile; this actinides-only method was supported by an experimental program called HTC. The method was accepted by the French Safety Authority. Moreover, in order to reduce again the calculated values of the reactivity for irradiated fuels, a French working group was set up in 1997 to define a conservative method which enables industrial companies to take burnup credit into account with some of the fission products and using a more precise profile. The work of this group has been divided into four tasks related to: the determination of (i) the composition of the fuel, (ii) a conservative profile, (iii) a conservative irradiation history, and (iv) the calculation scheme. This work is also supported by experimental programs related to the validation of the fission products effects, in terms of reactivity. 相似文献