共查询到20条相似文献,搜索用时 0 毫秒
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Yu. N. Zuev Yu. A. Kulinich V. D. Lartsev S. I. Strel'tsov Yu. I. Chernukhin L. I. Men'kin B. G. Polosukhin V. I. Tokarev S. Yu. Mitrofanov 《Atomic Energy》2002,92(3):246-253
The results of measurements of the efficiency of a 6LiD thermal-to-fast neutron converter for neutrons from DT and 6LiT fusion reactions with energy 14 MeV in the experimental channel of an IVV-2M reactor are presented. The first experimental estimates of the conversion coefficients for the corresponding fusion reactions are obtained: K
D 2.11·10–4 and K
Li 1.36·10–4. The value found in this work for the total conversion coefficient 3.47·10–4 is approximately 1.7 times greater than the previously measured value and about 20% greater than the maximum computed estimate for a 6LiD converter.An experimental apparatus with a 6LiD converter in an IVV-2M channel is an accessible, comparatively inexpensive, and unique (for now) source of 14 MeV neutrons that can provide continuous and approximately uniform irradiation of Ø4 × 20 cm samples by neutrons from DT and 6LiT fusion 2.7·1010 sec–1·cm–2 for a comparatively long time (500 h). 相似文献
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The main objective of this paper is to study the effects of various spacer grid models on the neutronic parameters of a VVER-1000 reactor. Specifically, the data of the nuclear power plant at the Bushehr site, which is of a VVER-1000 type, will be studied. Three models, representing the spacer grids along the fuel assemblies are presented. These three models are the homogeneous and the heterogeneous local spacer grid models and the shroud spacer grid model. In the homogeneous and the heterogeneous models, the spacer grids are considered at their actual locations in the axial direction. The only difference between the two models is that in the homogeneous model, the spacer grids are homogenized with the coolant while in the heterogeneous model, the spacer grids are modeled around the fuel cells at their exact axial positions. In the shroud model, the spacer grids are modeled in the shroud region containing the coolant and are not necessarily placed at their appropriate axial positions. 相似文献
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The kinetic parameters, α the coupling coefficient and
gt the mean neutron transit time have been determined using a reactor oscillator on the coupled-core of the Queen Mary College research reactor. By using correlation techniques it has proved possible to use detectors small enough to be inserted in the fuel tanks. It is shown that the simplified Baldwin model with one-group diffusion theory is inadequate to describe the kinetic behaviour and the experimentally-determined parameters are dependent upon the positioning of the detectors. 相似文献
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The effects of using different low enriched uranium fuels, having same uranium density, on the kinetic parameters of a material test research reactor were studied. For this purpose, the original aluminide fuel (UAlx-Al) containing 4.40 gU/cm3 of an MTR was replaced with silicide (U3Si-Al and U3Si2-Al) and oxide (U3O8-Al) dispersion fuels having the same uranium density as of the original fuel. Simulations were carried out to calculate prompt neutron generation time, effective delayed-neutron fraction, core excess reactivity and neutron flux spectrum. Nuclear reactor analysis codes including WIMS-D4 and CITATION were used to carry out these calculations. It was observed that both the silicide fuels had the same prompt neutron generation time 0.02% more than that of the original aluminide fuel, while the oxide fuel had a prompt neutron generation time 0.05% less than that of the original aluminide fuel. The effective delayed-neutron fraction decreased for all the fuels; the decrease was maximum at 0.06% for U3Si2-Al followed by 0.03% for U3Si-Al, and 0.01% for U3O8-Al fuel. The U3O8-Al fueled reactor gave the maximum ρexcess at BOL which was 21.67% more than the original fuel followed by U3Si-Al which was 2.55% more, while that of U3Si2-Al was 2.50% more than the original UAlx-Al fuel. The neutron flux of all the fuels was more thermalized, than in the original fuel, in the active fuel region of the core. The thermalization was maximum for U3O8-Al followed by U3Si-Al and then U3Si2-Al fuel. 相似文献
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《Annals of Nuclear Energy》2001,28(1):63-78
Using a model of the IBR-2 reactor based on the block structure with z-transformation of constants and experimentally determined feedback parameters, power transition processes have been evaluated at different values of the parameters of the automatic power regulator (APR). It has been shown that, at regular reactivity excitations, the best transition processes correspond to higher APR rates at the elimination of the APR smoothing unit. The recommendations are given for choosing the APR parameters when at normal operation of the IBR-2 reactor there are random reactivity excitations. 相似文献
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