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1.
The separation equation for predicting the deuterium recovery from H–D gas mixture by thermal diffusion in the cocurrent-flow Frazier schemes has been derived. The degrees of separation, as well as separation factors, for deuterium recovery in the Frazier scheme of cryogenic wall thermal-diffusion columns were estimated, with the use of the experimental data obtained by Arita et al. and the transport coefficients correlated in the previous work. Considerable enhancement in deuterium recovery is achievable if the number of thermal diffusion columns in a Frazier scheme is continuously increased, especially for the operation under higher volume flow rate and/or lower operating pressure.  相似文献   

2.
The effect of column number on thermal diffusion in the countercurrent-flow Frazier scheme with total sum of column heights (L = Nh) fixed, has been investigated. The equations, which may be employed to predict the proper column number for the best performance are derived. Considerable improvement in performance is obtainable if the scheme is constructed with the proper number of thermal diffusion columns, instead of using a single column with column height L (N = 1, h = L). This is because that increasing the column height in a thermal diffusion column though increases the effective separation section, the increment in performance with the increase of column height will decrease, and finally the separation efficiency reaches a limiting value.  相似文献   

3.
The effect of column number on the enrichment of heavy water from water-isotope mixture in the countercurrent-flow Frazier scheme with total sum of column heights L fixed, has been investigated. The equations, which may be employed to predict the optimal column numbers for maximum performances, have been derived. Considerable improvement in removal rate is obtainable if the scheme is constructed with the optimal column number of thermal diffusion columns, especially for larger flow rate with smaller L, or smaller flow rate with larger L.  相似文献   

4.
Deuterium recovery from water–isotopes mixture using thermal diffusion can be improved by employing the branch column device, instead of single column devices, with the same total column length. The remixing effect due to convection currents in a thermal diffusion column for heavy water enrichment is thus reduced and separation improvement increases when the flow rate or the total column length increases. The improvement in separation can reach about 50% for the numerical example given.  相似文献   

5.
A separation theory for the recovery of deuterium from water–isotopes mixture in the Frazier scheme of concentric-tube thermal diffusion columns with a tight fitting wire spiral, having a diameter equal to the annular spacing, wrapped on the entire inner tube, has been developed. Equations of the optimal wire angle of inclination for maximum separation, maximum production rate and minimum column height have been derived. Considerable improvement in performance is obtainable if the wire spiral is employed in the column at the optimum inclined wire-angle, instead of the absence of wire spiral, so that the convection strength can be properly reduced and controlled, resulting in suppression of the undesirable remixing effect while still preserving the desirable cascading effect.  相似文献   

6.
The modeling simulation for the separation of H-D gas mixture in batch-type concentric-tube thermal diffusion columns have been analyzed from the transport equation coupled with the application of mass balance. The most important assumption is that the concentrations of H2, HD and D2 are locally equilibrium at every points in the column as H2 + D2 ↔ 2HD. The concentration distribution equation was derived and the concentration difference between the bottom and top ends of the column could be estimated. The degree of separation and separation factor for recovery of deuterium from H-D gas mixture in the batch-type cryogenic-wall thermal diffusion column were estimated.  相似文献   

7.
The separation equations for predicting the recovery of deuterium from H-D gas mixture in a concentric-tube thermal diffusion column with transverse sampling streams, have been derived. The effects of column length, volume flow rate and operating pressure on the performance have been discussed. The degrees of separation, as well as separation factors, for deuterium recovery in the cryogenic-wall thermal diffusion columns were estimated, with the use of the transport coefficients correlated in the previous work from the experimental data obtained by Arita et al. The separation efficiencies obtained in feeding by transverse sampling streams are rather lower than those achieved by middle feeding.  相似文献   

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