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用间歇电解还原法研究了在有机玻璃电解槽中阳极镀铂钛网在UO2(NO3)2-HNO3-N2H5NO3-H2O体系中的耐腐蚀情况。研究结果表明:在无隔膜电解还原时,镀铂钛网上的Pt的腐蚀速率极低(<2.5×10-2μm/a),而在以阳离子交换膜作隔膜的电解还原中,镀铂钛网上的Pt有明显的腐蚀,其腐蚀速率为5.7μm/a。对这两种情况下Pt的腐蚀速率明显差别的原因进行了分析讨论。 相似文献
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~(210)Po是~(210)Po-Be中子源的原料。~(210)Po活度数据是计算中子产额的关键依据。我们在~(210)Po-Be中子源研制和生产过程中,是用量热计测量~(210)Po原料的放射性活度。但是,在秦山核电站启动中子源的中子产额测量中,发现中子源的~(210)Po投料量热测量数据与做成中子源后,其中~(210)Po量热测量数据有比较大的差异。表1是用同一台量热计在投料和做成源条件下的测量 相似文献
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~(210)Po是~(210)Po-Be中子源的原料。~(210)Po活度数据是计算中子产额的关键依据。我们在~(210)Po-Be中子源研制和生产过程中,是用量热计测量~(210)Po原料的放射性活度。但是,在秦山核电站启动中子源的中子产额测量中,发现中子源的~(210)Po投料量热测量数据与做成中子源后,其中~(210)Po量热测量数据有比较大的差异。表1是用同一台量热计在投料和做成源条件下的测量 相似文献
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研制了一台用于α、β核素测量的大功率量热计,量热计样品池尺寸空间为直径75mm、高120mm.性能测试表明,该量热计功率测量范围为1~300 W,当样品热功率不小于10 W时,测量精度优于1.0%. 相似文献
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本文在振动搅拌槽中,研究了UO_2(NO_3)_2-HNO_3-N_2H_5NO_3(H_2O)/30%TBP(煤油)体系的水相电解液组分浓度对U(Ⅵ)电解还原速率的影响。根据实验所得数据,经回归分析得到反应动力学微分方程 式中速度常数k一般说是温度的函数。25℃时,k=0.00187。在实验浓度范围内,U(Ⅵ)还原速率随U(Ⅵ)浓度升高而增大,表观反应级数为0.75级;而[N_2H_5~+]及[HNO_3]影响不大,反应级数近于0。 相似文献
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本文介绍我们研制的中子吸收剂量量热计的原理、结构及其测量系统。测量了池式研究用反应堆的中子吸收剂量并得到满意的结果。该量热计轻便、简单、测量迅速而准确。已精确知道比热数值的其它吸收材料均可采用本设计。 相似文献
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Two series of experiments were performed to determine the conditions of cell operation that produce sufficient excess heat to be useful for the production of energy. In the first series, the results from a differential temperature analysis of identical light- and heavy-water electrochemical cells were too ambiguous and, thus, not suitable for evaluating excess heat effects. In the second series, two Pd-D/LiOD-saturated D2O/Pt cells were operated at current densities between 12.5–500 mA/cm2 in a constant-heatloss-rate twin calorimeter for 460 hours. Water loss measurements during the experiments indicated that the recombination reaction (2D2 + O2 2D2O) did not occur. The D/Pd ratio was determined gravimetrically during the experiments. No excess heat was found within the sensitivity (0.13 W, 0.082 W/cm3 of Pd, 0.013 W/cm2 of Pd) and precision (±0.3 W) of the calorimeter. 相似文献
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Charles E. Scott Elias Greenbaum Gordon E. Michaels John E. Mrochek Eugene Newman Milica Petek Timothy C. Scott 《Journal of Fusion Energy》1990,9(2):115-119
Preliminary tests have been made with electrolytic cells utilizing 0.2N LiOD in D2O as the electrolyte and a palladium cathode surrounded by a wire-wound platinum anode operating at cathode current densities
of 100–400 mA/cm2. The cathodes were swaged to diameters of 2.8 or 5.5 mm with 8.5 cm of active length. The electrolyte temperature was controlled,
heat was removed by flowing water in a cooling jacket, and the cell was insulated. Cooling water and electrolyte temperatures
were measured by thermocouples, and neutron and gamma-ray spectra were recorded. The electrolyte level was periodically monitored
and replenished with D2O. Tests up to 2 weeks in duration were made with no sustained release of energy in excess of the electrical power input,
although there was one period of 12 h when an unaccountable heat excess was observed. In another test, an anomalous neutron
flux was measured during the first few hours that was 3.5 standard deviations above the background. 相似文献
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M. E. Hayden U. Närger J. L. Booth L. A. Whitehead W. N. Hardy J. F. Carolan E. H. Wishnow D. A. Balzarini J. H. Brewer C. C. Blake 《Journal of Fusion Energy》1990,9(2):161-164
We have developed a calorimeter suitable for testing cold fusion electrolytic cells that achieves better than 0.3% accuracy
in absolute energy balance. It uses self-sustained catalytic recombination of the evolved gases and so operates in a completely
closed fashion, and also it has demonstrated insensitivity to temperature gradients in the electrolytic cell. We work with
0.1M LiOD in D2O solutions and with vacuum degassed 99.9% Pd bars whose electrochemical charging curves have been carefully studied prior
to use. The charging rates show a discontinuity betweenx=0.6 andx=0.7 (close to the expected onset of the β phase) whereupon the rates slow considerably andx saturates at about 0.80–0.84 after half a day. Calorimetric studies on these samples have so far shown no excess heat generation
to the 0.3% level for input powers in the 4–18 watt range. 相似文献
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为探究低压低流速条件下的过冷沸腾换热特性,开展本实验研究。通过分析实验中采集的热工参数和可视化图像,探究了沸腾滞后现象、沸腾失稳现象以及沸腾换热特性。实验发现沸腾起始点壁面过热度较高,而沸腾的发生大幅提高了换热系数,因此出现了显著的沸腾滞后现象。实验中较为光滑的加热面可达到较高的过热度,而低压下快速产生的气泡尺寸较大,在较低的热流密度下气液界面发生剧烈变化,使气泡破裂为多个小气泡并成为核化点。在过冷沸腾换热系数的预测中,Dittus-Boelter对流换热关系式不再适用,采用Hallman关系式和Gnielinski关系式计算对流换热系数,并引入壁面过热度对池式沸腾换热系数进行修正,可使过冷沸腾换热系数的预测精度大幅提高。 相似文献
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《Journal of Nuclear Science and Technology》2013,50(10):801-812
For providing background information on the possible vapor explosion in the event of a core disruptive accident of LMFBRs, an experiment was conducted on the film boiling characteristics of liquid metal potassium in association with the Leidenfrost phenomenon. In a steel container filled with Ar gas, K droplets were put on a joule-heated plate of 316-SS or Ta. The behaviors of droplet were observed by a camera and a color VTR through viewports. The experimental conditions were the Ar pressure 1 bar, the initial K temperature 350~760°C, and the plate temperature 900~1,250°C for 316-SS and 1,100~1,600°C for Ta. Stable film boiling known as Leidenfrost phenomenon was observed for a high temperature condition of the plate, whereas an instantaneous break-up of droplet with extensive vaporization occurred for a low temperature. The heat transfer characteristics of film and transition boiling regions were obtained by estimating the heat flux from the volumetric reducing rate of droplet due to vaporization. The results in the film boiling region showed an appreciably good agreement with the prediction based on Bromley's expression combined with the theory of Baumeister et al. The minimum film boiling temperature and heat flux were found to be about 1,300°C and 15 W/cm2, respectively, for a droplet size of 0.15 cm3. 相似文献
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《Journal of Nuclear Science and Technology》2013,50(2):197-201
The terminal solid solubility (TSS) of hydrogen during hydride dissolution/precipitation is determined by differential scanning calorimetry technique for nonirradiated hafnium (Hf) that is used as control rods of light water reactors. The hydrogen concentration in hydrogenated Hf samples ranged from 27 to 300 wt ppm. The reliability of the TSS data obtained for Hf was confirmed using those for Zircaloy-2 (Zry-2) obtained in this study with the literature data, and best-fit equations for the obtained TSS curves for Hf are derived. The TSS for Hf at 573 K, which corresponds to an operational temperature of control rods in boiling water reactors, is in the range of 10–15 wt ppm, and is found to be 1/5–1/7 of the TSS for Zry-2. 相似文献