硝酸铀酰

无载体钍-234（UX1）的制备Ⅰ.乙醚萃取阴离子交换法自硝酸铀酰中分离无载体的UX1

Preparation of carrier-free thorium-234 ( ux_1 ) & i. the separation of carrier-free ux_1 from uranyl nitrate by ether EXTRACTION-ANION exchange method

8102、7601对大鼠急性硝酸铀酰中毒的解救

8102 and 7601 as antidotes for acute uranyl nitrate intoxication in rats

大鼠中毒硝酸铀酰（500μg／鼠）后给予不同剂量8102（0～100mg／kg），测定尿铀排出量及肾铀蓄积量。

METHODS After 8102 was administrated at various doses ( 0 ~ 100 mg / kg ) to rats poisoned by 500 μ g / rat Uranyl Nitrate , we determine Uranium in urine and in kidneys .

本文研究了一种新型烷基膦酸酯萃取剂（5208）从人工配制的模拟溶液中萃取硝酸铀酰及分离杂质的性能，并与现在广泛使用的TBP萃取剂作了对比。

The extraction properties of uranyl nitrate from simulated solutions and its separation from impurities with a new type alkylphosphonate ester extractant were studied in the paper . It was compared with the widely used TBP .

均匀腐蚀试验结果表明，在选定的腐蚀条件下，321不锈钢样品在960h内，其表面光洁度无明显变化，腐蚀速率小于0.04g/m2穐，在低酸度的硝酸铀酰溶液中耐蚀。

The uniform corrosion results showed that the corrosion rate of 321 stainless steel was less than 0.04g / m2 . h , and the visible change of surface smoothness was not observed through 960h . It was perfect corrosion-resisting in obtained conditions .

硝酸铀酰-硝酸-磷酸三丁酯体系的反萃取动力学研究

Kinetic Studies on the Stripping of Uranyl Nitrate in TBP-HNO_3 System

321不锈钢在低酸度硝酸铀酰溶液中的腐蚀特性

Corrosion Behavior of 321 Stainless Steel in Low-Acidity Uranium Nitrate Solution

火焰原子发射法测定硝酸铀酰中的微量铯

Determination of trace cesium in uranyl nitrate by flame atomic emission spectrophotometry

双取代单酰胺与硝酸铀酰萃合物的制备与表征

Preparation and Characterization of Extracted Species of Uranyl Nitrate with Disubstituted Monoamides

硝酸铀酰与缩二脲的固体配合物的合成及性质

Solid coordination compound of uranyl nitrate with biuret

甲醛光化还原硝酸铀酰制取硝酸铀（Ⅳ）的研究

Studies on the photochemical reduction of uranyl nitrate to produce uranium (ⅳ) nitrate by formaldehyde

求得萃取硝酸铀酰过程的平衡常数及反应的热力学函数。

The extraction constant of uranium ( VI ) with pyridines and the reaction enthalpy were calculated .

系列芳基烷基不对称亚砜硝酸铀酰配合物的合成及研究

Synthesis and studies on a series of u ( ⅵ ) complexes with ligand unsym - alkylaryl sulfoxides

核磁共振法测定烷基膦酸-硝酸铀酰体系的配位体交换反应速度常数及热力学函数

Determination of ligand exchange rate constants and its thermodynamic functions in alkyl phosphonate-uo_2 ( no_3 ) _2 systems by 1H-NMR

提出了溶液比重和硝酸铀酰与硝酸浓度的关系式。

Thus the relations between densities of the solution and concentrations of uranyl nitrate and nitric acid are provided for .

在流化床中硝酸铀酰脱硝－还原制备二氧化铀的试生产

The test and production in preparing uranium dioxide from uranyl nitrate in the fluidized bed by the denitration and reduction

合成了系列双取代单酰胺萃取剂，利用萃取方法获得了与硝酸铀酰的萃合物。

A series of disubstituted monoamides extractants were synthesized and their extracted species with uranyl nitrate were obtained by extraction method .

为了研究水溶液中铀酰离子与碳钢、321不锈钢的界面行为，在硝酸铀酰和碳酸铀酰钠溶液中进行了均匀腐蚀和电化学测量试验。

The uniform corrosion and electrochemical measurement test have been used to investigate interface behavior of uranyl ion in aqueous solution in forming on the surface of carbon steel and 321 stainless steel .

用腐蚀电化学法研究了321不锈钢在有溶解氧的硝酸铀酰溶液中的腐蚀电化学特性，测量了电极的腐蚀电位、腐蚀电流密度。

The electrochemical corrosion behavior study has been performed to investigate 321 stainless steel in uranium nitrate solutions of the dissolved and saturated oxygen . The corrosion potential and corrosion current density were obtained .

本文提出了硝酸铀酰和硝酸在水相和有机相的偏克分子体积、相体积变化关联为溶质浓度的函数。

In this paper are recommended the values of partical molar volumes of uranyl nitrate and nitric acid in aqueous phase and organic phase , and the change of phase volume was correlated as a function of the solute concentrations .

本文报道了硝酸铀酰、氯化铀酰和硝酸钍与冠醚DB18CR6、B15CR5、18CR6通过溶剂反应制得的8个固体络合物，对这些络合物进行了熔点测定、元素成分测定和红外光谱分析。

Reported herein are eight solid complex compounds obtained by reactions of uranyl nitrate , uranyl chloride and thorium nitrate with macro-cyclic polyethers dibenzo-18-crown-6 , benzo-15-crown-5 and 18-crown-6 in polar solvents . The complex compounds have been characterized by elemental analysis , melting points and infrared spectro-metric analysis .

介绍了在硝酸铀溶液核临界安全实验装置上进行不同浓度铀溶液的临界实验时，用倒数外推方法确定硝酸铀酰的核临界质量的过程；

The article presents the process of calculating the critical mass of nitride uranium solution by the reciprocal extrapolation method when doing the criticality safety experiment for different concentration of nitride uranium solution in the nitride solution nuclear criticality safety experimental facility .