LA-ICP-MS测定单颗粒氨基膦酸螯合树脂中的铀分布北大核心CSCD

以利用氨基膦酸螯合树脂从湿法磷酸(WPA)中回收铀为研究背景,对单颗粒氨基膦酸螯合树脂中铀分布进行研究,得到以下结论:确定激光剥蚀电感耦合等离子体质谱仪(LA-ICP-MS)最佳的激光频率为6 Hz、束斑直径为44μm、能量密度为6 J/cm^(2)。选择吸附饱和的树脂和洗脱完全的树脂分别作为吸附和淋洗过程的外标,对其进行均匀性测试,吸附饱和树脂中铀含量的相对标准偏差为3.87%(n=9),洗脱完全树脂中铀含量的相对标准偏差为3.52%(n=9),均一性良好。利用LA-ICP-MS对氨基膦酸螯合树脂中的铀进行原位微区分析,结果表明:铀在树脂上的吸附过程是由外向内逐渐完成,淋洗过程是由外向内逐渐完成,树脂内外铀浓度逐渐均匀统一,最终达到吸附饱和和淋洗完全。     

一种医用放射性铼一氨基膦酸化合物及其制备方法

本发明公开了一种标记率高、稳定性好的医用放射性铼-氨基膦酸化合物及制备方法。本发明的制备方法特点是：在反应器中加入适量反应配体、抗氧化剂、保护剂、放射性铼和还原剂，调节反应体系的pH值在一定范围，在适宜的温度条件下反应一段时间，即得到所需产物。铼氨基膦酸化合物可望用于骨肿瘤放射性诊治。     

铜镍矿样中铂和钯的离子交换预富集中子活化分析研究

在铂族元素中子活化分析中,应用溶剂萃取和磺酸型阳离子交换树脂相结合的方法,分离富集铜镍矿样中铂、钯的化学前处理流程,并对与该流程结合的中子活化方法进行了概述。各项相关参数均表明该方法可用于铜镍矿样中的铂钯分析。     

新型冠醚-膦酸锆材料的制备及其对锶吸附性能研究

为高效分离锶元素,本文采用直接反应插层的方法将4-氨基苯并-18-冠-6引入α相磷酸锆层间获得新型冠醚@膦酸锆复合材料（D-AM-ZrP）。通过控制反应过程中无机磷与有机膦的比例获得具有花状形貌及有序结构的D-AM-ZrP。该材料可有效的结合α-ZrP与4-氨基苯并-18-冠-6的优势,在复杂体系中对Sr²⁺具有良好的吸附性和选择性,在弱酸性条件下对Sr²⁺的吸附容量达到136.42 mg·g^-1,优于未插层的α-ZrP(28.17 mg·g^-1)。     

二苯基二硫代膦酸对镅和稀土元素萃取行为的研究

研究了二苯基二硫代膦酸（DPDTPI）/二甲苯溶液在HClO4-NaClO4体系中对镅和13种稀土元素的萃取行为,测定了各元素的分配比。结果表明,DPDTPI对镅和其它13种稀土元素的萃取能力较弱,但镅与铕的分离因数达到4.4。     

高吸附活性硅胶的合成及其对锆的选择分离

以水玻璃和盐酸为原料,通过添加表面活性剂制备出高比表面、高吸附活性的硅胶.用BET,DTA-TGA,IR,XRD,TEM等手段对硅胶的结构和性能进行了表征.结果表明,合成硅胶的适宜工艺条件为:水玻璃浓度4%,盐酸浓度5 mol/L,表面活性剂浓度5%,老化时间1 h,煅烧温度600 ℃.该硅胶的比表面积可达998 m2/g,对锆的静态吸附量可达32.6 mg/g,吸附分配系数为56.1 ml/g.     

153Sm标记二膦酸配体及其在羟基磷灰石上的吸附

制备了新的伯胺二膦酸类配体ABDP(4-氨基-1-羟丁基-1，1-二膦酸)和2-AEDP(2-氨基-亚乙基-1，1-二膦酸)的^153Sm标记物，研究其标记条件及体外性质。实验表明，使用^153Sm标记两个配体，其标记率均可以达到95％以上，增加配体量可以提高标记率和稳定性，通过研究标记物在羟基磷灰石(HA)上的吸附可以看出，^153Sm—ABDP在HA上的吸附率较高，提示它可能有较好的骨吸附。     

取代基对二烷基二硫代膦酸分离三价镧系和锕系元素的影响

初步研究了取代基对二烷基二硫代膦酸分离三价镧系和锕系元素的影响。分别以取代基为正辛基、1-甲基庚基、2-乙基己基、2,4,4-三甲基戊基的4种二烷基二硫代膦酸为萃取剂,煤油为稀释剂,测定水相酸度、萃取剂浓度对几种萃取剂萃取示踪量Am（Ⅲ）和Eu（Ⅲ）的影响。结果表明除二正辛基二硫代膦酸萃取示踪量Eu（Ⅲ）外,以lgD对pH作图得到斜率接近3的直线,以lgD对lgc（（HA）2）作图得到斜率接近2的直线。取代基为正辛基、1-甲基庚基、2-乙基己基、2,4,4-三甲基戊基的4种二烷基二硫代膦酸萃取示踪量Am（Ⅲ）的pH1/2分别为2.31、2.56、2.58、3.14;取代基为1-甲基庚基、2-乙基己基、2,4,4-三甲基戊基的3种二烷基二硫代膦酸萃取示踪量Eu（Ⅲ）的pH1/2分别为3.95、4.01、4.42。取代基对二烷基二硫代膦酸萃取Am（Ⅲ）和Eu（Ⅲ）的能力有明显影响,萃取能力按取代基为正辛基、1-甲基庚基、2-乙基己基、2,4,4-三甲基戊基的顺序依次减小,与几种萃取剂的酸性电离常数大小趋势相同,但它们萃取分离示踪量Am（Ⅲ）和Eu（Ⅲ）的分离系数SFAm/Eu则无明显差异。     

钯在氢同位素分离和纯化工艺中的应用

在迄今所知的金属-氢体系中，钯氢体系的同位素效应最强，因此，钯被广泛用于氢同位素处理工艺中。文章简述了钯氢体系的同位素效应，综述了钯及其合金在氢同位素分离和纯化工艺中的主要应用及其发展。     

Separation of Transplutonium and Rare-Earth Elements by Extraction with Di-isodecyl Phosphoric Acid from DTPA Solution

The distribution ratio Df and the separation factor β for Nd(III) to Am(III) were studied in DIDPA-DTPA systems to determine optimum conditions for applying DIDPA to the TALSPEAK type extraction process to separate transplutonides from lanthanoids in the partitioning of high-level waste of nuclear fuel reprocessing.

Extraction of lanthanoids from 0.05–0.1 M DTPA-1 M lactic acid (pH 3.0) aqueous solution into 0.2–0.3 M DIDPA in DIPB gives the separation factor of 20 revealing practicability of this system in the partitioning. The nature of diluent affects greatly Df, and DIPB proved to be the most appropriate one for the separation of transplutonides from lanthanoids. The presence of lactic acid in the aqueous phase improved the extraction kinetics in DIDPA-DTPA system.     

Effect of Platinum Group Elements on Denitration of High-Level Liquid Waste with Formic Acid

High-level liquid waste (HLW) from nuclear fuel reprocessing containing platinum group elements could be denitrated effectively with formic acid, and the solution indicated neutral even after the addition of excess formic acid. Platinum group elements, rhodium above all, were found to decompose formic acid and the action was more effective in the decomposition of excess formic acid in HLW. When HLW did not contain platinum group elements, both of unaltered nitric and formic acids remained after addition of stoichiometric amount of formic acid, leaving the solution slightly acidic. Excess formic acid in HLW not containing platinum metals was decomposed almost completely by irradiation with ⁶⁰Co γ-rays up to 2×10⁸R.     

Numerical Simulation for Chemical Reactions of Actinide Elements in Aqueous Nitric Acid Solution

A computer code REACT incorporating 30 rate equations of reactions, i.e. radiolytic formation and decomposition of HNO₂, redox and disproportionation reactions, was developed to simulate behavior of actinide elements in the aqueous nitric acid solution. Main aspects of REACT code were explained briefly and then calculated results were compared with reported data to evaluate the model in the systems of radiolytic accumulation of HNO₂, stabilization process of Pu solution. The study showed that some radiolytic products other than HNO₂ would play a significant role and should be taken into account for precise simulation of very slow valency change of Pu in the neat Pu solution particularly with high radiation power density. Some examples of calculation were also shown for systems of reduction of Pp and Np by uranous or HAN and oxidation of Np (V) to Np (VI).     

乙异羟肟酸用于Purex流程中Np/U的分离

研究了新型无盐试剂乙异羟肟酸在Purex流程Np/U分离中的应用。乙异羟肟酸是亲水性有机配位体 ,3 0℃下在水和 3 0 %TBP/煤油中的饱和浓度分别为 5 5 2 8g/L和 4 5g/L ;实验证明 :乙异羟肟酸能很好地络合Np(Ⅳ )并形成亲水性络合物 ,从而能把Np(Ⅳ )从 3 0 %TBP中反萃入水相。另外乙异羟肟酸还能将Np(Ⅵ )还原至难以萃取的Np(Ⅴ )。而乙异羟肟酸的存在对U(Ⅵ )在 3 0 %TBP的萃取的影响相对较小。因此 ,乙异羟肟酸可以用来从含U ,Np的 3 0 %TBP中选择性地反萃Np;基于这些实验结果 ,对乙异羟肟酸在Purex流程中可能的应用作了探讨。     

乙异羟肟酸改善Purex流程铀产品中U-Pu的分离

研究采用新的无盐络合剂乙异羟肟酸（ＡＨＡ）来改善Ｐｕｒｅｘ流程铀线Ｕ－Ｐｕ分离。萃取及洗涤体系中Ｐｕ（Ⅳ）及Ｕ（Ⅵ）的分配实验结果表明：ＡＨＡ能够很好地络合Ｐｕ（Ⅳ）,它既能抑制水相中Ｐｕ（Ⅳ）被３０％ＴＢＰ／ＯＫ萃取,又能有效地把萃取到３０％ＴＢＰ／ＯＫ中的Ｐｕ（Ⅳ）洗涤到水相。同时,ＡＨＡ的存在不影响３０％ＴＢＰ／ＯＫ对Ｕ（Ⅵ）的萃取。     

Extraction of Lanthanoids (III) with Di-isodecyl Phosphoric Acid from Nitric Acid Solution

The extraction of Nd(III) with di-isodecylphosphoric acid was studied and compared with that by di(2-ethylhexyl) phosphoric acid. DIDPA possesses higher D_f values in a strong acid medium but poorer separation factors against lanthanoids(III) than that of DEHPA. Mono (2-ethylhexyl) phosphoric acid increased extraction of Nd(III) with DIDPA in a similar manner as in the case of DEHPA, by a factor of D_f of 10³.

The extraction of Sr(II) was also investigated with DIDPA, which showed a maximum of D_f at pH 5.0. Results showed that DIDPA is a promising extractant for the partitioning of the high level liquid waste.