Preparation of113mIn and99mTc-microaggregated human serum albumin for liver scanning

Higher than 90% of^113mIn radioactivity was bound to microaggregates. The liver uptake in mice was (80%) with low lung uptake (1.3%). With respect to^99mTc-microaggregated albumin, the radiochemical yield was higher than 95%. The liver uptake in mice was about (80%) with low lung uptake (1.7%). The stability of the microaggregates was followed for two months.     

113mIn radioisotope generator system

Tin-indium generator systems were made with commercial hydrated zirconium oxide, silica gel and hydrated zirconium oxide prepared by the AMPHLETT method. The adsorption capacity of tin has been determined by both spectrophotometric analysis and gammaspectrometry. Zirconium break-through has been determined and compared with the literature values. The dependence of the adsorption capacity on the particle size has been investigated. The effect of autoclaving on the generator systems has been examined.     

113Sn-113mIn generator with a glass beads column

The adsorption characteristics of ¹¹³Sn(IV) and ^113mIn(III) on glass beads from NaCl solutions have been studied. On the basis of these studies, ¹¹³Sn-^113mIn generator has been prepared by adsorbing ¹¹³Sn on the glass beads column. ^113mIn has been eluted by the 0.16M NaCl solution with pH 3.0, remaining ¹¹³Sn adsorbed on the glass beads. The yield of ^113mIn has been about 73% in the first 6 ml of eluate, while the breakthrough of ¹¹³Sn has been about 0.042%.     

Radiochemical studies on generator eluted113mIn chloride

^113mIn is milked out of a¹¹³Sn-^113mIn generator with dilute hydrochloric acid for use in nuclear medicine. The concentrations of the various impurities like Sn, Zr and their colloidal forms which may trap^113mIn activity have to be initially evaluated before releasing the generator for medicinal use. The authors have evaluated the purity of the^113mIn-chloride obtained from the generators in detail. The possibility of using a mixture of HCl and NaCl as an alternative eluent for^113mIn has also been investigated. It has been observed that this new eluent gives greater yields of^113mIn and renders the final manipulation of isotonicity of indium labelled compounds easy.     

Separation of113mIn from113Sn on an isotope generator with inorganic ionite

A method of preparation of hydrated zirconium oxide suitable for^113mIn generators was elaborated. A good separation of^113mIn from¹¹³Sn was obtained in the course of routine use of generator, with a very small admixture of zirconium in the eluate.     

Purete radiochimique du complexe113 mIn,acide diethylene-triamino pentaacetique

The radiochemical purity of the¹¹³ mIn-DTPA complex is determined by two methods whose principle is different: filtration on ‘Sephadex” gel, and ascending paperchromatography. The two techniques give slightly different values for non-complexed indium; any way less than 5% mean value. They show that the reproducibility of the method used to prepare the compound is satisfactory.      

Methods for radiochemical and radionuclidic purity determination of some99mTc and113mIn radiopharmaceuticals

In order to determine the radiochemical impurities in pertechnetate solution as well as that of unbound^99mTc in its colloid and complex compounds, in indium chloride solution and related compounds, paper chromatography on Whatman No. 1, thin-layer chromatography on silica gel plates, and paper electrophoresis were applied. A simple method for the determination of radionuclidic purity was developed.     

Dünnschichtchromatographie als Hilfsmittel in der Radiochemie. 4. Mitteilung Trennung von 113Sn und 113mIn

Thin-layer chromatography is applied to the separation of ^113mIn from ¹¹³Sn. Different factors influencing migration and separation of the ions are investigated. The method can be used for the examination of the purity of isolated ^113mIn solutions.     

Adsorption of several tracer cations and separation of234Th from238U and113mIn from113Sn on tin dioxide

The uptake of 22 cations at tracer concentrations has been studied over hydrous tin dioxide exchanger material. A granular variety of tin dioxide was prepared from the reaction of tin(IV) chloride with NaOH solution, and the formula of the material was ascertained to be SnO₂·1.7 H₂O. Radiochemical separation of carrier-free²³⁴Th from²³⁸U and^113mIn from¹¹³Sn was achieved over a tin dioxide column. The separated products were of high radionuclidic purity. The overall separation procedures are very simple and quick with quantitative yield.     

Ceric tungstate as sorbent for polyvalent tracer cations and as an ion exchanger for separation of carrier-free95Nb from95Zr and113mIn from113Sn

The uptake of a few polyvalent ions Ca²⁺ Cu²⁺, Zn²⁺, Cd²⁺, UO²⁺, Cr³⁺, Y³⁺, Ce³⁺, Nd³⁺, Sm³⁺, Tb³⁺, Tm³⁺, Yb³⁺, Lu³⁺, Zr⁴⁺, Hf⁴⁺, Sn⁴⁺, Nb⁵⁺, Se⁶⁺, Mo⁶⁺ and W⁶⁺ at very small concentrations has been studied over ceric tungstate exchanger. A good column variety of the material was prepared by mixing ceric sulphate in 2N H₂SO₄ and aqueous solution of sodium tungstate in suitable proportion. The ratio of cerium: tungstate was obtained to be 11. Separation of carrier-free⁹⁵Nb from⁹⁵Zr and^113mIn from¹¹³Sn have been carried out by applying a very simple chemical procedure over the column of ceric tungstate. The -spectrum of separated⁹⁵Nb and^113mIn products were found to be of high radionuclidic purity. The separation procedure took less than 15 min and the yields were close to 100%.     

Separation of no-carrier-added 113,117mSn and 113m,114mIn from alpha particle irradiated natural cadmium target

A natural cadmium foil was irradiated by 42 MeV α-particles to produce ^113,117mSn, ^{111,113m,114m}In simultaneously in the target matrix. After the complete decay of short lived radionuclides, long-lived NCA products were separated sequentially from the bulk cadmium by liquid–liquid extraction using di-(2-ethylhexyl)phosphoric acid (HDEHP) dissolved in cyclohexane as organic phase and HCl as aqueous phase. At the optimum condition, 10^?2 M HCl and 5 % HDEHP, NCA In along with NCA Sn radionuclides (75 %) were separated from the bulk Cd resulting to high separation factors of 2.7 × 10⁴ (D _In/D _Cd) and 500 (D _Sn/D _Cd), respectively. The NCA In was stripped back completely to the aqueous phase by 6 M HCl leaving NCA Sn in the HDEHP phase with a separation factor (D _Sn/D _In) of 3.94 × 10⁶.     

A ready-to-use kit for the preparation of99mTc-phytate for liver scanning

Kits were developed-for the sterile labelling of phytate with^99mTc. The effect of molar ratio of phytate to stannous chloride, pH, dilution of the Sn-phytate with^99mTc-generator eluate, time of incubation, the shelf life of^99mTc-phytate and the storage time of Sn-phytate on the labelling yield of phytate with^99mTc was investigated using paper chromatography and gel chromatography column scanning method (GCS). Organ distribution was performed in rabbits and mice. Excellent human liver scans were obtained.     

115Cd photonuclear production for115Cd−115mIn generator

Production of¹¹⁵Cd by means of photonuclear reaction and preparation of a^115mIn generator, based on the genetic sequence of¹¹⁵Cd^115mIn, were studied. The production rates of¹¹⁵Cd by the¹¹⁶Cd(γ, n)¹¹⁵Cd reaction were determined as a function of the maximum bremsstrahlung energies between 35 and 60 MeV. Then the parent,¹¹⁵Cd, was produced by irradiating about 0.15g of CdO with the bremsstrahlung from a 60 MeV-150 μA electron beam. After the parent in the Cd ₄ ²⁻ form was adsorbed on the Dowex 1x8 resin column, the daughter was eluted with a physiologic saline adjusted to pH 1. The generator was milked over a period of 3 days, during which time about 900 ml of eluent were allowed to flow through the column. Even after the milkings were repeated 15 times with 60 ml of the eluent, no¹¹⁵Cd was found in the^115mIn fractions (the detection limit of inactive cadmium: 0.02 μg).     

Comparative evaluation of four different99mTc-sulfur colloid kits used for liver scanning

The distribution of four different commercially available A, B, C, D kits (^99mTc-sulfur colloid) for hepatoimaging was compared in mice by organ radioassay and in rabbits for blood clearance. The distribution of kits A and C (single step kits) was assessed in the human by blood clearance, external liver, spleen measurement, and scintillation camera imaging. Kit A reaches a high concentration in liver within 15–20 minutes with relatively high surrounding tissue background, and superior spleen scintiphotos. However, when kit C was used, a high activity concentration in the liver was reached within 10–15 minutes with low tissue background and faint visualization of the radiotracer in the spleen. Blood clearance of the four^99mTc-sulfur colloids was determined in rabbits. The data obtained indicated that the four hepatoagents exhibit rapid blood clearance but the initial decrease of blood activity curve of kit D was relatively faster than the other three hepatic agents. The biodistribution is similar for the four^99mTc-S-colloids but the blood retained higher activity residue using kit A compared with others. The formation of^99mTc-sulfur colloid using kits B, D (multistep kits) involves many steps after the addition of^99mTcO ₄ ^– to the reagent. These procedures are time consuming, required facilities at the medical institutions and give rise to the radiation exposure. While single step kits A and C have the same diagnostic value, the use of kit C allows a reduction of absorbed radiation, which may be useful in the liver exploration in children.     

Beta-branching fraction of117Cd isomers and it branching of117mIn

Using radiochemical and gamma spectrometric technique the branching fractions in the beta decay of¹¹⁷Cd isomers and the internal transition branching of^117mIn have been established. The beta branching fraction of^117gCd^117gIn was obtained as 0.86±0.06 and the value of^117mCd^117gIn was found to be less than 1%. The internal transitin branching and the isomer cross-section ratio were obtained as 0.31±0.02 and 0.197±0.002, respectively. From the measured isomer cross-section ratio the spin cut-off parameter was evaluated, which agreed with the value reported in the literature.     

《113》轴向取向稀土超磁致伸缩材料的制备与性能

利用低温度梯度水平炉, 成功地生长了113轴向取向的稀土超磁致伸缩材料, 该材料在低磁化场下具有很高磁致伸缩应变, 在10 MPa压应力、 80 kA*m-1磁场下的磁致伸缩应变λ=1540×10-6. 113轴向取向材料的高磁致伸缩应变来源于材料良好的取向; 定向生长的大晶粒; 施加磁场时较多的可转动磁矩.     

Adsorption of Freon 113

Summary The adsorption of Freon 113 (1,1,2 trichloro-1,2,2 trifluoroethane) at 260–310 K on Graphon was measured and compared with the adsorption of krypton at 104–120 K on the same surface. The adsorption isotherms, and resulting thermodynamics, for both adsorbates were similar over the entire pressure range studied. Surface area analysis of the data suggests that the Freon molecule occupies approximately 2.5 times the area of the krypton molecule on Graphon. Further, the Freon molecules are hindered in their rotational freedom on this surface at these temperatures, with their dipole axes aligning perpendicular to the surface of the Graphon.

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Zusammenfassung Es wurde die Adsorption von Freon 113 (1,1,2 Trichlor-1,2,2 Trifluoräthan) an Graphon bei 260–310 °K gemessen und mit der Adsorption von Krypton bei 104–120 °K auf der gleichen Grenzfläche gemessen. Die Adsorptionsisothermen und die daraus resultierenden thermodynamischen Daten waren für beide Adsorbate im gesamten untersuchten Druckbereich ähnlich. Eine Analyse der Daten legt nahe, daß ein Freonmolekiil annähernd das 2,5fache der Fläche eines Kryptonmoleküls auf Graphon beansprucht. Es ist anzunehmen, daß die Freonmoleküle auf dieser Oberfläche und bei diesen Temperaturen in ihren Rotationsfreiheitsgraden gehindert sind und ihre Dipolachsen senkrecht zur Oberfläche liegen.

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With 9 figures and 2 tables