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Abstract  

A very simple method for the determination of bromine in selenium has been developed. The manual handling of the irradiated selenium sample is reduced to a minimum. After the placing of the sample into the dissolution flask, no further manipulation is necessary except for the transference of the82Br counting sample from the dissolution apparatus to the scintillation counter.82Br is very selectively absorbed on columns prepared from surface-rich porous glass powder coated with silver nitrate. More than 95% of the bromine is absorbed on the columns and the decontamination factor for75Se is better than 10−7. Commercially available selenium brands with bromine contents down to 0.025 ppm have been analyzed.

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Abstract  

Silver-impregnated silica gels prepared by us have very good adsorption characteristics for both organic and inorganic radioiodine. Under the operating conditions applied, the adsorption capacity is up to 200 mg I g–1 and the utilization of silver on the sorbent is higher than 90%. The adsorbent can be used to remove iodine from nuclear fuel reprocessing off-gases and from air cleaning systems of nuclear reactors.

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Abstract  

The phase diagram of the binary AgNO3–CsNO3 system was constructed using differential thermal analysis (DTA) technique in the range 300–700 K. The apparatus is described briefly. The results exhibit a congruently melting compound CsNO3·AgNO3 (m.p.=453 K) characterized by two allotropic varieties and , an incongruently melting compound AgNO3·CsNO3 (m.p.=450 K) with three forms , and , two eutectics (16 mol% CsNO3, 442 K and 32.5 mol% CsNO3, 445 K) and a peritectic (38mol% CsNO3, 450 K). The occurrence of the transitions of intermediates was confirmed by X-ray diffraction at variable temperatures. The phase diagram exhibits also two plateaus at 429 K and 435 K corresponding to the phase transitions of CsNO3 and AgNO3, respectively.

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Abstract  

To study the coherence of thermodynamic data of the AgNO3-LiNO3 -RbNO3 ternary system, phase diagram of the binary system AgNO3 -LiNO3 has been obtained between 303 and 550 K by direct and differential thermal analysis technique. This system is characterized by an eutectic point (25% mol. LiNO3 , 445±1 K) and a plateau due to the solid-solid transition in AgNO3 at 434±1 K. In the solid state the solubility of each component in the other seems to be nil or negligible (no more than a few percents). Using other thermodynamic data, the excess properties of the binary liquid (AgNO3 - LiNO3 ) were calculated at 623 K.

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restoration. Next, the teeth were immersed into a solution of 50 wt% ammoniacal silver nitrate (Fisher Scientific, USA) (pH = 9.5) for 24 h, followed by 8 h in photo-developing solution (Eastman Kodak Co, Rochester, NY, USA) [ 27 ]. Then, specimens were washed

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Abstract  

The retention of 131I on ceramic rod coated with silver nitrate followed by coating with a polyurethane membrane to be applied in brachytherapy was studied. The concentration of silver nitrate (20 g/l), the volume of 131I as a sodium iodide solution (100 µl), the pH of the reaction mixture (pH 9) etc., were optimized to get a maximum uptake on the ceramic rod. The concentration of coating solution (5%, polyurethane in tetrahydrofuran) was also optimized to obtain a minimum leaching of 131I activity in normal saline solution. After coating with a polyurethane membrane, the 131I absorbed on the ceramic rod exhibited low leachability (0.03%). This method can be applied for the preparation of 125I interstitial sources to be used in eye and prostate cancer therapy.

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Abstract  

Two portable devices for the radiometric analysis of industrial water are described. Chlorides are precipitated by a known volume of standard silver nitrate labelled with110mAg; the decrease of activity is proportional to the amount of ionic chlorine. Determination of dissolved oxygen is achieved by dissolution of radioactive thallium, and the activity of the effluent is directly related to the concentration of oxygen.

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Abstract  

A simple method is described for the determination of radioruthenium. A solution containing radioruthenium is placed in a conical flask with small amounts of sulfuric acid, silver nitrate, and potassium periodate. The mouth of the flask is covered with a thin polyethylene film, which is fixed with a soft rubber band, and the flask is heated for 2 hrs on a water bath. Radioruthenium is oxidized to tetroxide, evaporated by steam-distillation, and fixed quantitatively on the inner surface of the polyethylene film as a firm black stain. Contamination ratios of other nuclides are under 2·10−4.

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Successful application of somatic hybridization in sunflower breeding is limited by low regeneration percentage from fusion products. The effect of pre-treatment media composition on shoot regeneration from electrofusion products of wild and cultivated sunflower was investigated in this paper, with the aim to determine if there is room for improvement of the existing regeneration protocols in order to make them less genotype-dependent. Protoplasts isolated from hypocotyls of two inbred lines of cultivated sunflower were electrofused with mesophyll protoplasts of H. mollis and H. maximiliani . The regeneration was induced only on calluses that were grown on the media with low auxin and high cytokinin contents during the development of calluses from microcalluses (pre-treatment), with silver nitrate as a medium component. Regeneration from fusion products was induced by treatment with a high concentration of TDZ or 2,4 D for a short period of time.

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Abstract  

A 10–5 mol 1–1 solutiopn of idododecane in n-dodecane was used to simulate a kerosene sample from nuclear fuel reporcessing. Several methods were developed for the quantitative removal of iodododecane from the n-dodecane solution. Decomposition to elemental iodine was achieved either by washing with hyperazeotropic nitric acid or by exposure to a high-intensity UV-light. Quantitative removal of iodododecane from n-dodecane was achieved by absorption on silver nitrate impregnated materila or on activated charcoal, which was impregnated with potassium thiocyanate or 1,4-diazabicyclo-2,2,2-octance. The reaction could be accelerated by stirring or heating. Thus a quantitative absorption of idododecane could be achieved within a few minutes. The results of the experiments were confirmed by absorption of iodoorganic compounds from kerosene of the Karl sruhe nuclear fuel reprocessing plant (WAK) on the tested material.

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