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  • 1
    Electronic Resource
    Electronic Resource
    Chemical study on the separation and purification of promethium-147 (1989)
    Springer
    Journal of radioanalytical and nuclear chemistry 130 (1989), S. 21-37 
    Details
    ISSN: 1588-2780
    Source: Springer Online Journal Archives 1860-2000
    Topics: Chemistry and Pharmacology , Energy, Environment Protection, Nuclear Power Engineering
    Notes: Abstract A chemical process for the separation of147Nd/147Pm from fission products of synthetic radioactive waste solution has been developed. The process includes: (1) denitration, (2) removal of high concentration of uranium by 30% TBP/kerosene extraction, (3) removal of95Nb,103Ru,137Cs and part of90Sr by 50% TBP/dodecane extraction, (4) separation of147Nd/147Pm from part of90Sr and95Zr by oxalic acid precipitation, and (5) removal of144Ce by mixture of 0.4M D2EHPA and 0.2M TBP extraction. Experimental results indicate that the recovery of147Nd/147Pm in the final separated solution is about 90%. The purification of147Nd and147Pm from some other rare earth elements, viz.153Sm,154Eu and144Ce was further investigated by using a Dowex 50W×8 ion-exchanger. Parameters of flow rate, eluent concentration and pH were examined. The results show that the recovery and radionuclide purity of147Nd plus147Pm under the present separation conditions are 77.8% and 98.6% for diethylenetriaminepentaacetic acid (DTPA) and 87.3% and 99.5% for nitrilotriacetic acid (NTA), respectively.
    Type of Medium: Electronic Resource
    URL: http://dx.doi.org/10.1007/BF02037697
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  • 2
    Electronic Resource
    Electronic Resource
    Determinations of boron and chloride in highly radioactive sample solution (1988)
    Springer
    Journal of radioanalytical and nuclear chemistry 123 (1988), S. 421-442 
    Details
    ISSN: 1588-2780
    Source: Springer Online Journal Archives 1860-2000
    Topics: Chemistry and Pharmacology , Energy, Environment Protection, Nuclear Power Engineering
    Notes: Abstract To meet the requirements of NUREG-0737 and Atomic Energy Council, Republic of China, the post accident sampling systems have recently been established at Taiwan power stations. The lead shielded cask for transportation of grab liquid sample from sampling station to the off-site backup laboratory was designed, based on the functions of sample taken vertically from sample station and the horizontal transferring of sample vial to the cell of backup laboratory. Spectrophotometric, titrimetric and ion chromatographic methods were studied and comparisons made for the analyses of boron and chloride. It can be concluded that suppressed ion chromatography with remote handling in a lead cell is best for determining boron and chloride simultaneously in a high radioactive sample solution. The method with high accuracy, less interference and rapid analysis is considered and discussed.
    Type of Medium: Electronic Resource
    URL: http://dx.doi.org/10.1007/BF02034908
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    Paper (German National Licenses)
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  • 3
    Electronic Resource
    Electronic Resource
    Preparation of 68Ge/68Ga Generator with a Binary Ga/Ag Electrodepositions as Solid Target (2000)
    Springer
    Journal of radioanalytical and nuclear chemistry 245 (2000), S. 25-30 
    Details
    ISSN: 1588-2780
    Source: Springer Online Journal Archives 1860-2000
    Topics: Chemistry and Pharmacology , Energy, Environment Protection, Nuclear Power Engineering
    Notes: Abstract A novel type of a binary Ga/Ag alloy electrodeposited on silver substrate as a solid target was developed. It was successfully used for the preparation of 68Gc/68Ga generator. The deposition was carried out in an alkali solution containing gallium, silver and certain electrolytes at controlled current and ambient temperature so that the quality of the deposits was proved to be suited for target irradiation. The yield of 68Ge with proton bombardment on this deposits via the 69Ga(p,2n) reaction was assessed. The chemical process for providing millicuries 68Ge/68Ga generator using a generic tin dioxide as an adsorbent was also established. It was revealed from long-term elution tests that approximately 60–70% of 68Ga could be eluted from the generator column with 4 ml of 1.0M HCl per elution, and high radio- and chemical purities of the eluates were quite satisfactory for application purposes.
    Type of Medium: Electronic Resource
    URL: http://dx.doi.org/10.1023/A:1006714022513
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  • 4
    Electronic Resource
    Electronic Resource
    Chemical process study on the separation of gadolinium-153 (1992)
    Springer
    Journal of radioanalytical and nuclear chemistry 160 (1992), S. 505-515 
    Details
    ISSN: 1588-2780
    Source: Springer Online Journal Archives 1860-2000
    Topics: Chemistry and Pharmacology , Energy, Environment Protection, Nuclear Power Engineering
    Notes: Abstract Three routes of chemical processes for a multicurie production of153Gd have been established and demonstrated using one gram of Eu2O3 as target irradiated under a neutron flux of 5.0·1013n/cm2/s for 42 days. Simulated experiments with the synthetic solution containing appropriate amounts of Gd and Eu and the tracers were performed throughout the established chemical process for verifying its feasibility and the effectiveness. The results show that a high specific activity of 100 Ci/g Gd with the desired radionuclide purity of greater than 99.999% of153Gd can be obtained. The chemical yield and processing time among the processes were compared.
    Type of Medium: Electronic Resource
    URL: http://dx.doi.org/10.1007/BF02037126
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  • 5
    Electronic Resource
    Electronic Resource
    Study on the preparation of a137Cs/137mBa radionuclide generator (1992)
    Springer
    Journal of radioanalytical and nuclear chemistry 160 (1992), S. 517-527 
    Details
    ISSN: 1588-2780
    Source: Springer Online Journal Archives 1860-2000
    Topics: Chemistry and Pharmacology , Energy, Environment Protection, Nuclear Power Engineering
    Notes: Abstract 137mBa has been applied successfully to dynamic studies for diagnosis in nuclear medicine for a long time. A variety of inorganic exchangers have been employed for the separation of137mBa from its parent137Cs. In the present study, cupric cobaltic ferrocyanide and amorphous zirconyl phosphate were synthesized and compared for use in a137Cs/137mBa generator. The results show that the former can adsorb137Cs more efficiently and provide high elution yield of137mBa with greater than 99.99% radionuclide purity. A new generator involving multimillicuries of137mBa, in connection with a computerized detection system, has been constructed.
    Type of Medium: Electronic Resource
    URL: http://dx.doi.org/10.1007/BF02037127
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  • 6
    Electronic Resource
    Electronic Resource
    A Simple and Rapid Method for the Preparation of 87Y/87mSr Generator (2000)
    Springer
    Journal of radioanalytical and nuclear chemistry 245 (2000), S. 31-36 
    Details
    ISSN: 1588-2780
    Source: Springer Online Journal Archives 1860-2000
    Topics: Chemistry and Pharmacology , Energy, Environment Protection, Nuclear Power Engineering
    Notes: Abstract A simple and efficient process for the preparation of 87Y/87mSr generator with adsorption chromatography on α-Fe2O3 was developed. A 0.25 g pallet of natural SrCl2 was employed as a solid target which was irradiated at INER TR30/15 cyclotron. After irradiation the target was dissolved into a saline solution and adjusted with HCl/NaOH to a pH of 6.3. This solution was then passed directly through the column (1 cm⊘×4 cm), loaded with appropriate amounts of α-Fe2O3, at a flowrate of 1.0 ml/min for adsorption of 87Y. Nonradioactive Sr was unadsorbed and washed out from the column. Above 90% of the available 87mSr with a 87Y breakthrough less than 10−3% could be obtained with 10 ml of 0.9% saline solution per elution from the generator system. The chemical contaminants of Fe and Sr in the eluates were found below 0.04 and 0.1 ppm, respectively.
    Type of Medium: Electronic Resource
    URL: http://dx.doi.org/10.1023/A:1006770123421
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  • 7
    Electronic Resource
    Electronic Resource
    Applications of gas chromatography and gamma spectrometry to fission gas measurements (1988)
    Springer
    Journal of radioanalytical and nuclear chemistry 123 (1988), S. 387-409 
    Details
    ISSN: 1588-2780
    Source: Springer Online Journal Archives 1860-2000
    Topics: Chemistry and Pharmacology , Energy, Environment Protection, Nuclear Power Engineering
    Notes: Abstract A gas sampler with lead shield has been designed for transferring the grab gas sample taken from the sampling station of Taiwan nuclear power reactor. The methods involving gas chromatography and gamma spectrometry have been developed for the determination of fission gases. A gas chromatograph equipped with TCD was used for measurement of gas composition. Column requirements are identified and optimum operating conditions are discussed. A single analysis is completed within 25 minutes for all of the gas constitutents and 12 minutes for only Xe and Kr. The detection limit is 0.005 mm partial pressure for Kr and Xe and a precision of ±1% relative is achieved for all the sample constituents. Combined error determinations for the method denote an attainable accuracy of less than ±2% for constituents at a sample pressure above 10 mm. Mixing and dispensing of the radioactive gases were carried out in a special gas mixing line. In experiment, calibration factors for measurement of133Xe and85Kr in ampules are determined in an isotope calibrator and by Ge(Li) gamma ray spectrometry. The relative precisions of 0.14% and 0.5% are readily achieved for85Kr and133Xe, respectively. The calibration uncertainty in85Kr measurement is 0.4%.
    Type of Medium: Electronic Resource
    URL: http://dx.doi.org/10.1007/BF02034906
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