[en] Half-life of krypton-88 is 2.84 hours, high fission yields and a relatively large gamma branching ratio is had. The gas is short-lived fission products in burnup measurements. Only New fission products can extract from extraction in gas of fissile irradiation target. But krypton-88 with krypton-85, krypton-87, xenon -135, and xenon-138 is coexisted together, thus radiochemical separation must quickly taken. selected the irradiation time is 1-2 hours and cooling time is best 2 hours for sample preparation, krypton and xenon were separated using activated carbon adsorption, the ratio of krypton and xenon were measured by gamma spectroscopy. Then according to the ratio of krypton-85 and xenon-125 count rate coefficient around separation were calculated yield of krypton and decontamination factor of xenon and the final the yield of krypton-85 is calculated. (authors)

[en] It is difficult to determine the concentration of a-emitting nuclides of raffinate and detergent in process feed solutions due to its low concentration. The conventional radiochemical analysis methods cannot meet the new demand. A novel analytic technique using scintillating glass to determine the concentration of a-emitting nuclides in liquid was present in this paper. The glasses and detection system were build and its performance index met the requirements and achieved the expected effect. (authors)

[en] An effective method is found that ⁹⁰Sr and ⁹⁰Y can be measured by measuring the bremsstrahlung produced in a ⁹⁰Sr and ⁹⁰Y sample. According to the metrical principle, the detection efficiency ratio k of ⁹⁰Y to ⁹⁰Sr is obtained by measuring a ⁹⁰Sr sample from which ⁹⁰Y has been removed by extraction of ⁹⁰Y with di (2-ethylhexly) phosphoric acid (HDEHP). The results indicate that the simultaneous measurement of ⁹⁰Sr and ⁹⁰Y is feasible and ⁹⁰Sr-⁹⁰Y can be directly used as the tracer of Y. (authors)

[en] A radiochemical procedure for separation of ⁷⁹Se from fission products with the main steps of nitrobenzene extraction and sulfur dioxide precipitation is presented. The procedure gives a chemical yield of selenium greater than 60% and has a satisfactory decontamination ability from all of the relating radioactive nuclides. The measurement conditions of ⁷⁹Se radioactivity using liquid scintillation technique are studied. The ⁷⁹Se samples obtained from the procedure have been used successfully for ⁷⁹se half-life determination

No abstract available

[en] CIEMAT/NIST method for calculating radioactivity of β-nuclides was introduced in this paper. The influences of KB value and quenching parameter on the radioactivity computation of ²⁴¹Pu, ¹⁰⁶Ru/¹⁰⁶Rh, ⁶³Ni, ¹⁵¹Sm and ¹⁴C were studied by CIEMAT/NIST method with ³H tracing. It is shown that the effect of KB value can be ignored if it varies in a proper range; Except for ¹⁰⁶Ru/¹⁰⁶Rh, the discrepancy between prediction and actual activity is lower than 2% in low quenching extent. However, it increases with quenching extent, and the largest discrepancy soars to nearly 13%. In addition, the reason for bad agreement of ¹⁰⁶Ru/¹⁰⁶Rh between prediction and actual activity was discussed. Efficiency calibration curves of ⁷⁹Se, ⁹³Zr and ¹⁰⁷Pd were also computed by CIEMAT/NIST method, compared with approximate replacement method or fitting and interpolation method. It is shown that CIEMAT/NIST method is no more accurate and suitable than the other two techniques. (authors)

[en] In order to prepare ⁸⁸Kr samples for the corresponding nuclear data measurement, a method for radiochemical separation of ⁸⁸Kr has been investigated by activated carbon adsorption in this work. The absorption conditions of activated carbon column were studied by using ⁸⁵Kr and ¹²⁵Xe as the radioactive gas tracers. The results show that Xe can be absorbed quickly on the activated carbon column at low temperature (0 ℃), whereas Kr shows no such property. ⁸⁸Kr samples are easily enriched from the irradiated uranium targets by utilizing the separation system which is designed for the short-lived gaseous fission products. The recovery yield of Kr is better than 90% and the decontamination factors for Xe and I are more than 1 × 10⁴. The whole procedure can be completed in less than 5 min. (authors)

[en] The performance of Empore^TM Strontium Rad Disk produced by 3M Corporation for the separation of strontium in aqueous solution was studied elaborately. The influences of sample acidity, volume and flow rate on strontium uptake efficiency were studied and maximum strontium capacity was determined. The adsorption behavior of ¹³⁷Cs and ⁹⁹Tc on the disk was investigated as well as the elution method of strontium and counting method of ⁹⁰Sr on the disk. Based on the results, an analysis procedure of ⁹⁰Sr in environmental water sample using SPE disks was presented. The minimum detectable activity is 0.033 Bq/L with a sample volume of 1 L and a detection time of 1 h. Finally, some ⁹⁰Sr spiked environmental water samples were determined to testify the procedure. (authors)

[en] The performance of anion solid phase extraction disk for the separation of TcO₄^- ion in aqueous solution was studied systematically. The effects of flow rate, acidity, sample volume and soil matrix on adsorption were evaluated with different flow rate load conditions. And on this basis, an analysis procedure using solid phase extraction disk for the routine determination of ⁹⁹Tc in soil was presented. The procedure was validated by some simulated contaminated soil samples. The results show that ¹³⁷Cs, ⁹⁰Sr-⁹⁰Y, natural uranium and background radionuclides in soil do not interfere with the analysis procedure. The chemical yield of technetium is more than 95% for the whole procedure. The minimum detectable concentration is 1.1 Bq/kg with sample quantity of 10 g, background counting rate of 10 min^-1 and detection time of 10 h. (authors)

[en] The radiochemical separation procedure of ¹³²i was designed on the basis of half-lives of iodine and tellurium isotopes in mixed fission products. It mainly includes the evaporation step with concentrated HBr and the extraction step with CCl₄. Decontamination of iodine was studied by the process of evaporation with concentrated HBr. The effects of HNO₃ concentration, KI quantity in aqueous phase and I₂ quantity in CCl₄ on extraction recovery of ¹³²I were also researched. ¹³²I was back-extracted by SO₂-aqueous solution in separation procedure. Using designed procedure, ¹³²I was separated from mixed fission products. The activity of ¹³¹I in separated ¹³²I is 1.3% of ¹³²I. The chemical recovery of ¹³²I is about 60% and the decontamination factor is more than 10³ for most γ-emitters. (authors)