共查询到20条相似文献,搜索用时 31 毫秒
1.
Sultan Şahin Fatih Külahcı Mahmut Doğru 《Journal of Radioanalytical and Nuclear Chemistry》2011,290(2):313-318
In this study, 90Sr (540 keVβ −), 129I (150 keVβ −) and the gross beta radioactivity concentrations were determined for the samples of tea as the most leading consumed hot
drink in the markets (processed and packaged for sale) in our country. Furthermore, the obtained data were statistically analyzed.
For determination of 129I (150 keVβ−), 90Sr (540 keVβ−) and gross radioactivity concentrations in tea samples, a sensor system consisting of scintillation detector with BP4 probe
sensitive to beta radiation and a radiation meter (ST7) configurable for windows at desired power was used. 相似文献
2.
Chang Heon Lee Myung Ho Lee Sun Ho Han Yeoung-Keong Ha Kyuseok-Song 《Journal of Radioanalytical and Nuclear Chemistry》2011,288(2):319-325
A simple and rapid separation procedure was systemized for the determination of 99Tc, 90Sr, 94Nb, 55Fe and 59,63Ni in low and intermediate level radioactive wastes. The integrated procedure involves precipitation, anion exchange and extraction
chromatography for the separation and purification of individual radionuclide from sample matrix elements and from other radionuclides.
After separating Re (as a surrogate of 99Tc) on an anion change resin column, Sr, Nb, Fe and Ni were sequentially separated as follows; Sr was separated as Sr (Ca-oxalate)
co-precipitates from Nb, Fe and Ni followed by purification using Sr-Spec extraction chromatographic resin. Nb was separated
from Fe and Ni by anion exchange chromatography. Fe was separated from Ni by anion exchange chromatography. Ni was separated
as Ni-dimethylglyoxime precipitates after the removal of 134,137Cs and 110mAg by Cs-phosphotungstate and AgCl precipitation, respectively. Finally, the radionuclide sources were prepared by precipitation
for their radioactivity measurements. The reliability of the procedure was evaluated by measuring the recovery of chemical
carriers added to a synthetic radioactive waste solution. 相似文献
3.
Chang Heon Lee Moo Yul Suh Kwang Yong Jee Won Ho Kim 《Journal of Radioanalytical and Nuclear Chemistry》2007,272(1):187-194
A sequential separation procedure has been developed for the determination of 99Tc, 94Nb, 55Fe, 90Sr and 59/63Ni in various radioactive wastes generated from nuclear power plants. Ion exchange and extraction chromatography were adopted
for individual separation of the radionuclides. Precipitation was supplementarily utilized for both purification of the individual
radionuclides and preparation of the radionuclide sources for use in a radioactivity measurement. The chromatographic separation
behavior of the radionuclides both from the sample matrix metals and from one another was investigated using stable metals,
Re (as a surrogate of 99Tc), Nb, Fe, Sr and Ni. The validity of the procedure for reliability and applicability was evaluated by measuring the recovery
of the metal carriers added to synthetic radioactive waste solutions. The recoveries by the chromatographic separation were
in the range of 84.8 to 102.2% with 2s of less than 8.6%, the recoveries by the precipitation being in the range of 84.3 to 97.3% with 2s of less than 10.9%. 相似文献
4.
Rajesh Chakraborty Sanjoy Dhara Sukalyan Basu Pabitra Chattopadhyay 《Journal of Radioanalytical and Nuclear Chemistry》2011,287(1):55-59
An inorganic ion exchanger, quinolinephosphomolybdate has been synthesized and characterized by elemental analysis, infrared
(IR) and X-ray diffraction (XRD) spectroscopy. This compound is highly stable toward thermal, chemical and radiation dose.
This has been employed in the separation of carrier-free 90Y from its parent 90Sr from an equilibrium mixture. The absorbed daughter was recovered by using 0.0284 mol L−1 ascorbic acid solutions at pH 5.0 as eluting agent. 相似文献
5.
N. E. Bores M. K. Schultz J. M. Rankin A. J. Denton G. F. Payne 《Journal of Radioanalytical and Nuclear Chemistry》2009,282(3):985-990
The Intercomparison Studies Program (ISP) at the Oak Ridge National Laboratory (ORNL, Oak Ridge, TN USA) provides natural-matrix
human urine quality-assurance/quality-control (QA/QC) samples to radiobioassay analysis laboratories. Samples are provided
to these laboratories as “single-blind” or “double-blind” unknowns, spiked with radioactive-solution standards at “low” levels
(e.g., 0.7–7 Bq g−1 for 3H and 0.7–7 Bq kg−1 for 90Sr). Participants use the results as a tool for self-evaluation and a measure of performance. In this paper, sample preparation
and the results of testing during the years 2001–2005 for 3H and 90Sr are presented and discussed. 相似文献
6.
Donald E. Dry Warren J. OldhamJr. Scott M. Bowen 《Journal of Radioanalytical and Nuclear Chemistry》2009,282(2):635-640
The long-lived rare earth isotopes 151Sm (90 years, β
max = 76.3 keV) and 147Pm (2.62 years, β
max = 224.6 keV) are low-yield fission products that generally require lengthy separation procedures to isolate and count by
their beta emissions. We will describe novel liquid scintillation counting techniques using radioactive tracers to determine
radiochemical yields from an environmental matrix. The recovery of 151Sm is determined from the alpha decay (2.25 MeV) of 147Sm in the natural Sm carrier and is in excellent agreement with the gravimetric recovery. The 147Pm recovery is determined by the use of 145Pm (17.7 years, EC) tracer, custom-produced at LANL using an isotopically enriched target of 144Sm. We have determined the 145Pm recovery both from the 37.4 keV kα1 X-ray, and the electron-capture emissions by LSC. A comparison of these recovery methods is presented. 相似文献
7.
Marin Ayranov Dorothea Schumann 《Journal of Radioanalytical and Nuclear Chemistry》2010,286(3):649-654
The station for pions cancer therapy was operated at PSI from 1980 to 1992. After a cooling time of 12 years it’s made of
copper beam dump was cut and samples were taken for analytical purposes. The sampling collected about 500 g of high active
copper chips that can be used for separation of exotic radionuclides. The analyses by gamma spectrometry, LSC and AMS showed
main nuclides present to be 60Co, 54Mn, 22Na, 65Zn, 26Al, 53Mn, 59Ni, 63Ni, 55Fe and 60Fe and 44Ti with a daughter nuclide 44Sc. In the frame of ERAWAST project a procedure combining selective precipitation and ion exchange for the separation of the
rare radionuclides from the copper beam dump was developed. The proposed separation procedure is easy for remote controlled
implementation in a hot cell. The ion exchange separation of Ni, Al, Mg, Ti and Fe was complete and high decontamination factors
for copper and cobalt were achieved. Based on the developed procedure a remotely controlled system for separation of exotic
radionuclides from the copper chips was set up. The full scale system was installed in a hot cell where high activity levels
can be handled. In order to evaluate the reliability and functionality of the system extensive tests have been done. During
the test period 13.86 g in total of the proton irradiated copper beam dump were processed for separation of 26Al, 59Ni, 53Mn, 44Ti and 60Fe. The results showed that the system was operational and the radionuclide separation was selective with high chemical yield.
The procedure manages as well the generated liquid wastes containing high level of 60Co activity. 相似文献
8.
P. Tavčar B. Smodišs L. Benedik 《Journal of Radioanalytical and Nuclear Chemistry》2007,273(3):593-596
An analytical procedure for the determination of activation products 238Pu, 241Pu, 239Pu/240Pu, 241Am, 237Np, and a fission product 90Sr in radioactive wastes is presented. Samples were decomposed using Fenton’s reaction. The separation was performed by anion-exchange
chromatography, extraction chromatography, using TRU and Srresin, and precipitation techniques, followed by α-spectrometry
and LSC counting. Tracer solutions and pure ion exchange resins were used to prepare artificial samples and trace nuclides
during the analytical procedure. Some real samples of spent ion-exchange resins originating from our TRIGA Mark II research
reactor were analyzed. 相似文献
9.
Yonnhee Jung Hyuncheol Kim Jong-Myoung Lim Kun Ho Chung 《Journal of Radioanalytical and Nuclear Chemistry》2017,313(2):401-408
This study investigated an analytical method for detecting 90Sr in soil samples for the routine monitoring of environmental radioactivity. Mineral acid leaching and fusion methods were first used to digest the soil sample, and the analytical results were compared. DGA resin was employed to separate 90Y, being a daughter of 90Sr. Then, 90Y was analyzed by liquid scintillation counter (LSC). These analytical results were compared with those obtained using Sr resin, which is a well-known, simple and reliable separation method. With the DGA resin approach a minimum detectable activity of ~0.28 Bq kg?1 was detected in a 50 g sample, with 180 min of counting time, 70% recovery and ~97% counting efficiency using a LSC. 相似文献
10.
Tsuey-Lin Tsai Chun-Chih Lin Tsung-Yuan Wang Hwa-Jou Wei Lee-Chung Men 《Journal of Radioanalytical and Nuclear Chemistry》2010,286(1):145-154
A rapid, accurate and less labor intensive approach to determining 226Ra in environmental samples was examined; this utilized quadrupole-based inductively coupled plasma mass spectrometry (ICP-QMS).
The procedure used chemical separation by ion exchange chromatography to remove most of the matrices after coprecipitation
with BaSO4. The average chemical recovery of the NIST SRM preparation method ranged from 60.5 to 85.9% using 133Ba as internal tracer by gamma counting. This technique was capable of completing a 226Ra measurement within 3 min. It did not require an in-growth period to allow radon and its progeny to achieve secular equilibrium
with the parent 226Ra as is needed for liquid scintillation analyzer (LSA). The method detection limits for the determination of 226Ra in geothermal water and sediment samples were 0.02 mBq L−1 (0.558 fg L−1) and 0.10 Bq kg−1 (2.79 fg g−1), respectively. The results obtained with various natural samples and the suitability of the method when applied to various
environmental matrices such as geothermal water and sediment are discussed. When ICP-QMS was compared to double-focusing magnetic
sector field inductively coupled plasma mass spectrometry (ICP-SFMS), good agreement was obtained with a correlation coefficient,
r
2 = 0.982. 相似文献
11.
Sz. Osváth N. Vajda Zs. Molnár É. Széles Zs. Stefánka 《Journal of Radioanalytical and Nuclear Chemistry》2010,286(3):675-680
The majority of long-lived radionuclides produced in the nuclear fuel cycle can be regarded as “difficult-to-measure” nuclides,
hence chemical separation is needed before the nuclear measurement of them. A combined radiochemical procedure that enables
the simultaneous determination of some “difficult-to-measure” nuclides in medium and low level radioactive wastes has been
developed in our laboratory. Recently, this method has been extended for determination of 237Np and 93Zr. 237Np and 93Zr are pre-concentrated by co-precipitation on iron(II) hydroxide and zirconium oxide, separated by extraction chromatography
using UTEVA, and measured by inductively coupled plasma mass spectrometry (ICP-MS). As even traces of polyatomic ions and
isotopes at m/z 237 or 93 cause considerable interferences during ICP-MS detection, a purification step by extraction chromatography
was needed. Analyzing real samples (evaporation concentrates of a nuclear power plant) 66–99% and 31–99% chemical yields were
achieved for Np and Zr, respectively. 相似文献
12.
T. C. Oliveira R. P. G. Monteiro A. H. Oliveira 《Journal of Radioanalytical and Nuclear Chemistry》2011,289(2):497-501
The zirconium isotope 93Zr is a long-lived pure β-particle-emitting radionuclide produced from 235U fission and from neutron activation of the stable isotope 92Zr and thus occurring as one of the radionuclides found in nuclear reactors. Due to its long half life, 93Zr is one of the radionuclides of interest for the performance of assessment studies of waste storage or disposal. Measurement
of 93Zr is difficult owing to its trace level concentration and its low activity in nuclear wastes and further because its certified
standards are not frequently available. A radiochemical procedure based on liquid–liquid extraction with 1-(2-thenoyl)-3,3,3-trifluoroacetone
in xylene, ion exchange with Dowex resin and selective extraction using TRU resin has to be carried out in order to separate
zirconium from the matrix and to analyze it by liquid scintillation spectrometry technique (LSC). To set up the radiochemical
separation procedure for 93Zr, a tracer solution of 95Zr was used in order to follow the behavior of zirconium during the process by γ-ray spectrometry through measurement of the
95Zr. Then, the protocol was applied to low level waste (LLW) and intermediate level waste (ILW) from nuclear power plants.
The efficiency detection for 63Ni was used to determination of 93Zr activity in the matrices analyzed. The limit of detection of the 0.05 Bq l−1 was obtained for 63Ni standard solutions by using a sample:cocktail ratio of 3:17 mL for OptiPhase HiSafe 3 cocktail. 相似文献
13.
Heung N. Lee S. W. Kim M. G. Hur S. D. Yang W. H. Kim K. Y. Jee 《Journal of Radioanalytical and Nuclear Chemistry》2011,287(2):617-620
3H and 14C Measurements of the dry active waste (DAW), such as the cotton, paper, and vinyl, generated from a nuclear power plant (NPP)
were conducted with wet oxidation using open vessel equipment based on simulation results. The recovery efficiency with the
simulated samples was around 93% with a relative standard deviation (RSD) of 1–3%. A liquid scintillation counter (LSC) was
used for counting and adjusted to a quenching correction curve. The counting value was evaluated for the minimum detectable
activity (MDA), which was found to be about 4 × 10−1 Bq/g for 3H and 2 × 10−2 for 14C when approximately 5 g of the samples were measured. The measured DAW samples for the cotton, paper, and vinyl generated
from NPP achieved of RSD values of 25, 25, and 60%, respectively, for 3H and 0–50% for 14C. 相似文献
14.
Xiaolin Hou 《Journal of Radioanalytical and Nuclear Chemistry》2017,314(2):659-668
Technetium-99m is the principal radioisotope used in medical diagnostics; radionuclidic impurity is the major concern of its quality. This work presents a analytical method for sequential determination of all radionuclidic impurities listed in pharmacopoeia including gamma emitters, alpha emitters, 89Sr and 90Sr. Radioactive decay for removal of 99mTc, ion exchange and extraction chromatography for removal of 99Mo and 99Tc are effective for separation of interferences. Gamma spectrometry, LSC with alpha/beta discrimination, and Cherenkov counting using LSC are sensitive methods for measurement of the impurity radionuclides. The detection limits of this method are well meet the requirement of the quality control according to the limitation of the pharmacopoeia. 相似文献
15.
Š. Palágyi K. Štamberg H. Vodičková 《Journal of Radioanalytical and Nuclear Chemistry》2010,283(3):629-636
Transport and sorption of water-soluble 85Sr2+ and 125I− in the columns with beds of crushed crystalline rocks from synthetic groundwater has been studied under dynamic flow conditions.
Samples of crystalline rocks: diorite-I, diorite-II, gabbro, granite and tonalite, having the grain size between 0.25 and
0.80 mm, were used. Plastic syringes of 8.8 cm length and 2.1 cm in diameter were applied as columns. The synthetic groundwater
was pumped downward through the columns with a seepage velocity of about 0.2 cm/min and the given radioactive nuclide was
added into the water stream individually in a form of a short pulse. In case of 85Sr, desorption from diorite-I was also studied using an artificial acid rainfall and then, the longitudinal distribution of
the residual 85Sr activity along the bed was measured. Retardation, distribution and hydrodynamic dispersion coefficients were determined
by the evaluation of respective breakthrough curves. A corrected integral form of a simple advection–dispersion equation was
derived and used for fitting the experimental data. The K
d-parameters resulting from dynamic experiments were also compared with the results of static sorption experiments. 相似文献
16.
Zack Varve Edward P. C. Lai Chunsheng Li Baki B. Sadi Gary H. Kramer 《Journal of Radioanalytical and Nuclear Chemistry》2012,292(3):1411-1415
A rapid bioassay for 90Sr was developed involving preconcentration of 90Sr/90Y from human urine samples with a cation exchange polymer (poly–acrylamido–methyl–propanesulfonic acid) coated onto magnetic
nanoparticles, followed by selective elution of 90Sr (over 90Y) with phosphate for determination by liquid scintillation analysis. The minimum detectable activity for this method (4.9 ± 0.5 Bq/L)
is lower than the required sensitivity of 19 Bq/L for 90Sr in human urine samples, as defined in the requirements for radiation emergency bioassay techniques for the public and first
responders based on the dose threshold for possible medical attention recommended by the International Commission on Radiological
Protection. The relative bias was 9.2%, the relative precision was 3.2%, and the linear dynamic range covered 12–600 Bq/L.
This simple and rapid bioassay method is found to be in compliance with the HPS ANSI N13.30 performance criteria for radiobioassay. 相似文献
17.
Özlem Selçuk Zorer Tekin Şahan 《Journal of Radioanalytical and Nuclear Chemistry》2011,288(2):417-421
Gross α and gross β activities and 238U concentrations were determined in 18 surface water samples collected from Van Lake. The instrumentations used to count the
gross α and gross β activities and to determine the 238U concentrations were α/β counter of the multi-detector low background system (PIC-MPC-9604) and Inductively Coupled Plasma-Mass
Spectrometry (Thermo Scientific Element 2), respectively. Concentrations ranging from 0.001 to 0.021 Bq L−1 and from 0.111 to 2.794 Bq L−1 were observed for the gross α and β activities in surface waters, respectively. For all samples the gross β activities were
higher than the corresponding gross α activities. The results indicated that the gross α radioactive contamination in water
samples was lower than recommended values for the guideline of drinking waters and most of the gross β activities in water
samples were higher than those in the same procedure. The 238U concentrations ranged from 74.49 to 113.2 μg L−1 in surface waters. The obtained results have showed that 238U concentrations are higher than guideline values for uranium. 相似文献
18.
T. Jabbar K. Khan M. S. Subhani P. Akhter 《Journal of Radioanalytical and Nuclear Chemistry》2009,279(2):377-384
Assessment of 90Sr is of great interest owing to the fact that this artificially produced radionuclide has high radiological importance because
of its high fission yield, chemical similarity to calcium and its relatively long biological and physical half-life. To assess
the likely hazard to population, low level 90Sr in environmental samples is determined using pre-equilibrated tri-butyl phosphate (TBP) solvent and extraction-liquid scintillation
procedure. 90Y is selectively extracted from nitric acid solution into TBP solvent and stripped into aqueous phase as oxalate. The activity
is finally measured by low level liquid scintillation counter using Cerenkov radiation. The specific activity is found only
in three vegetation samples with average value of 2.86±1.7 Bq·kg−1 of dry weight. In all other samples analyzed, the activity is below the detectable limit, i.e., 0.03 Bq. Results obtained
are comparable with other areas of Pakistan. The chemical recovery of 90Y varies from 75 to 90% for soil, vegetation and water. The present study provides a general background of the detectable
radionuclide for the surveyed area that will be helpful in any radiological emergency. 相似文献
19.
Željko Grahek Astrid Gojmerac Ivšić Nikolina Krljan Marijana Nodilo 《Journal of Radioanalytical and Nuclear Chemistry》2011,289(2):437-449
This paper describes the procedures of isolating strontium from wine and soil samples which enable creating of procedure for
rapid determination of 90Sr. The method of determination of 90Sr includes binding of Sr on the cationic exchanger IR-120 from the sample and simultaneous elution from the cation column
and binding on the Sr column, separation of Sr on Sr resin with HNO3 even in presence of alcohols and subsequent Cherenkov counting. Sr can be efficiently bind on Sr resin and separated from
the other elements with lower acid concentrations in the presence of a low portion of alcohol, or even from a wine sample
without the loss of Sr resin capacity. The binding strength of Sr on Sr resin decreases with the rising of HNO3 concentration (1–5 M) in the presence of 13% of ethanol or methanol, and with the rising of the alcohol portion in constant
concentration of HNO3. Application of cation exchanger for Sr binding in phase of sample preparation decreases Sr column loading and improve Sr
recovery. The method allows the determination of 90Sr activities in wine and soil sample lower than 10 mBq in reasonable time. 相似文献
20.
S. P. D. Bhade P. J. Reddy A. Narayanan K. K. Narayan D. A. R. Babu D. N. Sharma 《Journal of Radioanalytical and Nuclear Chemistry》2010,284(2):367-375
Simultaneous measurement of gross alpha and gross beta activities by liquid scintillation counting technique using LKB Wallac
Quantulus 1220 liquid scintillation counter (LSC) equipped with Pulse Shape Analyzer (PSA) is described. Three sets of pure
alpha and pure beta standards simulating the activity concentration values of real samples in terms of α/β activity ratios
were used to calibrate the LSC. Calibration methodology for the Quantulus 1220 with respect to the above measurements using
241Am and 90Sr/90Y standards of respective activity concentrations of ~25 dpm and ~104 dpm is described in detail. Also highlighted the need to calibrate the LSC using another set of 241Am and 90Sr/90Y standards of low and high activity concentrations respectively. The practicability and working performance of these calibration
plots was checked by the validation trials with test samples spiked with 241Am and 90Sr/90Y covering range of α/β activity ratios from 1:1 to 1:50. 相似文献