Journal of Radioanalytical and Nuclear Chemistry (J RADIOANAL NUCL CH )

Publisher: Springer Verlag

Description

An international periodical publishing original papers letters review papers and short communications on nuclear chemistry. The subjects covered include: Nuclear chemistry Radiochemistry Radiation chemistry Radiobiological chemistry Environmental radiochemistry Production and control of radioisotopes and labelled compounds Nuclear power plant chemistry Nuclear fuel chemistry Radioanalytical chemistry Radiation detection and measurement Nuclear instrumentation and automation etc.

  • Impact factor
    1.47
    Show impact factor history
     
    Impact factor
  • 5-year impact
    1.11
  • Cited half-life
    6.30
  • Immediacy index
    0.12
  • Eigenfactor
    0.01
  • Article influence
    0.21
  • Website
    Journal of Radioanalytical and Nuclear Chemistry website
  • Other titles
    Journal of radioanalytical and nuclear chemistry (Online)
  • ISSN
    0236-5731
  • OCLC
    45254640
  • Material type
    Document, Periodical, Internet resource
  • Document type
    Internet Resource, Computer File, Journal / Magazine / Newspaper

Publisher details

Springer Verlag

  • Pre-print
    • Author can archive a pre-print version
  • Post-print
    • Author can archive a post-print version
  • Conditions
    • Authors own final version only can be archived
    • Publisher's version/PDF cannot be used
    • On author's website or institutional repository
    • On funders designated website/repository after 12 months at the funders request or as a result of legal obligation
    • Published source must be acknowledged
    • Must link to publisher version
    • Set phrase to accompany link to published version (The original publication is available at www.springerlink.com)
    • Articles in some journals can be made Open Access on payment of additional charge
  • Classification
    ​ green

Publications in this journal

  • [Show abstract] [Hide abstract]
    ABSTRACT: The purpose of this study was to determine the kinetics of the dissolution of a uranium residue in ammonium carbonate media. The residue is generated in the production of medical isotopes. The effects of parameters, such as varying peroxide and carbonate concentrations, dissolution time as well as temperature on the extraction rate have been separately studied. Results indicate complete dissolution of the residue at 60 °C, after 30 min, in ammonium carbonate solution enriched with hydrogen peroxide. The yield and rate of uranium extraction were found to increase as a function of both temperature, in the range of 25–60 °C, and hydrogen peroxide concentration. The extraction process was governed by chemical reaction as the activation energy was found to be 45.5 kJ/mol. The order of reaction with respect to uranium concentration was found to be approximately first order.
    Journal of Radioanalytical and Nuclear Chemistry 10/2014; 302(1).
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    ABSTRACT: Analysis of post-nuclear detonation materials provides information on the type of device and its origin. Compositional analysis of trinitite glass, fused silicate material produced from the above ground plasma during the detonation of the Trinity nuclear bomb, reveals gross scale chemical and isotopic heterogeneities indicative of limited convective re-homogenization during accumulation into a melt pool at ground zero. Regions rich in weapons grade Pu have also been identified on the surface of the trinitite sample. The absolute and relative abundances of the lanthanoids in the glass are comparable to that of average upper crust composition, whereas the isotopic abundances of key lanthanoids are distinctly non-normal. The trinitite glass has a non-normal Nd isotope composition, with deviations of −1.75 ± 0.60 ε (differences in parts in 104) in 142Nd/144Nd, +2.24 ± 0.75 ε in 145Nd/144Nd, and +1.01 ± 0.38 ε in 148Nd/144Nd (all errors cited at 2σ) relative to reference materials: BHVO-2 and Nd-Ames metal. Greater isotopic deviations are found in Gd, with enrichments of +4 ± 1 ε in 155Gd/160Gd, +4.19 ± 0.75 ε in 156Gd/160Gd, and +3.48 ± 0.52 ε in 158Gd/160Gd compared to BHVO-2. The isotopic deviations are consistent with a 239Pu based fission device with additional 235U fission contribution and a thermal neutron fluence between 1.4 and 0.97 × 1015 neutrons/cm2.
    Journal of Radioanalytical and Nuclear Chemistry 10/2014; 302(1).
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    ABSTRACT: This paper presents the assessment of inhalation exposure potential of broken uranium ore piles in different stopes of Jaduguda uranium mines of India. 222Rn emanation coefficient of broken uranium ore was measured in laboratory by collecting air sample from airtight glass jar containing ore sample. An attempt was also made to correlate the emanation coefficient with 226Ra content of the ore. The 222Rn progeny doses estimated based on radon activity concentration of broken ore, occupancy period and equilibrium ratio in different stopes were well below the prescribed limit of International Commission on Radiological Protection. The maximum 222Rn progeny dose contribution from broken ore piles was worked out to be 0.22 mSv year−1. This suggests that the broken ore piles are not the significant contributor of inhalation exposure under the existing ventilation condition of Jaduguda uranium mine.
    Journal of Radioanalytical and Nuclear Chemistry 10/2014; 302(1).
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    ABSTRACT: Solvent extraction of microamounts of trivalent europium and americium into nitrobenzene by using a synergistic mixture of hydrogen dicarbollylcobaltate (H+B−) and magnesium ionophore III (L) was studied. The equilibrium data were explained assuming that the species HL+, \( \text{HL}_{2}^{ + } , \) \( {\text{ML}}_{2}^{3 + } , \) and \( {\text{ML}}_{3}^{3 + } \) (M3+ = Eu3+, Am3+; L = magnesium ionophore III) are extracted into the nitrobenzene phase. The values of extraction and stability constants of the cationic complex species in nitrobenzene saturated with water were determined and discussed.
    Journal of Radioanalytical and Nuclear Chemistry 10/2014; 302(1).
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    ABSTRACT: The independent isomeric yield ratios of 148Pm from the natSm(γ, x) reaction at the end-point bremsstrahlung energy of 45–64 MeV have been determined using an off-line γ-ray spectrometric technique at the 100 MeV electron linac of Pohang accelerator laboratory, Pohang, Korea. We also have determined the isomeric yield ratios of 148Pm from the natNd(p,xn) reactions in the proton energy of 5.08–44.72 MeV by a stacked-foil activation and an off-line γ-ray spectrometric techniques at the MC-50 cyclotron of the Korean Institute of Radiological and Medical Sciences, Korea. The determined isomeric yield ratios of 148Pm were compared with literature data and theoretical values estimated by the TALYS 1.4. The present data along with the similar data from literature at other energies shows that the isomeric yield ratio of 148Pm increases with the excitation energy both in the natSm(γ, x) and the natNd(p, xn) reactions. The isomeric yield ratios of 148Pm from the natNd(p, xn) reactions are always higher than those from the natSm(γ, x) reactions at the same excitation energy, which indicate the role of input angular momentum besides excitation energy.
    Journal of Radioanalytical and Nuclear Chemistry 10/2014; 302(1).
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    ABSTRACT: Eggshell material was used as low-cost and eco-friendly biosorbent for removal of 134Cs, 60Co and 152+154Eu radionuclides from aqueous solution. The eggshell material was calcined at 500 and 800 °C, and then characterized. Comparative studies on the natural and calcined eggshell for sorption of the three radionuclides were carried out. It was found that, the uptake is in the order: Eu(III) > Co(II) > Cs(I). Further, column chromatography was used in separation of 134Cs, 60Co and 152+154Eu using 0.15, 0.2 and 0.5 mol/l nitric acid, respectively. Eggshell material can be considered as a promising material for separation of radionuclides from radioactive waste solution.
    Journal of Radioanalytical and Nuclear Chemistry 10/2014; 302(1).
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    ABSTRACT: [131I]-5,10,15,20-tetrakis(4-hydroxyphenyl)porphyrin and [131I]-5-(4-aminophenyl)-10,15,20-triphenylporphyrin (131I-TPPOH and 131I-TPPNH2) were prepared and their biodistribution properties were evaluated in normal Kunming (KM) mice and SMMC-7721 tumor-bearing BALB/c mice. The optimized labeling yields were 98 and 96 % for 131I-TPPOH and 131I-TPPNH2, respectively. They were stable in vitro saline and in vivo. Both compounds had a specific affinity to liver and lung, and mainly metabolized through liver. They showed a time-dependent accumulation and retainable characteristics in SMMC-7721 tumor. These results supported their potential value for targeted tumor therapy agents.
    Journal of Radioanalytical and Nuclear Chemistry 10/2014; 302(1).
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    ABSTRACT: The ability of ordered mesoporous carbon CMK-3 has been explored for the removal and recovery of thorium from aqueous solutions. The textural properties of CMK-3 were characterized using small-angle X-ray diffraction and N2 adsorption–desorption, and the BET specific surface area, pore volume and the pore size were 1143.7 m2/g, 1.10 cm3/g and 3.4 nm. The influences of different experimental parameters such as solution pH, initial concentration, contact time, ionic strength and temperature on adsorption were investigated. The CMK-3 showed the highest thorium sorption capacity at initial pH of 3.0 and contact time of 175 min. Adsorption kinetics was better described by the pseudo-second-order model and adsorption process could be well defined by the Langmuir isotherm. The thermodynamic parameters, △G°(298 K), △H° and △S° were determined to be -0.74 kJ·mol−1, 9.17 kJ·mol−1 and 33.24 J·mol−1·K−1, respectively, which demonstrated the sorption process of CMK-3 towards Th(IV) was feasible, spontaneous and endothermic in nature. The adsorbed CMK-3 could be effectively regenerated by 0.02 mol/L HCl solution for the removal and recovery of Th(IV).
    Journal of Radioanalytical and Nuclear Chemistry 10/2014; 302(1).
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    ABSTRACT: Ordered mesoporous carbon (OMC) was used as an adsorbent for the removal of pertechnetate (TcO4−) anion. The maximum uptake (93 %) of TcO4− was obtained after 60 min of contact. The adsorption of TcO4− is almost pH-independent in very wide pH region (from 4.0 to 10.0). Maximum K d of 6.6 × 103 cm3 g−1 was found at pH 2.0. TcO4− interacts with carboxylic functional groups present at the surface of the OMC by displacing the OH− ions with TcO4− via ion exchange mechanism.
    Journal of Radioanalytical and Nuclear Chemistry 10/2014; 302(1).
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    ABSTRACT: Small-molecular probe 18F-labeled bis(zinc(II)-dipicolylamine) complex (18F-FB-DPAZn2) was evaluated for PET imaging of sterile inflammation. In comparison with 18F-2-deoxy-β-d-glucose (18F-FDG), 18F-radiolabeled Annexin V (18F-FB-Annexin V) showed rapid clearance of radioactivity from the kidney and low uptake in most tissues. Both the lower radioactivity accumulation in brain and heart and the higher uptakes in the lung, liver, and intestine were observed for the biodistribution of 18F-FB-DPAZn2. In PET imaging, 18F-FDG showed significantly higher tumor and inflammation uptake than did of 18F-FB-DPAZn2 and 18F-FB-Annexin V in the S-180 fibrosarcoma mouse model and sterile inflammation mouse model. Both 18F-FB-DPAZn2 and 18F-FB-Annexin V performed the specifically localization in inflammation, and the ratios of inflammatory lesion-to-muscle and tumor-to-muscle were 1.83 ± 0.20 and 0.90 ± 0.12 (P 18F-FB-DPAZn2, and 1.51 ± 0.14 and 1.21 ± 0.12 (P > 0.05) for 18F-FB-Annexin V, respectively. Terminal deoxynucleotide end-labeling (TUNEL) assays performed on the dissected tissues showed the significantly more TUNEL-positive nuclei in the inflammatory muscle than in tumor and normal muscle, and these TUNEL results correlated with the uptake of 18F-FB-DPAZn2 in dissected tissues. Biodistribution and PET imaging studies showed that the 18F-FB-DPAZn2 is suitable for imaging sterile inflammation in vivo and is capable of the differentiating tumor from inflammation.
    Journal of Radioanalytical and Nuclear Chemistry 10/2014; 302(1).
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    ABSTRACT: This article discusses the age dating results of plutonium/uranium chronometers with a focus on the consequences for age plutonium determination when the basic assumptions of the methodology are not fully met: Incomplete removal of the daughter nuclides at the production date and uranium contamination of plutonium samples. In addition to the 238Pu/234U, 239Pu/235U and 240Pu/236U, the 242Pu/238U chronometer is discussed. The 242Pu/238U radiochronometer has only scarcely been used, due to its high sensitivity to residual uranium. However, it can be a very useful indicator for uranium contamination of aged plutonium samples.
    Journal of Radioanalytical and Nuclear Chemistry 10/2014; 302(1).
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    ABSTRACT: Radioactive 82Sr/82Rb produced at Los Alamos National Laboratory is routinely used in generators for hospitals and medical laboratories to support cardiac imaging. The proper quantification of strontium radioisotopes in a sample is important to ensure quality and regulatory compliance. However, the quantification of the impurity 85Sr is difficult, because its primary gamma-ray at 514 keV interferes with the annihilation peak at 511 keV from 82Rb. Synthetic spectra were created as a quality test of several gamma-ray spectral analysis tools’ ability to resolve peaks in the 511/514 keV multiplet. The peak fitting results from the spectroscopy tools (RAYGUN, SPECANAL, GammaVision, UNISAMPO, and GAMANAL) are presented. These spectra can also be useful for other programs to test their annihilation peak analysis procedures.
    Journal of Radioanalytical and Nuclear Chemistry 10/2014; 302(1).
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    ABSTRACT: The dependence of efficiency of a gas-flow proportional counter with respect to the source thickness and α-particle energy was evaluated using the code SRIM. Results for the mass-efficiency curves were evaluated for 209Po and 241Am in a substrate of NaNO3. The results revealed good agreement with a linear and a hyperbolic dependence for low and high thickness sources, respectively. However, some deviations were found for very thin thicknesses, which can be explained by taking into account scattering effects. A function is proposed for predicting the dependence of efficiency with α-particle energy in the range from 4 to 8 MeV.
    Journal of Radioanalytical and Nuclear Chemistry 10/2014; 302(1).
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    ABSTRACT: Dynamic adsorption of radiocesium on titanium ferrocyanide grains from reactor coolant simulating solution containing salts at moderate concentrations has been investigated. Effective decontamination of the neutral solutions has been achieved, in the amounts of a more than 20 thousand bed volumes. After adsorption the titanium ferrocyanide was transferred to titanates and calcined at 900 °C. The leaching test of the obtained lithium titanates indicates that the loaded adsorbent can serve as an effective primary barrier in nuclear waste repositories.
    Journal of Radioanalytical and Nuclear Chemistry 10/2014; 302(1).
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    ABSTRACT: Functional β-cyclodextrin-attapulgite nanorods (β-CD-APT) were synthesized to remove U(VI) under varied environmental conditions. Adsorption results demonstrated that the removal capacity of β-CD-APT nanorods for U(VI) (51 %) was higher than bare APT (38 %). The thermodynamic data indicated that the adsorption of U(VI) onto β-CD-APT nanorods was an endothermic and spontaneous process. The desorption results showed a reversible hysteresis loop for β-CD-APT, suggesting complete U(VI) desorption could happen without intervention. It is demonstrated that the β-CD-APT nanorods can be a promising material for the preconcentration and solidification of U(VI) in environmental cleanup.
    Journal of Radioanalytical and Nuclear Chemistry 10/2014; 302(1).
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    ABSTRACT: The uranium isotopic abundance and the 238U–226Ra secular equilibrium were determined in nine Hungarian coal slag samples. The 226Ra activity concentration was measured based on the radon decay products and also the 226Ra peak at 186 keV. Secular equilibrium existed in eight samples, whereas one sample showed a slight disequilibrium. The direct and fast measurement using only the 186 keV peak was validated which can be used after measuring the uranium isotopic ratio and verifying the 238U–226Ra secular equilibrium. This method can be used to measure the 226Ra content of high number of samples from the same geochemical background.
    Journal of Radioanalytical and Nuclear Chemistry 10/2014; 302(1).
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    ABSTRACT: The controlled synthesis of rhodium (Rh) and iridium (Ir) nanoparticles was carried out by gamma irradiation of aqueous solutions containing the metal precursor salt and polyvinylpyrrolidone (PVP). The nanoparticles were synthesized at various PVP and precursor concentrations with absorbed doses between 20 and 60 kGy. Nanoparticles with average sizes of 2.4 and 2.6 nm and narrow particle size distributions were obtained at metal precursor/PVP concentrations of 6/0.3 and 6/3 mM for Ir and Rh when irradiated at 60 kGy. The interaction of the nanoparticles surfaces with the PVP was studied.
    Journal of Radioanalytical and Nuclear Chemistry 10/2014; 302(1).
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    ABSTRACT: Following physical examination and radiography analysis, cystotomy was performed to remove a rabbit’s single bladder stone. This rabbit urolith was analyzed by X-ray fluorescence spectrometry (EDXRF) and scanning electron microscopy (SEM). The EDXRF technique was successful for the determination of major elements (Ca, Mg, P, K and S) and presented sufficient sensitivity to also trace elements (Sr, Fe, Cu, V, Cr, Mn, Zn and Pb) determination. The results showed significant quantitative and structural variations among the urolith regions. The EDXRF technique using the fundamental parameters method and SEM attend as complementary techniques that can be useful in the management of urinary stone analysis.
    Journal of Radioanalytical and Nuclear Chemistry 10/2014; 302(1).
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    ABSTRACT: A new metal matrix composite material has been developed to serve as a thermal neutron absorber for testing fast reactor fuels and materials in an existing pressurized water reactor. The performance of this material was evaluated by placing neutron fluence monitors within shrouded and unshrouded holders and irradiating for up to four cycles. The monitor wires were analyzed by gamma and X-ray spectrometry to determine the activities of the activation products. Adjusted neutron fluences were calculated and grouped into three bins—thermal, epithermal, and fast—to evaluate the spectral shift created by the new material. A comparison of shrouded and unshrouded fluence monitors shows a thermal fluence decrease of ~11 % for the shielded monitors. Radioisotope activity and mass for each of the major activation products is given to provide insight into the evolution of thermal absorption cross-section during irradiation. The thermal neutron absorption capability of the composite material appears to diminish at total neutron fluence levels of ~8 × 1025 n/m2. Calculated values for dpa in excess of 2.0 were obtained for two common structural materials (iron and nickel) of interest for future fast flux experiments.
    Journal of Radioanalytical and Nuclear Chemistry 10/2014; 302(1).

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