Published since June 20, 1962

Radiochimica Acta

International Journal for chemical aspects of nuclear science and technology

ISSN: 2193-3405

Editor-in-chief: Syed M. Qaim

Edited by: Thomas Albrecht-Schoenzart, Zhifang Chai, Silvia S Jurisson, Prasanta Kumar Mohapatra, Claire Le Naour, Akihiko Yokoyama

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About this journal

Objective
Radiochimica Acta (RCA) publishes manuscripts encompassing chemical aspects of nuclear science and technology. The journal is meant for scientists who are actively engaged in research work.

Topics

radiochemical study of nuclear reactions including heavy ion reactions
radiochemically determined nuclear data for applications
chemical effects of nuclear transformations
radiation chemistry
chemistry of the actinides, transactinides and other radioelements
radioanalytical chemistry
radiopharmaceutical chemistry
scientific and technological applications of radionuclides, stable isotopes and nuclear methods in all fields
environmental and ecological studies using radiochemical techniques
chemistry of the nuclear fuel cycle (especially partitioning)
chemistry of radionuclides in geomedia (especially speciation, migration, etc.)

Article formats
Original Papers, Review Articles, and Rapid Communications (short communications of more timely interest)

Your Benefits

Your benefits:

Specialized journal dedicated to all aspects of radiochemistry
Leading journal in the field
Fundamental and applied novel research results
Rigorous peer-review

History

The journal Radiochimica Acta was founded in 1962, under the patronage of the Nobel Laureate Otto Hahn, to cater for the publishing needs of the then fast expanding field of radiochemistry. In those days the radiochemists published their work in several different journals of chemistry and physics and had thus no platform of their own for technical communications. With the introduction of Radiochimica Acta a new era dawned for radiochemistry. Although published in Germany, right from its inception the journal aimed at inculating an international character and flavor. The international character has been maintained, continuously nurtured and further developed over its liefe of 50 years. Today all the articles are published in English language.

Visit our Special Jubilee Issue

Visit our open access journal Proceedings of Radiochemistry

Other publications in the field
P. Adloff, K. Lieser, G. Stöcklin,One Hundred Years after the Discovery of Radioactivity, De Gruyter 2008.

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Volumes 1 to 103.

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Volume 111 Issue 6

June 2023

Publicly Available June 1, 2023

Frontmatter

Page range: i-iii

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Original Papers

March 9, 2023

Investigation of charged-particle induced reactions on ²⁷Al up to 100 MeV leading to the formation of ²²Na and ²⁴Na

Deniz Canbula, Bora Canbula

Page range: 415-423

Abstract

Studies using theoretical models are of great importance for understanding of reaction process and its nature. In this study, nuclear level density model calculations of the cross sections of 27 Al are investigated by using TALYS 1.96 computer code. The cross section calculations of 27 Al( α ,x) 22 Na, 27 Al( α ,x) 24 Na, 27 Al(3He,x) 22 Na, 27 Al(3He,x) 24 Na, 27 Al(p,x) 22 Na and 27 Al(p,x) 24 Na reactions were carried out for incident particle energy up to 100 MeV. In these calculations, four nuclear level density models, namely constant temperature model (CTM), back-shifted Fermi gas model (BSFGM), generalized superfluid model (GSM) and recently proposed semi-classical Fermi gas model (CSCFGM) are used. This model is developed using the simplest model BSFGM. The most obvious difference between CSCFGM and other models is the inclusion of the collective effects in the base of the formulation. The predicted results are discussed and compared with each other and the available experimental data taken from EXFOR library. In order to better evaluate the model results, chi-squared values are calculated and compared with each other for all analyzed reactions. According to the chi-squared results, CSCFGM gives closer predictions to the experimental data compared with the other models in 4 of the 6 analyzed reactions. Therefore, in this study, it is presented that this model can be reliably used in the reaction cross section calculations.

March 20, 2023

Preparation and potential application of amino-functionalized titanosilicates to removal of Th(IV) in aqueous solutions: optimization using response surface methodology (RSM)

Saeid Alamdar Milani, Rasoul Neishabori Salehi, Peyman Manouchehri, Mohammad Faryadi

Page range: 425-438

Abstract

Mesoporous titanosilicates (TiSil) with a size of almost 25 nm were prepared by an alkali-assisted hydro-thermal route, as an choice for developing efficient adsorbents of Th(IV) ions. TiSil were functionalized with the amino functional group (-NH 2 ) from 3-aminopropyltriethoxysilane (APTES) by post-preparation method. The obtained amino-grafted titanosilicates (TiSilNH 2 ) were characterized by Scanning Electron Microscopy (SEM), Brunauer–Emmett–Teller (BET), X-ray Diffraction (XRD) and Fourier-Transform Infrared Spectroscopy (FTIR) techniques. Adsorption of Th(IV) ions on TiSilNH 2 was examined in aqueous solution. Response surface methodology (RSM) based on central composite design (CCD) was applied to optimize the four essential process variables namely initial pH and initial concentration of Th(IV) ions of aqueous solution, amount of adsorbent, and adsorption process temperature for the Th(IV) removal. The adequacy of the model was investigated, and it was deemed to be statistically significant. The optimal predicted adsorption capacity of TiSilNH 2 for Th(IV) ions was 83.04 mg/g and the actual value was 84.8 mg/g. The equilibrium adsorption data were fitted to Langmuir, Freundlich, Dubinin–Radushkevich and Temkin isotherm models. The equi-librium data were best re-presented by Langmuir isotherm model, showing maximum monolayer adsorption capacity of 87.71 mg/g. The thermodynamic parameters indicated that the Th(IV) adsorption on the TiSilNH 2 was a spontaneous, and endo-thermic process at the studied temperatures and occurred via physisorption. Adsorbent recovery by using 0.5 M HNO 3 solution for adsorbent reuse indicated that the adsorbent was regenerable and could be employed frequently.

March 28, 2023

Radiation fabrication of hybrid activated carbon and functionalized terpolymer hydrogel for sorption of Eu(III) and Sm(III) ions

Ahmed M. Elbarbary, S. E. A. Sharaf El-Deen, E. M. Abu Elgoud, G. E. Sharaf El-Deen

Page range: 439-457

Abstract

In this work, a hybrid composite of activated carbon (AC) functionalized with terpolymer hydrogel of polyvinyl alcohol/polyacrylamide/polyacrylic acid (PVA/PAAm/PAA) was prepared by γ-irradiation and used efficiently for sorption of Eu(III) and Sm(III) ions from aquatic solutions. Sewage sludge from the wastewater treatment plant was used to prepare AC, then activated by zinc chloride (ZnCl 2 ) and thermal treatment at 550 °C. The modification of AC by functionalized terpolymer has successfully occurred mainly to limit its precipitation and to increase its adsorption capacity which allowed capable interaction with the metal ions. Different advanced techniques were used to investigate the structure and properties of (PVA/PAAm/PAA)/AC composite before and after the sorption process. Using 20 kGy is sufficient to get gel fraction of 87.5% and equilibrium swelling was 39.1 g/g. The (PVA/PAm/PAA)/AC composite hydrogel showed a pH pzc at pH ∼3. FTIR and EDS confirmed the successful integration of the functional groups and constituent elements of AC into terpolymer hydrogel components. XRD results confirmed the typical diffraction peaks of AC in the composite and the calculated average crystallite size was 167.4 nm. The SEM morphology of AC appeared as grains distributed well into the composite. The effect of synthesized AC, PVA/PAAm/PAA and (PVA/PAAm/PAA)/AC sorbents were tested to uptake of Eu(III) and Sm(III) ions. The highest uptake was noticed for (PVA/PAAm/PAA)/AC composite and it was selected for studying the parameters affecting the sorption process such as pH, shaking time, initial concentration, and adsorbent dosage. Results of the experimental data showed that Langmuir isotherm and Pseudo-second-order kinetic models fit well the sorption process of both Eu(III) and Sm(III) ions with maximum sorption capacities of 173.24 and 160.41 mg/g and uptake percentage of 82.3% and 83.4%, respectively at the optimum conditions of pH 4, 180 min, 100 mg/L metal concentration and 0.01 g adsorbent mass. The thermodynamic parameters indicated endothermic and spontaneous nature of the sorption process. Additionally, the as-prepared composite afford high selectivity and uptake capacity for Eu(III) and Sm(III) ions at pH 4 even in the presence of competing cations; Cd(II), Co(II), Sr(II) and Cs(I). The (PVA/PAAm/PAA)/AC composite was used efficiently as a unique and selective adsorbent for the sorption of Eu(III) and Sm(III) ions.

April 21, 2023

Effect of varying Nd₂O₃ contents on the structure and mechanical properties of the radioactive waste form: aluminosilicate glass-ceramics

Pan Tan, Xiaoyan Shu, Lingshuang Li, Yanrong Cheng, Du Liu, Xiaoan Li, Xirui Lu, Yi Xie, Shunzhang Chen, Bing Liao, Faqin Dong

Page range: 459-470

Abstract

The magmatic diagenetic environment was simulated by high-temperature melting and natural cooling. A series of glass-ceramics with different Nd 2 O 3 contents were prepared by using complex component granite (aluminosilicate material). The phase evolution of the matrix at different temperatures was studied by X-ray diffraction (XRD). The structure of glass-ceramics was analyzed by infrared spectroscopy (IR) and scanning electron microscopy (SEM). The mechanical properties of glass-ceramics were also evaluated. The results showed that the glass transition of pure matrix begins at 1200 °C, and the sample with the highest degree of vitrification is obtained at 1500 °C. The addition of Nd 2 O 3 promoted the melting of Fe 3 O 4 crystal, resulting in the complete amorphous matrix when the Nd 2 O 3 amount is in the range of 20–26  wt .%. With the further increase of Nd 2 O 3 content, Nd-bearing feldspar first appeared. No raw material Nd 2 O 3 was found, indicating that the formation of Nd-bearing feldspar may increase the carrying capacity of the material. The Gaussian fitting results showed that the glass-ceramic samples with Nd 2 O 3 content of 29  wt .% are mainly composed of Q 2 and Q 3 structural units. In the EDS result, part of neodymium was clustered with small bright spots, while the spots were uniformly distributed on the sample surface as a whole. Meanwhile, the addition of Nd 2 O 3 increased the mechanical properties of the samples (3.20 g/cm 3 , 8.33 GPa for the sample with 29  wt .% of Nd 2 O 3 ). The results provide a strategy for the treatment of solid waste with radioactive residual actinides.

February 20, 2023

Production of ¹⁹²Ir sealed sources in Es Salam research reactor for non-destructive testing

Fateh Khechekhouche, Abderrahmane Ararem, M'hamed Salhi, Hocine Benkharfia, Mourad Kadouma, Mohamed Touiza

Page range: 471-479

Abstract

An iridium-192 miniature sealed source was produced by irradiation of 12 metal disks of natural iridium (470.5 mg) under a thermal neutron flux of 9.4 × 10 13 n cm −2 s −1 during 200 h in Es Salam research reactor (Algeria). The preliminary activity was measured after 10 days decay time by a CAPINTEC type CRC-712 M dose calibrator, the given activity was 1.9 × 10 11 Bq (5.2 Ci). To estimate source activity, a modeling of reactor core and irradiation container with the targets was made by MCNP5 code with and without iridium targets to evaluate the effect of the disturbance and reaction; the calculated activity using disturbed flux was comparable with that measured. A non-destructive test using 192 Ir sealed sources with GammaMat TSI type B(U) projectors was carried out to evaluate the integrity of the weld joint at the bend of a carbon steel pipe. The weld quality of two plates; carbon steel and stainless steel was also evaluated. In terms of sensitivity, the resulting gamma images matched well and reported a real finding on the state of tested samples.

December 26, 2022

Eco-friendly flaxseed mucilage biofilms fabricated by gamma irradiation

Heba A. Raslan, Rehab Sokary

Page range: 481-493

Abstract

With looming the global energy crisis and environmental problems Biodegradable green blends based on natural resources and biodegradable polymers have increasingly attracted many researches interest due to their advantages of low cost, use of renewable resource, and biodegradability. In this study, flaxseed mucilage (FM) was extracted with distilled water and utilised to make films with varying ratios of polyvinyl alcohol (PVA) and chitosan (Cs). Gamma irradiation was used as green method to improve the performance of the produced films. Then the films were characterized by scanning electron microscopy (SEM), Fourier transform infrared spectroscopy (FTIR), UV–vis spectrophotometry and XRD analysis. The tensile measurements, moisture content were used to evaluate the films’ qualities. When flaxseed mucilage is mixed with PVA/Cs blend, it forms films that are less resistive, less rigid, and more flexible, improves mechanical properties and thermal stability. Films containing mucilage and PVA/Cs blend exhibited a compact and homogeneous structure under SEM, confirming the FTIR spectra that suggested a chemical interaction between these three biopolymers. Based on all above properties of the developed films, it can be envisaged to use these films for packaging applications.

March 22, 2023

Grafting of heavy metal oxides onto pure polyester for the interest of enhancing radiation shielding performance

Sabina Yasmin, Nouf Almousa, Mohammad I. Abualsayed, Mohamed Elsafi

Page range: 495-502

Abstract

In the interest of obtaining new polyester, heavy metal oxides PbCO 3 , Bi 2 O 3 , and CdO with numerous ratios have been added to the polyester resin. Five samples of labeled PR-1, PR-2, PR-3, PR-4, and PR-5 were prepared for this study. The values of linear attenuation coefficients (LAC) of the new polyester samples were measured using an HPGe detector. In the interest of ensuring the experimental setup, the value of LAC obtained from the HPGe detector as well as the value of LAC calculated using Phy-X software, have both been placed in one graph, which revealed a consistent result. The experimental value of those new polyester samples has been measured within the energy region 0.06–1.332 MeV, whereas the theoretical values have been calculated within the energy limit of 0.015–15 MeV. The results of all the new polyester samples showed an uplifting trend according to the rising energy at 0.06, 0.66, 1.17, and 1.33 MeV. At energy 0.06 MeV, sample PR-5 ( ρ = 2.180 g/cm 3 ) showed the lowest half value layer (HVL) among the polyester samples. This result is due to the addition of Bi 2 O 3 and CdO into the samples’ composition, increasing their density and enhancing the polyester’s reduction ability. Considering the measured shielding parameters studied herein, it has been found that sample PR-5 (50 wt% Polymer resin, 25 wt% Bi 2 O 3 , 25 wt% CdO) had the highest shielding ability compared with the rest of the polyester samples.

Ahead of Print / Just Accepted

Ahead of Print / Just Accepted

Volume 111 (2023)

Volume 110 (2022)

Volume 109 (2021)

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5-year Journal Impact Factor	1.819
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Editorial

Editor-in-Chief
Professor Dr. Dr. h. c. mult. S. M. Qaim
s.m.qaim@fz-juelich.de
Forschungszentrum Jülich GmbH
Institut für Neurowissenschaften und Medizin
INM-5:Nuklearchemie
52425 Jülich
Germany

Editors
Professor Dr. T. E. Albrecht-Schönzart (albrecht-schmitt@chem.fsu.edu)
Professor Dr. Z. Chai (chaizf@mail.ihep.ac.cn)
Professor Dr. Ch. E. Düllmann (duellman@uni-mainz.de)
Professor Dr. S. S. Jurisson (jurissons@missouri.edu)
Professor Dr. P. K. Mohapatra (mpatra@barc.gov.in)
Dr. C. Naour (lenaour@ipno.in2p3.fr)
Professor Dr. A. Yokoyama (yokoyama@se.kanazawa-u.ac.jp)

Advisory Board
W. Cha, Daejon (France)
N. Dacheux, Monpellier (France)
R. Eichler, Villigen (Switzerland)
C. Ekberg, Gothenburg (Sweden)
N. D. M. Evans, Loughborough (United Kingdom)
M. Fassbender, Los Alamos (U.S.A.)
H. Geckeis, Karlsruhe (Germany)
J. John, Prague (Czech Republic)
S. N. Kalmykov, Moscow (Russia)
S. Lahiri (Kolkata)
V. K. Manchanda, Suwon (Korea)
Y. Nagame, Ibaraki (Japan)
S. Parry, Ascot (United Kingdom)
F. Rösch, Mainz (Germany)
Th. J. Ruth, Vancouver (Canada)
R. Taylor, Warrington (United Kingdom)
A. Türler, Bern (Switzerland)
M. S. Uddin, Dhaka (Bangladesh)
J. H. Zaidi, Islamabad (Pakistan)

Technical Editor
Birgit Zoglmeier
birgit.zoglmeier@degruyter.com

(Deutsch)

Online ISSN: 2193-3405
Print ISSN: 0033-8230
Type: Journal
Language: English
Publisher: De Gruyter (O)
First published: June 20, 1962
Publication Frequency: 12 Issues per Year
Audience: researchers in the field of radiochemistry

Radiochimica Acta

International Journal for chemical aspects of nuclear science and technology

Frontmatter

Investigation of charged-particle induced reactions on 27Al up to 100 MeV leading to the formation of 22Na and 24Na

Abstract

Preparation and potential application of amino-functionalized titanosilicates to removal of Th(IV) in aqueous solutions: optimization using response surface methodology (RSM)

Abstract

Radiation fabrication of hybrid activated carbon and functionalized terpolymer hydrogel for sorption of Eu(III) and Sm(III) ions

Abstract

Effect of varying Nd2O3 contents on the structure and mechanical properties of the radioactive waste form: aluminosilicate glass-ceramics

Abstract

Production of 192Ir sealed sources in Es Salam research reactor for non-destructive testing

Abstract

Eco-friendly flaxseed mucilage biofilms fabricated by gamma irradiation

Abstract

Grafting of heavy metal oxides onto pure polyester for the interest of enhancing radiation shielding performance

Abstract

Investigation of charged-particle induced reactions on ²⁷Al up to 100 MeV leading to the formation of ²²Na and ²⁴Na

Effect of varying Nd₂O₃ contents on the structure and mechanical properties of the radioactive waste form: aluminosilicate glass-ceramics

Production of ¹⁹²Ir sealed sources in Es Salam research reactor for non-destructive testing