RADIOCHIMICA ACTA 出版涵盖核科学和技术化学方面的手稿。

The journal "Radiochimica Acta" publishes manuscripts covering research in nuclear science and technology as well as chemistry.

《Radiochimica Acta》期刊出版涵盖核科学与技术及化学领域的研究手稿。

Radiochimica Acta

Abstract Separation of trivalent actinide (An) and lanthanide (Ln) elements is one of the burning topics in the back end of the nuclear fuel cycle due to the similarity in their chemical behaviour. A significant amount of research is being carried out worldwide to develop suitable ligands for the separation of the trivalent actinides and lanthanides. Some of the research groups are engaged in continuous improvement of the di-ethylene-triamine-penta acetic acid (DTPA) based Ln/An separation method, whereas extensive research is going on for the development of the lipophilic and hydrophilic ‘N’ donor heteropolycyclic ligands as the actinide selective ligand. A number of ‘S’ donor ligands are also explored for the Ln/An separation. In the present review, we made an attempt to highlight various separation processes based on soft donor ligands developed for Ln/An separations. Beside the conventional solvent extraction processes, separation possibilities membrane based and solid phase extraction techniques are evaluated for the Ln/An separation and are compiled in the present review.

Arunasis Bhattacharyya

Prasanta K. Mohapatra

Separation of trivalent actinides and lanthanides using various ‘N’, ‘S’ and mixed ‘N,O’ donor ligands: a review

三价锕系和镧系元素的分离：使用各种‘N’、‘S’及混合‘N,O’供体配体的综述

Abstract Neptunium is one of the most important minor actinide elements with some of its isotopes having very long half-lives, therefore necessitating its separation from acidic radioactive wastes. Solvent extraction of Np 4+ and NpO 2 2+ was studied using three multiple diglycolamide (DGA) extractants with n -propyl, n -octyl and 3-pentyl substituents termed as L I , L II and L III , respectively, in a mixed diluent of 5% isodecanol and 95% n -dodecane. For comparison purpose, the extraction of Pu 4+ and UO 2 2+ was carried out under identical conditions. The extraction efficiency of the ligands for the tetravalent ions followed the trend: L II &gt; L I &gt; L III , which changed to L III &gt; L II &gt; L I for the hexavalent ions. While the extraction of the tetravalent ions was reasonably good (ca. 90–98%) with an extremely low (5.0 × 10 −5 M) ligand concentration, poor extraction (ca. 5–16%) of the hexavalent ions was seen even with a 20 times higher concentration of the ligand. In general, Pu 4+ was better extracted than Np 4+ , while NpO 2 2+ was marginally better extracted then UO 2 2+ . A ‘solvation’ type extraction mechanism was proposed based on the extraction profiles obtained as a function of the concentrations of the feed nitric acid, extractant as well as nitrate ion. The extracted species were found out to be M(NO 3 ) 4 ·mL and MO 2 (NO 3 ) 2 ·nL (M = Np or Pu, 1 &lt; m &lt; 2, n ≃ 1).

Rajesh B. Gujar

Parveen K. Verma

Mudassir Iqbal

Jurriaan Huskens

Willem Verboom

Extraction of tetra- and hexavalent actinide ions from nitric acid solutions using some diglycolamide functionalized calix[4]arenes

使用一些二甘醇酰胺功能化的杯[4]芳烃从硝酸溶液中提取四价和六价锕系离子

Abstract Extraction behavior of Np 4+ and Pu 4+ was investigated using several tetraalkylsubstituted diglycolamide (DGA) extractants such as N , N , N ′, N ′-tetrapentyl-diglycolamide (TPDGA), N , N , N ′, N ′-tetrahexyl diglycolamide (THDGA), N , N , N ′, N ′-tetraoctyl diglycolamide (TODGA), and N , N , N ′, N ′-tetradecyl diglycolamide (TDDGA). The organic phases used were 0.1 M solutions of the diglycolamide extractants in n -dodecane modified with 30% iso -decanol for avoiding third phase formation while the aqueous phases contained dilute nitric acid solutions spikes with the radiotracers. The stoichiometry of the extracted species was ascertained by ligand concentration variation experiments and was found to be M(NO 3 ) 4 · 2L, where M was Np and Pu and L was the substituted DGA ligand. In general, the extraction equilibrium constant (log K ex ) values for both Np 4+ and Pu 4+ showed an increasing trend with increasing alkyl group chain length and the log K ex values were higher for Pu 4+ as compared to those for Np 4+ . While for Np 4+ , the K ex values were 7.03 ± 0.04 for TPDGA which increased steadily up to 7.98 ± 0.05 for TDDGA, for Pu 4+ , the respective value for TPDGA was 7.32 ± 0.05 which increased to 7.78 ± 0.03 for TDDGA. Thermodynamic parameters were also determined for the two-phase extraction equilibrium reaction.

R. B. Gujar

G. B. Dhekane

P. K. Mohapatra

Liquid–liquid extraction of Np4+ and Pu4+ using several tetra-alkyl substituted diglycolamides

几种四烷基取代二甘醇酰胺对Np4+和Pu4+的液-液萃取

Abstract A novel and useful extraction spectrophotometric method for the rapid determination of uranium and free acidity in nuclear fuel process samples using the reagent, 2,3-dihydroxynaphthalene as an extractant as well as color forming agent is described. Uranium at milligram level forms a yellowish- orange anionic complex with the ligand, 2,3-dihydroxynaphthalene over a pH range, 10–12. This anionic complex is easily extracted into ethylacetate as an ion-pair complex with cetyltrimethylammonium cation (CTA + ). The absorbance of the ion-pair complex in ethylacetate is measured at 390 nm. The molar absorptivity and Sandell’s sensitivity of the system being 5.0×10 3 L·mol −1 cm −1 and 0.047 μg cm −2 , respectively at 390 nm. This very reagent (2,3-dihydroxynaphthalene) also forms a yellowish-orange nitro product with free nitric acid (HNO 3 ) in the presence of concentrated sulfuric acid. This nitro- product is easily extracted into the same solvent (ethylacetate) and absorbs maximum at 380 nm. The molar absorptivity (ε) and Sandell’s sensitivity of the system being 2.4×10 3 L·mol −1 cm −1 and 0.027 μg cm −2 , respectively. By using the single chromophoric agent (2,3-dihydroxynaphthalene), both uranium and free acidity can be easily and reliably determined separately in the process solution. The relative standard deviations (RSD) are in the range, 0.5–2.0% and 1.5–2.0%, respectively for uranium and free nitric acid determinations. The method has been applied to nuclear fuel process solutions, and the results obtained have been found to be favorably comparable with those obtained from standard methods.

Raghbendra Thakur

Pranab K. Tarafder

Raj Ranjan Jha

A novel method for the determination of uranium and free acidity in nuclear fuel process samples by extraction spectrophotometry

核燃料工艺样品中铀和游离酸度测定的新方法——萃取光度法

Abstract We summarize historical perspective of the transuranium elements, neptunium (Np) through lawrencium (Lr), and recent progress on production, and nuclear and chemical properties of these elements. Exotic decay properties of heavy nuclei are also introduced. Chemical properties of transuranium elements in aqueous and solid states are summarized based on the actinide concept.

Y. Nagame

M. Hirata

Production and properties of transuranium elements

超铀元素的制备与性质

Abstract The uptake of Eu, Th, U, and Pu by Korean granite and biotite gneiss was investigated in a series of batch experiments. Experiments were conducted under well-defined redox conditions, i.e. , oxidizing (air), mildly reducing (Ar-atmosphere and buffered with hydroquinone, pe + pH ≈ 8–9), and strongly reducing (Ar-atmosphere and buffered with Na 2 S 2 O 4 , pe + pH ≈ 0.5–3). Radionuclide concentration, pH and E h were systematically monitored up to t ≤ 113 days after the addition of the radionuclide. The natural content of Eu, Th and U in pristine granite and biotite gneiss materials was quantified by means of alkaline fusion. Eu exhibited moderate sorption on biotite gneiss displaying higher distribution ratios ( R d ) compared to granite. This observation was possibly explained by the affinity of Ln(III)/An(III) towards biotite mineral absent in the investigated granite material. Strong sorption was observed for Th, U, and Pu in reducing systems where the predominance of the +IV oxidation state is expected. For these three systems, the strength of the uptake follows the order R d (Pu(IV)) &gt; R d (U(IV)) &gt; R d (Th(IV)), consistent with the hydrolysis strength of the corresponding aquo-ions. A significantly weaker sorption was observed for U and Pu under oxidizing conditions, although R d values are manifestly higher for Pu than U. Thermodynamic calculations for the oxidizing conditions predicted the predominance of U(VI) and Pu(V)/Pu(IV), explaining observed differences in retention under oxidizing conditions. These results contribute to a quantitative description and a better understanding of the retention of redox-sensitive radionuclides in crystalline host rocks. Emphasis is placed on the importance of utilizing both redox-stable probes ( e.g. , Eu, Th) and redox-sensitive actinides ( e.g. , U, Pu), as well as well-defined redox conditions for accurate predictions of radionuclide retention.

Hyeonjin Eun

Peter Gyula Szabo

Darlyn Rehhorn

Seungwoo Lee

Yongheum Jo

Marcus Altmaier

Jinyoung Lee

Xavier Gaona

Jong-Il Yun

Uptake of Eu, Th, U, and Pu by granite and biotite gneiss in Korean fresh groundwater under oxidizing and reducing conditions

韩国淡地下水中氧化和还原条件下花岗岩和黑云母片麻岩对铕、钍、铀和钚的吸收

Abstract The current study investigates the presence 222 Rn in tap water, natural spring water, and well water from various locations in Er-Rachidia, Morocco, to assess the potential radiological risks posed to the local community. Radon, a radioactive gas produced by the decay of uranium and thorium in rocks and soil, poses significant radiation hazards. Using a Nuclear Track Detector (LR-115), researchers investigated the presence of radon in water from wells, dams, and rivers. The highest radon concentrations are found in well water, with an average of 1.92 Bq/L. The concentration of river water is the lowest, coming in at 0.53 Bq/L, while the average concentration of dam water is 0.84 Bq/L. On average, the annual effective dosage for well water is 4.57 ms per year. The water dosages from dams range from 1.74 to 2.44 μSv/y, with 1.98 being the average. River water ranges from 0.51 to 1.69 mSv/y, averaging 1.24 µSv/y. The excess lifetime cancer risk varies significantly across water sources: 1.27 × 10−3 to 1.84 × 10−3 (average 1.60 × 10−3) for well water, 0.61 × 10−3 to 0.85 × 10−3 (average 0.69 × 10−3) for dam water, and 0.18 × 10−3 to 0.59 × 10−3 (average 0.43 × 10−3) for river water. The results dispel fears of significant radioactive dangers to the locals by suggesting that the measured radon concentrations are within the limits set by international organizations.

Khadour Said

Taha Yaseen Wais

Hassanain H. Al-Kazzaz

El Boukili Abderrahman

Laith A. Najam

Lhoucine Oufni

Moulay Brahim Sedra

Moha Amrane

M. I. Sayyed

Abdelmoneim Saleh

Howaida Mansour

Joseph Emmanuel Ndjana Nkoulou II

Assessing carcinogenic radon levels in water from Er-Rachidia, Morocco using LR-115 nuclear track detectors

评估摩洛哥Errachidia水中致癌氡水平使用LR-115核径迹探测器

Abstract Specific and accurate diagnostic tools are important to determine diagnosis for various lung diseases with complex characteristics. In this study, high-energy milling (HEM) was utilized to prepare micro-sized carbon from palm kernel shell charcoal as a potential aerosol agent for lung ventilation scintigraphy. The HEM parameters investigated in this experiment were milling time and ball-to-powder ratio (BPR), while the characterization of the obtained powder involves particle size distribution, porosity, specific surface area, and XRD pattern. The optimization of technetium-99m ( 99m Tc) labeling of the obtained carbon powder was carried out concerning SnCl 2 amount, carbon dosage, incubation time, and pH. The optimal milling time and BPR were 180 min and 5:1, respectively, resulting in Dx(50) of 1.71 µm. Generally, the 99m Tc labeling yield increased with the increase of SnCl 2 amount, carbon dosage, and incubation time, while it decreased as the pH increased. The optimal 99m Tc labeling condition, SnCl 2 amount of 300 µg, carbon dosage of 50 mg, incubation time of 30 min, and pH 5, resulted in an adsorption capacity of 178.89 TBq of 99m Tc/g carbon. These results demonstrate that aerosol scintigraphy agents can potentially be prepared from palm kernel shell charcoal with optimization of radiolabeling method, milling process, and further in vitro aerosol performance prior to pre-clinical and clinical stages.

Miftakul Munir

Indra Saptiama

Moch Subechi

Ahid Nurmanjaya

Marlina Marlina

Alfian M. Forentin

Veronika Y. Susilo

Maiyesni Maiyesni

Aulia A. Billah

Rudi Gunawan

Ahsanal Fikri

Fernanto Rindiyantono

Rohmad Salam

Imam Prasetyo

Teguh Ariyanto

Kurnia S. S. Putri

Development of technetium-99m (99mTc) labeled carbon from palm kernel shell as lung scintigraphy agent

钯-99m (99mTc)标记的棕榈仁壳碳作为肺闪烁显像剂的开发

Abstract A study was conducted to examine the production cross sections of nuclear reactions nat Fe(p,x) 56,57,58 Co, nat Cu(p,x) 63,65 Zn, nat Ti(p,x) 48 V, nat W(p,x) 182m,182g,184g,186 Re, nat Ti(α,x) 49,51 Cr, nat Cu(α,x) 66,67,68 Ga, and nat Fe(α,x) 57 Ni, 57 Co, within the low energy range. Experiments were performed using a 5 MV tandem (Pelletron) accelerator situated at the National Centre for Physics (NCP) in Islamabad, Pakistan we employed the foil activation technique and used an off-line gamma ray spectroscopy system having Genie 2,000 software to detect the reaction products. The data analysis indicated the production of a number of radioisotopes with important applications in nuclear, industrial and medical fields. We compared our measured results with previously evaluated data as well as with theoretical predictions from the TENDL-library, based on TALYS-1.9 code calculations, to validate our findings.

Naveed Muhammad

Muhammad Adil

Shuja Ul Mulk

Ishaq Ahmad

Javed Hussain

Turab Ali Abbas

Mahwish Anwer

Ayano Makinaga

Muhammad Shahid

Proton and alpha-particle activation studies of natFe, natCu, natTi and natW targets at low energies

低能质子和阿尔法粒子活化研究：natFe、natCu、natTi 和 natW 靶材

Abstract Male prostate cancer (PCa) is considered among the most fatal illnesses. Despite the recent decrease in prostate cancer incidence attributed to advancements in early detection and therapy, these reductions have not effectively mitigated the elevated fatality rate linked to this disease. The drug Nilutamide was effectively radiolabeled with technetium-99m, producing a radiochemical yield of 96 ± 0.14 % under optimal conditions. In our study, two cohorts of mice were utilized, namely the control group and the group with prostate cancer. Various biochemical parameters, including PSA levels in serum, were assessed, revealing a significantly elevated value in the group with prostate cancer, indicating potential tumor development. Furthermore, the activities of antioxidant enzymes (CAT, SOD) were notably lower in the group with prostate cancer compared to the healthy control group, while the oxidative activity reflected by MDA levels, the final product of lipid peroxidation, was higher in the prostate cancer group than in the healthy control group. The biodistribution analysis showed rapid localization of 99m Tc-Nilutamide in prostate cancer tissue after 2 h post-injection, with a substantial value of 11.4 ± 1.1 % I. D/g tissue. Consequently, it was deduced that radiolabeled 99m Tc-Nilutamide can serve as an effective imaging tool for prostate cancer.

M.H. Sanad

Safaa B. Challan

H.M. Essam

Fatma Y. Abdou

A.B. Farag

Design of a novel complex 99mTc-Nilutamide as a tracer for prostate cancer disorder detection in mice

一种新型复杂99mTc-尼鲁他胺作为小鼠前列腺癌紊乱检测示踪剂的设计

Abbreviation	Radiochim. Acta
Journal Impact	1.51
Quartiles(Global)	NUCLEAR SCIENCE & TECHNOLOGY(Q3)

ISSN	0033-8230, 2193-3405
h-index	73

Publication Information	Publisher: Walter de Gruyter GmbH，Publishing cycle: Monthly，Journal Type: journal，Open Access Journals: No
Basic data	Year of publication: 1962，Proportion of original research papers: 96.51%，Self Citation Rate:7.10%， Gold OA Rate: 5.02%
Average review cycle	网友分享经验：较慢,6-12周
Average recruitment ratio	网友分享经验：容易

Radiochimica Acta

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Separation of trivalent actinides and lanthanides using various ‘N’, ‘S’ and mixed ‘N,O’ donor ligands: a review

Extraction of tetra- and hexavalent actinide ions from nitric acid solutions using some diglycolamide functionalized calix[4]arenes

Liquid–liquid extraction of Np⁴⁺ and Pu⁴⁺ using several tetra-alkyl substituted diglycolamides

A novel method for the determination of uranium and free acidity in nuclear fuel process samples by extraction spectrophotometry

Production and properties of transuranium elements

Uptake of Eu, Th, U, and Pu by granite and biotite gneiss in Korean fresh groundwater under oxidizing and reducing conditions

Assessing carcinogenic radon levels in water from Er-Rachidia, Morocco using LR-115 nuclear track detectors

Development of technetium-99m (^99mTc) labeled carbon from palm kernel shell as lung scintigraphy agent

Proton and alpha-particle activation studies of ^natFe, ^natCu, ^natTi and ^natW targets at low energies

Design of a novel complex ^99mTc-Nilutamide as a tracer for prostate cancer disorder detection in mice