Applied Radiation and Isotopes最新文献

{"title":"Adverse reactions to therapeutic radiopharmaceuticals","authors":"","doi":"10.1016/j.apradiso.2024.111527","DOIUrl":"10.1016/j.apradiso.2024.111527","url":null,"abstract":"<div><div>Radiopharmaceuticals are drugs used in treatment or diagnosis that contain a radioactive part, usually a pharmaceutical part in their structure. Adverse drug reactions are harmful and unexpected responses that occur when administered at normal doses. Although radiopharmaceuticals are regarded as safe medical products, adverse reactions should not be ignored. More serious adverse reactions such as myelosuppression, pleural effusion, and death may develop in therapeutic radiopharmaceuticals due to their use at higher doses than those used in diagnosis. Therefore, monitoring adverse reactions and reporting them to health authorities is important. This review aims to provide information about adverse reactions that may be related to radiopharmaceuticals used in treatment.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":null,"pages":null},"PeriodicalIF":1.6,"publicationDate":"2024-09-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142323801","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Conceptual design of sandwich walls for shielding against secondary neutrons using MC simulations with FLUKA","authors":"","doi":"10.1016/j.apradiso.2024.111525","DOIUrl":"10.1016/j.apradiso.2024.111525","url":null,"abstract":"<div><div>FLUKA Monte-Carlo transport code was employed to evaluate the secondary neutron spectra emerging from spherical sandwich shielding configurations composed of concrete and soil, similar to that used at the particle therapy facility MedAustron. This study provides a comparative analysis of neutron spectra attenuated by a concrete-soil-concrete (CSC) sandwich wall shielding configuration versus a full concrete wall design (CCC). Furthermore, we enhanced the shielding performance of the CSC configuration by adding an additional concrete layer (CCSC) to achieve results comparable to the CCC shielding. Two scenarios were tested for shielding performance: (1) primary protons at 100 MeV, and (2) primary carbon ions (C-ions) at 190 MeV/u. Our simulations with primary protons of 100 MeV showed that adding additional internal concrete wall to the CSC configuration, therefore designing the CCSC configuration, the RP performance becomes slightly improved – the HE-peak drops from (1.43 ± 0.11)10⁻¹¹ to (5.62 ± 0.3)10⁻¹², about 2.5 times. Still, the HE-peak of the exiting neutron spectrum from CCC -(6.29 ± 1.87) 10⁻¹³ is about 9 times lower than that exiting CCSC - (5.62 ± 0.3) 10⁻¹².</div><div>Our simulations with primary C-ions showed that by placing an additional internal concrete wall to the CSC configuration (CCSC) the RP performance becomes slightly improved – the exiting HE peak can be further attenuated from (6.92 ± 0.40)10⁻⁹ for CSC to (3.79 ± 0.15)10⁻⁹, becoming comparable to the one exiting the CCC configuration, (0.92 ± 0.04)10⁻⁹, only 4 times higher. Future research should be focused on improvements of the RP performance of the CCSC, by increasing the soil layer thickness and taking into consideration the humidity (water content) in the soil and concrete and also improve the number of primaries to 10⁹ or even 10¹⁰ for better statistical outcome.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":null,"pages":null},"PeriodicalIF":1.6,"publicationDate":"2024-09-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142323800","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Feasibility of new polymeric matrices in the production of ferrous sulphate dosimeters","authors":"","doi":"10.1016/j.apradiso.2024.111526","DOIUrl":"10.1016/j.apradiso.2024.111526","url":null,"abstract":"<div><div>External beam radiotherapy is a treatment modality that employs high doses for curative or palliative purposes. Safety in such treatments, particularly with high-precision equipment, necessitates strict adherence to quality control protocols to ensure the efficacy of oncological treatments. In this context, chemical dosimeters, particularly the Fricke gel, have emerged as valuable tools for quantitatively analysing absorbed radiation doses. These dosimeters can be applied both as tissue-equivalent phantoms and as radiation detectors in radiotherapy centers. The objective of this study was to evaluate the feasibility of new gelling matrices, comprising common materials such as CMC, GGU, and PVA, for producing ferrous sulphate dosimeters aimed at the relative quantification of radiation dose. A rheological study was conducted for different Fricke gel dosimetric formulations. Initially, the performance of these dosimeters, produced at various gel concentrations, was evaluated in terms of their consistency at room temperature. This was achieved through the straightforward process of humidification the gels with glycerine. These matrices consist of both natural and synthetic polymers that are readily accessible, easy to handle, and can be easily incorporated into the acidic ferrous sulphate solution. Parameters such as the influence of gelling matrix concentration, linearity, and stability were assessed and correlated with those previously investigated for Fricke gel produced with bloom 300 pig skin gelatine (GEL). Ferrous sulphate dosimeters fabricated with sodium carboxymethylcellulose (CMC), guar gum (GGU), and polyvinyl alcohol (PVA) exhibited a coefficient of variation of less than 1% relative to the dose response evaluated in this study. By using readily available and easily manageable materials, it is possible to replicate dosimeters with a favourable dosimetric response for high-dose measurements.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":null,"pages":null},"PeriodicalIF":1.6,"publicationDate":"2024-09-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142318669","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Radiolabeling and preclinical evaluation of technetium-99m labeled colistin","authors":"","doi":"10.1016/j.apradiso.2024.111524","DOIUrl":"10.1016/j.apradiso.2024.111524","url":null,"abstract":"<div><h3>Introduction</h3><p>Antibiotic resistance is a burden on the healthcare system. In present study, we have labeled an antibiotic named Colistimethate sodium (CMS) with technetium-99m (^99mTc) to develop a SPECT based imaging tracer.</p></div><div><h3>Methods</h3><p>We standardised the labeling using 0.5–2 mg of CMS (in water) using stannous chloride dihydrate as a reducing agent followed by addition of 370 ± 74 MBq of ^99mTc. A group of mice were injected intravenously (in tail vein) with 4–6 MBq of [^99mTc]Tc-CMS diluted with saline and euthanized at various time intervals. microSPECT Imaging (ϒ-eye) was acquired to study the biodistribution in the healthy mice.</p></div><div><h3>Results</h3><p>We standardised the labeling using 0.5 mg of colistin in 0.5 ml of saline with addition of 30 μg stannous chloride dihydrate. The retention factor value was 0.1–0.3 as compared to 0.9–1.0 for free ^99mTc by TLC and retention time was found to be 14.2 ± 1.3 min as evaluated by HPLC. The biodistribution data showed uptake in lungs, spleen, and liver at 30 min but the uptake decreased in lung at 60 min. The imaging data corroborated with the biodistribution data.</p></div><div><h3>Conclusions</h3><p>We could successfully label [^99mTc]Tc-CMS ^99mTc and we could study its biodistribution in healthy mice.</p></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":null,"pages":null},"PeriodicalIF":1.6,"publicationDate":"2024-09-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142243762","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Thermoluminescence and optically stimulated luminescence studies of Gypsum for retrospective dosimetry","authors":"","doi":"10.1016/j.apradiso.2024.111523","DOIUrl":"10.1016/j.apradiso.2024.111523","url":null,"abstract":"<div><p>This study examines the use of gypsum for radiation dosimetry using Thermoluminescence (TL) and Optically Stimulated Luminescence (OSL) techniques. It is observed that gypsum preserves the information of radiation dose despite the loss of water upon heating in a laboratory. Deconvolution of the thermoluminescence glow curve suggests thermoluminescence glow peaks at 125, 150, 280, 320, and 440 °C. The glow peak at 440 °C has a minimum detectable dose of 200 mGy, and it bleaches to approximately 50% with 300 min of daylight exposure. The Blue Light Stimulated Luminescence (BLSL) comprises a slow component and is correlated to 255 °C TL glow peak. The alpha efficiency of luminescence production per unit Gy of alpha dose with respect to the beta dose for the TL glow peaks at 440 °C is calculated at 0.18 ± 0.01. For BLSL, the value is calculated at 0.15 ± 0.01. A measurement protocol for the use of gypsum for retrospective dosimetry is also presented.</p></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":null,"pages":null},"PeriodicalIF":1.6,"publicationDate":"2024-09-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142173690","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Design of a mixed material moderator in a beam-shaping assembly for proton accelerator-based boron neutron capture therapy","authors":"","doi":"10.1016/j.apradiso.2024.111515","DOIUrl":"10.1016/j.apradiso.2024.111515","url":null,"abstract":"<div><p>Boron Neutron Capture Therapy is being promoted with the development of accelerator neutron sources, and many new accelerator-based BNCT facilities are being built. In Particle Accelerator Facility project of Sun Yat-sen University, we plan to build a terminal for BNCT research based on an 8 MeV, CW 3 mA proton accelerator. In this paper, we present a beam-shaping assembly for this proton accelerator with such low 24 kW beam power, using composite moderator materials composed of five elements: Mg, Al, F, O, and Li. The calculation result of FLUKA with ENDF/B and JENDL libraries shows that the epithermal neutron beam flux is <span><math><mrow><mn>1.57</mn><mo>×</mo><msup><mn>10</mn><mn>9</mn></msup><mi>n</mi><mo>/</mo><msup><mtext>cm</mtext><mn>2</mn></msup><mo>/</mo><mi>s</mi></mrow></math></span> with the CW 3 mA proton beam. The fast neutron component and the gamma ray component under free-air condition are <span><math><mrow><mn>1.49</mn><mo>×</mo><msup><mn>10</mn><mrow><mo>−</mo><mn>13</mn></mrow></msup><mspace></mspace><mtext>Gy</mtext><mo>∙</mo><msup><mtext>cm</mtext><mn>2</mn></msup></mrow></math></span> and <span><math><mrow><mn>8.12</mn><mo>×</mo><msup><mn>10</mn><mrow><mo>−</mo><mn>14</mn></mrow></msup><mspace></mspace><mtext>Gy</mtext><mo>∙</mo><msup><mtext>cm</mtext><mn>2</mn></msup></mrow></math></span> respectively, in line with IAEA-TECDOC-1223 design recommendations. The thermal analysis shows that the maximum temperature of beryllium target is 706.5 K, and the structure materials of BSA do not melt.</p></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":null,"pages":null},"PeriodicalIF":1.6,"publicationDate":"2024-09-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142173592","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Personalized selection of unequal sub-arc collimator angles in VMAT for multiple brain metastases","authors":"","doi":"10.1016/j.apradiso.2024.111513","DOIUrl":"10.1016/j.apradiso.2024.111513","url":null,"abstract":"<div><h3>Purpose</h3><p>Investigating the effects of unequal sub-arc personalized collimator angle selection on the quality of Volumetric Modulated Arc Therapy (VMAT) plans for treating multiple brain metastases.</p></div><div><h3>Methods</h3><p>This study included 21 patients, each with 2–4 target volumes of multiple brain metastases. Two stereotactic radiotherapy (SRT) approaches were utilized: sub-arc collimator VMAT (SAC-VMAT) and fixed collimator VMAT (FC-VMAT). In the SAC-VMAT group, multi-leaf collimators (MLC) shaped the target area, dividing the full arc into four unequal sub-arcs under the beam's eye view (BEV). Each sub-arc had an appropriate collimator angle selected to mitigate ‘island blocking problems'. Conversely, the FC-VMAT group used a fixed collimator angle of 15° or 345°. A comparative analysis of the dosimetric parameters of the target volumes and normal tissues, along with the monitor units (MU), was conducted between the two groups.</p></div><div><h3>Results</h3><p>The mean dose and dose-volume to normal brain tissue (2–26 Gy, with a step of 2 Gy) were significantly lower in the SAC-VMAT group (P &lt; 0.01). There was no statistical difference between the two groups in dose to the target volumes, conformity index (CI), homogeneity index (HI), and other normal tissues (P &gt; 0.05). Compared with the FA-VMAT group, the SAC-VMAT group significantly reduced the gradient index (GI) (4.5 ± 0.59 vs 5.2 ± 0.75, P &lt; 0.001) and MU (1774.33 ± 181.77 vs 2001.0 ± 344.86, P &lt; 0.001). Notably, with an increase in the number of PTV, the SAC-VMAT group demonstrated more significant improvements in the dose-volume of normal brain tissue, GI, and MU.</p></div><div><h3>Conclusions</h3><p>In this study, personalized selection of the unequal sub-arc collimator angle ensured the prescribed dose to the PTV, CI, and HI, while significantly reducing the GI, MU, and the dose to normal brain tissue in the VMAT plan for multi-target brain metastases in the cohort of cases with 2–4 target volumes. Particularly as the number of targets increase, the advantages of this method become more pronounced.</p></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":null,"pages":null},"PeriodicalIF":1.6,"publicationDate":"2024-09-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142173689","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Thermoluminescence (TL) properties of Eu3+ incorporated with CaB4O7 phosphors prepared by solution-combustion process","authors":"","doi":"10.1016/j.apradiso.2024.111522","DOIUrl":"10.1016/j.apradiso.2024.111522","url":null,"abstract":"<div><p>The solution-combustion approach was used to create CaB₄O₇:Eu³⁺phosphors using Ba (NO₃)₂, Eu (NO₃)₃·5H₂O, H₃BO₃, NH₃(ON)H₂, and NH₄NO₃ as source materials. We investigated the thermoluminescence (TL) characteristics of beta (<span><strong>β</strong></span>)-irradiated CaB₄O₇:Eu³⁺. When the TL intensity was evaluated at different dosages of <span><strong>β</strong></span>, it rose with the dose. Changes in peak temperature were observed because of the investigation of the effects of varying heating rates on TL glow curves. Moreover, the positions of the peak temperature and the TL intensity did not change when the same sample was measured again, suggesting that the sample was stable. Additionally, the study calculated several kinetic parameters, including activation energy (E), frequency factor (s), and geometrical factor (<span><strong><em>μ</em></strong></span>g), for distinct TL glow curves. Through geometric analysis of TL glow peaks, the study determined activation energies and kinetic orders, enabling the calculation of the frequency factor. The findings highlight the suitability of the prepared phosphor for dosimetry and provide insights into trap characteristics crucial for continuous illumination at room temperature. The study also emphasises the importance of optimising trap depth for prolonged afterglow, shedding light on the interplay between trap energies and luminescence characteristics. These findings deepen our comprehension of phosphor behavior and open the door to better dosimetry applications.</p></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":null,"pages":null},"PeriodicalIF":1.6,"publicationDate":"2024-09-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142244132","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Half-life determination of 72Ga","authors":"","doi":"10.1016/j.apradiso.2024.111517","DOIUrl":"10.1016/j.apradiso.2024.111517","url":null,"abstract":"<div><p>Gallium-72 is an important Comprehensive Nuclear-Test-Ban Treaty relevant radionuclide that arouses significant interest. However, the reported half-lives of ⁷²Ga are discrepant. In the current work, three solution samples of different concentrations were prepared and sequentially measured by a high-purity Germanium (HPGe) spectrometer. The count rates as a function of time of the 834.1 keV and 630.0 keV γ-lines were followed for the half-life determination. Through mass normalization, the datasets of three samples are combined and the statistical uncertainties are reduced. Half-life values were derived from datasets of each sample and mass normalization and corresponding complete uncertainty budgets are presented. The final half-life determined for ⁷²Ga is 13.94 (2) h, showing a deviation of 1.12% from the last nuclear data sheets (NDS) recommended value. Comparing with the values of previous publications, the result from this work is smaller than most results and consistent with the latest value which has one large uncertainty. A recommended value of 14.07 (3) h is estimated using the power-moderated mean (PMM) method.</p></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":null,"pages":null},"PeriodicalIF":1.6,"publicationDate":"2024-09-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142173688","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"TDCRPy: A python package for TDCR measurements","authors":"","doi":"10.1016/j.apradiso.2024.111518","DOIUrl":"10.1016/j.apradiso.2024.111518","url":null,"abstract":"<div><p>The TDCR (Triple-to-Double Coincidence Ratio) measurement technique is a primary standardization method used by metrology laboratories to accurately determine the activity of radioactive solutions, particularly for radionuclides unsuitable for traditional coincidence counting methods, such as pure beta emitters. The TDCR method leverages a liquid scintillation counter equipped with three photomultiplier tubes (PMTs). This paper introduces TDCRPy, a novel Python package developed by the BIPM, designed to calculate detection efficiency of liquid scintillation counters using Monte Carlo simulations and decay data evaluations from the Decay Data Evaluation Project (DDEP). The software simulates particle interactions within the liquid scintillation counter, utilizing pre-calculated probability distributions for energy deposition. Comparisons with the PENNUC/NUR code and tests with measurement from the BIPM.RI(II)-K1.Co-60 key comparison demonstrate the potential of TDCRPy. This open-source package is distributed at <span><span>https://pypi.org/project/TDCRPy</span><svg><path></path></svg></span> and available for collaborative development on GitHub <span><span>https://github.com/RomainCoulon/TDCRPy</span><svg><path></path></svg></span>, where detailed user documentation can be found.</p></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":null,"pages":null},"PeriodicalIF":1.6,"publicationDate":"2024-09-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142173591","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}