Radiation protection dosimetry最新文献

{"title":"Development of a method for evaluation of absorbed doses in preclinical in vivo μCT.","authors":"Richard T Deyhle, Christian Bernhardsson, Lars E Olsson, Marie Sydoff","doi":"10.1093/rpd/ncaf023","DOIUrl":"https://doi.org/10.1093/rpd/ncaf023","url":null,"abstract":"<p><p>In vivo preclinical X-ray micro-computed tomography (μCT) imaging is widely used to obtain three-dimensional anatomical information of small animals. However, the potential for radiation exposure to influence experimental outcomes necessitates accurate dose estimation. The aim of this study was to develop a robust and reproducible method for estimating and evaluating absorbed doses in small animals undergoing preclinical in vivo μCT imaging. Absorbed doses were measured at four separate positions within a dedicated polymethyl methacrylate phantom using MCP-N (LiF, Cu, P) thermoluminescence dosemeters (TLDs) and a novel type of optically stimulated luminescence dosemeter (OSLD) made from household salt (NaCl). The findings were benchmarked against the vendor's absorbed dose estimates, revealing a discrepancy between the measured and provided values. The results for the OSLDs followed a similar trend to the TLDs, though significant statistical differences were found between the luminescent dosemeters and the vendor values. In this study, a method for measuring the absorbed doses from μCT systems was presented. The results indicate a need for thorough dose measurements prior to performing longitudinal imaging studies.</p>","PeriodicalId":20795,"journal":{"name":"Radiation protection dosimetry","volume":"201 13-14","pages":"868-876"},"PeriodicalIF":0.7,"publicationDate":"2025-08-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://www.ncbi.nlm.nih.gov/pmc/articles/PMC12392905/pdf/","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144966452","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"环境科学与生态学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Radionuclides in algae from Swedish coastal waters for over half a century.","authors":"Sören Mattsson, Kristina Eriksson Stenström, Guillaume Pédehontaa-Hiaa, Christian Bernhardsson, Mattias Jönsson, José Maria López-Gutiérrez, Victoria Lérida-Toro, Elena Chamizo Calvo","doi":"10.1093/rpd/ncaf070","DOIUrl":"https://doi.org/10.1093/rpd/ncaf070","url":null,"abstract":"<p><p>Samples of Fucus serratus and Fucus vesiculosus have been regularly collected at Särdal (56.76 N, 12.63E) on the Swedish west coast since 1967, for most of the time, every two months. In 2020, sampling of Fucus spp. was extended to 44 other locations along the Swedish west, south, and east coast for comparison with Särdal data. At seven of these locations, water samples and extra samples of Fucus spp. were also taken for 3H analysis. Measurements have been performed by gamma spectrometry, or by radiochemical separation followed by low background beta measurements, alpha spectrometry or accelerator mass spectrometry. Time variations of the measured concentrations of various radionuclides (3H, 14C, 60Co, 99Tc, 129I, 131I, 134Cs, 137Cs, 236U, 238U, 239Pu, and 240Pu) are reported. The concentrations have been correlated with emissions from the nuclear fuel reprocessing facilities at Sellafield (UK) and La Hague (France). Contributions from the nuclear power plants in Ringhals and Barsebäck have also been identified, as has fallout from Chernobyl still stored mainly in the sediments and water of the Baltic Sea. In recent decades, studies have shown increasing levels of 129I and 236U and decreases in 137Cs, 99Tc, and 239 + 240Pu concentrations over time. The 14C analyses show an impact of anthropogenic 14C from activities other than atmospheric nuclear weapons tests in the 1950s and 1960s. The considerable variation in the concentration of different radionuclides over time and along the coasts warrants further studies to determine the possible origin of these radionuclides and to map background data in the event of future releases.</p>","PeriodicalId":20795,"journal":{"name":"Radiation protection dosimetry","volume":"201 13-14","pages":"974-994"},"PeriodicalIF":0.7,"publicationDate":"2025-08-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://www.ncbi.nlm.nih.gov/pmc/articles/PMC12392896/pdf/","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144966475","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"环境科学与生态学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Projected external doses from an accidental release of ESS spallation-target products: time-dependence and radionuclide contribution.","authors":"Christopher Rääf, Robert Frost, Christian Bernhardsson, Guillaume Pédehontaa-Hiaa","doi":"10.1093/rpd/ncaf039","DOIUrl":"https://doi.org/10.1093/rpd/ncaf039","url":null,"abstract":"<p><p>The Swedish Radiation Safety Authority has presented a report on severe accident scenarios at the European Spallation Source (ESS) for dimensioning the emergency preparedness zones around the facility. The source-term in the scenario consisted of more than 80 tungsten-target spallation products with physical half-life (T½) exceeding 1 hour. The purpose of this study is to establish which of these radionuclides will become of highest importance in terms of the radiological consequences to residents in areas affected by an accident release. In analogy with accidents at nuclear power plants, where the fission product 137Cs is a key nuclide for estimating projected external doses to affected residents, a corresponding key nuclide for ESS is required for the emergency preparedness. Using existing accident source terms in combination with reported values on ecological half-times of the gamma emitter 137Cs, the external dose rates and cumulative doses per unit initial ground deposition of the suggested key-nuclide (182Ta) could be estimated. In terms of 50 y dose from a dry deposition of the released source-term, 172Lu (T½ = 6.7 d, supported by 172Hf with T½ = 1.87 y) contributes up to 50% of the 50 y dose, depending on the ecological half-times for the element. The isomer 178nHf (T½ = 31 y) is the second largest contributor to gamma-ray dose, followed by 182Ta (T½ = 115 d), that contribute with about 15% and 10% of the 50 y dose, respectively. The results thus suggest that 172Hf/172Lu may be more suitable for long-term follow-up of projected doses from accidental ESS releases than 182Ta.</p>","PeriodicalId":20795,"journal":{"name":"Radiation protection dosimetry","volume":"201 13-14","pages":"860-867"},"PeriodicalIF":0.7,"publicationDate":"2025-08-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://www.ncbi.nlm.nih.gov/pmc/articles/PMC12392911/pdf/","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144966478","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"环境科学与生态学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Experimental study of dosimetric properties of radiophotoluminescent glass dosemeters using high-energy X-rays.","authors":"Hao Qi, Xiang Du, Sheng-Ri Li, Chunyong Yang, Jin Wang","doi":"10.1093/rpd/ncaf079","DOIUrl":"10.1093/rpd/ncaf079","url":null,"abstract":"<p><p>This study evaluates the dosimetric performance of GD-302M radiophotoluminescent glass dosemeters (RPLGDs) under high-energy X-rays (6-15 MV) as a potential alternative to thermoluminescent dosemeters for radiotherapy audits in China. Key properties-dose linearity, uniformity, reproducibility, energy response, fading, build-up effects, and signal depletion-were systematically assessed using a medical linear accelerator under reference conditions. The results demonstrated excellent dose linearity (R2 = 0.9987, 1-4 Gy), uniformity (coefficient of variation = 0.9%), and reproducibility (standard deviation = 0.42%). Energy-dependent variations remained within 1.3%, while fading effects showed a cumulative signal loss of 3% over 110 d. Unpreheated RPLGDs retained 98% of preheated signals after 30 d, with minimal signal depletion per readout (0.016%). A water-to-solid phantom conversion coefficient of 0.998 was established. The total experimental uncertainty was 2.4%. These findings validate RPLGDs as a stable, reproducible, and cost-effective tool for enhancing radiotherapy quality assurance in resource-constrained settings.</p>","PeriodicalId":20795,"journal":{"name":"Radiation protection dosimetry","volume":" ","pages":"841-851"},"PeriodicalIF":0.7,"publicationDate":"2025-08-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144626993","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"环境科学与生态学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Optimizing radiation dose and image quality in neonatal mobile radiography.","authors":"Takahiko Maeda, Makoto Hara, Hiroyuki Yamasaki, Makoto Nakahara, Yoshinori Tanabe","doi":"10.1093/rpd/ncaf080","DOIUrl":"10.1093/rpd/ncaf080","url":null,"abstract":"<p><p>Children are more susceptible to radiation exposure than adults. Therefore, determining an appropriate radiation dose requires balancing and minimizing radiation exposure while maintaining image quality (IQ) for accurate diagnosis. We evaluated the optimal radiation dose parameters for neonatal chest and abdominal mobile radiography by assessing entrance surface dose and IQ indices. A range of exposure parameters was tested on neonatal and acrylic phantoms, and the optimal settings were determined through visual and physical evaluations. Overall, 65 kVp and 1.2 mAs provided the best balance between minimizing radiation exposure and maintaining high IQ for neonates. This study offers essential insights into optimizing radiographic conditions for neonatal care, contributing to safe and effective radiological practices. These optimized parameters can help guide future clinical applications by ensuring reduced radiation risk and enhanced diagnostic accuracy.</p>","PeriodicalId":20795,"journal":{"name":"Radiation protection dosimetry","volume":" ","pages":"812-820"},"PeriodicalIF":0.7,"publicationDate":"2025-08-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://www.ncbi.nlm.nih.gov/pmc/articles/PMC12341940/pdf/","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144660039","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"环境科学与生态学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Comprehensive investigation of radiation protection in veterinary hospitals in Changzhou, China.","authors":"Qiang Wang, Qiang Fu, Sheng Yang","doi":"10.1093/rpd/ncaf075","DOIUrl":"10.1093/rpd/ncaf075","url":null,"abstract":"<p><p>To assess the current status of radiation protection in Changzhou veterinary hospitals. Questionnaires were used to survey the veterinary hospitals and their radiation workers, questions included veterinary hospitals' basic information, location, type of X-ray diagnostic equipment, and personal information, status survey, the radiation cognition of the radiation workers. In search of veritable data for the estimation of occupational doses, an AT1123 radiation survey dosemeter was used to simulate the measurement of the ambient dose equivalents around the head and neck of a radiation worker operating in the imaging room. RaySafe RF was used to measure the air kerma at the center of the irradiation field and 0.5 cm from it. RaySafe RF and related phantoms were used for performance tests of X-ray diagnostic equipment. A total of 118 veterinary hospitals, 118 radiation workers, and 119 X-ray diagnostic equipment were surveyed. Among the 119 X-ray diagnostic equipment, 118 were DR (Digital Radiography) for veterinary practice, and 1 was a general-purpose CT scanner. The 118DRs cover 31 brands (manufacturers), the top six brands of DRs accounted for 68% of the total. A portion of the veterinary hospitals did not fully consider radiological protection in site selection (most veterinary hospitals were located near shops or residential areas), imaging room location (only 53 X-ray diagnostic devices are set on the first floor), and imaging room shielding. One hundred and seventeen (98.3%) X-ray diagnostic equipment needs to be operated while the radiation workers stay in the imaging room. Individual monitoring of occupational external exposure was carried out in 117 (99.2%) veterinary hospitals, and 59 (50.0%) did not carry out health surveillance for radiation workers. Twenty three (19.5%) veterinary hospitals placed Thermoluminescent Dosimeter (TLDs) in the imaging room or even next to the X-ray tube. The vast majority of radiation workers manually restrained pets (93.2%) and the majority (84.7%) of radiation workers refused to wear lead gloves during restraints, resulting in occasional exposure of their hands to the primary beam. The performance tests of X-ray diagnostic equipment of six DRs found that DRs of four (66.6%) brands had unqualified indexes, and the main unqualified indexes were the linearity of tube output of two DRs (33.3%) and alignment of X-ray field of three DRs (50.0%). The air kerma in the irradiation field of DRs ranged from 122.3 to 410.4 uGy, and there were obvious differences between the air kerma in the irradiation field and out of it (Z = -5.125， P <.001). The ambient dose equivalents around the head and neck of animal restrainers ranged from 22 to 182 nSv. The site selection of the veterinary hospitals, and the placement of the imaging room are not optimized because of the lack of occupational hazard assessment, the routine performance tests of X-ray diagnostic equipment are not carried out, and the occupational health ex","PeriodicalId":20795,"journal":{"name":"Radiation protection dosimetry","volume":" ","pages":"831-840"},"PeriodicalIF":0.7,"publicationDate":"2025-08-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144691353","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"环境科学与生态学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Radiation doses for pediatric cardiac computed tomography angiography: weight-based radiation typical values at a tertiary hospital in southern Thailand.","authors":"Tshering Yangdon, Supika Kritsaneepaiboon, Saowapark Poosiri","doi":"10.1093/rpd/ncaf072","DOIUrl":"10.1093/rpd/ncaf072","url":null,"abstract":"<p><p>This study determined weight-based median radiation dose levels or typical values as defined by the International Commission on Radiological Protection of pediatric cardiac computed tomography angiography (CTA) in a tertiary hospital. A total of 211 cardiac CTA studies from 194 children (<15 years old) were retrospectively analyzed. The study examinations were organized into categorized base on body weight ranges. The typical values for CTDIvol(mGy) and DLP(mGy.cm) were respectively determined for each weight band as follows: <5 kg(n = 42): 1.02,12.16; 5 ≤ 15 kg(n = 57): 1.42, 25.0; 15 ≤ 30 kg(n = 53): 2.15, 40.94; 30 ≤ 50 kg(n = 26): 3.80, 100.04; and 50 ≤ 80 kg(n = 3): 8.06, 212.23. The overall median (interquartile range) for each CT dose parameter were as follows: E = 1.80 (1.16-2.83) mSv, SSDEDw = 3.23 (2.54-4.78) mGy, SSDEAP = 3.17 (2.51-4.68) mGy, SSDELAT = 3.18 (2.54-4.50) mGy, SSDEAP + LAT = 3.25 (2.60-4.57) mGy, and SSDEEff = 3.21 (2.57-4.55) mGy. Further research is needed to develop local, regional, and national weight-based lifetime attributable risks for cardiac CTA in children.</p>","PeriodicalId":20795,"journal":{"name":"Radiation protection dosimetry","volume":" ","pages":"821-830"},"PeriodicalIF":0.7,"publicationDate":"2025-08-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144660040","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"环境科学与生态学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Analysis of occupational radiation doses in nuclear medicine and radiography students during clinical training.","authors":"George Rouvalis, Pradip Deb, Mohamed Khaldoun Badawy","doi":"10.1093/rpd/ncaf083","DOIUrl":"10.1093/rpd/ncaf083","url":null,"abstract":"<p><p>An analysis compared the occupational radiation doses received by Nuclear Medicine Technologist (NMT) and radiography students during their clinical training at an Australian University from 2017 to 2020. Utilising Optically Stimulated Luminescence dosemeters to measure the personal dose equivalent, the retrospective cohort included students with dose readings above 100 μSv per monitoring period. Of the total number of students monitored, ~68% received doses below the minimum reportable threshold of 100 μSv per monitoring period, suggesting that most students had minimal exposure during their placements. A chi-square test revealed a significant difference between NMT and radiography students in the proportion of doses below this threshold (Hp(10): χ2(1, N = 1367) = 168.24, P < .001; Hp(0.07): χ2(1, N = 1367) = 139.27, P < .001). Analysing doses above this threshold revealed that NMT students had significantly higher median radiation doses than radiography students, with median Hp(10) doses of 161 μSv versus 130 μSv, respectively (P < .001). Year-to-year analysis indicated that NMT student doses remained stable over the study period, while radiography student doses varied significantly. Comparison with hospital staff doses showed that NMT students received significantly lower doses than professional NMTs (P < .001), whereas radiography students received higher doses than professional radiographers (P < .001). After limiting hospital staff doses to include those only above 100 μSv in a reporting period, radiography students still received higher doses than professional radiographers. The elevated exposure among NMT students compared to radiography students however, emphasizes the need for enhanced radiation protection strategies in nuclear medicine education, emphasising specialized training and regular dose assessments to ensure student safety without compromising educational quality.</p>","PeriodicalId":20795,"journal":{"name":"Radiation protection dosimetry","volume":" ","pages":"803-811"},"PeriodicalIF":0.7,"publicationDate":"2025-08-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144660038","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"环境科学与生态学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Experimental testing and simulation analysis of radiation shielding performance of 90SR-90Y radiation sources using different materials.","authors":"Yi Han, Xiaomiao Chi, Qinjian Cao, Liye Liu, Yuchen Liu, Faguo Chen","doi":"10.1093/rpd/ncaf077","DOIUrl":"10.1093/rpd/ncaf077","url":null,"abstract":"<p><p>The study investigated the maximum range of 90Sr-90Y sources in different shielding materials and assessed β-directional dose equivalent rates and γ ambient dose equivalent rates across varying thicknesses of shielding. Results indicated: (1) Significant differences in 90Sr-90Y source ranges among materials, with the shortest β-ray range observed in tungsten alloy (0.00 to 0.50 mm) and high-purity lead (0.5 to 1.0 mm). (2) Generally, there was good agreement between experimental and simulation data, except at a thickness of 0.5 mm for high-purity lead, where a deviation of 51.4 per cent in β-directional dose rates was observed, likely due to errors in the lead cross-section data. (3) Comparative analysis demonstrated that combinations such as \"304 + W\" or \"304 + Pb\" offer enhanced shielding effectiveness against 90Sr-90Y sources. This study provides valuable insights for selecting β-radiation shielding materials and structures.</p>","PeriodicalId":20795,"journal":{"name":"Radiation protection dosimetry","volume":" ","pages":"775-785"},"PeriodicalIF":0.7,"publicationDate":"2025-07-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144637811","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"环境科学与生态学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Cost-effective shielding design based on the dose length product method for shielding calculations in X-ray computed tomography systems.","authors":"Kimiya Noto, Wataru Mitsui, Tadanori Takata, Hironori Kojima, Kosuke Matsubara, Ichiro Yamaguchi","doi":"10.1093/rpd/ncaf078","DOIUrl":"10.1093/rpd/ncaf078","url":null,"abstract":"<p><p>In medical facilities, pre-shielding calculations are essential when introducing new X-ray equipment to protect the staff from radiation. For computed tomography (CT), the dose length product (DLP) method is commonly used for shielding calculations. This method allows the evaluation of the dose at any wall position. This study proposed a cost-effective design for CT room shielding, adjusting the material thickness based on the operator's exposure and the room's environment. Scattered radiation was measured using an optically stimulated luminescence dosemeter. The calculated values were 2.0 to 7.5 times higher than the measured values inside the CT room, confirming the accuracy of the DLP method in estimating the actual dose. No scattered radiation was detected outside the CT room. This study demonstrates that the DLP method enables pre-installation shielding calculations that balance cost and safety.</p>","PeriodicalId":20795,"journal":{"name":"Radiation protection dosimetry","volume":" ","pages":"795-801"},"PeriodicalIF":0.7,"publicationDate":"2025-07-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144619934","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"环境科学与生态学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}