Health physics最新文献

{"title":"Effective Dose Estimation with IDAC and OLINDA for 18F-FDG and 68Ga-PSMA PET/CT Procedures.","authors":"Fatma Hilal Bikirli, Nesrin Altinsoy, Türkay Toklu","doi":"10.1097/HP.0000000000002034","DOIUrl":"https://doi.org/10.1097/HP.0000000000002034","url":null,"abstract":"<p><strong>Abstract: </strong>Internal dosimetry is a part of radiation safety for patients and radiation workers in nuclear medicine procedures. This study retrospectively determined the effective dose for oncology patients undergoing PET/CT scans by using widely used computer codes, and the results were compared with each other and literature. The study focused on the radiopharmaceuticals 18F-FDG (n = 220) and 68Ga-PSMA (n = 85), administered to 305 patients for cancer imaging at Yeditepe University Kosuyolu Hospital's nuclear medicine department. PET dose was calculated using OLINDA/EXM, IDAC-Dose 1.0 and IDAC-Dose 2.1 programs while ImPACT software was used to determine the effective dose from the CT scan. All effective doses were derived in accordance with ICRP 60 and ICRP 103 tissue weighting factors. PET effective doses from highest to lowest were calculated with OLINDA/EXM, IDAC-Dose 1.0, IDAC-Dose 2.1 (ICRP 60) and IDAC-Dose 2.1 (ICRP 103) as 9.96, 9.07, 7.01, 6.28 mSv respectively for 18F-FDG. The highest PET effective dose was also calculated with OLINDA/EXM software as 3.65 mSv for 68Ga-PSMA. For the total effective dose in PET/CT scans, CT contributed about 92% for 68Ga-PSMA protocol and 75% for 18F-FDG protocol.Key words: effective dose; internal dosimetry; 18F-FDG; 68Ga-PSMA; OLINDA/EXM; IDAC Dose 2.1; IDAC-Dose 1.0; PET/CT.</p>","PeriodicalId":12976,"journal":{"name":"Health physics","volume":" ","pages":""},"PeriodicalIF":1.4,"publicationDate":"2025-08-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144951683","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"医学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Development of a Physical Phantom for Occupational Eye Lens Dosimetry in a Non-homogeneous Radiation Field.","authors":"Jeongin Kim, Hyunjun Na, Seonghoon Cho, Seokon Kang, Yunmi Baek, Seungjin Choi","doi":"10.1097/HP.0000000000002030","DOIUrl":"https://doi.org/10.1097/HP.0000000000002030","url":null,"abstract":"<p><strong>Abstract: </strong>Following the reduction in the occupational eye lens dose limit by the International Commission on Radiological Protection (ICRP), a physical phantom was developed to enable lens dose monitoring in complex radiation environments. The design is based on a validated eye model used to derive lens dose conversion coefficients. After evaluating various materials using Monte Carlo simulations, polymethyl methacrylate (PMMA) was selected for its ease of manufacturing and decontamination. The phantom's dose conversion coefficients were calculated for a range of photon energies and irradiation angles. Lens doses were measured using thermoluminescent dosimeter (TLD) chips embedded in the phantom and exposed to a 137Cs reference field. Measurements were compared with simulation results, demonstrating good agreement. This newly developed PMMA phantom offers a practical solution for evaluating lens dose in non-uniform radiation fields such as those found in nuclear power plants.</p>","PeriodicalId":12976,"journal":{"name":"Health physics","volume":" ","pages":""},"PeriodicalIF":1.4,"publicationDate":"2025-08-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144951699","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"医学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Fractional Deposition of Radioactive Aerosols in the Respiratory Tract: Effects of Anatomical and Physiological Differences between Chinese and Caucasians.","authors":"Lai Zhou, Yuanyuan Liu, Bin Wu, Xiangpeng Meng, Yu Wang, Ao Ju, Jianping Cheng","doi":"10.1097/HP.0000000000001999","DOIUrl":"https://doi.org/10.1097/HP.0000000000001999","url":null,"abstract":"<p><strong>Abstract: </strong>For the calculation of fractional deposition of radioactive aerosols, the deposition model in ICRP Publication 130 has been widely used. However, the deposition model is based on the anatomical and physiological characteristics of Caucasians. Since physiology and anatomical parameters of Chinese differ from those of Caucasians, this difference can affect the applicability of depositional models to Chinese people. ICRP suggests that the corresponding parameters can be replaced when the parameters of concerned people are known. Therefore, this paper investigates the physiological and anatomical parameters of Chinese people and establishes a respiratory deposition model applicable to Chinese people. It is found that the dependence of fractional deposition on aerosol particle size on Chinese people is qualitatively similar to that in Caucasian people. However, the value of fractional deposition is quantitatively different. When the AMAD (activity median aerodynamic diameter) is 1 μm (public exposure), the ratio of fractional deposition between Chinese and Caucasian light workers could reach up to 1.22 in the AI region, and the ratios of fractional deposition in other regions also ranged from 0.87-0.93; when the AMAD is 5 μm (occupational exposure), the ratio of fractional deposition between Chinese and Caucasian light workers could reach up to 1.35 in the AI region, and the ratios of fractional deposition in other regions also ranged from 0.95-1.30. The fractional deposition is used as input to biokinetic models to simulate the transport of radionuclides through the body after inhalation and ultimately impacts the dose conversion factor calculations.</p>","PeriodicalId":12976,"journal":{"name":"Health physics","volume":" ","pages":""},"PeriodicalIF":1.4,"publicationDate":"2025-08-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144951738","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"医学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"An Affordable Open-source Flexible Spectroscopic Radiation Mapping System Employing Sound Card Digitization.","authors":"Caleb M Bush, Ryan A Kim, Kimberlee J Kearfott","doi":"10.1097/HP.0000000000002026","DOIUrl":"https://doi.org/10.1097/HP.0000000000002026","url":null,"abstract":"<p><strong>Abstract: </strong>In sound card-based gamma spectroscopy, a computer sound card serves as the multichannel analyzer in a spectroscopic system with a lower price point and more compact form factor than many traditional systems. A mobile system for radiation measurements, named RadMap, was created to investigate the potential of using sound card spectroscopy in a handheld, mobile radiation measurement and spectroscopic device. RadMap was designed using commercially available parts, including a sound card spectrometer, and is compatible with most photomultiplier tube scintillators for spectroscopic applications or Geiger-Mueller detectors for non-spectroscopic usage. Measurements of 137Cs, 22Na, 54Mn, and 60Co were made using RadMap and two professional desktop gamma spectroscopy systems to characterize RadMap's spectroscopic capabilities relative to those commercial devices. Radiation surveys were created of a 14,000 m2 outdoor space on a college campus using RadMap and other commercially available survey meters for comparison. The results of these experiments suggest that RadMap can provide high quality spectroscopic information and mapable survey information in a device with a favorable price point while enabling easy user modifications. Exact details regarding the components used and their functions are provided to facilitate the creation or further development of a similar system by any interested party.</p>","PeriodicalId":12976,"journal":{"name":"Health physics","volume":" ","pages":""},"PeriodicalIF":1.4,"publicationDate":"2025-08-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144951705","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"医学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Heating Rate Optimization for Enhanced Precision in Thermoluminescent Dosimetry.","authors":"Jordan D Noey, Joseph S Kopke, Kimberlee J Kearfott","doi":"10.1097/HP.0000000000002017","DOIUrl":"https://doi.org/10.1097/HP.0000000000002017","url":null,"abstract":"<p><strong>Abstract: </strong>This study investigates the impact of heating rates, ranging from 1 °C s⁻1 to 20 °C s⁻1, on the precision of integrated peak counts determined using various thermoluminescent dosimeter materials. Lower heating rates influence precision due to prolonged integration of signal noise, while higher heating rates affect precision by pronounced thermal quenching effects. Using time-temperature profiles constructed with a linear heating ramp and a constant hold at maximum temperature, a range of heating rates was evaluated to identify an optimal condition that minimizes variance in integrated peak counts resulting from these effects. In addition, kinetic parameters of glow peaks were determined through peak deconvolution of each glow curve obtained and analyzed as a function of heating rate, with observed trends fit to appropriate models. These results were then compared to trapping parameters - namely the activation energy and frequency factor - independently extracted using the variable heating rate method to assess consistency across techniques. The results indicate that peak temperatures and intensities exhibit strong exponential dependence on heating rate, while activation energies and frequency factors show weak linear correlations. Trapping parameters obtained using the variable heating rate method fell within the range of values derived from peak deconvolution, supporting consistency between the two approaches. An optimal heating rate of 4 °C s⁻1 was identified for minimizing variance in integrated peak counts across all dosimeter types tested. Both noise and thermal effects were shown to influence measurement variance, with thermal quenching effects having a more pronounced impact at higher heating rates. Additional factors affecting precision included dosimeter material, glow peak temperature, and overall glow curve complexity. These findings enhance the understanding of thermoluminescent dosimeter behavior and highlight the importance of optimizing the heating rate for improved measurement reliability.</p>","PeriodicalId":12976,"journal":{"name":"Health physics","volume":" ","pages":""},"PeriodicalIF":1.4,"publicationDate":"2025-08-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144821193","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"医学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Depth Dose Profile and Exposure Time Calculation in an 60Co Irradiation Processing Facility: MCNP and GEANT4 Calculation.","authors":"Farshid Tabbakh, Ali Nabipour Chakoli, Sufian M Tajudin, Farbod Tabbakh, Hadi Gaffari","doi":"10.1097/HP.0000000000002019","DOIUrl":"https://doi.org/10.1097/HP.0000000000002019","url":null,"abstract":"<p><strong>Abstract: </strong>The present research is proposing a mathematical method to calculate the dose absorbed by a moving object in a non-uniform radiation field. In such conditions, the dose is the function of time and position of the object relative to the radiation source. In this regard, a 60Co irradiation processing facility has been investigated in which, the non-uniform planar source of gamma-rays, irradiates the boxes moving which move around the source. In irradiation facilities, addition to the strength of 60Co source, the speed of boxes is in great importance in obtaining the desired total dose to the boxes, however in most cases, the speed has been determined traditionally and by try-and-error method after the construction and installation of the radiation source. In this research, the speed of boxes (conveyor's speed) was determined so that, the desired dose has been delivered to each box. The dose profile inside of the boxes has been calculated based on the different positions from the rack. The presented calculations aim to optimize the detailed design of the mentioned facility and for the more efficient performance because, it helps to make the faster radiation processing in a smaller place. The calculations have been conducted using MCNPX.2.7 and Geant4.10.5 Monte Carlo tools in order to obtain most reliable results.Health Phys. 000(0):000-000; 2025.</p>","PeriodicalId":12976,"journal":{"name":"Health physics","volume":" ","pages":""},"PeriodicalIF":1.4,"publicationDate":"2025-08-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144794226","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"医学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Bridging Frameworks: A Comparison of Occupational Health and Safety's Hierarchy of Controls and the International System of Radiological Protection.","authors":"T Lynn MacDonald","doi":"10.1097/HP.0000000000001972","DOIUrl":"10.1097/HP.0000000000001972","url":null,"abstract":"<p><strong>Abstract: </strong>Those responsible for radiological protection in the workplace come to the role through many different pathways. In the process of training radiation safety officers and x-ray safety officers, instructors at the Radiation Safety Institute of Canada have observed that, while many course participants will have previous radiological protection training, it is common for a significant number to have experience managing traditional occupational health and safety or industrial hygiene programs and no radiological protection background. Humans use mental models or schemas to understand the world. They assimilate new information based on their existing schemas. Those formally trained in radiological protection are well versed in the International System of Radiological Protection, based on the fundamental principles of justification, optimization, and limitation as described in International Commission on Radiological Protection Publication 103. Those with training in occupational health and safety or industrial hygiene in Canada or the United States work within a framework called the hierarchy of controls. Given here is a comparison of these safety frameworks with consideration of how the health and safety schema of these two groups of radiological protection personnel may differ and areas on which to build a common understanding of radiological protection in the workplace. Hopefully, consideration of this topic will lead to improved communication and help safety professionals avoid misconceptions that might arise owing to differences in foundational knowledge.</p>","PeriodicalId":12976,"journal":{"name":"Health physics","volume":" ","pages":"141-144"},"PeriodicalIF":1.0,"publicationDate":"2025-08-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143630347","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"医学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Modeling Plutonium Decorporation in a Female Nuclear Worker Treated with Ca-DTPA after Inhalation Intake.","authors":"Sara Dumit, Maia Avtandilashvili, Stacey L McComish, Guthrie Miller, Jasen Swanson, Sergey Y Tolmachev","doi":"10.1097/HP.0000000000001859","DOIUrl":"10.1097/HP.0000000000001859","url":null,"abstract":"<p><strong>Abstract: </strong>The present work models plutonium (Pu) biokinetics in a female former nuclear worker. Her bioassay measurements are available at the US Transuranium and Uranium Registries. The worker was internally exposed to a plutonium-americium mixture via acute inhalation at a nuclear weapons facility. She was medically treated with injections of 1 g Ca-DTPA on days 0, 5, and 14 after the intake. Between days 0 and 20, fecal and urine samples were collected and analyzed for 239 Pu and 241 Am. Subsequently, she was followed up for bioassay monitoring over 14 y, with additional post-treatment urine samples collected and analyzed for 239 Pu. The uniqueness of this dataset is due to the availability of: (1) both early and long-term bioassay data from a female with plutonium intake; (2) data on chelation therapy for a female; and (3) fecal measurement results. Chelation therapy with Ca- and/or Zn-salts of DTPA is known to aid in reducing the internal radiation dose by enhancing the excretion of plutonium and americium from the body. Such enhancement affects plutonium biokinetics in the human body, posing a challenge to the internal dose assessment. The current radiation dose assessment practice is to exclude the data affected by Ca-DTPA from the analysis. The present analysis is the first to explicitly model the chelation-affected bioassay data in a female by using a newly developed chelation model. Thus, the bioassay data collected during and after the Ca-DTPA administrations were used for biokinetic modeling and dose assessment. The Markov Chain Monte Carlo method was used to investigate model parameter uncertainty, based on the bioassay data and assumed prior probability distributions. A χ2 /nData (number of data points) ≈ 1 was observed in this study, which indicates self-consistency of the data with the model. Results of this study show that the worker's 239 Pu intake was 12 Bq, with a committed effective dose to the whole-body of 1.2 mSv and a committed equivalent dose to the bone surfaces, liver, and lungs of 37.8, 9.1, and 0.8 mSv, respectively. This study also discusses the worker's dose reduction due to chelation treatment.</p>","PeriodicalId":12976,"journal":{"name":"Health physics","volume":" ","pages":"71-80"},"PeriodicalIF":1.0,"publicationDate":"2025-08-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://www.ncbi.nlm.nih.gov/pmc/articles/PMC12237124/pdf/","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141733967","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"医学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Estimation of Effects of Filtration and Ventilation on Worker Inhalation Dose from Aerosols Produced during Nuclear Decommissioning Processes.","authors":"Nicholas Somer, Glenn Harvel, Ed Waller","doi":"10.1097/HP.0000000000001967","DOIUrl":"10.1097/HP.0000000000001967","url":null,"abstract":"<p><strong>Abstract: </strong>During the decommissioning of nuclear power plants, radioactive contaminants may be released into the work environment in the form of aerosols, which can expose workers through inhalation, ingestion, and submersion pathways. During dismantlement work, aerosol concentrations may increase due to release from materials. Typical engineering controls to reduce concentrations include air exchange as well as air filtration, which captures aerosols at their source. This work presents a model of radioactive aerosol concentration to estimate the reduction of (a) effluent aerosol concentration into the environment and (b) worker committed effective dose. Controlling the aerosol concentration mitigates the dose that the workers receive. Given that there exists a variety of filtration methods of varying efficiencies and throughputs, a method of estimating dose reduction for a variety of work scenarios is desirable. This work models the time-evolution of radionuclide aerosol concentration as a function of dismantlement work parameters such as work time, aerosol source rate, air exchange, and air filtration. The committed effective dose to a worker as well as the environmental radionuclide aerosol emissions are estimated over a typical 10-h work shift.</p>","PeriodicalId":12976,"journal":{"name":"Health physics","volume":" ","pages":"103-113"},"PeriodicalIF":1.0,"publicationDate":"2025-08-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143630349","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"医学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"INTDOSKIT: An R-Code for Calculation of Dose Coefficients and Studying Their Uncertainties.","authors":"Bastian Breustedt, Niranjan Chavan, Thomas Makumbi","doi":"10.1097/HP.0000000000001833","DOIUrl":"10.1097/HP.0000000000001833","url":null,"abstract":"<p><strong>Abstract: </strong>An R-code, which allows the calculation of the time dependent activity distribution based on ICRP reference models, the number of decays in a commitment period, and the dose coefficients for tissues and organs of the human body, has been developed. R Language was chosen due to its powerful mathematical and statistical modeling features, as well as its graphical capabilities. The developed set of functions and constants (called \"INTDOSKIT\") can be sourced in R-scripts that define or import the models and calculations to be performed. The code has been tested on models of several radionuclides and was successfully validated against reference data taken from ICRP OIR Data Viewer software. Furthermore, the code has been tested and verified on the modeling of the radioactivity of decay chains using data of the 233 Ra model presented by Höllriegl and colleagues. The results of calculations with INTDOSKIT demonstrated that the code is able to reproduce the ICRP bioassay data and dose coefficients. Deviations are a few percent only and are due mainly to rounding in the original data. Lastly, the code is able to handle uncertainty and sensitivity studies as demonstrated by the results in a pilot study of injection of 241 Am, which estimated geometric standard deviations (GSD) for dose coefficients ranging between 1.25 (bone-surface) and 1.66 (testes); these results are consistent with those obtained from similar studies done by other researchers who reported GSD values ranging from 1.13 to 1.73.</p>","PeriodicalId":12976,"journal":{"name":"Health physics","volume":" ","pages":"50-60"},"PeriodicalIF":1.0,"publicationDate":"2025-08-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142285890","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"医学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}