Health physics最新文献

{"title":"Determination of 222 Rn Exhalation Rates and Health Effect Evaluation of Some Marbles and Granites Used in Van Province, Turkey: An Experimental Study.","authors":"Halime Erzen Yildiz, Mehmet Türkmenoğlu","doi":"10.1097/HP.0000000000002129","DOIUrl":"10.1097/HP.0000000000002129","url":null,"abstract":"<p><p>Radon ( 222 Rn) accounts for approximately 60% of natural radiation (2.4 mSv y -1 ) and is a well -documented concern as the primary contributor to indoor exposure. Radon itself is inert, but its decay products ( 218 Po, 214 Pb, 214 Bi, and 214 Po) are reactive and tend to attach to airborne aerosol particles, lodging in the respiratory tract (bronchi, bronchioles, and lungs). During the decay process, they deposit a large amount of radiation, emitting alpha particles into surrounding tissues, ultimately causing biological damage. While radon is most commonly released from soil or rocks, building materials are another potential source of indoor atmospheric pollution. The rate at which radon escapes from a solid substance or diffuses into the surrounding air is known as the solid's \"radon exhalation rate.\" Accurately knowing the exhalation rate plays a crucial role in determining the radon source power in building materials and soil. This study aimed to determine the 222 Rn exhalation rate and assess radiological risks in some marble and granite samples commonly used in the Van Province of Turkey. The study employed an LR-115 type II plastic film detector and a closed-box technique. After chemical etching and alpha track counting on the detector, the following parameters were calculated: C Rn (radon concentration), C Ra (radium concentration), E A (surface exhalation rate), E M (mass exhalation rate), D eff (annual effective dose), WLM (annual exposure), F (%) (radon emission coefficient), A Rn (indoor radon concentration contribution), and ELCR (excess lifetime cancer risk). The average E A and E M values calculated for marbles were found to be 313.45 ± 10.90 mBq m -2 h -1 and 12.05 ± 0.41 mBq kg -1 h -1 , respectively. The average E A and E M values for granites were found to be 313.66 ± 11.24 mBq m -2 h -1 and 12.06 ± 0.42 mBq kg -1 h -1 , respectively. The highest values were obtained in sample M2. While the calculated radon concentrations were above the international limit value and the global average, radiological risk values were calculated based on data on indoor radon concentration contributions. It was determined that the use of both marble and granite samples in the construction sector did not pose any risk to human health.</p>","PeriodicalId":12976,"journal":{"name":"Health physics","volume":" ","pages":"405-413"},"PeriodicalIF":1.2,"publicationDate":"2026-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147354709","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 Independent Comparison of VARSKIN v2.1 and Geant4 for Skin Dose Calculations.","authors":"G James, M Memmott, F Morgan, N Dickinson, L Perry, D Deidda, C Ferreira, Amie Roberts","doi":"10.1097/HP.0000000000002140","DOIUrl":"10.1097/HP.0000000000002140","url":null,"abstract":"<p><p>VARSKIN is becoming more commonplace in nuclear medicine departments to calculate skin dose from droplet or surface contamination due to its accessibility and ease of use. VARSKIN uses simplified dose kernels, which give dose estimates quickly; however, the disadvantage is that some accuracy may be compromised. The aim of this article was to independently compare the VARSKIN (v2.1) skin dose module against Geant4 for typical skin contamination scenarios. Realistic skin contamination scenarios were modeled in Geant4 including droplet and surface contamination. Three droplet volumes (10, 30, and 50 μL) were considered as well as an infinitely thin disk source (A = 1 cm 2 ) to model surface contamination. Four basal depths (70, 140, 220, and 370 µm) were considered in combination with two glove layers defined by 0.1 mm and 0.2 mm of natural rubber (ρ = 0.92 g cm -3 ) as well as an absent glove layer. The Geant4 models were then replicated as closely as possible using VARSKIN (v2.1) skin dose module. Forty-four (44) radionuclides were considered giving a total of 2,112 direct comparisons of instantaneous skin dose rates between VARSKIN (v2.1) and Geant4. Most data (86%) were within ±50% (relative) difference between VARSKIN and Geant4 with a median difference of only +4.0% for all data. However, the 95% confidence interval was wide at -29% to +210%, showing a large positive skew. This skewness is predominantly caused by large relative differences observed for photon emitting radionuclides including 57 Co, 51 Cr, 67 Ga, 123 I, 125 I, 129 I and 111 In. However, the differences were low in absolute terms for these radionuclides. Despite large relative differences between VARSKIN and Geant4 for certain radionuclides and geometries, the differences were low in absolute terms. Overall, we conclude that VARSKIN (v2.1) is a reliable tool for skin dose assessment for the radionuclides and geometries studied in this article.</p>","PeriodicalId":12976,"journal":{"name":"Health physics","volume":" ","pages":"468-481"},"PeriodicalIF":1.2,"publicationDate":"2026-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"148470050","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":"Radiation Dose to the Breast in Occupationally Exposed Healthcare Professionals: A Case Series.","authors":"Mohamed Khaldoun Badawy, Tran Nguyen Bao Trinh, Lee-Anne Slater, Brianna Hart, Lucy Corlette, Alice Gutowski","doi":"10.1097/HP.0000000000002240","DOIUrl":"https://doi.org/10.1097/HP.0000000000002240","url":null,"abstract":"<p><strong>Objective: </strong>To quantify breast dose at the upper outer quadrant (UOQ) and identify factors influencing exposure in female healthcare professionals during routine digital subtraction angiography (DSA) procedures.</p><p><strong>Methods: </strong>This preliminary case series combined optically stimulated luminescence dosimetry with structured exposure characterization interviews to measure UOQ breast dose in three female healthcare professionals during routine procedures over a two-month period. Dosimeters were worn under lead garments, and interviews captured professional role, procedural involvement, positioning practices, and protective garment features. Cumulative kerma-area product, reference air kerma, and fluoroscopy time were recorded for each participant. Normalized equivalent dose rates were calculated and descriptively compared with values reported in a published phantom study.</p><p><strong>Results: </strong>Measurable bilateral UOQ breast dose was detected in two participants, whereas no dose above the minimum reportable dose was recorded in one participant. Absolute doses were low but detectable despite the use of protective garments compliant with current standards. Observed variation in dose appeared to be associated with factors such as armhole gap size and working distance from the x-ray source.</p><p><strong>Conclusions: </strong>Measurable UOQ breast dose can occur in clinical practice despite standard protective garments. Further studies with larger cohorts and detailed procedural characterization are required to better define breast exposure patterns and inform breast-specific occupational radiation protection strategies.</p>","PeriodicalId":12976,"journal":{"name":"Health physics","volume":" ","pages":""},"PeriodicalIF":1.2,"publicationDate":"2026-10-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"149206798","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":"Deposition, Retention, and Clearance of Depleted Uranium and Tungsten Following Inhalation Exposure: Biokinetic Analysis and Implications for Long-term Health Effects.","authors":"Lydia J Keifer, Emmanuel Matey Mate-Kole, Shaheen Azim Dewji","doi":"10.1097/HP.0000000000002219","DOIUrl":"https://doi.org/10.1097/HP.0000000000002219","url":null,"abstract":"<p><strong>Objective: </strong>This study evaluates respiratory deposition and subsequent biokinetic behavior of DU and W aerosols using computational modeling informed by reported military exposure conditions.</p><p><strong>Methods: </strong>Particle deposition fractions in the respiratory tract were calculated using REDCALdep, which implements the ICRP Publication 66 respiratory tract deposition model with relevant updates from ICRP Publication 130. Deposition fractions were used as initial conditions within the Radiological Exposure Dose Calculator (REDCAL) framework, a Python-based computational toolkit, to estimate time-dependent biokinetic distributions following inhalation. A representative activity median aerodynamic diameter (AMAD) of 5 μm was assumed for respirable aerosols, and DU (19 g cm-3) and W (19.3 g cm-3) were modeled as moderately soluble (Type M). Additional sensitivity analyses were conducted for AMADs of 1, 5, and 10 μm and absorption types F, M, and S.</p><p><strong>Results: </strong>Increasing density from the ICRP Publication 130 default value to DU and W values shifted deposition toward deeper lung regions. Modeled retention profiles indicate systemic distribution beyond the respiratory tract, including systemic organs, with substantial early urinary and fecal excretion. Despite model uncertainties, patterns were consistent with published experimental and epidemiological observations reported for DU and W inhalation exposures.</p><p><strong>Conclusion: </strong>The findings contribute to understanding mechanistically plausible pathways associated with long-term internal retention relevant to symptom profiles described in Gulf War Illness literature, while supporting improved exposure assessment and risk characterization for military and occupational settings.</p>","PeriodicalId":12976,"journal":{"name":"Health physics","volume":" ","pages":""},"PeriodicalIF":1.2,"publicationDate":"2026-10-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"149136486","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":"Workflow-Based Radiation Protection During In-house 18F-FDG Production at a Hospital-based Cyclotron Facility.","authors":"Hiroshi Yamaguchi, Kazuyuki Minami","doi":"10.1097/HP.0000000000002242","DOIUrl":"https://doi.org/10.1097/HP.0000000000002242","url":null,"abstract":"<p><p>Automation limits operator contact during routine 18F-fluorodeoxyglucose (FDG) production, but residual manual tasks and nonroutine interventions may still determine occupational exposure. This study quantified workflow-specific effective dose during in-house FDG production at a hospital-based cyclotron facility. Production records from 39 batches performed from 4 July to 23 August 2024 were reviewed. Two radiological technologists were monitored during seven routine production sessions, and five pharmacists were monitored during 10 quality-control (QC) observations. Semiconductor electronic pocket dosimeters were worn at the head, chest, and abdomen; effective dose was estimated from the three 1-cm dose equivalent readings using a nonuniform exposure formula. For technologists, average effective dose was 0.4 ± 0.1 µSv per session for cyclotron operation and synthesis, 0.2 ± 0.1 µSv for transport, 1.1 ± 0.3 µSv for cleaning, and 1.6 ± 0.3 µSv for the total routine workflow. The average pharmacist QC dose was 2.5 ± 1.2 µSv per observation. Two of 39 batches (5.1%) required a nonroutine intervention. Event-related effective doses were 32.2 µSv for manual recovery after QC vial-transfer failure and 30.7 and 31.6 µSv for two operators recovering residual FDG after incomplete transfer. These values were approximately 19-20 times the average total routine technologist dose. Routine exposure was low, whereas infrequent disruptions produced disproportionate exposure. Radiation protection should therefore combine routine monitoring with prevention, rehearsal, shielding, and time-minimized procedures for manual QC and nonroutine recovery.</p>","PeriodicalId":12976,"journal":{"name":"Health physics","volume":" ","pages":""},"PeriodicalIF":1.2,"publicationDate":"2026-10-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"149136475","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":"Metrology, Standards, and Mission: Synopsis of the 2026 Annual Meeting of the Council on Ionizing Radiation Measurements and Standards (CIRMS).","authors":"Wesley S Culberson, Spencer Mickum, Autumn Walter-Denzin, Stewart J Becker, Sergio Morató, Jacob Lambeck, Emmanuel Mate-Kole, Leonard S Fifield, Michael Christofaro, Amitava Adhikary, Shaheen Dewji, Cody Wilson, Matthew M Mille","doi":"10.1097/HP.0000000000002218","DOIUrl":"10.1097/HP.0000000000002218","url":null,"abstract":"<p><p>The Council on Ionizing Radiation Measurements and Standards (CIRMS) is an independent, non-profit council composed of experts from academia, government, and industry across all areas of ionizing radiation science and technology, providing leadership, focus, and coordinated action on emerging radiation metrology needs. This mission is achieved through the organization of an annual scientific conference and the periodic publication of a Needs Report which identifies priority areas in ionizing radiation measurements and standards. This article summarizes the outcomes from the CIRMS 2026 meeting which was held 13-15 April 2026 at The Universities at Shady Grove in Rockville, Maryland, United States. Participants represented a broad cross-section of the radiation science community, including radiation metrologists, academic researchers, government scientists, and industry stakeholders. The meeting featured plenary presentations, topical breakouts, and poster sessions. The breakout sessions were organized by the three subcommittees of the CIRMS Science and Technology Committee: Medical Applications, Radiation Protection and Homeland Security, and Radiation Processing and Material Effects. Topics covered during the meeting included cobalt-60 (60Co) and cesium-137 (137Cs) production, medical device sterilization, FLASH radiotherapy dosimetry, neutron dosimetry, radiation standards for next-generation fusion power systems, Monte Carlo modeling, and other topics relevant to radiation measurements and standards. The CIRMS 2026 meeting highlighted challenges that must be addressed to advance ionizing radiation science and technology and provide important input for the next Needs Report.</p>","PeriodicalId":12976,"journal":{"name":"Health physics","volume":" ","pages":""},"PeriodicalIF":1.2,"publicationDate":"2026-10-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://www.ncbi.nlm.nih.gov/pmc/articles/PMC13674516/pdf/","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"149126717","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":"Pre- and Post-Assessments (Performance, Progress, and Risk) for Radiological Impact at Uranium Mine Facilities (Case Study Coles Hill) for a 100-y Rainfall Event Including Surface Water Transport and Fate Modeling.","authors":"David B Weyant, Jaewan Yoon","doi":"10.1097/HP.0000000000002187","DOIUrl":"https://doi.org/10.1097/HP.0000000000002187","url":null,"abstract":"<p><p>The general guidance for a radiological impact using pre- and post-assessments for legacy, new, and planned uranium mining facilities are presented. Specific items to consider during the process and the rationale such as mitigation, order of model, loading functions and approaches, hydrographs, pollutographs, water quality modeling, and health physics are provided. A case study using a conventional Coles Hill proposed uranium mine in Virginia demonstrates typical pollutograph construction processes for a worst-case scenario 100-y intense rainfall pre-assessment. For the case study, an intense 3-h duration, 100-y synthetic rain event overlapping a sudden rupture of a full 5.00 × 104 m3 leachate (= 2.78 × 105 Bq m-3) storage tank over a 3-h duration was considered. Having similar characteristics, a surrogate Rio Road Watershed hydrograph was used to emulate the local watershed at White Horn Creek, Coles Hill. The uranium mine waste (leachate, slime, sand) was transported over the local land area and river embankment into the nearby Banister River as it mixed with a spatial temporal runoff rate (q-Series). A Continuous Spill/Step Loading Runkel water quality model determined the concentrations in 15-min increments the entire length of the Banister River downstream to the Kerr Dam. There was insignificant evidence that there would be an exceedance of the MCL for 226Ra/228Ra (= 1.85 × 10-2 Bq m-3), total alpha (= 5.55 × 10-2 Bq m-3), or uranium (= 3.00 × 10-6 Kg m-3) at the Town of Halifax's drinking water intakes (approximately 50 km). Therefore, it is highly unlikely that there would be an exceedance of 226Ra/228Ra, total alpha, or uranium near the drinking water intakes of the Town of Halifax, Virginia, or further downstream at Clarkesville's and Kerr Dam's drinking water intakes. Furthermore, there would be a need for post-disaster data collection and potential remedial action of radioactive contamination in water, soil, sediment, building structure, and the ecosystem.</p>","PeriodicalId":12976,"journal":{"name":"Health physics","volume":" ","pages":""},"PeriodicalIF":1.2,"publicationDate":"2026-10-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"149108694","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":"Radiological Environmental Impact Assessment and Radon Contribution Due to Civil Engineering Works in Port City of Kribi, Cameroon.","authors":"Feutseu Talla Simplice Aimé, Guillaume Samuel Bineng, Takoukam Soh Serge Didier, Awe Richard, Saïdou","doi":"10.1097/HP.0000000000002121","DOIUrl":"10.1097/HP.0000000000002121","url":null,"abstract":"<p><p>This study, conducted in Kribi, South Cameroon, assesses radioactivity levels, effective doses, and radiological risks. The aim is to show the impact of civil engineering activities on public exposure to natural radioactivity, particularly radon. Using the RESRAD-ONSITE 7.2 code, results were projected over 100 y. The maximum total effective dose was 0.4 mSv y -1 at t=10 y. The main contributions to this dose were 47.95%, 28.15%, 21.06%, 1.11%, 0.76%, 0.33%, and 0.30%, respectively, from radon inhalation, terrestrial radiation, plant ingestion, milk ingestion, 14 C and 3 H inhalation, meat ingestion, and accidental soil ingestion, respectively. The total excess risk of maximum cancer morbidity, estimated at 8.965 × 10 -4 and achieved at time, was 3 times higher than the limit value of 3 × 10 -4 given by the World Health Organization. The risk significantly decreased after the tenth year, coinciding with the completion of major construction projects, unlike areas with intensive agro-pastoral and mining activities. The study highlights that radon inhalation, terrestrial radiation, and consumption of contaminated plants were the main exposure pathways, likely due to high levels of dust and airborne particles. Thus, in a given locality, exposure pathways to radionuclide and associated radiological risk are strongly related to the type of anthropomorphic activity carried out and its duration.</p>","PeriodicalId":12976,"journal":{"name":"Health physics","volume":" ","pages":"303-316"},"PeriodicalIF":1.2,"publicationDate":"2026-10-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146219559","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":"Organ and Effective Dose Assessments Using MCNP with Computational PIMAL Phantoms and Realistic Eye Model in Radiological Workplaces.","authors":"Salah Djeffal, Jacques Dubeau, Jiansheng Sun, Fawaz Ali, Alireza Talebitaher","doi":"10.1097/HP.0000000000002124","DOIUrl":"10.1097/HP.0000000000002124","url":null,"abstract":"<p><p>The female and male computational phantom with moving arms and legs (PIMAL) are useful models for the calculation of the effective doses to workers in radiological occupational settings. In this study, Monte Carlo N-Particle (MCNP) Version 6.2 is used with PIMAL phantoms to simulate exposure in nuclear and medical settings. The PIMAL phantoms, defined by mathematical representation of the human body, allow for detailed assessment of equivalent dose to organs. These values are converted to effective dose (E) using sex- and age-average tissue weighting factors from ICRP Publication 103. Initial simulations of monoenergetic photons, electrons, and neutrons in the anterior-posterior (AP) geometry show good agreement with comparable results in the literature, obtained using the ICRP adult reference voxel phantoms and PIMAL phantoms in the standard upright position. For nuclear power applications, effective dose rates ( ) are estimated for workers contaminated by radionuclides and compared with personal dose equivalent rates at 0.07 mm depth, (0.07). Additionally, effective dose rates from neutron and gamma fields are calculated for personnel inside a CANDU-600 (CANada Deuterium Uranium) nuclear reactor at full-power. In medical applications, effective dose rates to staff exposed to positron emitters, either from injected patients or activated cyclotron targets, are also assessed. Across all scenarios, effective dose derived from PIMAL phantoms are consistent with operational dose quantities when available, supporting their use in dose assessment and radiation protection planning.</p>","PeriodicalId":12976,"journal":{"name":"Health physics","volume":" ","pages":"377-390"},"PeriodicalIF":1.2,"publicationDate":"2026-10-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147283316","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 Real-time Radiation Detection System that Uses IoT to Provide Real-time Monitoring on a Custom-built Website.","authors":"Mubin Hossain Omio, Abdus Sattar Mollah","doi":"10.1097/HP.0000000000002127","DOIUrl":"10.1097/HP.0000000000002127","url":null,"abstract":"<p><p>Effective radiation monitoring is crucial for ensuring public security and safety, particularly in the event of nuclear (e.g., nuclear accident, fallout, etc.) or radiological (e.g., radiation source spill, dirty bombs, etc.) emergencies. Traditional monitoring methods often lack real-time capabilities and comprehensive data visualization and analysis, which can delay response time and increase further risks. To address this gap, this research proposes an Advanced Radiation Detector for real-time radiation monitoring. The novelty is in its use of an internet of things (IoT)-based framework to collect and transmit all the data (e.g., radiation level, temperature, pressure, humidity, and air quality) via a GSM module to web cloud all from one device with enhanced visualization in the self-made website. The study setup will obtain data across the area of the Military Institute of Science and Technology (MIST), Mirpur Cantonment, Dhaka, Bangladesh, using this Advanced Radiation Detector. This data is visualized by creating a scatter circle map of spatial distribution of radiation measurements. By visualizing radiation data taken from the self-developed detector and visualizing it using the self-made website, we found the Advanced Radiation Detector meets its objectives perfectly. This research aims to enable real-time radiation monitoring and provides timely insights for emergency responses. By integrating IoT in the system, it has directly overcome the limitation of traditional methods. The Advanced Radiation Detector has immense potential to improve security and safety measures. The current Rooppur Nuclear Power Plant (RNPP) development in Bangladesh emphasizes the necessity of customized solutions for efficient radiological risk management. In order to improve Bangladesh's nuclear safety framework, this study presents a revolutionary IoT-based radiation monitoring system that uses machine learning for real-time assessment and predictive analytics.</p>","PeriodicalId":12976,"journal":{"name":"Health physics","volume":" ","pages":"317-330"},"PeriodicalIF":1.2,"publicationDate":"2026-10-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146149603","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}