Journal of Radiological Protection最新文献

{"title":"A Systematic Approach for Estimating ICRU Report 95 Operational Quantities for Personnel Monitoring using a 3-element TLD Badge System.","authors":"Munir Pathan, Suresh M Pradhan, Selvam T Palani, Balvinder Kaur Sapra","doi":"10.1088/1361-6498/adc939","DOIUrl":"https://doi.org/10.1088/1361-6498/adc939","url":null,"abstract":"<p><p>The introduction of ICRU Report 95 marks a revision of operational quantities for individual monitoring due to external radiation exposures. This revision has a major impact, particularly in low photon energy range (20-100 keV), where the conversion coefficients of existing [(Hp(10)] and new [(Hp)] operational quantities for whole body dose differ by a factor up to 5. The shift from Hp(10) to Hp poses considerable challenges for its integration into existing personnel dosimetry systems. This is particularly relevant to the diagnostic radiology sector, where photon energies predominantly range between 20 and 100 keV and approximately 70% of monitored occupational workers are from this sector. In this context, the present study investigates the feasibility of implementing the updated operational quantities for multi-element passive dosimetry systems, such as CaSO4:Dy-based thermoluminescent dosimeters and outlines a systematic approach.&#xD;Three approaches were demonstrated for the implementation of Hp: a linear equation-based method, a non-linear equation approach, and a multi-stage machine learning model. The results indicate that all methods achieved promising accuracy in dose estimation, with the machine-learning model exhibiting a slight advantage. Notably, approximately 99% of the estimated doses fell within ±30% of the actual delivered dose, underscoring the reliability of these approaches for practical application.&#xD;The present study highlights the distinct advantage of multi-element passive dosimeters, demonstrating their capability to accommodate Hp without necessitating significant design modifications. Through a systematic approach for estimating Hp, this study establishes the efficacy of multi-element passive dosimeters as a viable solution for the implementation of ICRU-95 operational quantities in personnel monitoring systems.&#xD.</p>","PeriodicalId":50068,"journal":{"name":"Journal of Radiological Protection","volume":" ","pages":""},"PeriodicalIF":1.4,"publicationDate":"2025-04-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143788906","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":"Occupational radiation exposure during blood sample collection post I-131 therapeutic administration in thyroid cancer patients.","authors":"Amna Juma Al-Jabri, Jennie Cooke, Seán Cournane, Marie-Louise Healy","doi":"10.1088/1361-6498/adc8b3","DOIUrl":"https://doi.org/10.1088/1361-6498/adc8b3","url":null,"abstract":"<p><strong>Purpose: </strong>&#xD;The blood sampling required for the verification of dose delivered during radioactive iodine (¹³¹I) therapy is a source of radiation exposure for healthcare staff. This study aims to estimate staff exposures, using Monte Carlo modelling, as well as experimental measurements. The study further aimed to validate the models with staff exposure measurements and examine the impact of protective measures on the procedure.&#xD;Material and methods:&#xD;The clinical set-up of blood sampling post¹³¹I patient administration, within a dedicated¹³¹I ablation therapy suite, was modelled using EGSnrc Monte Carlo simulations (MCS). The dose scoring regions representing deep dose (Hp(10)) and skin dose (Hp(0.07)) was estimated, and validated with experimental approach and clinical monitoring of staff members using electronic personal dosimeters (EPD).&#xD;Results:&#xD;Monte Carlo simulations and experimental value did not show significant difference between the two approaches (p>0.05), with simulated values having lower uncertainties. It was demonstrated that the model is capable of being tailored to clinical scenarios at any centre. The simulations were corroborated with dosimetry data of blood sampling from 14 patients post administering 3.7 GBq¹³¹I, amounting to a total of 54 measurements from 14 staff members. With the employed protective shielding, none of the staff were exposed to a dose rate approaching the annual dose constraint of 0.3 mSv.year^-1.&#xD;Conclusion:&#xD;The experimental and MCS data showed good agreement with the clinical data, demonstrating the advantages of MCS approaches for providing useful information for planning and carrying out risk assessments before implementing a new dosimetry practice.&#xD.</p>","PeriodicalId":50068,"journal":{"name":"Journal of Radiological Protection","volume":" ","pages":""},"PeriodicalIF":1.4,"publicationDate":"2025-04-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143781657","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":"Approaches to Harmonize Mortality Data Sets in Three Diverse Radiation Worker Cohorts.","authors":"Jianqi Zhang, Daniel O Stram, Sarah S Cohen, Michael T Mumma, David Pawel, Howard D Sesso, Richard W Leggett, Andrew J Einstein, John D Boice","doi":"10.1088/1361-6498/adc7bf","DOIUrl":"https://doi.org/10.1088/1361-6498/adc7bf","url":null,"abstract":"<p><p>While there is a well-established link between ionizing radiation and cancer, there are uncertainties with effects following low doses delivered at low dose rates. To address these gaps, the ongoing Million Person Study of Radiation Workers and Veterans (MPS) is investigating the likelihood of a variety of cancer and non-cancer effects following chronic exposure to low dose-rate ionizing radiation. One challenge is and will be combining and harmonizing diverse cohorts with widely different measures of socio-economic status, birth cohorts, dose distributions and sex ratios. Herein, we have evaluated non-cancer mortality in three cohorts for which dose reconstructions have been completed: Rocketdyne (Atomics International, California, 1948-2008), Mound (Dayton, Ohio, 1944-2009) and nuclear weapons test participants (Atomic Veterans, 1945-2012). These three cohorts represent a small fraction of the overall Million Person Study (MPS) but provide valuable insight into methods of combining and harmonizing data from multiple diverse cohorts that can later be considered for all MPS cohorts. Heart disease mortality, including both underlying and contributing causes of death, was chosen for illustrating the statistical approaches. In all three cohorts, radiation dose estimates were distributed very differently by different measures of socio-economic status. Further, the effect of birth cohort was significantly different for heart disease mortality in all three cohorts, with all studies showing that later birth cohorts have lower rates of heart disease mortality than the earlier. The goal of this paper is not to quantify radiation effects based on these combined cohorts and it would be inappropriate to do so. Rather these cohorts are used to illustrate approaches for combining multiple data sets that incorporate the full set of individual confounder and cofactor information available from each cohort, though widely different.&#xD;We identified five different methods to combine the results of these three datasets: the simple pooled analysis, pooled analysis including study interactions, traditional stratified analysis, and both fixed and random effects meta-analysis. We describe the similarities and differences between the combined results using these approaches. &#xD.</p>","PeriodicalId":50068,"journal":{"name":"Journal of Radiological Protection","volume":" ","pages":""},"PeriodicalIF":1.4,"publicationDate":"2025-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143765502","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":"The vital role of radiation protection research in Europe's future: a PIANOFORTE white paper.","authors":"Jacqueline Garnier-Laplace, Jean-Christophe Gariel, Filip Vanhavere, Florian Rauser, Andrzej Wojcik, Elizabeth A Ainsbury, Simon Bouffler, Marie Davídková, Tomasz Kalita, Christoph Hoeschen","doi":"10.1088/1361-6498/adc7c0","DOIUrl":"https://doi.org/10.1088/1361-6498/adc7c0","url":null,"abstract":"<p><p>Radiation protection is a cornerstone of public health, occupational safety, patient welfare, and environmental stewardship. A strong emphasis on radiation protection is necessary to contribute to the well-being of citizens, innovation and sustainable growth across Europe, and to meet the challenges by application of new technologies, and emerging threats. The use of ionising radiation and radioactive substances has long been integral to advancements in medicine, as well as nuclear and non-nuclear industries, with well-established applications in energy, research, and manufacturing. However, these uses pose risks that must be carefully managed in environmental and health policies. Effective radiation protection knowledge and expertise help balance the benefits and risks of ionising radiation use, empowering European society to safely harness its potential. Neglecting investment in radiation protection research and development could lead to increased risks, delayed innovation, and risk-disproportionate radiation protection policy and regulation frameworks, hindering Europe's progress and resilience. This white paper advocates sustained investment in radiation protection research, in the follow-up of the dedicated PIANOFORTE pan-european partnership (2022-2029). In the context of the 10th Framework Programme of Research and Innovation and its related&#xD;EURATOM's part, this should be achieved with a funding envelope for radiation protection research of at least 75M€ through a continued PIANOFORTE-like partnership, including actions related to infrastructure and education and training. Such investment forms an essential component of Europe's strategy for competitiveness, security, and quality of life, including quality of environmental resources and natural capital, notably but not only in the context of the energy transition. Key challenges related to occupational exposure, medical diagnostics and treatments, emergency preparedness and response, exposure to natural sources of radiation and environmental protection underscore the need for comprehensive research to support evidence-based policy decisions, harmonised regulations and safe, sustainable and integrated practices that address protection of both human and environmental health.&#xD.</p>","PeriodicalId":50068,"journal":{"name":"Journal of Radiological Protection","volume":" ","pages":""},"PeriodicalIF":1.4,"publicationDate":"2025-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143765504","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":"Thorium bioassay of miners revisited.","authors":"G S Hewson, M Ralph, M Cattani","doi":"10.1088/1361-6498/adc312","DOIUrl":"10.1088/1361-6498/adc312","url":null,"abstract":"<p><p>This study aimed to revisit previous<i>in-vitro</i>thorium studies on workers and reevaluate their significance against the current International Commission on Radiological Protection (ICRP) models for thorium intake. Thorium concentrations in the urine and blood serum of Western Australian mineral sands workers had previously been interpreted using biokinetic models recommended by the ICRP. These findings revealed significant inconsistencies with those of other monitoring methods, including<i>in-vivo</i>lung counting and personal air sampling. Data on thorium concentrations in the urine and blood serum of workers and their exposure records were extracted from the previously published research and assessed using the Taurus internal dosimetry software application. Inhalation intake parameters such as aerosol particle size and lung solubility were selected to reflect the chronic intake of relatively insoluble mineral sands dust. The literature values for the urinary excretion of thorium by other thorium-exposed workers were also reviewed. Internal dosimetry modelling highlights the sensitivity of urinary thorium excretion as a function of the dust particle size distribution and particle dissolution rate. The timing of urine sample collection is particularly critical during the early years of chronic intake, especially in certain work rosters. The significantly lower urinary thorium concentrations predicted for chronic intake of Type S thorium compounds highlight the need for sensitive analytical techniques for bioassays and a better understanding of non-occupational (environmental) intake. Current ICRP biokinetic models applied to urinary thorium concentrations reported for mineral sands workers and other thorium-exposed workers infer that past doses are likely to be underestimated and are now significant.</p>","PeriodicalId":50068,"journal":{"name":"Journal of Radiological Protection","volume":" ","pages":""},"PeriodicalIF":1.4,"publicationDate":"2025-03-28","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143671385","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":"Numerical modelling of the transport and impact of¹³⁷Cs and¹³¹I on the Meuse-Campine Canals after a potential nuclear accident.","authors":"Amit Ravindra Patil, Fabricio Fiengo Perez, Jonathan Lambrechts, Eric Deleersnijder","doi":"10.1088/1361-6498/adc1db","DOIUrl":"10.1088/1361-6498/adc1db","url":null,"abstract":"<p><p>The Meuse River in Belgium can be impacted by the two nuclear power plants (Tihange and Chooz) located on its banks. Nuclear disasters such as the Fukushima and Chernobyl accidents have illustrated the risks associated with the civilian nuclear industry. In such situations, predictive models become crucial for developing environmental strategies to minimize the potential impact. In this study, we use the SLIM model to simulate the transport of¹³⁷Cs and¹³¹I in the Meuse River system in Belgium. Several hypothetical accidental scenarios are considered for the radionuclide releases based on past nuclear accidents. The simulated radioactive distributions are then used to estimate the individual dose for drinking water. The radionuclide transport in the Meuse River is within days. While the higher peak concentration in the Meuse River results in higher individual dose. The Albert canal being the largest channel among the Campine canals; therefore, the radioactive plume stays over a month. The estimated individual doses for releases from Chooz Nuclear power plant near Tailfer reached 0.2 mSv within three days. Although it takes days, the doses in the Albert Canal reach values up to 0.46 mSv at Haccourt (hypothetical locations). The water extraction points in Herentals, located downstream of the canal, has a negligible individual dose estimation. Higher doses are the consequence of¹³¹I than¹³⁷Cs due to the larger release scenario.</p>","PeriodicalId":50068,"journal":{"name":"Journal of Radiological Protection","volume":" ","pages":""},"PeriodicalIF":1.4,"publicationDate":"2025-03-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143659580","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":"Occupational exposure and radiological risks from x-ray baggage screening in eastern China.","authors":"Peng Dang, Ziya Feng, Xiaoyong Yang, Xingjiang Cao, Xiaolei Shen, Jin Wang","doi":"10.1088/1361-6498/adc014","DOIUrl":"10.1088/1361-6498/adc014","url":null,"abstract":"<p><p>The occupational personnel of x-ray baggage screening may experience chronic or abnormal radiation exposure. However, their exposure hazards and individual protections remain ambiguous, especially for some new applications and key positions. In this work, exposure levels were analysed through on-site inspection and Monte Carlo simulation. The effective dose and radiological risk were estimated using the International Commission on Radiological Protection, United Nations Scientific Committee on the Effects of Atomic Radiation, and Biologic Effects of Ionizing Radiation VII risk models. The results show that the workplace dose rate could be controlled at a low level under normal use, with a mean value of 0.21<i>µ</i>Sv·h^-1from the survey. However, it is necessary to strengthen radiation protection for some new applications, such as workshops, whose maximum dose rate could reach up to 2.07<i>µ</i>Sv·h^-1. Additionally, the maximum leakage dose could greatly exceed dose limits under abnormal working conditions. Furthermore, the radiological risk to maintenance and commissioning should be given more attention, as they may be exposed to risks of up to 1.3 × 10^-3% during one work shift. This result is beneficial to deepen the understanding of occupational exposure risks, which could guide individual protection and workplace management.</p>","PeriodicalId":50068,"journal":{"name":"Journal of Radiological Protection","volume":" ","pages":""},"PeriodicalIF":1.4,"publicationDate":"2025-03-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143626702","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 Ca-DTPA/Zn-DTPA therapy for internal decorporation: transitioning from intravenous to oral route with insights on safety and toxicity.","authors":"Nidhi Sandal, Riya Mahar, Pooja Sharma","doi":"10.1088/1361-6498/adc013","DOIUrl":"10.1088/1361-6498/adc013","url":null,"abstract":"<p><p>Ca-DTPA and Zn-DTPA are the decorporating agents approved by the USFDA for removing plutonium, americium, or curium from the subjects known or suspected to be contaminated with these radionuclides. Ca-DTPA and Zn-DTPA are well-known chelating agents with a strong affinity for many bivalent, trivalent, and certain tetravalent metal ions, including plutonium (Pu⁺⁴) and thorium (Th⁺⁴). The major problem associated with Ca-DTPA and Zn-DTPA therapy is that the only approved route of administration is intravenous or inhalation due to its extremely poor bioavailability. Both these drugs belong to BCS class III drugs with high solubility and low permeability. Researchers are exploring various approaches to make these drugs bioavailable via alternate routes, especially the oral route. This will enable pre-hospital care, better patient compliance, and minimize its clinically significant side effect of electrolyte imbalance. The present paper highlights the practical feasibility and challenges of establishing an oral route for delivering Ca-DTPA and Zn-DTPA with the research around it. Also, the paper highlights the importance of establishing an oral dose and the dosing schedule for Ca-DTPA and Zn-DTPA before plunging into its formulation development. These advancements underline the potential of orally administered chelating agents and alternative delivery methods in addressing the limitations of current intravenous formulations and improving accessibility and patient outcomes.</p>","PeriodicalId":50068,"journal":{"name":"Journal of Radiological Protection","volume":" ","pages":""},"PeriodicalIF":1.4,"publicationDate":"2025-03-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143626703","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":"Reducing risks through regulatory cooperation: a review of bilateral regulatory cooperation between the Norwegian Radiation and Nuclear Safety Authority and corresponding authorities in countries of the former Soviet Union.","authors":"Malgorzata Sneve, Graham Smith","doi":"10.1088/1361-6498/adbe82","DOIUrl":"10.1088/1361-6498/adbe82","url":null,"abstract":"<p><p>The Norwegian government has maintained a plan of action on nuclear safety and security for over 25 years. The need for such a plan grew from extensive nuclear activities during the Cold War, both civil and military, that led eventually to significant amounts of radioactive waste (RW) and nuclear material being stored in unsafe conditions in Northwest Russia. As part of the program to implement the plan of action, the Norwegian Radiation and Nuclear Safety Authority has maintained a program of bilateral regulatory cooperation with corresponding authorities in countries of the former Soviet Union for over 25 years. This paper reviews the background to that regulatory program, identifies the main radiologically hazardous objects and the related regulatory challenges, and then documents how bilateral cooperation has contributed to the substantial progress made in risk reduction. The review then considers how bilateral work has contributed to and benefitted from sharing results and experience with international partners and draws conclusions and lessons for future work. The primary conclusion is that bilateral regulatory cooperation has supported reduction of radiation and nuclear risks at a range of complex legacy sites and facilities in countries of the former Soviet Union. Key to this process has been a clear strategy to help build and maintain an up-to-date, robust and independent regulatory process. Only with well-coordinated regulatory bodies with clear responsibilities and functions is it possible to address the diverse threats effectively. Among the most radiologically significant sites and facilities where risk has been significantly reduced or eliminated are the LEPSE spent fuel and RW storage vessel, the site for temporary storage for spent fuel and RW at Andreeva Bay, and the very large radio-isotope thermo-electric generators sources previously used in navigational devices all across the Russian arctic coastline. Noting the clear potential for transboundary impacts, this represents a substantial regional benefit. Following the full-scale invasion of Ukraine by the Russian Federation in February 2022, the bilateral cooperation activities with Russian authorities ceased. Using the successfully developed regulatory working methods and experience gained in Russia, substantial regulatory enhancement has also been achieved in countries of Central Asia and Ukraine, commencing in 2008 and 2014 respectively. Continuing such support in Ukraine, in the face of new regulatory challenges arising due to the full-scale Russian invasion, remains a high priority for the DSA within the Norwegian Nansen program.</p>","PeriodicalId":50068,"journal":{"name":"Journal of Radiological Protection","volume":" ","pages":""},"PeriodicalIF":1.4,"publicationDate":"2025-03-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143598232","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":"Harmonization of practice of release of patients after radiopharmaceutical therapy.","authors":"Larisa Chipiga, Anastasia Likhacheva, Aleksandr Vodovatov, Irina Zvonova, Andrey Stanzhevskiy, Daria Vazhenina, Dmitrii Maystrenko","doi":"10.1088/1361-6498/adba70","DOIUrl":"10.1088/1361-6498/adba70","url":null,"abstract":"<p><p>The implementation of novel therapeutic radiopharmaceuticals requires developing, updating, and harmonizing requirements for radiation safety in radiopharmaceutical therapy (RPT). Public exposure from patients with administered radiopharmaceuticals and biological radioactive waste management have been identified as the main problems in RPT. The aim of our study was to compare different approaches to the development of patient release criteria after RPT with different radiopharmaceuticals, considering radiation exposure of members of the public in transport, biological elimination of radionuclides from a patient's body, and the generation of biological waste. The study was performed for the following radiopharmaceuticals:¹⁷⁷Lu-PSMA-617,¹⁷⁷Lu-DOTATATE, Na¹³¹I,¹³¹I-mIBG, and¹⁵³Sm-oxabifor. Two base approaches to patient release criteria were considered. The first approach is based on the radioactive decay of radionuclides and is divided into two groups: considering one radiopharmaceutical administration and considering several radiopharmaceutical administrations per course. The second approach is based on the radioactive decay of radionuclides and biological elimination of radiopharmaceuticals from the patient's body (effective half-life) and is divided into groups based on 1 and 5 mSv dose constraints per course. The ffective dose rates from patients and sewage tanks to passengers and staff on public transport were estimated for various scenarios of patients traveling after RPT. The results demonstrated that the radiation safety of members of the public in transport should be considered when establishing the release criteria of patients after RPT. Based on the results, it is recommended to follow the approach based on the radioactive decay of radionuclides and dose constraints to members of the public in contact with patients of 1 mSv per radiopharmaceutical administration, and keep patients in the nuclear medicine department after radiopharmaceutical administration for at least 4-6 h. The patient release criteria defined according to this approach comply with patient release criteria used in different countries, and allow the radiation safety of the public to be maintained.</p>","PeriodicalId":50068,"journal":{"name":"Journal of Radiological Protection","volume":" ","pages":""},"PeriodicalIF":1.4,"publicationDate":"2025-03-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143517187","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}