Pub Date : 2025-01-01Epub Date: 2024-09-13DOI: 10.1097/HP.0000000000001858
Carly E Evans, Kimberlee J Kearfott
Abstract: Affordable, accurate, and robust temporal measurement devices are desirable for screening and assessment of radon levels in private homes and workplaces. This research expands upon prior research, using the RadonFTlab RadonEye device through a comparison of multiple samples of this instrument with a laboratory-grade instrument, the Saphymo AlphaGUARD, over a more extensive period than reported previously. Data were collected over 291 d in a poorly ventilated basement space in an occupied building. Environmental conditions varied naturally, changing both the radon source term and radon entry into the space approximating typically deployed conditions. The R-squared linear regression correlation coefficient and relative sensitivities of each RadonEye with the AlphaGUARD were computed. Overall temporal and diurnal variations were also studied. The sensitivities of all RadonEyes and the AlphaGUARD agreed to within 22% throughout the entire deployment period.
{"title":"A 291-day Evaluation of the Performance of a Consumer-grade Temporal Radon Detector.","authors":"Carly E Evans, Kimberlee J Kearfott","doi":"10.1097/HP.0000000000001858","DOIUrl":"10.1097/HP.0000000000001858","url":null,"abstract":"<p><strong>Abstract: </strong>Affordable, accurate, and robust temporal measurement devices are desirable for screening and assessment of radon levels in private homes and workplaces. This research expands upon prior research, using the RadonFTlab RadonEye device through a comparison of multiple samples of this instrument with a laboratory-grade instrument, the Saphymo AlphaGUARD, over a more extensive period than reported previously. Data were collected over 291 d in a poorly ventilated basement space in an occupied building. Environmental conditions varied naturally, changing both the radon source term and radon entry into the space approximating typically deployed conditions. The R-squared linear regression correlation coefficient and relative sensitivities of each RadonEye with the AlphaGUARD were computed. Overall temporal and diurnal variations were also studied. The sensitivities of all RadonEyes and the AlphaGUARD agreed to within 22% throughout the entire deployment period.</p>","PeriodicalId":12976,"journal":{"name":"Health physics","volume":" ","pages":"60-65"},"PeriodicalIF":1.0,"publicationDate":"2025-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142285888","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}
Pub Date : 2025-01-01Epub Date: 2024-09-02DOI: 10.1097/HP.0000000000001889
Krishnakumar Divakar Nangeelil, Haven Searcy, Beverly Parker, Zaijing Sun
Abstract: A comprehensive radiological study was conducted in the surrounding public zones of the Nevada National Security Site to identify traces of resuspended radioactivity and heavy elemental contamination that might have resulted from various activities. The study used passive and active nuclear methods, specifically gamma spectrometry and instrumental neutron activation analysis, respectively. Passive gamma spectra analysis of air filter papers from various Community Environmental Monitoring Program stations conclusively verified the presence of radionuclides exclusively originating from the natural decay series of 238 U and 232 Th. Furthermore, gamma spectrometry and instrumental neutron activation analysis of plant samples from surrounding areas of the Nevada National Security Site revealed the absence of any unusual elemental contamination in the environment. These results demonstrated that there was no measurable radiological impact on the public zones surrounding the site resulting from the spread of radioactive materials or toxic heavy metals associated with previous or ongoing activities at Nevada National Security Site. Therefore, the safety of public zones concerning retained radioactivity and harmful elemental contamination arising from Nevada National Security Site operations is negligible. The significance of this study is further pronounced in the current geopolitical context, as it establishes the baseline elemental composition for various desert plants for future reference.
{"title":"Assessing Radiation Fallout in Public Zones near the Nevada National Security Site (NNSS): A Recent Study.","authors":"Krishnakumar Divakar Nangeelil, Haven Searcy, Beverly Parker, Zaijing Sun","doi":"10.1097/HP.0000000000001889","DOIUrl":"10.1097/HP.0000000000001889","url":null,"abstract":"<p><strong>Abstract: </strong>A comprehensive radiological study was conducted in the surrounding public zones of the Nevada National Security Site to identify traces of resuspended radioactivity and heavy elemental contamination that might have resulted from various activities. The study used passive and active nuclear methods, specifically gamma spectrometry and instrumental neutron activation analysis, respectively. Passive gamma spectra analysis of air filter papers from various Community Environmental Monitoring Program stations conclusively verified the presence of radionuclides exclusively originating from the natural decay series of 238 U and 232 Th. Furthermore, gamma spectrometry and instrumental neutron activation analysis of plant samples from surrounding areas of the Nevada National Security Site revealed the absence of any unusual elemental contamination in the environment. These results demonstrated that there was no measurable radiological impact on the public zones surrounding the site resulting from the spread of radioactive materials or toxic heavy metals associated with previous or ongoing activities at Nevada National Security Site. Therefore, the safety of public zones concerning retained radioactivity and harmful elemental contamination arising from Nevada National Security Site operations is negligible. The significance of this study is further pronounced in the current geopolitical context, as it establishes the baseline elemental composition for various desert plants for future reference.</p>","PeriodicalId":12976,"journal":{"name":"Health physics","volume":" ","pages":"37-46"},"PeriodicalIF":1.0,"publicationDate":"2025-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142106900","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}
Pub Date : 2025-01-01Epub Date: 2024-07-08DOI: 10.1097/HP.0000000000001821
Theodore Thomas, Jason Harris
Abstract: Nuclear safety and security are essential elements of radiation protection. Integration of nuclear safety and security provides a means to identify conflict and synergy points. Research has not been performed to enable integrated practices at the facility level. A tool was developed through research to help staff and regulators assess the level of integration practiced within a research reactor. This tool aims to improve the identification of synergistic and conflict points. Eight criteria of nuclear safety and security integration were used to create the integration assessment tool: access control, transportation, emergency response, proper disposal of materials, testing and maintenance, defense in depth, training and education, and culture. The tool's final score can range from 0.0375 to 1, with a score of 1 indicating complete integration. The tool was used by research reactor staff to assess practiced integrative techniques. The testing and maintenance criterion scored the highest level of integration (0.84). Training and education and culture scored the lowest levels of integration (0.50). The areas with the highest scores identified points of actively practiced integration. In contrast, those areas with lower scores indicated a lack of integrative practices. The total integration score was 0.69. This tool determined that the facility practiced an adequate level of integration. By analyzing integration levels with this tool, a measurable standard of integrative practices can be employed to achieve improved radiation protection.
{"title":"Development of a Nuclear Safety and Security Integration Assessment Tool for Research Reactors and Associated Facilities.","authors":"Theodore Thomas, Jason Harris","doi":"10.1097/HP.0000000000001821","DOIUrl":"10.1097/HP.0000000000001821","url":null,"abstract":"<p><strong>Abstract: </strong>Nuclear safety and security are essential elements of radiation protection. Integration of nuclear safety and security provides a means to identify conflict and synergy points. Research has not been performed to enable integrated practices at the facility level. A tool was developed through research to help staff and regulators assess the level of integration practiced within a research reactor. This tool aims to improve the identification of synergistic and conflict points. Eight criteria of nuclear safety and security integration were used to create the integration assessment tool: access control, transportation, emergency response, proper disposal of materials, testing and maintenance, defense in depth, training and education, and culture. The tool's final score can range from 0.0375 to 1, with a score of 1 indicating complete integration. The tool was used by research reactor staff to assess practiced integrative techniques. The testing and maintenance criterion scored the highest level of integration (0.84). Training and education and culture scored the lowest levels of integration (0.50). The areas with the highest scores identified points of actively practiced integration. In contrast, those areas with lower scores indicated a lack of integrative practices. The total integration score was 0.69. This tool determined that the facility practiced an adequate level of integration. By analyzing integration levels with this tool, a measurable standard of integrative practices can be employed to achieve improved radiation protection.</p>","PeriodicalId":12976,"journal":{"name":"Health physics","volume":" ","pages":"24-36"},"PeriodicalIF":1.0,"publicationDate":"2025-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141554715","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}
Pub Date : 2025-01-01Epub Date: 2024-06-18DOI: 10.1097/HP.0000000000001845
Chandler Cotton, Charles Wilson, Robert Heath, Emily Caffrey
Abstract: At the University of Alabama at Birmingham (UAB), many diagnostic and therapeutic procedures involving radioactive materials or radiation-producing machines are performed daily. A growing number of minor but preventable incidents related to radiation safety have brought up concerns related to the effectiveness of the training program. A comprehensive literature review was performed to summarize post-COVID insights into andragogic online training practices, statistical analyses, and overall retention competencies in radiation safety. Andragogic research shows that the best method of training adult learners is controlled simulation that tests critical thinking and problem-solving capabilities, drawing upon previous knowledge or experiences. A new training curriculum based on these andragogic principles was designed and administered to a subgroup of UAB radiation workers. Scores from pre-testing and post-testing were collected and analyzed. An ANCOVA was used to account for differences in the pre-test scores between the control and experimental groups, which was found to be statistically significant (p = 0.018), suggesting that small changes in a radiation safety training program can have significant impacts in retention of key information.
{"title":"Andragogic Improvements in Radiation Safety Training.","authors":"Chandler Cotton, Charles Wilson, Robert Heath, Emily Caffrey","doi":"10.1097/HP.0000000000001845","DOIUrl":"10.1097/HP.0000000000001845","url":null,"abstract":"<p><strong>Abstract: </strong>At the University of Alabama at Birmingham (UAB), many diagnostic and therapeutic procedures involving radioactive materials or radiation-producing machines are performed daily. A growing number of minor but preventable incidents related to radiation safety have brought up concerns related to the effectiveness of the training program. A comprehensive literature review was performed to summarize post-COVID insights into andragogic online training practices, statistical analyses, and overall retention competencies in radiation safety. Andragogic research shows that the best method of training adult learners is controlled simulation that tests critical thinking and problem-solving capabilities, drawing upon previous knowledge or experiences. A new training curriculum based on these andragogic principles was designed and administered to a subgroup of UAB radiation workers. Scores from pre-testing and post-testing were collected and analyzed. An ANCOVA was used to account for differences in the pre-test scores between the control and experimental groups, which was found to be statistically significant (p = 0.018), suggesting that small changes in a radiation safety training program can have significant impacts in retention of key information.</p>","PeriodicalId":12976,"journal":{"name":"Health physics","volume":" ","pages":"47-51"},"PeriodicalIF":1.0,"publicationDate":"2025-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141418600","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}
Pub Date : 2025-01-01Epub Date: 2024-06-18DOI: 10.1097/HP.0000000000001842
Joeun L Kot, Jason T Harris
Abstract: Radiation protection contains the key elements of nuclear safety and security. Despite the overlap between nuclear safety and security, their objectives differ fundamentally, focusing on unintentional accidents and intentional malicious events, respectively. As such, the Potential Facility Risk Index (PFRI), originally created for security purposes, has evolved into an approach that combines conventional probabilistic risk assessment (PRA), which is a widely employed method to evaluate the safety risks of nuclear facilities. This research has developed a risk assessment model within the PFRI framework to calculate the probability of nuclear terrorism. Three essential components of the model are integrated: an analysis of historical nuclear terrorism data to determine an initial threat frequency; the target-specific factor using analytical hierarchy process (AHP) target attractiveness analysis; and the adversary motivation factor based on site-specific social influences from the Profiles of Individual Radicalization in the United States (PIRUS) dataset. Applied to a hypothetical nuclear facility, the model produces a nuclear terrorism probability of 8.97 × 10 -3 y - 1 . The systematic methodology proposed in the study enables the derivation of nuclear terrorism probability with results in the same risk unit as safety risk assessment. This method allows decision makers to seamlessly incorporate nuclear safety and security risk assessments, offering a comprehensive perspective. Consequently, it enriches comprehension of nuclear facility risks and establishes the groundwork for future advancements.
摘要:辐射防护包含核安全与核安保的关键要素。尽管核安全与核安保之间存在重叠,但两者的目标却有本质区别,分别侧重于非蓄意事故和蓄意恶意事件。因此,最初为安保目的而创建的 "潜在设施风险指数"(PFRI)已发展成为一种结合了传统概率风险评估(PRA)的方法,这是一种广泛用于评估核设施安全风险的方法。这项研究在 PFRI 框架内开发了一个风险评估模型,用于计算核恐怖主义的概率。该模型集成了三个基本组成部分:分析历史核恐怖主义数据以确定初始威胁频率;使用分析层次过程(AHP)进行目标吸引力分析的特定目标因素;以及基于美国个人激进化概况(PIRUS)数据集的特定场所社会影响的对手动机因素。将该模型应用于假定的核设施,可得出核恐怖主义概率为 8.97 × 10-3 y - 1。研究中提出的系统方法可推导出核恐怖主义概率,其结果与安全风险评估的风险单位相同。这种方法允许决策者将核安全与核安保风险评估无缝结合,提供了一个全面的视角。因此,它丰富了对核设施风险的理解,并为未来的进步奠定了基础。
{"title":"Risk Assessment for Nuclear Terrorism Probability and Its Application on a Hypothetical Nuclear Facility.","authors":"Joeun L Kot, Jason T Harris","doi":"10.1097/HP.0000000000001842","DOIUrl":"10.1097/HP.0000000000001842","url":null,"abstract":"<p><strong>Abstract: </strong>Radiation protection contains the key elements of nuclear safety and security. Despite the overlap between nuclear safety and security, their objectives differ fundamentally, focusing on unintentional accidents and intentional malicious events, respectively. As such, the Potential Facility Risk Index (PFRI), originally created for security purposes, has evolved into an approach that combines conventional probabilistic risk assessment (PRA), which is a widely employed method to evaluate the safety risks of nuclear facilities. This research has developed a risk assessment model within the PFRI framework to calculate the probability of nuclear terrorism. Three essential components of the model are integrated: an analysis of historical nuclear terrorism data to determine an initial threat frequency; the target-specific factor using analytical hierarchy process (AHP) target attractiveness analysis; and the adversary motivation factor based on site-specific social influences from the Profiles of Individual Radicalization in the United States (PIRUS) dataset. Applied to a hypothetical nuclear facility, the model produces a nuclear terrorism probability of 8.97 × 10 -3 y - 1 . The systematic methodology proposed in the study enables the derivation of nuclear terrorism probability with results in the same risk unit as safety risk assessment. This method allows decision makers to seamlessly incorporate nuclear safety and security risk assessments, offering a comprehensive perspective. Consequently, it enriches comprehension of nuclear facility risks and establishes the groundwork for future advancements.</p>","PeriodicalId":12976,"journal":{"name":"Health physics","volume":" ","pages":"13-23"},"PeriodicalIF":1.0,"publicationDate":"2025-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141418602","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}
Pub Date : 2024-12-13DOI: 10.1097/HP.0000000000001921
William Evans
Abstract: Three topics related to ANSI/HPS Standard N13.56, Sampling and Monitoring Releases of Airborne Radioactivity in the Workplace, are discussed. First, due to the omission of consideration of the activity's half-life in the standard's continuous particulate air monitor (CPAM) quantitative method, it is possible for concentration estimates produced by that calculation to be underestimated. Second, the concentration estimate found in air grab sampling, as discussed in the standard, is not, as claimed, an average unless the activity is "long-lived" (negligible decay during sampling). It is nonetheless possible for this calculation to produce a concentration estimate that is not significantly different from the average, depending on both the half-life of the activity and the sampling time. Third, the issue of when to change the filter for the CPAM method is addressed.
{"title":"Three Developments Related to ANSI/HPS Standard N13.56.","authors":"William Evans","doi":"10.1097/HP.0000000000001921","DOIUrl":"https://doi.org/10.1097/HP.0000000000001921","url":null,"abstract":"<p><strong>Abstract: </strong>Three topics related to ANSI/HPS Standard N13.56, Sampling and Monitoring Releases of Airborne Radioactivity in the Workplace, are discussed. First, due to the omission of consideration of the activity's half-life in the standard's continuous particulate air monitor (CPAM) quantitative method, it is possible for concentration estimates produced by that calculation to be underestimated. Second, the concentration estimate found in air grab sampling, as discussed in the standard, is not, as claimed, an average unless the activity is \"long-lived\" (negligible decay during sampling). It is nonetheless possible for this calculation to produce a concentration estimate that is not significantly different from the average, depending on both the half-life of the activity and the sampling time. Third, the issue of when to change the filter for the CPAM method is addressed.</p>","PeriodicalId":12976,"journal":{"name":"Health physics","volume":" ","pages":""},"PeriodicalIF":1.0,"publicationDate":"2024-12-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142817852","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}
Pub Date : 2024-12-10DOI: 10.1097/HP.0000000000001942
Ryan Misseldine, Ryan Kocak, Andrew Dietz, Ronald Leuenberger, David Jordan
Abstract: The roles and responsibilities of radiation safety officers (RSO), medical health physicists (MHP) and diagnostic medical physicists (DMP) have evolved significantly over the past 20 years. With the availability of enterprise software systems and aggregated data platforms for various radiologic healthcare systems, the roles of these professions are expanding beyond their original scopes in managing the Radioactive Materials License (RSO, MHP) and Machine Specific Physics Testing (DMP). Workers in medical radiation safety are transitioning from siloed workers working within their specific disciplines as new emerging technology and clinical care require these roles to evolve. This paper aims to demonstrate the value in embracing the change in these roles to better serve the patients and occupational workers RSOs, MHPs, and DMPs serve. As medical physics enterprise solutions evolve, so will the relationships between these valuable stakeholders.
{"title":"Evolution of Diagnostic Medical Physics Enterprise.","authors":"Ryan Misseldine, Ryan Kocak, Andrew Dietz, Ronald Leuenberger, David Jordan","doi":"10.1097/HP.0000000000001942","DOIUrl":"https://doi.org/10.1097/HP.0000000000001942","url":null,"abstract":"<p><strong>Abstract: </strong>The roles and responsibilities of radiation safety officers (RSO), medical health physicists (MHP) and diagnostic medical physicists (DMP) have evolved significantly over the past 20 years. With the availability of enterprise software systems and aggregated data platforms for various radiologic healthcare systems, the roles of these professions are expanding beyond their original scopes in managing the Radioactive Materials License (RSO, MHP) and Machine Specific Physics Testing (DMP). Workers in medical radiation safety are transitioning from siloed workers working within their specific disciplines as new emerging technology and clinical care require these roles to evolve. This paper aims to demonstrate the value in embracing the change in these roles to better serve the patients and occupational workers RSOs, MHPs, and DMPs serve. As medical physics enterprise solutions evolve, so will the relationships between these valuable stakeholders.</p>","PeriodicalId":12976,"journal":{"name":"Health physics","volume":" ","pages":""},"PeriodicalIF":1.0,"publicationDate":"2024-12-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142800564","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}
Pub Date : 2024-12-10DOI: 10.1097/HP.0000000000001934
T Sahmaran, S Nur, H I Atılgan, H Peker
Abstract: In this study, the occupational radiation dose, radon gas, and non-ionizing radiation doses originating from electromagnetic fields (EMF) to which radiation workers are exposed were monitored and evaluated for 1 y. Using electronic personnel dosimeters (EPD), average daily radiation doses based on the number of patients and annual average effective dose results of radiation workers were obtained over a period of 1 y. Also, the annual effective dose and risk values were calculated for 8 h and 24 h by taking radon gas measurements at 2-mo intervals in the nuclear medicine department. Finally, electric field measurements were made one day a week in the selected areas. All the results obtained were compared with national and international dose limits. The results obtained as a result of EPD, radon gas, and EMF measurements made in the nuclear medicine department were found to be far below the international and national legal dose limits.
{"title":"Dose Estimation for Indoor Radon, Occupational Radiation, and Electromagnetic Field Exposure in a Nuclear Medicine Department in Turkiye.","authors":"T Sahmaran, S Nur, H I Atılgan, H Peker","doi":"10.1097/HP.0000000000001934","DOIUrl":"https://doi.org/10.1097/HP.0000000000001934","url":null,"abstract":"<p><strong>Abstract: </strong>In this study, the occupational radiation dose, radon gas, and non-ionizing radiation doses originating from electromagnetic fields (EMF) to which radiation workers are exposed were monitored and evaluated for 1 y. Using electronic personnel dosimeters (EPD), average daily radiation doses based on the number of patients and annual average effective dose results of radiation workers were obtained over a period of 1 y. Also, the annual effective dose and risk values were calculated for 8 h and 24 h by taking radon gas measurements at 2-mo intervals in the nuclear medicine department. Finally, electric field measurements were made one day a week in the selected areas. All the results obtained were compared with national and international dose limits. The results obtained as a result of EPD, radon gas, and EMF measurements made in the nuclear medicine department were found to be far below the international and national legal dose limits.</p>","PeriodicalId":12976,"journal":{"name":"Health physics","volume":" ","pages":""},"PeriodicalIF":1.0,"publicationDate":"2024-12-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142800561","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}
Pub Date : 2024-12-10DOI: 10.1097/HP.0000000000001932
Jan Beyea
Abstract: In reviewing a video series that they created for the website of the Health Physics Society (HPS), past leaders of the Health Physics Society have treated as authoritative and trustworthy the scientific misconduct theories of University of Massachusetts Professor Edward Calabrese. No mention is made of detailed critiques of Calabrese's work. I show that Calabrese's historical work as presented by HPS's authors is unreliable because it overlooks key historical text and key statistical concepts about the limits of an early atomic bomb genetics study. When these errors are corrected, claims of scientific misconduct on the part of historical figures evaporate. Claims of threshold behavior in early radiation genetic experiments are wrong for atomic bomb data. Calabrese's unique claims about thresholds in early animal genetic data are not credible for human cancer, given the doses at which they were carried out (>30 R). Recent epidemiological studies of both acute and protracted exposure in humans fail to show dose-rate effects or a dose threshold above 30 R. Such results from human data should be more relevant for most regulators and review committees than Calabrese's claims about old data on animals. Disclaimers, errata, and links to critiques should be added to the HPS webpage hosting the 22-part video series. Failure to do so can cause damage to reputations and historical accuracy because it erroneously validates Calabrese's inflammatory claims of scientific misconduct against past scientists, including three Nobel Prize winners, members of the NAS, and presidents of the AAAS.
{"title":"False and Misleading Claims of Scientific Misconduct in Early Research into Radiation Dose-response: Part 1. Overlooking Key Historical Text.","authors":"Jan Beyea","doi":"10.1097/HP.0000000000001932","DOIUrl":"https://doi.org/10.1097/HP.0000000000001932","url":null,"abstract":"<p><strong>Abstract: </strong>In reviewing a video series that they created for the website of the Health Physics Society (HPS), past leaders of the Health Physics Society have treated as authoritative and trustworthy the scientific misconduct theories of University of Massachusetts Professor Edward Calabrese. No mention is made of detailed critiques of Calabrese's work. I show that Calabrese's historical work as presented by HPS's authors is unreliable because it overlooks key historical text and key statistical concepts about the limits of an early atomic bomb genetics study. When these errors are corrected, claims of scientific misconduct on the part of historical figures evaporate. Claims of threshold behavior in early radiation genetic experiments are wrong for atomic bomb data. Calabrese's unique claims about thresholds in early animal genetic data are not credible for human cancer, given the doses at which they were carried out (>30 R). Recent epidemiological studies of both acute and protracted exposure in humans fail to show dose-rate effects or a dose threshold above 30 R. Such results from human data should be more relevant for most regulators and review committees than Calabrese's claims about old data on animals. Disclaimers, errata, and links to critiques should be added to the HPS webpage hosting the 22-part video series. Failure to do so can cause damage to reputations and historical accuracy because it erroneously validates Calabrese's inflammatory claims of scientific misconduct against past scientists, including three Nobel Prize winners, members of the NAS, and presidents of the AAAS.</p>","PeriodicalId":12976,"journal":{"name":"Health physics","volume":" ","pages":""},"PeriodicalIF":1.0,"publicationDate":"2024-12-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142800575","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}
Pub Date : 2024-12-01Epub Date: 2024-09-19DOI: 10.1097/HP.0000000000001874
Yanling Yi, Michael G Stabin
Abstract: Objectives: To analyze the effects of normal x-ray inspection, machine washing, and machine drying on thermoluminescent dosimeter (TLD) measurements during external individual monitoring and to provide suggestions for determining individual monitoring measurements under the mentioned abnormal situations. In this study, we focused on three abnormal situations: x-ray inspection, machine washing, and machine drying, which are common in external individual dose monitoring. We measured and compared the doses from TLD with and without 11, 23, 35, and 50 security checks. We used different radiation sources to expose the TLDs before or after machine washing with or without hot drying. The three radiation sources are natural background radiation, 137 Cs γ rays, and 320 kVp x-rays. We measured 20 TLDs for each situation. The average doses for the TLDs with 11, 23, 35, 50 security checks are 27.7 μGy, 59.7 μGy, 84.1 μGy, and 121.0 μGy, respectively. We measured an average dose of 2.5 μGy per exposure. The doses showed no significant difference between different times of washing with different radiation sources, natural background radiation, 137 Cs, or x-ray exposures. There was also no significant difference between the dose coming from the controlled group, drying at 60 °C and 90 °C for 1 h after exposure to 137 Cs γ rays and 320 kVp x-rays. The common machine drying under the temperature of 90 °C did not affect TLD measured doses.
摘要:目的:分析正常的 X 射线检查、机器清洗和机器烘干对体外个体监测期间热释光剂量计(TLD)测量值的影响,并为确定上述异常情况下的个体监测测量值提供建议。在本研究中,我们重点研究了三种异常情况:X 射线检查、机器清洗和机器烘干,这三种情况在外部个体剂量监测中很常见。我们测量并比较了有和没有 11、23、35 和 50 次安检的 TLD 剂量。我们使用了不同的辐射源,在有或没有热烘干的机器清洗之前或之后对 TLD 进行照射。这三种辐射源分别是天然本底辐射、137Cs γ 射线和 320 kVp X 射线。我们在每种情况下测量了 20 个 TLD。11、23、35、50 次安检的 TLD 平均剂量分别为 27.7 μGy、59.7 μGy、84.1 μGy 和 121.0 μGy。我们测得每次照射的平均剂量为 2.5 μGy。在不同辐射源、天然本底辐射、137Cs 或 X 射线照射下,不同清洗时间的剂量没有明显差异。在对照组中,137Cs γ 射线和 320 kVp X 射线照射后在 60 °C 和 90 °C 下烘干 1 小时所产生的剂量也没有明显差异。在 90 ℃ 的温度下进行普通机器干燥不会影响 TLD 测得的剂量。
{"title":"The Effects of Abnormal Exposure on Individual Dose Monitoring with TLD Dosimeters.","authors":"Yanling Yi, Michael G Stabin","doi":"10.1097/HP.0000000000001874","DOIUrl":"10.1097/HP.0000000000001874","url":null,"abstract":"<p><strong>Abstract: </strong>Objectives: To analyze the effects of normal x-ray inspection, machine washing, and machine drying on thermoluminescent dosimeter (TLD) measurements during external individual monitoring and to provide suggestions for determining individual monitoring measurements under the mentioned abnormal situations. In this study, we focused on three abnormal situations: x-ray inspection, machine washing, and machine drying, which are common in external individual dose monitoring. We measured and compared the doses from TLD with and without 11, 23, 35, and 50 security checks. We used different radiation sources to expose the TLDs before or after machine washing with or without hot drying. The three radiation sources are natural background radiation, 137 Cs γ rays, and 320 kVp x-rays. We measured 20 TLDs for each situation. The average doses for the TLDs with 11, 23, 35, 50 security checks are 27.7 μGy, 59.7 μGy, 84.1 μGy, and 121.0 μGy, respectively. We measured an average dose of 2.5 μGy per exposure. The doses showed no significant difference between different times of washing with different radiation sources, natural background radiation, 137 Cs, or x-ray exposures. There was also no significant difference between the dose coming from the controlled group, drying at 60 °C and 90 °C for 1 h after exposure to 137 Cs γ rays and 320 kVp x-rays. The common machine drying under the temperature of 90 °C did not affect TLD measured doses.</p>","PeriodicalId":12976,"journal":{"name":"Health physics","volume":" ","pages":"730-733"},"PeriodicalIF":1.0,"publicationDate":"2024-12-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142285891","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}