Pub Date : 2022-01-01DOI: 10.1051/radiopro/2022020
T. Tsujiguchi, S. Shukunobe, Y. Sagisaka, K. Yamanouchi, K. Ito, T. Koiwa, K. Kudo, Y. Takei, S. Hosokawa, Y. Takahashi
Occupational exposure of radiation workers, including nurses, is an important issue that should always be considered. However, there are limited reports on external exposure of nurses working in nuclear medicine investigated using a personal dosimeter with a trend function. We investigated the relationship between the personal dose equivalent and behavior of nurses in nuclear medicine using a personal dosimeter with a trend function. It was found that the external exposure of nurses was high when they cleaned hospital rooms where patients who received radiopharmaceutical drugs were admitted. However, none of the nurses surveyed exceeded 3μ. Visualization of the contamination in the hospital room showed that the area around the sink and trash can was particularly contaminated. Hence, nurses need to be more careful when cleaning. Although it is unlikely that the nurses surveyed will be affected by external exposure, data in this report is valuable for nurses at medical institutions to consider work hours and personnel strategies.
{"title":"Analysis for external exposure of nurses engaged in nuclear medicine using a personal dosimeter with a trend function","authors":"T. Tsujiguchi, S. Shukunobe, Y. Sagisaka, K. Yamanouchi, K. Ito, T. Koiwa, K. Kudo, Y. Takei, S. Hosokawa, Y. Takahashi","doi":"10.1051/radiopro/2022020","DOIUrl":"https://doi.org/10.1051/radiopro/2022020","url":null,"abstract":"Occupational exposure of radiation workers, including nurses, is an important issue that should always be considered. However, there are limited reports on external exposure of nurses working in nuclear medicine investigated using a personal dosimeter with a trend function. We investigated the relationship between the personal dose equivalent and behavior of nurses in nuclear medicine using a personal dosimeter with a trend function. It was found that the external exposure of nurses was high when they cleaned hospital rooms where patients who received radiopharmaceutical drugs were admitted. However, none of the nurses surveyed exceeded 3μ. Visualization of the contamination in the hospital room showed that the area around the sink and trash can was particularly contaminated. Hence, nurses need to be more careful when cleaning. Although it is unlikely that the nurses surveyed will be affected by external exposure, data in this report is valuable for nurses at medical institutions to consider work hours and personnel strategies.","PeriodicalId":21009,"journal":{"name":"Radioprotection","volume":"6 1","pages":""},"PeriodicalIF":1.1,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"78748677","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 : 2022-01-01DOI: 10.1051/radiopro/2022007
Z. Tahiri, M. Talbi, M. El Mansouri
The large use of Computed Tomography Scan (CT scan) is a principal cause of increasing medical ionizing radiation exposure. Children are considered a population at risk for the occurrence of radiation-induced pathologies, and the implementation of radiation protection measures relies on the knowledge and skills of healthcare professionals. This analytical cross-sectional study aimed to assess the knowledge of Moroccan physicians prescribing pediatric CT scan examinations on the radiation protection of patients, radiation doses, and potential health risks of radiation exposure from CT scan. A questionnaire was distributed to all clinicians on the medical staff who prescribe pediatric CT examinations in five Moroccan pediatric hospitals. The questions have a focusing on prescribers’ practices and their knowledge of patient radiation protection, radiation doses, the potential health risks of radiation exposure from CT scan, and training on radiation protection. One hundred and ninety-two questionnaires were submitted to prescribers and among them, 88% responded. The data were analyzed using the Statistical Package of Microsoft Office Excel. Knowledge gaps regarding CT scan radiation doses and associated health risks among Moroccan physicians are evident from this study results, initial and continuing training of health care staff and the implementation of referral guidelines for medical imaging could lead to improve practitioners’ knowledge of patient radiation protection.
{"title":"Evaluation of Moroccan physician’s knowledge about radiation doses and risks from pediatric computed tomography","authors":"Z. Tahiri, M. Talbi, M. El Mansouri","doi":"10.1051/radiopro/2022007","DOIUrl":"https://doi.org/10.1051/radiopro/2022007","url":null,"abstract":"The large use of Computed Tomography Scan (CT scan) is a principal cause of increasing medical ionizing radiation exposure. Children are considered a population at risk for the occurrence of radiation-induced pathologies, and the implementation of radiation protection measures relies on the knowledge and skills of healthcare professionals. This analytical cross-sectional study aimed to assess the knowledge of Moroccan physicians prescribing pediatric CT scan examinations on the radiation protection of patients, radiation doses, and potential health risks of radiation exposure from CT scan. A questionnaire was distributed to all clinicians on the medical staff who prescribe pediatric CT examinations in five Moroccan pediatric hospitals. The questions have a focusing on prescribers’ practices and their knowledge of patient radiation protection, radiation doses, the potential health risks of radiation exposure from CT scan, and training on radiation protection. One hundred and ninety-two questionnaires were submitted to prescribers and among them, 88% responded. The data were analyzed using the Statistical Package of Microsoft Office Excel. Knowledge gaps regarding CT scan radiation doses and associated health risks among Moroccan physicians are evident from this study results, initial and continuing training of health care staff and the implementation of referral guidelines for medical imaging could lead to improve practitioners’ knowledge of patient radiation protection.","PeriodicalId":21009,"journal":{"name":"Radioprotection","volume":"64 1","pages":""},"PeriodicalIF":1.1,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"84826134","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 : 2022-01-01DOI: 10.1051/radiopro/2022028
S. Andresz, T. Jobert, C. Schieber
The reference monetary value of the man.sievert is a pragmatic decision-aiding technique to “take into account economic and societal factors” associated with the optimisation principle and to help decide whether a protection option is “reasonable” or not. EDF has adopted a system of reference monetary values in 1992, updated it in 2002, and was considering a new update. In 2019 and 2020, a designated EDF-CEPN working group investigated the elements (through survey, literature and feedback analysis) that might support a change and in which direction. A simplified system, based on one single reference monetary value of the man.sievert, has been proposed. The value takes into account the most recent recommendations from ICRP and French State administration and uses the state-of-the-art methodology in calculating the Value of Statistical Life and has been adjusted with an aversion risk factor considering the EDF radiation protection policy. The new reference value is 4,500 €/man.mSv. An upper value of 7,000 €/man.mSv can be used if the project presents radiation protection benefits (positive externalities) in addition to a reduction in collective dose. The Radiation Protection Manager makes the decision on which value should be selected, and the Radiation Protection Service, in collaboration with the other services, integrates the value in the optimization analysis, bearing in mind that the output will guide the decision (and not determine it) bringing also objectivity and transparency.
{"title":"The evolution of the reference monetary value of the man.sievert at Électricité de France","authors":"S. Andresz, T. Jobert, C. Schieber","doi":"10.1051/radiopro/2022028","DOIUrl":"https://doi.org/10.1051/radiopro/2022028","url":null,"abstract":"The reference monetary value of the man.sievert is a pragmatic decision-aiding technique to “take into account economic and societal factors” associated with the optimisation principle and to help decide whether a protection option is “reasonable” or not. EDF has adopted a system of reference monetary values in 1992, updated it in 2002, and was considering a new update. In 2019 and 2020, a designated EDF-CEPN working group investigated the elements (through survey, literature and feedback analysis) that might support a change and in which direction. A simplified system, based on one single reference monetary value of the man.sievert, has been proposed. The value takes into account the most recent recommendations from ICRP and French State administration and uses the state-of-the-art methodology in calculating the Value of Statistical Life and has been adjusted with an aversion risk factor considering the EDF radiation protection policy. The new reference value is 4,500 €/man.mSv. An upper value of 7,000 €/man.mSv can be used if the project presents radiation protection benefits (positive externalities) in addition to a reduction in collective dose. The Radiation Protection Manager makes the decision on which value should be selected, and the Radiation Protection Service, in collaboration with the other services, integrates the value in the optimization analysis, bearing in mind that the output will guide the decision (and not determine it) bringing also objectivity and transparency.","PeriodicalId":21009,"journal":{"name":"Radioprotection","volume":"5 1","pages":""},"PeriodicalIF":1.1,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"90868435","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 : 2022-01-01DOI: 10.1051/radiopro/2022002
J. Bertho, F. Gabillaud-Poillion, C. Reuter, O. Riviere
The French Nuclear Safety Authority (ASN) issued in 2012 a first version of a doctrine establishing the principles of management of a post-accidental situation following a major nuclear accident. Since this publication, the feedback of the Fukushima-Daiichi accident continued and numerous evolutions occurred, both in French and European regulations and in international recommendations from IAEA and ICRP. This had led to further developments in the French doctrine for management of a post-accidental situation. This will result in the publication of a new version of the French doctrine next year. This evolution also prompted questioning about the existence of such doctrines in other countries, especially in neighboring countries. It appeared also interesting to evaluate the agreement of these doctrines, including the French one, with international recommendations, especially the recently published general safety requirements (GSR), part 11, from IAEA. A benchmark study comparing the different post-accidental management doctrines available was then conducted and is presented here.
{"title":"Comparative study of nuclear post-accident management doctrines in Europe and North America","authors":"J. Bertho, F. Gabillaud-Poillion, C. Reuter, O. Riviere","doi":"10.1051/radiopro/2022002","DOIUrl":"https://doi.org/10.1051/radiopro/2022002","url":null,"abstract":"The French Nuclear Safety Authority (ASN) issued in 2012 a first version of a doctrine establishing the principles of management of a post-accidental situation following a major nuclear accident. Since this publication, the feedback of the Fukushima-Daiichi accident continued and numerous evolutions occurred, both in French and European regulations and in international recommendations from IAEA and ICRP. This had led to further developments in the French doctrine for management of a post-accidental situation. This will result in the publication of a new version of the French doctrine next year. This evolution also prompted questioning about the existence of such doctrines in other countries, especially in neighboring countries. It appeared also interesting to evaluate the agreement of these doctrines, including the French one, with international recommendations, especially the recently published general safety requirements (GSR), part 11, from IAEA. A benchmark study comparing the different post-accidental management doctrines available was then conducted and is presented here.","PeriodicalId":21009,"journal":{"name":"Radioprotection","volume":"36 3 1","pages":""},"PeriodicalIF":1.1,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"86434789","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 : 2022-01-01DOI: 10.1051/radiopro/2022026
D. Hadipour, A. Monfared, A. Ebrahiminia, K. Gorji, N. Ghaemian, F. Niksirat
This study was designed to investigate the effect of the different topograms (AP and dual AP/Lateral) on patient dose indices and image quality in thorax and abdomen-pelvis CT. Size-specific dose estimation (SSDE), volumetric CT dose index (CTDIvol), milliampere seconds (mAs), effective dose, as well as signal to noise ratio (SNR) and contrast to noise ratio (CNR) of 60 thorax and 60 abdomen-pelvis CT scans were analyzed. In thorax CT, SSDE, mAs, CTDIvol and effective dose were significantly reduced by using dual topograms (p < 0.05) but not significantly reduced in abdominal-pelvic scans (p > 0.05). There was no significant difference between CNR parameter in the two groups for thorax CT (p > 0.05) and SNR parameter in abdomen-pelvic CT (p < 0.05) and all images were diagnostically acceptable. The use of two topograms in thorax CT is an efficient approach to reduce dose indices without decreasing the image quality.
{"title":"The role of topogram views on dose indices and image quality in thorax and abdomen-pelvis CT scan","authors":"D. Hadipour, A. Monfared, A. Ebrahiminia, K. Gorji, N. Ghaemian, F. Niksirat","doi":"10.1051/radiopro/2022026","DOIUrl":"https://doi.org/10.1051/radiopro/2022026","url":null,"abstract":"This study was designed to investigate the effect of the different topograms (AP and dual AP/Lateral) on patient dose indices and image quality in thorax and abdomen-pelvis CT. Size-specific dose estimation (SSDE), volumetric CT dose index (CTDIvol), milliampere seconds (mAs), effective dose, as well as signal to noise ratio (SNR) and contrast to noise ratio (CNR) of 60 thorax and 60 abdomen-pelvis CT scans were analyzed. In thorax CT, SSDE, mAs, CTDIvol and effective dose were significantly reduced by using dual topograms (p < 0.05) but not significantly reduced in abdominal-pelvic scans (p > 0.05). There was no significant difference between CNR parameter in the two groups for thorax CT (p > 0.05) and SNR parameter in abdomen-pelvic CT (p < 0.05) and all images were diagnostically acceptable. The use of two topograms in thorax CT is an efficient approach to reduce dose indices without decreasing the image quality.","PeriodicalId":21009,"journal":{"name":"Radioprotection","volume":"10 1","pages":""},"PeriodicalIF":1.1,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"86875164","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 : 2022-01-01DOI: 10.1051/radiopro/2022006
T. Kanzaki, T. Higuchi, X. Zhang, Y. Takahashi, M. Sakai, Y. Tsushima
Radiological technologists in nuclear medicine departments (NMRTs) are exposed to higher radiation doses than other nuclear medicine staff. Consequently, the Australian Radiation Protection and Nuclear Safety Agency recommends using a 0.5-mm lead equivalence protective apron (PA) for staff with radiation exposure > 800 MBq of 99mTc. However, 0.5 mm PA is heavy and cumbersome to use. We evaluated the effectiveness of a 0.25 mm lead equivalence lightweight protective apron (L-PA) for NMRT radiation exposure during daily nuclear medicine procedures. The work was performed both with a phantom and in a real situation in our study. The phantom study was conducted with five radioisotopes (RI) placed 0.5 m from the human phantom with and without L-PA. In the clinical study, NMRT recorded the radiation dose for 20 days inside and outside the L-PA using clinical agents (140 examinations). In the phantom study, L-PA decreased the measured doses by 63% with 201Tl, 41% with 99mTc, 27% with 67Ga, 33% with 123I, and 10% with 131I. In the clinical study, L-PA reduced the average dose per day by 43%. Therefore, L-PA could have sufficient shielding ability for daily work, mainly using 99mTc, and could be recommended by considering PA weight.
核医学部门(NMRTs)的放射技术人员比其他核医学工作人员受到更高的辐射剂量。因此，澳大利亚辐射防护和核安全局建议对辐射暴露量大于800 MBq或99mTc的工作人员使用0.5 mm铅当量防护围裙(PA)。但是，0.5 mm PA使用起来很重，很麻烦。我们评估了0.25 mm铅当量轻质防护围裙(L-PA)在日常核医学操作中对NMRT辐射暴露的有效性。在我们的研究中，这项工作是在模拟和真实情况下进行的。研究人员将五种放射性同位素(RI)放置在距离人体幻肢0.5 m处，有或没有L-PA。在临床研究中，NMRT使用临床药物记录了L-PA内外20天的辐射剂量(140次检查)。在幻影研究中，L-PA使201Tl组的测量剂量减少63%，99mTc组减少41%，67Ga组减少27%，123I组减少33%，131I组减少10%。在临床研究中，L-PA使每天的平均剂量减少了43%。因此，L-PA对日常工作有足够的屏蔽能力，以99mTc为主，可考虑PA重量推荐使用。
{"title":"A lightweight 0.25 mm lead equivalence protective apron for shielding radiological technologists from radiation exposure during single-photon emission computed tomography in nuclear medicine","authors":"T. Kanzaki, T. Higuchi, X. Zhang, Y. Takahashi, M. Sakai, Y. Tsushima","doi":"10.1051/radiopro/2022006","DOIUrl":"https://doi.org/10.1051/radiopro/2022006","url":null,"abstract":"Radiological technologists in nuclear medicine departments (NMRTs) are exposed to higher radiation doses than other nuclear medicine staff. Consequently, the Australian Radiation Protection and Nuclear Safety Agency recommends using a 0.5-mm lead equivalence protective apron (PA) for staff with radiation exposure > 800 MBq of 99mTc. However, 0.5 mm PA is heavy and cumbersome to use. We evaluated the effectiveness of a 0.25 mm lead equivalence lightweight protective apron (L-PA) for NMRT radiation exposure during daily nuclear medicine procedures. The work was performed both with a phantom and in a real situation in our study. The phantom study was conducted with five radioisotopes (RI) placed 0.5 m from the human phantom with and without L-PA. In the clinical study, NMRT recorded the radiation dose for 20 days inside and outside the L-PA using clinical agents (140 examinations). In the phantom study, L-PA decreased the measured doses by 63% with 201Tl, 41% with 99mTc, 27% with 67Ga, 33% with 123I, and 10% with 131I. In the clinical study, L-PA reduced the average dose per day by 43%. Therefore, L-PA could have sufficient shielding ability for daily work, mainly using 99mTc, and could be recommended by considering PA weight.","PeriodicalId":21009,"journal":{"name":"Radioprotection","volume":"11 1","pages":""},"PeriodicalIF":1.1,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"78583897","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 : 2022-01-01DOI: 10.1051/radiopro/2021037
Ç. Özbay, T. Özbay, A. Güler Yiğitoğlu, M. Bayburt
The recent rapid development and increasing complexity of radiotherapy devices and applications has increased the importance of correct and safe treatment. Risk management is very important in radiotherapy (RT), because incorrect treatment can have serious consequences in terms of mortality or morbidity. However, there are currently few studies on risk analysis in RT. This quantitative and qualitative study of the radiotherapy system (all radiotherapy process) uses the fault tree method, one of the probabilistic risk assessment methods in radiotherapy applications, which is used to devise accident preventive actions. First of all, RT applications were divided into simulation, treatment planning and treatment delivery. For each, work flow charts were determined, and fault trees were created in SAPHIRE (Systems Analysis Programs for Hands-on Integrated Reliability Evaluations) software. Fault probabilities were determined using the expert judgment method. This analysis allowed the identification of the weak points of the system, both qualitatively and quantitatively. The analyzes also revealed that there was a 0.5% occurrence probability of a top event, determined as an incorrect dose or dose distribution in RT. It was determined that the greatest contribution to this probability value was matching error with image guidance, 7.88%. Fault tree analysis (FTA) was found to facilitate a detailed examination of the radiotherapy system. After the risk analysis, the appropriate quality control method for weak points should be determined and implemented for safety management in radiotherapy.
{"title":"Probabilistic risk assessment of radiotherapy application","authors":"Ç. Özbay, T. Özbay, A. Güler Yiğitoğlu, M. Bayburt","doi":"10.1051/radiopro/2021037","DOIUrl":"https://doi.org/10.1051/radiopro/2021037","url":null,"abstract":"The recent rapid development and increasing complexity of radiotherapy devices and applications has increased the importance of correct and safe treatment. Risk management is very important in radiotherapy (RT), because incorrect treatment can have serious consequences in terms of mortality or morbidity. However, there are currently few studies on risk analysis in RT. This quantitative and qualitative study of the radiotherapy system (all radiotherapy process) uses the fault tree method, one of the probabilistic risk assessment methods in radiotherapy applications, which is used to devise accident preventive actions. First of all, RT applications were divided into simulation, treatment planning and treatment delivery. For each, work flow charts were determined, and fault trees were created in SAPHIRE (Systems Analysis Programs for Hands-on Integrated Reliability Evaluations) software. Fault probabilities were determined using the expert judgment method. This analysis allowed the identification of the weak points of the system, both qualitatively and quantitatively. The analyzes also revealed that there was a 0.5% occurrence probability of a top event, determined as an incorrect dose or dose distribution in RT. It was determined that the greatest contribution to this probability value was matching error with image guidance, 7.88%. Fault tree analysis (FTA) was found to facilitate a detailed examination of the radiotherapy system. After the risk analysis, the appropriate quality control method for weak points should be determined and implemented for safety management in radiotherapy.","PeriodicalId":21009,"journal":{"name":"Radioprotection","volume":"32 1","pages":""},"PeriodicalIF":1.1,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"82146085","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 : 2022-01-01DOI: 10.1051/radiopro/2021033
M. Saeed, Abdullah Asiri, Q.S. Alhamami, K. Alshamrani
The purpose of this study was to determine local diagnostic reference levels (DRLs) for patients undergoing intraoral and panoramic dental examinations at the intraoral radiology units of the public hospitals in Najran, Saudi Arabia. DRLs were determined based on measurements of dose area product (DAP) at intraoral and dental panoramic radiology units. This study has covered over 47% of the public hospitals in Najran with the intention to establish the local DRLs for all the possible intraoral and panoramic X-ray examinations for children and adults. For intraoral, the values for the estimated DAP ranged from 6 to 70 mGy.cm2 (average: 27.6, 29.8, 39.9 and 39.6 mGy.cm2 for incisive, both premolar and canine, molar upper and lower jaw, respectively). For panoramic, the mean value of DAP is 61.5 and 89.8 mGy.cm2 for paediatric and adult patients, respectively. DRLs were established at the 3rd quartile for incisive, both premolar and canine, molar upper and lower jaw protocols are 29.2, 37.1, 50.2 and 50.1 mGy.cm2, respectively. Furthermore, DRLs for panoramic radiography for paediatric and adult patients are 72.7 and 92.3 mGy.cm2, respectively. The proposed DRLs were comparable to those previously reported in other countries, such as UK and India.
{"title":"Intraoral and dental panoramic imaging: A diagnostic reference level study comparing radiation dose using two dosimeters in Saudi Arabia","authors":"M. Saeed, Abdullah Asiri, Q.S. Alhamami, K. Alshamrani","doi":"10.1051/radiopro/2021033","DOIUrl":"https://doi.org/10.1051/radiopro/2021033","url":null,"abstract":"The purpose of this study was to determine local diagnostic reference levels (DRLs) for patients undergoing intraoral and panoramic dental examinations at the intraoral radiology units of the public hospitals in Najran, Saudi Arabia. DRLs were determined based on measurements of dose area product (DAP) at intraoral and dental panoramic radiology units. This study has covered over 47% of the public hospitals in Najran with the intention to establish the local DRLs for all the possible intraoral and panoramic X-ray examinations for children and adults. For intraoral, the values for the estimated DAP ranged from 6 to 70 mGy.cm2 (average: 27.6, 29.8, 39.9 and 39.6 mGy.cm2 for incisive, both premolar and canine, molar upper and lower jaw, respectively). For panoramic, the mean value of DAP is 61.5 and 89.8 mGy.cm2 for paediatric and adult patients, respectively. DRLs were established at the 3rd quartile for incisive, both premolar and canine, molar upper and lower jaw protocols are 29.2, 37.1, 50.2 and 50.1 mGy.cm2, respectively. Furthermore, DRLs for panoramic radiography for paediatric and adult patients are 72.7 and 92.3 mGy.cm2, respectively. The proposed DRLs were comparable to those previously reported in other countries, such as UK and India.","PeriodicalId":21009,"journal":{"name":"Radioprotection","volume":"40 1","pages":""},"PeriodicalIF":1.1,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"78899851","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 : 2022-01-01DOI: 10.1051/radiopro/2022022
H. M. Swartz, S. Swarts, E. Ainsbury, R. Wilkins, M. Port, F. Trompier, A. Flood, L. Roy
As COVID-19 emerged, there are parallels between the responses needed for managing SARS-CoV-2 infections and radiation injuries. While some SARS-CoV-2-infected individuals present as asymptomatic, others exhibit a range of symptoms including severe and rapid onset of high-risk indicators of mortality. Similarly, a variety of responses are also observed after a radiological exposure depending on radiation dose, dose heterogeneity, and biological variability. The impact of acute radiation syndrome (ARS) has guided the identification of many biomarkers of radiation exposure, the establishment of medical management strategies, and development of medical countermeasures in the event of a radiation public health emergency. Biodosimetry has a prominent role for identifying exposed persons during a large scale radiological emergency situation. Identifying exposed individuals is also critical in the case of pandemics such as COVID-19, with the additional goal of controlling the spread of disease. Conclusions and significance: IABERD has taken advantage of its competences in biodosimetry to draw lessons from current practices of managing the testing strategy for nuclear accidents to improve responses to SARS-CoV-2. Conversely, lessons learned from managing SARS-CoV-2 can be used to inform best practices in managing radiological situations. Finally, the potential need to deal with testing modalities simultaneously and effectively in both situations is considered.
{"title":"Complementary lessons learned from the testing strategies used for radiation emergencies and COVID-19: A white paper from The International Association of Biological and Electron Paramagnetic Resonance (EPR) Radiation Dosimetry (IABERD)","authors":"H. M. Swartz, S. Swarts, E. Ainsbury, R. Wilkins, M. Port, F. Trompier, A. Flood, L. Roy","doi":"10.1051/radiopro/2022022","DOIUrl":"https://doi.org/10.1051/radiopro/2022022","url":null,"abstract":"As COVID-19 emerged, there are parallels between the responses needed for managing SARS-CoV-2 infections and radiation injuries. While some SARS-CoV-2-infected individuals present as asymptomatic, others exhibit a range of symptoms including severe and rapid onset of high-risk indicators of mortality. Similarly, a variety of responses are also observed after a radiological exposure depending on radiation dose, dose heterogeneity, and biological variability. The impact of acute radiation syndrome (ARS) has guided the identification of many biomarkers of radiation exposure, the establishment of medical management strategies, and development of medical countermeasures in the event of a radiation public health emergency. Biodosimetry has a prominent role for identifying exposed persons during a large scale radiological emergency situation. Identifying exposed individuals is also critical in the case of pandemics such as COVID-19, with the additional goal of controlling the spread of disease. Conclusions and significance: IABERD has taken advantage of its competences in biodosimetry to draw lessons from current practices of managing the testing strategy for nuclear accidents to improve responses to SARS-CoV-2. Conversely, lessons learned from managing SARS-CoV-2 can be used to inform best practices in managing radiological situations. Finally, the potential need to deal with testing modalities simultaneously and effectively in both situations is considered.","PeriodicalId":21009,"journal":{"name":"Radioprotection","volume":"44 1","pages":""},"PeriodicalIF":1.1,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"90537642","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 : 2022-01-01DOI: 10.1051/radiopro/2022024
N. Alomairy
Occupational ionizing radiation doses for medical radiation workers (MRWs) from different medical departments in a major specialized hospital in Saudi Arabia were measured and analyzed to establish a baseline for the annual mean effective dose (AMED) for MRWs. A statistical analysis of dose records was conducted on effective doses for 355 MRWs in the following medical departments. The overall AMED for all MRWs reported in this study was 1.60 mSv. The AMEDs in each medical department were 1.17 mSv in diagnostic radiology, 1.61 mSv in interventional radiology, 2.72 mSv in nuclear medicine, 1.59 mSv in radiation therapy, 1.32 mSv in operation room, 1.06 mSv in dentistry, and 1.54 mSv in others. A one-way ANOVA test indicated statistically significant differences between the departments’ workers (P = 0.001). The study reveals that the workers in the nuclear medicine department received the highest AMED among the other workers. The results reveal that no single occupational dose has exceeded the annual dose limit of 20 mSv. However, to avoid unwanted radiation exposures, it is still required to control the workplace and manage MRWs, particularly for workers in NM, who were found to get more dose than MRWs in other medical departments.
{"title":"Occupational ionizing radiation exposure monitoring in several medical departments","authors":"N. Alomairy","doi":"10.1051/radiopro/2022024","DOIUrl":"https://doi.org/10.1051/radiopro/2022024","url":null,"abstract":"Occupational ionizing radiation doses for medical radiation workers (MRWs) from different medical departments in a major specialized hospital in Saudi Arabia were measured and analyzed to establish a baseline for the annual mean effective dose (AMED) for MRWs. A statistical analysis of dose records was conducted on effective doses for 355 MRWs in the following medical departments. The overall AMED for all MRWs reported in this study was 1.60 mSv. The AMEDs in each medical department were 1.17 mSv in diagnostic radiology, 1.61 mSv in interventional radiology, 2.72 mSv in nuclear medicine, 1.59 mSv in radiation therapy, 1.32 mSv in operation room, 1.06 mSv in dentistry, and 1.54 mSv in others. A one-way ANOVA test indicated statistically significant differences between the departments’ workers (P = 0.001). The study reveals that the workers in the nuclear medicine department received the highest AMED among the other workers. The results reveal that no single occupational dose has exceeded the annual dose limit of 20 mSv. However, to avoid unwanted radiation exposures, it is still required to control the workplace and manage MRWs, particularly for workers in NM, who were found to get more dose than MRWs in other medical departments.","PeriodicalId":21009,"journal":{"name":"Radioprotection","volume":"33 1","pages":""},"PeriodicalIF":1.1,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"75243817","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}
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