Pub Date : 2022-01-01DOI: 10.1051/radiopro/2022008
M. Talbi, Z. Tahiri, K. Eddaoui, M. El Mansouri, O. Nhila, M. Benmessaoud, I. Ait Ouaggou, E. Chakir, R. Sebihi, M. Khalis
In Morocco, the radiation protection of patients undergoing medical imaging examinations using ionizing radiation sources is now governed by specific provisions of Chapter VII of Law no142-12 (Loi no142-12 – AMSSNuR, 2015). The principle of justification of procedures and the principle of optimization of doses delivered constitute the basis of the legislation governing medical exposure. DRLs are considered as an important optimization tool encouraging healthcare professionals to optimize their practice and assure a better patient safety. In this survey, Local Diagnostic Reference Levels (LDRLs) were established for the eight most frequent examinations in Morocco. Data from 1747 patients were collected from seven regional hospitals. The proposed LDRLs were defined as the 75th percentile of the mean entrance surface dose distribution (ESD) in mGy using the indirect dosimetry method according to the IAEA Report Series No. 457. The LDRLs values reported in this study were for the eight examinations: skull (PA) 2.8 mGy, chest (PA) 0.51 mGy, abdomen (AP) 7.6 mGy, pelvis (AP) 6.45 mGy, lumbar (AP) 7.8 mGy, lumbar (Lat) 10.7 mGy, cervical (AP) 2.2 mGy, and cervical (Lat) 2.4 mGy. The DRLs reported in Morocco were compared with those of international authorities and other countries: IRSN (France), NRPB (UK), Japan, Sudan, and Iran. The present work assesses the local DRLs in Morocco and constitutes a starting point that will provide professionals with a tool to help them optimize the doses delivered to patients. Furthermore, the definition of national DRLs by radiography is an essential step in the process of optimizing medical exposures.
{"title":"Local Diagnostic Reference Levels (LDRLs) for routine X-ray examinations in Morocco","authors":"M. Talbi, Z. Tahiri, K. Eddaoui, M. El Mansouri, O. Nhila, M. Benmessaoud, I. Ait Ouaggou, E. Chakir, R. Sebihi, M. Khalis","doi":"10.1051/radiopro/2022008","DOIUrl":"https://doi.org/10.1051/radiopro/2022008","url":null,"abstract":"In Morocco, the radiation protection of patients undergoing medical imaging examinations using ionizing radiation sources is now governed by specific provisions of Chapter VII of Law no142-12 (Loi no142-12 – AMSSNuR, 2015). The principle of justification of procedures and the principle of optimization of doses delivered constitute the basis of the legislation governing medical exposure. DRLs are considered as an important optimization tool encouraging healthcare professionals to optimize their practice and assure a better patient safety. In this survey, Local Diagnostic Reference Levels (LDRLs) were established for the eight most frequent examinations in Morocco. Data from 1747 patients were collected from seven regional hospitals. The proposed LDRLs were defined as the 75th percentile of the mean entrance surface dose distribution (ESD) in mGy using the indirect dosimetry method according to the IAEA Report Series No. 457. The LDRLs values reported in this study were for the eight examinations: skull (PA) 2.8 mGy, chest (PA) 0.51 mGy, abdomen (AP) 7.6 mGy, pelvis (AP) 6.45 mGy, lumbar (AP) 7.8 mGy, lumbar (Lat) 10.7 mGy, cervical (AP) 2.2 mGy, and cervical (Lat) 2.4 mGy. The DRLs reported in Morocco were compared with those of international authorities and other countries: IRSN (France), NRPB (UK), Japan, Sudan, and Iran. The present work assesses the local DRLs in Morocco and constitutes a starting point that will provide professionals with a tool to help them optimize the doses delivered to patients. Furthermore, the definition of national DRLs by radiography is an essential step in the process of optimizing medical exposures.","PeriodicalId":21009,"journal":{"name":"Radioprotection","volume":"88 1","pages":""},"PeriodicalIF":1.1,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"88950041","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/2022029
M. Saeed, A. Sulieman, Y.M. Abdullah, M. Yousef, A. Ali, A. Alzoubi
Anthropomorphic phantoms, which can provide equivalent human tissue densities, are one of the best solutions for verifying the quality of radiotherapy treatment plans produced by treatment planning systems. The goal of this work was to develop and fabricate a breast phantom to estimate radiation doses to the breast, lung, and surface using radiochromic films (EBT3) for basically two techniques of three-dimensional conformal radiotherapy (3D-CRT) treatment planning. Thirty-two acrylic slices were used to construct the phantom. Cork and Teflon were used to mimic the lung and bone, respectively. Four slots were drilled for dosimetry purposes to allow access to the areas of ionization chamber installation. Both wedged and open of two tangential beams techniques were applied. With a mean deviation of 1.02 ± 1.1, the variation between estimated point doses and measurements using the three ionization chambers ranged from 2.9 to 1.4%. Using 0, 5 and 10 mm boluses, the mean percentage doses on the target surface were 54.7, 88.6 and 91.7% of the prescribed dose (PD), respectively. The homemade phantom was appropriate for conducting quality control (QC) tests for 3D-CRT planning techniques for breast radiotherapy.
{"title":"Three-dimensional conformal radiotherapy breast cancer planning: An evaluation study comparing two techniques using homemade phantom","authors":"M. Saeed, A. Sulieman, Y.M. Abdullah, M. Yousef, A. Ali, A. Alzoubi","doi":"10.1051/radiopro/2022029","DOIUrl":"https://doi.org/10.1051/radiopro/2022029","url":null,"abstract":"Anthropomorphic phantoms, which can provide equivalent human tissue densities, are one of the best solutions for verifying the quality of radiotherapy treatment plans produced by treatment planning systems. The goal of this work was to develop and fabricate a breast phantom to estimate radiation doses to the breast, lung, and surface using radiochromic films (EBT3) for basically two techniques of three-dimensional conformal radiotherapy (3D-CRT) treatment planning. Thirty-two acrylic slices were used to construct the phantom. Cork and Teflon were used to mimic the lung and bone, respectively. Four slots were drilled for dosimetry purposes to allow access to the areas of ionization chamber installation. Both wedged and open of two tangential beams techniques were applied. With a mean deviation of 1.02 ± 1.1, the variation between estimated point doses and measurements using the three ionization chambers ranged from 2.9 to 1.4%. Using 0, 5 and 10 mm boluses, the mean percentage doses on the target surface were 54.7, 88.6 and 91.7% of the prescribed dose (PD), respectively. The homemade phantom was appropriate for conducting quality control (QC) tests for 3D-CRT planning techniques for breast radiotherapy.","PeriodicalId":21009,"journal":{"name":"Radioprotection","volume":"43 1","pages":""},"PeriodicalIF":1.1,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"72852274","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/2021038
P. Ondo Meye, C. Chaley, S.Y. Loemba Mouandza, B.C. Mabika Ndjembidouma, G. Ben-Bolie
Exposure of people to external ionizing radiation is controlled by time, distance and shielding. In the latter case, the radiation dose is reduced if shielding attenuates the radiation. The present study was aimed at comparing gamma-ray shielding calculation methods, the well-known trial-and-error method and a direct calculation method that make use of build-up factor’s empirical fitting formulas. The latter method was then applied to a practical case in gamma industrial radiography. The results showed that both methods provide comparable results. For high energies and high-density materials, it has been observed that all the build-up factor forms studied provide similar values. Contrariwise, it has also been observed that the linear form of the build-up factor seemed to underestimate shielding thickness for low gamma energies (lower than ≈ 1 MeV). Furthermore, the application of the method using empirical build-up factor functions to a practical case in gamma industrial radiography showed that the calculations are in agreement with the measurements carried out on the field. This demonstrates that this method is efficient and can still be used even though more sophisticated and accurate methods are now available.
{"title":"Gamma-ray shielding calculations using empirical formulas for build-up factor: application to a practical case \u0000To Professor J.J. Fletcher","authors":"P. Ondo Meye, C. Chaley, S.Y. Loemba Mouandza, B.C. Mabika Ndjembidouma, G. Ben-Bolie","doi":"10.1051/radiopro/2021038","DOIUrl":"https://doi.org/10.1051/radiopro/2021038","url":null,"abstract":"Exposure of people to external ionizing radiation is controlled by time, distance and shielding. In the latter case, the radiation dose is reduced if shielding attenuates the radiation. The present study was aimed at comparing gamma-ray shielding calculation methods, the well-known trial-and-error method and a direct calculation method that make use of build-up factor’s empirical fitting formulas. The latter method was then applied to a practical case in gamma industrial radiography. The results showed that both methods provide comparable results. For high energies and high-density materials, it has been observed that all the build-up factor forms studied provide similar values. Contrariwise, it has also been observed that the linear form of the build-up factor seemed to underestimate shielding thickness for low gamma energies (lower than ≈ 1 MeV). Furthermore, the application of the method using empirical build-up factor functions to a practical case in gamma industrial radiography showed that the calculations are in agreement with the measurements carried out on the field. This demonstrates that this method is efficient and can still be used even though more sophisticated and accurate methods are now available.","PeriodicalId":21009,"journal":{"name":"Radioprotection","volume":"19 1","pages":""},"PeriodicalIF":1.1,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"81746478","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}