Uso de barreras primarias en función del ángulo del gantry en búnker de radioterapia / Uso de barreiras primárias em função do ângulo do gantry em bunkers de radioterapia / Use of primary barriers as a function of gantry angle in radiotherapy bunker

Introducción: el diseño de los búnkeres de radioterapia es de vital importancia no solo por la seguridad radiológica, sino también por el costo que implican. Los cálculos de blindaje de las paredes primarias de los búnkeres de los aceleradores lineales de radioterapia se determinan a partir del factor de uso de estas paredes. Los documentos internacionales como el NCRP 151 utilizan para el cálculo de estas barreras un factor de uso igual a 0.25. Objetivo: estudiar la distribución del uso de las barreras primarias en función de los tratamientos realizados buscando contrastar la homogeneidad en el uso de las barreras. Material y Métodos: con los datos de pacientes realizados durante un año (2021) en dos aceleradores lineales, uno dual y otro monoenergético, se generó una base de datos con la que se calculó la frecuencia de uso de las paredes primarias. En el presente trabajo se evalúa la diferencia entre el uso dado de las barreras y las estimaciones de uso internacional. Resultados: se encuentra que en el acelerador dual en la energía de 15X los campos más usados tienen ángulos de gantry 0º, 90º, 180º, 270º, teniendo un peso acumulado aproximado al 65% al igual que la carga de trabajo para esos ángulos, esto implica que los ángulos diferentes a estos tienen un uso muy inferior al previsto por el cálculo inicial. En el acelerador dual en la energía de 6X el campo más usado es a 0º teniendo un peso aproximado al 14%, pero la carga de trabajo a 0º no se diferencia apreciablemente del resto de los ángulos ya que la distribución no tiene direcciones preferenciales, ninguno de los valores llega a 10% que concuerda con el uso homogéneo de la barrera. En el acelerador monoenergético el peso relativo de los ángulos de 90º y 270º en el uso de las barreras es aproximadamente 34% para cada una, superior al 25% estimado inicialmente. Conclusiones: las barreras primarias de los búnkeres de radioterapia tienen espesores marcados por el cálculo de blindaje, los cuales se pueden hacer basados en documentos internacionales que son referencia del tema. Se considera en las referencias para la barrera primaria un factor de uso igual para las mismas, sin embargo en la práctica clínica se pueden tener un factor de uso no uniforme respondiendo a los tipos de tratamientos que se designen realizar en el equipo. Esta realidad abre la puerta para plantear blindajes optimizados que podrían generar búnkeres más económicos y mejor utilización del espacio de acuerdo a las condiciones dadas para cada caso en particular.

Introduction: The design of radiotherapy bunkers is of vital importance not only for radiation safety, but also for the cost involved. The shielding calculations of the primary walls of radiotherapy linear accelerator bunkers are determined from the use factor of these walls. International documents such as NCRP 151 use for the calculation of these barriers a usage factor equal to 0.25. Objective: to study the distribution of the use of primary barriers according to the treatments performed, seeking to contrast the homogeneity in the use of the barriers. Material and Methods: with the data of patients performed during one year (2021) in two linear accelerators, one dual and the other monoenergetic, a database was generated with which the frequency of use of the primary walls was calculated. The present work evaluates the difference between the given use of the barriers and the estimates of international use. Results: it is found that in the dual accelerator at 15X energy the most used fields have gantry angles 0º, 90º, 180º, 270º, having an accumulated weight of approximately 65% as well as the workload for those angles, this implies that the angles different from these have a use much lower than the one foreseen by the initial calculation. In the dual accelerator at 6X energy the most used field is at 0º having an approximate weight of 14%, but the workload at 0º is not appreciably different from the rest of the angles since the distribution does not have preferential directions, none of the values reaches 10% which is consistent with the homogeneous use of the barrier. In the monoenergetic accelerator, the relative weight of the 90º and 270º angles in the use of the barriers is approximately 34% for each one, higher than the 25% initially estimated. Conclusions: the primary barriers of radiotherapy bunkers have thicknesses marked by the shielding calculation, which can be made based on international documents that are a reference on the subject. It is considered in the references for the primary barrier an equal use factor for them, however in clinical practice they can have a non-uniform use factor responding to the types of treatments that are designed to be performed in the equipment. This reality opens the door to propose optimized shielding that could generate more economical bunkers and better use of space according to the conditions given for each particular case.

Introdução: O projeto de bunkers de radioterapia é de vital importância não apenas para a segurança da radiação, mas também para o custo envolvido. Os cálculos de blindagem para as paredes primárias dos bunkers de aceleradores lineares de radioterapia são determinados com base no fator de uso dessas paredes. Documentos internacionais, como o NCRP 151, usam um fator de uso igual a 0,25 para o cálculo dessas barreiras. Objetivo: estudar a distribuição do uso de barreiras primárias de acordo com os tratamentos realizados, buscando contrastar a homogeneidade no uso das barreiras. Material e métodos: com os dados de pacientes tratados durante um ano (2021) em dois aceleradores lineares, um dual e outro monoenergético, foi gerado um banco de dados com o qual foi calculada a frequência de uso das paredes primárias. Este artigo avalia a diferença entre o uso determinado de barreiras e as estimativas internacionais de uso. Resultados: verifica-se que no acelerador duplo com energia de 15X os campos mais utilizados são os ângulos de pórtico 0º, 90º, 180º, 270º, com um peso acumulado de aproximadamente 65%, assim como a carga de trabalho para esses ângulos, o que implica que os ângulos diferentes desses têm um uso muito menor do que o previsto pelo cálculo inicial. No acelerador duplo a 6X de energia, o campo mais utilizado é o de 0º com um peso aproximado de 14%, mas a carga de trabalho em 0º não é sensivelmente diferente do resto dos ângulos, já que a distribuição não tem direções preferenciais, nenhum dos valores chega a 10%, o que é consistente com o uso homogêneo da barreira. No acelerador de monoenergia, o peso relativo dos ângulos de 90º e 270º no uso das barreiras é de aproximadamente 34% para cada um, superior aos 25% estimados inicialmente. Conclusões: as barreiras primárias dos bunkers de radioterapia têm espessuras balizadas pelo cálculo de blindagem, que pode ser feito com base em documentos internacionais que são referência no assunto. As referências para a barreira primária consideram um fator de uso igual para elas, mas na prática clínica elas podem ter um fator de uso não uniforme, dependendo do tipo de tratamento que o equipamento foi projetado para realizar. Essa realidade abre as portas para uma blindagem otimizada que poderia gerar bunkers mais econômicos e melhor uso do espaço de acordo com as condições dadas para cada caso específico.

Survey on the awareness and application of radiation shielding specifications for γ-ray radiotherapy room / 中国职业医学

Objective: To investigate the implementation of GBZ/T 201.3-2014 Radiation Shielding Specification for Radiotherapy Room--Part 3: Radiotherapy Room of γ-ray Sources (hereinafter referred to GBZ/T 201.3-2014). Methods: A total of 129 personnels, who were involved in the approval and supervision of radiation diagnosis and treatment construction projects in 19 provincial administrative agencies, engaged in radiation protection testing and evaluation of γ-ray radiotherapy rooms in radiation health technology service institutions, and used GBZ/T 201.3-2014 in other institutions (environmental impact assessment, education and scientific research), were selected as the participants using a stratified random sampling method. A questionnaire survey was conducted to assess their awareness and application of the standard. Results: The participants' awareness of GBZ/T 201.3-2014 was ≥63.6%, but the training rate was only 9.1% to 50.0%. The familiarity with the various chapters of the standard was over 86.4%. And 42.6% of the participants reported using the standard at least once a year. Regarding the applicability of the standard, all of the participants believed that the standard meets the needs of approval, supervision, testing, or evaluation, and adapts to the updated development of radiotherapy equipment and technology. And 94.6% of the participants believed that the use of the standard could improve the level of protection design and management, and 92.2% believed that the standard was widely applied. Regarding the adequacy of the standard, 97.7% of the participants believed that the standard's reference for ambient dose equivalent rate was reasonable, while 34.1% believed that the standard needs revision. Conclusion: The participants are satisfied with the standard and believe its applicability. They have a good level of awareness of the standard, but there is a room for improvement in their familiarity with the shielding calculation related content of the standard. The promotion, training, and practicality of the standard need to be strengthened.

Analysis of induced radiation and shielding materials in proton therapy room / 中国辐射卫生

Objective To analyze the dose distribution of induced radiation in fixed proton beam therapy room and the influence of shielding materials, and to provide a basis for radiation protection and shielding material selection in proton therapy. Methods FLUKA was used to simulate the dose distribution of induced radiation in fixed proton beam therapy room, the dose over time, and the influence of different concrete materials. Results The dose of induced radiation was mainly concentrated around the target, and the dose rapidly decreased to 1/5-1/10 of the value at the time of stopping irradiation after cooling for 3-5 min. The induced radiation in concrete formed a slightly higher dose area at the end of the main beam near the inner side of the shield. The content of Fe, O, and H in concrete had significant effects on induced radiation (P < 0.01), and the dose was negatively correlated with the content of Fe. Conclusion The patients after proton therapy as well as the induced radiation in air and shielding materials are the main sources of external radiation dose for workers, and waiting for a period of time is the most effective way to protect the staff. Without considering the difficulty in construction and based on the analysis of shielding materials in protection against external irradiation and their influence on induced radiation, heavy concrete with a relatively high level of Fe is the best choice of the shielding material for proton therapy room.

Evaluation of the radiation shielding effect of the novel self-shielding radiotherapy system Zap-X / 中国辐射卫生

Objective Based on the measurement of the ambient dose equivalent rate of points around the novel self-shielding Zap-X radiotherapy system, its self-shielding effect was evaluated and analyzed, and suggestions were proposed for the revision and improvement of related standards in China. Methods The ambient dose equivalent rates were measured at 15 points around the Zap-X system under 6 system operating conditions. The radiation shielding effect of the Zap-X system was evaluated according to the domestic and international radiation protection standards of radiotherapy equipment. Results Measurement of ambient dose equivalent rate and dose evaluation showed that the shielding effect of the Zap-X system met the requirements of international standards, but the dose rates at some points failed to satisfy the reference control levels in the domestic standards. Conclusion Without the shielded treatment room, the self-shielding effect of the Zap-X radiotherapy system is insufficient to meet the requirements of domestic standards for radiation safety and protection. The system should be operated in the treatment room to meet domestic standards.

Assessment of Radiation Shielding Requirements in Room of Radiotherapy Installations—Part 1: General Principle (GBZ/T 201.1—2007): A survey of relevant personnel in technical service institutions / 中国辐射卫生

Objective　 @#To evaluate the implementation, application, and problems and suggestions of the Radiation Shield- ing Requirements in Room of Radiotherapy Installations—Part 1: General Principle (GBZ/T 201.1—2007) through a survey of relevant personnel in radiation health technical service institutions, and to provide a scientific basis for further revision and implementation of this standard.@*Methods@#A questionnaire survey was conducted among randomly selected per- sonnel in radiation health technical services across China, which mainly investigated the awareness, training, application, and revision suggestions related to the GBZ/T 201.1—2007. The results were aggregated and analyzed.@*Results@#A total of 184 evaluation questionnaires on the GBZ/T 201.1—2007 were collected from technical service staff in 25 provinces. Among the responders, 64.1% thought that the standard had been widely applied; 91.8% thought that the standard could meet work needs; only 54.3% ever received relevant training on the standard; 68.5% used the standard once or more per year; 33.7% thought that the standard needed to be revised.@*Conclusion@#The personnel in radiation health technical services have a high awareness rate of the GBZ/T 201.1—2007 and its contents, but their familiarity with and application of the standard need to be improved. Relevant departments should strengthen the training and promotion of the standard, and part of the standard should be revised.

Percepciones de personas económicamente activas obligadas a realizar trabajo remoto durante la pandemia de COVID-19 por tener una comorbilidad: estudio cualitativo / Perceptions of economically active people who had to do remote work during the COVID19 pandemic due to having a comorbidity: a qualitative study

Introducción: la probabilidad de presentar una forma grave de COVID-19 es mayor en personas con algunas condiciones preexistentes. En la Argentina, las personas con alguna de estas comorbilidades realizaron un trabajo remoto y diferenciado respecto de sus compañeros. Esta estrategia se denomina shielding y tiene resultados heterogéneos, ya que ­si bien evita las infecciones­ puede tener algún impacto en las vivencias y salud de las personas. Métodos: investigación exploratoria a través de un diseño cualitativo basado en entrevistas semiestructuradas. Resultados: se realizaron 21 entrevistas. Se organizaron los conceptos en ejes temáticos de análisis. Como principales hallazgos se identificó que la salud general de las personas empeoró durante la pandemia a pesar de realizar trabajo diferenciado, y que durante el período explorado surgieron múltiples emergentes que incluyeron hábitos no saludables y estrategias positivas de afrontamiento. Respecto de lo laboral predominaron los sentimientos negativos. Conclusión: la implementación de shielding resulta insuficiente como única medida para la preservación de la salud de las personas con mayor riesgo de desarrollar formas graves de COVID-19. (AU)

Introduction: people with some pre-existing conditions are more likely to have a severe form of COVID-19. In Argentina, people with any of these comorbidities performed remote and differentiated work compared to their peers. This strategy is known as shielding and has heterogeneous results, since although it prevents infections it can have some impact on people's experiences and health. Methods: exploratory research through a qualitative design based on semi-structured interviews. Results: 21 interviews were conducted. The concepts were organized in thematic axes of analysis. As the main findings, we identified that the general health of the people worsened during the pandemic despite performing differentiated work, and that during the period explored, emerged both unhealthy habits and positive coping strategies. Regarding work, negative feelings predominated over positives. Conclusion: the implementation of shielding is insufficient as the only measure for the preservation of the health of people at higher risk of developing severe forms of COVID-19. (AU)

Particular consideration on radiation shielding of a CyberKnife room / 中华放射医学与防护杂志

Objective:To verify radiation shielding effect of the maze of the CyberKnife room, so as to identify and correct the deficiencies in the shielding designs in certain circumstances.Methods:In line with the radiation protection shielding design scheme of the CyberKnife room provided by the producer, the consideradtions are focused on the useful beam that could mainly pass through the image center, but not the outer wall of the maze. However, during the inspection and acceptance of radiological protection in the built room, it was found that in a certain situations useful wire did not pass through the imaging center. Therefore, the additional shielding and protection facilities were built and verified.Results:After verification and acceptance on the scene, in the case where the useful beam was passing through the image center, the highest ambient dose equivalent rate at the concerned points 30 cm away from the outer wall of the maze was 0.31 μSv/h, less than the control level 10 μSv/h. In the opposite case, the highest ambient dose equivalent rate at the same points as above was 301.67 μSv/h, ablut 30 times as much as the control level. After the thickness in maze outer wall was enhanced, the highest ambient dose equivalent rate at the same as above was 2.14 μSv/h. This testing result met the concerned national standard.Conclusions:It is desirable that in designing the outer wall shielding in the maze in a CyberKnife room, attention should be paid to whether or not the useful beam could pass through the image center, or otherwise directly irradiate on the maze on the basis of the movement range of the accelerator. Shielding wall thickness should be calculated on the basis of the irradiation ragne and the distance between source location and the concerned points to ensure being in compliance with the requirements of the concerned national standard. Meanwhile, it should protect the workers occupying at the concerned locations from receiving higher radiation doses.

Radiation shielding for the intraoperative radiotherapy using low energy X-rays / 中华放射医学与防护杂志

Objective:To assess the shielding requirements of low energy X-ray intraoperative radiotherapy room under the domestic and foreign standards and guidelines, to measure the sured transmission factors for a range of shielding materials, the ambient dose equivalent rate around concerned positions and the shielding effect of protective devices, so as to provide references for shielding design of such radiotherapy units and applications of radiological protection devices.Methods:The required shielding thicknesses for a treatment room with INTRABEAM intraoperative radiotherapy system were calculated under the Chinese national standard GBZ 121, IPEM report No. 75 and NCRP report No. 151, respectively. The transmission factors for a range of shielding materials including solid water slab, shielding sheet and shielding apron were measured. Moreover, the ambient dose equivalent rates were measured under the simulated working conditions and the shielding effectiveness of a lead screen was evaluated.Results:The required lead thicknesses calculated under different standards and guidelines were less than 0.6 mm for all the concerned points, with the differences at sub-millimeter level. The low energy X-rays generated by this equipment attenuated rapidly in the shielding materials. The measured transmission factors of 0.05 mm lead equivalent shielding sheet and 0.25 mm lead equivalent shielding apron were 0.068 and 0.003 8, respectively. When the radiation was delivered using spherical applicator without any attenuation, the ambient dose equivalent rates at 1 m and 2 m from the X-ray source were 10.7 and 2.6 mSv/h, respectively. The corresponding measurement values decreased to 3.8 and 0.9 μSv/h, respectively, when the spherical applicator was inserted into a small water tank. Meanwhile, the ambient dose equivalent rate at 2 m was reduced to the background level when using protective screen.Conclusions:The shielding requirements for a low energy X-ray intraoperative radiotherapy facility are minimal, with low effective energy of X-rays generated by this equipment, but the dose rate close to the unshielded radiation source is high. The shielding scheme of treatment room should be optimized in design and the protective device should be used in a reasonable way.

Discussion of radiation shielding optimization for proton cyclotron therapy system plants / 中国辐射卫生

Objective To explore the radiation shielding optimization plan for a medical proton cyclotron developing and commissioning building at various commissioning stages. Methods According to the maximum source termsat different commissioning stages, we used the empirical formula to estimate the instantaneous dose rate at the point of interest outside the shield of the building, and optimized the building’s shielding ateach commissioning stage. Results When adding 1.0 m mobile concrete shielding blocks (“blocks” below) each to wall 3 and wall 4 at the cyclotron commissioning stage, 1.0 m blocks to wall 4 and 1.25 m blocks to wall 5 at the beam transport line commissioning stage, and 1.0 m blocks to wall 9 and 0.4 m blocks to the ceiling at the simulated treatment room commissioning stage, the dose rates at the points of interest outside the shield could meet the dose rate limit requirements. Conclusion The application of mobile concrete shielding blocks not only meets the shielding requirements, but also has economical and space-saving advantages, conforming to the principle of shielding optimization. This can be an approach to the optimization of radiation shielding for high-energy particle accelerators or similar scientific projects.

An exploration of shielding optimization for self-shielded accelerators / 中国辐射卫生

Objective To analyze the room layout and shielding of three types of self-shielded accelerators, and to provide a basis for optimizing the shielding design of rooms for self-shielded accelerators. Methods We compared the radiation shielding levels (transmitted radiation dose rate outside the primary barrier and scattered radiation dose rate outside the secondary barrier) of three self-shielded accelerator rooms by Monte Carlo simulation and empirical formula calculation. Results According to Monte Carlo simulation and empirical formula calculation, for the Unity MR Linac accelerator, the scatter radiation dose rate outside the secondary barrier was significantly higher (up to five times) than the transmitted primary radiation dose rate outside the primary barrier. The scatter radiation dose rate of the cross section was significantly higher than that of the sagittal section for both Unity MR Linac and TOMO accelerators. Conclusion The differences in the shape, material, and thickness of self-shielding structures complicate the shielding calculation and design for accelerator rooms. The shielding calculation method should be improved to optimize the radiation shielding of novel accelerator rooms.

Discussion on shielding calculation method for proton therapy room / 中国辐射卫生

@#<b>Objective</b> To discuss the shielding calculation method for proton therapy room, and to provide a scientific basis for shielding design of proton therapy room and improvement of existing national standards. <b>Methods</b> Using the calculation formula and key characteristic parameters from national standards and Chinese and foreign literature, combining with the FLUKA Monte Carlo method, empirical formula calculation and Monte Carlo simulation were conducted for the neutron ambient dose equivalent rates of the focuses outside the shielding of proton therapy room. The estimation results of the two methods were analyzed. <b>Results</b> Relative to the calculation results of the single exponential formula in the two directions of 0° and 50° in the beam loss point of divergence slit (0.13 and 12.4), the calculation results of the double exponential formula (0.40 and 17.9) were more consistent with the Monte Carlo simulation results (0.32 ± 0.19 and 18.2 ± 4.98). The Monte Carlo simulation results of copper target and nickel target were similar, suggesting that the key characteristic parameters of concrete shielding for copper target could be well applied to the calculation of nickel target, but the neutron ambient dose equivalent rates were underestimated when applied to tantalum target, with a difference of 5.7 times and 1.3 times in the two directions of 0° and 40°, respectively. <b>Conclusion</b> The dose rate estimates based on the calculation formula and key characteristic parameters from Chinese and foreign literature are consistent with FLUKA simulation results, and this method can be used in the shielding design of proton therapy room as a supplement and improvement to the existing national standards.

Shielding performance of six different types of concrete in proton therapy room / 中国辐射卫生

@#<b>Objective</b> To study the dose level of proton beams outside the main shield of the 230 MeV proton therapy room with six different types of concrete as the main wall, and to obtain the shielding performance of six different types of concrete. <b>Methods</b> The FLUKA program was used to build a calculation model, and different concrete compositions were introduced into the FLUKA program to simulate the change in ambient dose equivalent rate of the focus with concrete thickness under 230 MeV proton beam irradiation. The transmission curves of six different types of concrete were fitted to obtain shielding performance parameters. <b>Results</b> On the condition that the 230 MeV proton beam irradiated to the water target in 90° direction and the concrete thickness exceeded 40 cm, the proton beam was exponentially decayed for six different types of concrete, and the fitted decay curves had a <i>R</i>² of > 0.99. The linear attenuation coefficients for normal concrete, barite concrete, magnetite concrete, limonite concrete, phosphorite concrete, and ferrosilicate concrete were 0.0148 cm⁻¹, 0.0172 cm⁻¹, 0.0196 cm⁻¹, 0.0219 cm⁻¹, 0.0256 cm⁻¹, and 0.0290 cm⁻¹, respectively. <b>Conclusion</b> The composition and proportion of elements in concrete materials directly affect the shielding ability of concrete against proton beams to a large extent, and the shielding performance of six different types of concrete against proton beams varies greatly. Therefore, shielding materials for the proton therapy room should be selected by a comprehensive consideration of the material compositions and shielding performance of concrete, the difficulty of construction, and construction cost.

Effects of Total Hip Arthroplasty on Proximal Femoral Bone Remodeling / 医用生物力学

Objective To analyze the influence of total hip arthroplasty (THA) on the process of proximal femoral bone remodeling by using the Wolff bone remodeling theory. Methods According to control equation of bone remodeling, the program of bone remodeling was written in Python language. Preoperative femur model and postoperative femur and prosthesis finite element models were established respectively in ABAQUS software. The process of bone reconstruction before and after THA operation was compared to analyze the effect of prosthesis implantation on mechanical properties of the femur in the middle and long term after THA operation. Results The stress in proximal femur continued to decrease after prosthesis implantation, and the stress site was transferred from the femoral head to the prosthesis, resulting in an obvious stress shielding phenomenon. Bone loss in the stress shielding area was serious. The femoral shaft cortical bone became thinner and the stress shielding was relieved. The medial side at the bottom of the prosthesis was compressed, and the stress was significantly higher than that of the lateral side, where the bone was unevenly distributed. Conclusions After THA operation, obvious stress shielding occured at proximal medial side of the femur, leading to bone loss and prosthesis loosening. The difference in stress levels on both sides at the bottom of the prosthesis resulted in an uneven bone distribution, causing the discordance between the prosthesis and the femur, as well as postoperative pain in the middle part of the thigh.

Comparison of Chinese and international radiation shielding standards in application for after loading bunker shielding design / 中华放射医学与防护杂志

Objective:To compare the calculation result and analyzes the reasons for their differences so as to provide reference for the revision and improvement of the current national standards on radiation shielding design for the room of brachytherapy.Methods:For the initial activity 10 Ci (1 Ci=3.7×10 10 Bq) of radioactive sources, the shielding schemes of brachytherapy room were designed in accordance with UK Institnte of Physics and Engineering in Medicine(IPEM) Report 75, USA NCRP Report 151 and the national standard GBZ/T 201.3-2014, respectively. The differences in shielding limits, occupancy factors and other relevant factors are compared in detail. Results:The annual exposure time in a typical brachytherpy room was about 330 h. The point-specific concrete thickness were 70, 65, 61, 70, 50 cm as required by NCRP Report 151, 41, 43, 30, 40, 39 cm by IREM regulations and 84, 79, 46, 88, 39 cm by GBZ/T 201.3, respectively. The concerned concrete shielding thickness calculated under the GBZ/T 201.3-2014 was generally thicker, with lesser difference from NCRP Report 151 result, whereas that from the IPEM75 report was thinnest. The equivalent lead shielding thicknesses of the protective doors calculated using the three method are 1.170, 0.854 and 1.040 cm, respectively.Conclusions:The shielding thickness calculated using the calculation method and evaluation index recommended by the current Chinese shielding standards for brachytherapy bunker is similar to that reported in NCRP151, but is conservative. In particular, the evaluation index of instantaneous dose equivalent rate required by the current national standards and the relative conservative value of occupancy factor will significantly increase the shielding thickness required by the main shielding area.

The phantom study of bismuth shielding combined with organ tube current modulation in brain CT / 中华放射医学与防护杂志

Objective:To evaluate the application value of bismuth shielding combined with organ tube current modulation (X-care) in brain CT scanning by measuring the radiation dose of sensitive organs.Methods:The head and neck phantom was scanned with Siemens dual source CT at the same volume CT dose index (CTDI vol) by X-care, bismuth shielding and x-care combined with bismuth shielding, and by dual energy CT angiography (DE-CTA) with and without bismuth shielding. The CT values of cerebral vessels, adjacent brain tissues and cerebrospinal fluid and image noise were measured, and the contrast noise ratio of cerebral vessels and brain parenchyma was calculated. Organ dose equivalent ( HT) was calculated by placing thermoluminescent personal dosimeter (TLD), and CTDI vol and dose length product (DLP) were recorded after each scan. Results:Under the same CTDI vol, the mean values of HT, lens with X-care, Bi shielding and X-care combined with Bi shielding were(37.89 ± 2.00), (42.20 ± 2.96) and (28.21 ± 1.31) mSv, respectively, significantly lower than those of conventional sequence scanning( F=186.52, P<0.05). The values of HT, thyroid with Bi shielding and X-care combined with Bi shielding were (0.77 ± 0.07) and (0.89 ± 0.08) mSv, lower than those of routine brain scan and X-care( F=103.26, P<0.05). The values of HT, lens and HT, thyroidof DE-CTA with bismuth shielding were (11.56 ± 1.04) and (0.32 ± 0.03) mSv, respectively, significantly lower than those without bismuth shielding( t=5.07, P<0.05). There was no significant difference in noise and CNR in routine brain scan between with and without X-care, bismuth shielding and X-care combined with bismuth shielding. There was no significant difference in noise and CNR in dual energy CTA scanning between with and without Bi shielding. Conclusions:Using bismuth shielding and organ tube current modulation, we can significantly reduce organ dose of lens and thyroid during brain CT scanning without sacrificing the image quality.

Biomechanical Study on Personalized Titanium Alloy Short Femoral Prosthesis / 医用生物力学

Objective To evaluate biomechanical properties of the personalized titanium alloy short femoral prosthesis by finite element analysis. Methods Based on the validated femoral finite element model, the base of the femoral neck was simulated, and by inserting different short femoral prostheses, four total hip replacement (THR) models, namely, the SMF stem model (Model A), BE1 stem model (Model B), MINI stem model (Model C) and personalized stem model (Model D) were established, respectively. The same loads and constraints were applied to four groups of models, and the von Mises stress distribution and deformation were calculated and analyzed, so as to compare mechanical stability of each model. Results The deformation of all THR models was smaller than that of the femur model under physiological state. The deformation of Model B was close to that of Model C, and the deformation of Model A was close to that of Model D. The peak stress of Model C was higher than that of the other 3 models, reaching 9555 MPa. The overall stress trend was Model C > Model B > Model D> Model A > Model under physiological state. Conclusions The peak stress, stress distribution of personalized short femoral stem were similar to that of SMF stem, with reasonable stress distribution, small stress shielding of the proximal femur, minimum overall deformation and shear stress of the prosthesis, and its effectiveness and stability could meet the requirements of human biomechanics, which could provide references for joint surgeons and prosthesis researchers.

Evaluation on radiation shielding of the Halcyon linear accelerator room in a hospital / 中国职业医学

OBJECTIVE: To explore the radiation shielding problem of Halcyon linear accelerator room. METHODS: According to the dose estimation method recommended by GBZ/T 201.2—2011 Radiation Shielding Requirements for Radiotherapy room--Part 2: Radiotherapy Room of Electron Linear Accelerators(hereinafter referred to as GBZ/T 201.2—2011) and NCRP report No.151 Structural Shielding Design and Evaluation for Megavoltage X-and Gamma-Ray Radiotherapy Facilities the required shielding thickness of 6.0 MeV Halcyon linear machine room is evaluated and compared with the existing machine room. After the equipment was put into use, we measured and verified the dose equivalent rate around each point. RESULTS: ⅰ) The transmittance of the main beam passing through the self-shielding system was 0.06%. The theoretical shielding thickness of the main beam path sites A, C and L of the accelerator(two main shielding walls and room top sites respectively) was 136.00, 130.00 and 136.00 cm, which was lower than the required shielding thickness of the main shielding area specified in GBZ/T 201.2—2011 for 6.0 MeV accelerator. ⅱ) Compared with the existing equipment rooms in the hospital, except that the thickness of the top secondary shield(80.00 cm) and the thickness of the west section of the outer wall of the labyrinth(100.00 cm) are smaller, the rest meets the shielding requirements. ⅲ) After the transformation of the computer room and the installation of Halcyon linear accelerator, the surrounding dose equivalent rate was lower than the control level required by GBZ/T 201.2—2011. CONCLUSION: The self-shielding design of Halcyon linear accelerator can effectively protect 6.0 MeV rays used for treatment, reduce the shielding thickness required for the main shielding area, reduce the shielding construction cost of the equipment room and increase the usable area of the equipment room.

El fin de la protección gonadal en radiografía de pelvis: una revisión / The end of gonadal protection in pelvic radiography: a review

Resumen: La protección gonadal ha sido durante largo tiempo un importante factor para abordar el requisito "tan bajo como sea razonablemente posible" ALARA. El presente artículo realiza una revisión sistemática sobre la utilidad de la protección gonadal en la radiografía de pelvis en la cual se han destacado los factores que tienen que ver con su realización diaria, es decir, la dosis de radiación involucrada, la radiosensibilidad de las gónadas, la posición del protector gonadal y el factor psicológico de la población en relación con su uso. La incorporación de equipamientos modernos, con dosis y protocolo optimizados, transforma el beneficio de la protección en un tema al menos debatible. Mientras algunos siguen respaldando la medida, otros organismos y autores ya no la respaldan. Es necesario reconsiderar prácticas actuales fundadas en consensos científicos que pueden estar obsoletos y considerar el factor de cambio cultural basados en estos nuevos consensos para su implementación, sin generar mayor preocupación en la población.

Abstract: Gonadal protection has long been an important factor in addressing the ALARA "as low as reasonably possible" requirement. This article performs a systematic review on the usefulness of gonadal protection in pelvic radiography, in which the factors that have to do with its daily performance have been highlighted, that is, radiation dose involved, the radiosensitivity of the gonads, the position of the gonadal shielding and the psychological factor of the population in relation to its use. The incorporation of modern equipment, with optimized dose and protocols, transforms the benefit of gonad shielding into an issue that is at least debatable. While some continue to support the measure, other agencies and authors no longer support it. It is necessary to reconsider current practices based on scientific consensus that may be obsolete and consider the factor of cultural change based on these new consensus for its implementation, without generating major concern in the population.

Herramienta basada en código abierto para el cálculo de blindaje en las instalaciones de Medicina Nuclear / Open Source Based Tool for Shielding Calculation in Nuclear Medicine Installations

Uno de los requerimientos indispensables en el diseño de las instalaciones donde se trabaja con radiación ionizante es la determinación del espesor adecuado de las paredes, pisos, techo y puertas de los locales, que garanticen dosis por debajo de las restricciones establecidas por la autoridad regulatoria. El objetivo del presente trabajo es desarrollar una herramienta interactiva, libre y de código abierto para calcular los blindajes requeridos en una instalación de Medicina Nuclear. En el código, desarrollado en Phyton utilizando el entorno interactivo Jupiter Notebook, se incluyó el análisis tanto para Tomografía por Emisión de Fotón Único como para Tomografía por Emisión de Positrones. La herramienta fue implementada para el cálculo de los blindajes de un departamento de Medicina Nuclear del Centro Internacional de Restauración Neurológica (CIREN). Esta herramienta libre y de código abierto facilita los cálculos de blindaje aumentando la velocidad, lo que contribuye a lograr una optimización de la protección radiológica, pero también puede usarse como herramienta pedagógica(AU)

One of the indispensable requirements in the design of the facilities where ionizing radiation is used is the determination of the adequate thickness of the walls, floors, ceiling and doors of the premises, which guarantee doses below the restrictions established by the regulatory authority. The goal of this work is to develop an interactive, free and open source tool to calculate the shields required in a Nuclear Medicine installation. Analysis for both Single Photon Emission Tomography and Positron Emission Tomography was included in the code, developed in Phyton using the interactive Jupiter Notebook environment. The tool was implemented to calculate the shields of a Nuclear Medicine department of the International Center for Neurological Restoration (CIREN). This free and open source tool facilitates shielding calculations by increasing speed, which contributes to the optimization of radiation protection, but can also be used as a pedagogical tool(AU)

Designing method of magnetic resonance biplane self-shielding gradient coil based on gradient inductance constraint and graphic processing unit acceleration algorithm / 中国医学影像技术

Objective: To purpose an effective solution of reducing MRI time when rapid change and gradient switching rate of gradient magnetic field are restrained by eddy current caused by self induction and mutual inductance of gradient coil in MR system. Methods: With the constraints of gradient inductance minimization and gradient magnetic field self-shielding, a mathematical model was established by combining the target field point method to solve the winding distribution of the double-plane gradient coil, so as to reduce the magnetic field energy of the gradient coil and the eddy current on the performance of the gradient coil. At the same time, in order to shorten the operation time of solving the above complex mathematical model matrix by MATLAB software, graphic processing unit (GPU) acceleration algorithm was used to realize the calculation of gradient coil. Results: By minimizing gradient inductance, eddy current effect could be effectively reduced, the magnetic field self-shielding could be realized, the gradient switching rate was good, and the overall performance of the gradient coil could be improved. Conclusion: The new target field point method for biplane gradient coil is effective and feasible, which can realize minimization of gradient inductance and designing self-shielding gradient coil of gradient magnetic field.