Effects of occupational radiation exposure on peripheral blood lymphocyte count and cell cycle in logging workers / 中国辐射卫生

Objective To investigate the effects of prolonged low-dose neutron-γ radiation on peripheral blood lymphocytes of logging workers. Methods The health information of workers in a logging company was collected by on-site blood sample collection and questionnaire survey. Individual doses of γ and neutron radiation were recorded using LiF elements and CR-39, respectively. Lymphocyte count in peripheral blood was measured by blood cytometer. Cell cycle and cyclins were detected by flow cytometry. Results The annual dose of some logging workers exceeded 5 mSv. Lymphocyte counts showed a difference of 15% between the group exposed to the lowest annual dose of 0–1 mSv (mean: 2.45 × 109/L) and the group exposed to the highest annual dose of 5–25 mSv (mean: 2.08 × 109/L). In comparison to pre-shift workers, logging workers exhibited a G1-phase arrest in the lymphocyte cycle, along with increased expression of cyclins p21 and CDK2. Conclusion Prolonged exposure to low-dose neutron-γ radiation leads to reduced lymphocyte counts as well as changes in lymphocyte cycle and cyclin expression.

Research progress in personal neutron dose monitoring / 中国辐射卫生

With the extensive use of neutron sources in industry, medicine, and scientific research, the number of people exposed to neutron has been increasing, which highlights the importance of personal neutron dose monitoring in the field of radiation protection. In the past decades, researchers have developed and improved a variety of techniques and methods for personal neutron dose monitoring. This paper focuses on the problems and research progress of track dosimeters (solid-state nuclear track dosimeters and fluorescent nuclear track dosimeters), luminescent dosimeters (thermoluminescent dosimeters and optically stimulated luminescent dosimeters), and bubble dosimeters in personal neutron dose monitoring.

Analysis of neutron beam quality control test items in boron neutron capture therapy (BNCT) equipment / 中华放射医学与防护杂志

Objective:To provide reference for establishing the testing method for quality control of neutron beam in boron neutron capture therapy (BNCT) equipment in China by testing the radiation characteristic parameters and dosimetry characteristic parameters of epithermal neutron beam in hospital neutron irradiator (IHNI).Methods:By comparing the uncertainties in the result of various test items with the deviation values recommended by the European Joint Research Center (EC-JRC), the feasibility of the relevant of testing method was analyzed and evaluated.Results:The uncertainty in epithermal neutron fluence rate was 2.7%. The uncertainty in ratio of thermal to epithermal neutron fluence rate was 3.1%. The uncertainty in ratio of fast neutron air kerma to epithermal neutron fluence rate was 9.3%. The uncertainty in ratio of gamma air kerma to epithermal neutron fluence rate was 8.7%. The uncertainty in spatial distribution of neutron fluence rate was 2.7%. The uncertainty in thermal neutron fluence rate in phantom was 1.8%. The uncertainty in neutron and gamma-ray dose rate in phantom was 17.1% and 4.0%, respectively.Conclusions:The uncertainty in neutron dose rate measurement result in phantom is higher, and further research is needed to improve the accuracy of the testing method. The uncertainty in the measurement result of other test items is lower, and the accuracy of the test result is expected to meet the allowable deviation value recommended by the European Joint Research Center, and the test method is feasible.

Development of dose verification methods for boron neutron capture therapy / 中华放射医学与防护杂志

To summarize the progress in BNCT dose verification method in the world and discusses their development prospects. Boron neutron capture therapy (BNCT) utilizes the specific capture reaction between the neutrons and boron drugs enriched in tumor cells to selectively kill tumor cells. In order to verify the accuracy of the radiotherapy plan and ensure the therapeutic effect on patients, it is necessary to measure the dose before treatment and compare the experimental radiation dose with the planned dose. The current BNCT dose measurement method mainly include point dose measurement method based on ionization chambers, thermoluminescence dosimeters and activation foils, two-dimensional dose measurement method based on films, and three-dimensional dose measurement method based on gel dosimeters.

A preliminary analysis of individual neutron dose monitoring with 6LiF-7LiF and CR39 / 中国辐射卫生

Objective To preliminarily compare 6LiF-7LiF and CR39 in individual neutron dose monitoring, and to provide a reference for improving individual neutron dose monitoring. Methods According to the GBZ 128-2019, 26 radiation workers from 7 institutions received individual neutron dose monitoring with 6LiF-7LiF and CR39 at the same time. The monitoring results were analyzed. Results For most of the workers, the personal neutron dose equivalent Hp(10) was less than the minimum detectable level. The results with the two monitoring methods differed in 6 of 26 workers. Conclusion Both 6LiF-7LiF and CR39 monitoring methods can be used for individual neutron dose monitoring for radiation workers, but the difference between 6LiF-7LiF and CR39 (in threshold energy, energy response, etc.) should be considered so that different types of radiation workers receive appropriate individual neutron dose monitoring.

Radiation dose estimation and protective measure discussion of 241Am-Be neutron source logging / 中国辐射卫生

Objective To investigate the radiation dose to operators in the process of 241Am-Be neutron source logging, and discuss neutron source management and protective measures for operators in well logging. Methods Through on-site observation and measurement of 241Am-Be neutron source logging in a company, we obtained the surface γ dose rate and neutron dose rate of the neutron source, as well as the operating time and distance of various processes including source taking, transfer, and loading, calculated the radiation dose to operators in various processes, and analyzed the source and proportion of the personal effective dose to operators. Results The effective doses of neutron irradiation and γ irradiation were 94.17 μSv and 2.72 μSv, respectively, for the combined processes of source tank inspection, transfer, and detection; 36.66 μSv and 24.08 μSv, respectively, for source loading and unloading; and 130.83 μSv and 26.80 μSv, respectively, for the whole neutron source logging process. The total annual effective dose of neutron source logging was 15.78 mSv, as estimated by logging 100 times per year. Conclusion In the process of 241Am-Be neutron source logging in the company, the effective dose to operators mainly arises from neutron irradiation. Therefore, it is necessary to strengthen neutron source management and take effective protective measures against neutron radiation.

Preliminary study on radiation safety management of Gas Dynamic Trap based D-T fusion volumetric neutron source / 中国辐射卫生

The fusion neutron source based on Gas Dynamic Trap (GDT) device has the advantages of high neutron flux, large testing space and low construction cost, so it is an ideal solution for high-flux fusion volumetric neutron source. As a new type of radioactive facility, how to carry out radiation safety management under the current nuclear safety regulatory laws and regulations in China is an important issue that must be addressed before the construction of this facility. In this paper, the radiation safety characteristics of GDT fusion neutron source was analyzed and the main radiation terms of GDT fusion neutron source were expounded. Combined with the existing nuclear safety regulatory laws and regulations in China, the key points of radiation protection and safety management in the process of construction and application of GDT fusion neutron source were put forward. It is recommended that the GDT neutron source should be managed as a class I radiological device. Prior to operation, radiation safety permit and nuclear material permit should be obtained, and special attention should be paid to the safety protection of radioactive tritium. This study will pay the way for the radiation safety management of the international high flux fusion neutron source ALIANCE project, and also provide the reference for the related nuclear and radiation safety management departments in China.

Measurement and analysis of induced radioactivity in medical electronic linear accelerator / 中国辐射卫生

Objective By measuring the induced radioactivity of the medical electron linear accelerator, and analyzing the measuring results and the measuring process, the cooling law of the induced radioactivity was studied, to provide basic data for evaluating additional doses to patients, medical staff and the public. Methods Five Medical Electron Linear accelerators were used to measure the induced radioactivity by using automes-6150AD6/H+6150AD-b/H x-γ radiation peripheral dose equivalent rate meter for environmental monitoring. Results The level of induced radioactivity of 5 medical electron linear accelerators is related to the factors such as measuring position and time: 10 second after the end of beam output, the maximum dose equivalent rate is 5.55 μSv/h around 5 cm on the surface of the head housing of the accelerator, and the maximum ambient dose equivalent rate at 1 m from the fixed point of the housing is 4.07 μSv/h, 5 minutes after the end of output, the maximum dose equivalent rate is 2.11 μSv/h around the 5 cm surface and 1.77 μSv/h around the 1 m fixed point. Conclusion The measured radioactivity induced by the medical electron linear accelerator gradually cools over time, the measurement valuesare maintained in a relatively fixed range, and the fluctuation range of the values is narrow.

Study on the radiation device of 241Am-Be neutron source and its dosimetric properties / 中国辐射卫生

Objective To design and build a set of experimental equipment for neutron radiation irradiation by using the 241Am-Be neutron source. Methods In the preliminary work, the spatial distribution data of the neutron energy spectrum and the gamma energy spectrum inside and outside the device were simulated by Monte Carlo method, and the changes of radiation fluence rate with spatial distribution was studied. The model of the 241Am-Be neutron device was established, and the neutron transport process in the irradiation field was studied using the method of shadow cone, inverse square law and other data analysis methods. Results Based on the simulation results, the normalized effective does of fast neutron fluence at the measurement point is about 72.9 pSv/n, and the one of photon fluence is about 3.04 pSv/γ. The ratio of effective dose of photon fluence to neuteon is about 4.17%. Conclusion Using Monte Carlo method, a standard model of 241Am-Be neutron source was constructed, the shadow cone design was optimized, and the feasibility of using the shadow cone conversion method to establish a standard neutron source radiation device was discussed.

Review on Pharmacoscintigraphy

Pharmacoscintigraphy is a non-invasive technique for determining the fate of drugs after administration into humans. Collecting valuable information through the pharmacoscintigraphyabout absorption and release mechanisms of drugs from formulations, and thus proving to be an invaluable tool in developing newer and more effective formulations. Such studies can be used to determine the behavior of drugs, formulation as well as diagnostic agents that are administered. In this technique, radiolabelled formulations are administered to patients by their intended route of administration. Their transit through the body is monitored using sophisticated imaging cameras. Since the amount of radiotracer that is used is very low, this is a safe, efficient, and accurate method for studying the behavior of drugs in the human body. Preclinical studies of newer drugs have successfully been carried out using the pharmacoscintigraphic technique

Estudios de contaminación ambiental en La Habana mediante técnicas nucleares y conexas / Assessment of environmental pollution in Havana city using nuclear and related techniques

RESUMEN Se resumen las diferentes experiencias en la aplicación de las técnicas nucleares y conexas en el estudio de diversos problemas ambientales de la Ciudad de La Habana. El análisis medioambiental mediante las técnicas de Análisis por Activación Neutrónica (AAN) y Gamma (AAG), Fluorescencia de Rayos X (FRX), Espectrometría por Absorción Atómica (EAA) y por Inducción de plasma acoplado (ICP), así como la Espectrometría Gamma de Bajo Fondo (EGBF), han permitido obtener información muy relevante sobre el comportamiento de los metales pesados, antibióticos y radionúclidos en los sedimentos marinos y fluviales, suelos urbanos y agrícolas, aguas, arenas de balnearios, polvos urbanos y productos de la agricultura urbana de la ciudad de La Habana.

ABSTRACT Various nuclear and related analytical techniques applied to study different environmental problems in Havana city are presented. The environmental analysis by means of Neutron and Gamma Activation analyses, X-ray Fluorescence Atomic Abortion and Induced Coupled Plasma spectroscopies and Low Background , Gamma Spectrometry, have allowed to obtain important information about the behavior of heavy metals, antibiotics and radionuclides in sediments, urban and agricultural soils, waters, beach sands, urban dusts and agricultural products farmed in the Havana city.

Measurement of the contralateral breast photon and neutron dose in breast cancer radiotherapy: A Monte Carlo study

Introduction: This study aimed to calculate the photon and neutron doses received to the contralateral breast (CB) during breast cancer radiotherapy for various field sizes in the presence of a physical wedge. Materials and Methods: Varian 2100 C/D linear accelerator was simulated using a MCNP4C Monte Carlo code. Then, a phantom of real female chest was simulated and the treatment planning was carried out on tumoral breast (left breast). Finally, the received photon and neutron doses to CB (right breast) were calculated in the presence of a physical wedge for 18 MV photon beam energy. These calculations were performed for different field sizes including 11 cm × 13 cm, 11 cm × 17 cm, and 11 cm × 21 cm. Results: The findings showed that the received doses (both of the photon and neutron) to CB in the presence of a physical wedge for 11 cm × 13 cm, 11 cm × 17 cm, and 11 cm × 21 cm field sizes were 9.87%, 12.91%, and 27.37% of the prescribed dose, respectively. In addition, the results showed that the received photon and neutron doses to CB increased with increment in the field size. Conclusion: From the results of this study, it is concluded that the received photon and neutron doses to CB in the presence of a physical wedge is relatively more, and therefore, they should be reduced to as low as possible. Therefore, using a dynamic wedge instead of a physical wedge or field-in-field technique is suggested

Sistema de adquisición de datos en tiempo real para un detector modular de neutrones en los experimentos con el RIBRAS / A real time pulse processing Data acquisition for neutron modular detector on RIBRAS experiments

Resumen Con la finalidad de maximizar las posibilidades experimentales en el estudio de los núcleos exóticos utilizando el haz del sistema "Radioactive Ion Beams in Brasil" (RIBRAS), fue desarrollado un sistema modular de detectores centelleantes orgánicos con buena eficiencia y amplio ángulo sólido, conocido como Pared de Neutrones. La detección de los neutrones emitidos en coincidencia con los fragmentos de reacción incrementa las posibilidades experimentales y constituye una de las técnicas más usadas en el campo de la Astrofísica Nuclear. El obsoleto sistema de adquisición de datos de la Pared de Neutrones debe ser remplazado por un sistema basado en módulos del patrón Versa Module Euro Card (VME). El nuevo esquema será definido para incluir el arreglo de detectores de bandas para partículas cargadas y la Pared de Neutrones con el máximo de eficiencia de adquisición, sin tiempo muerto, con selección de datos y sincronización de eventos. Los módulos digitalizadores garantizan tareas como la supresión de ceros y la saturación en la lectura de la señal. Adicionando tarjetas FPGA (field programmable gate array) a la adquisición de datos se garantiza el procesamiento pre y post-algorítmico de los datos.

Abstract In order to potentiate the experiments for studying the exotic nuclei with Brazil Radioactive Ion Beam (RIBRAS), a modular organic scintillation detector (Neutron Wall), with good efficiency and extended solid angle was developed. The detection of neutrons emitted in coincidence with the reaction fragments increases the experimental possibilities and represents one of the most popular techniques in the Nuclear Astrophysics field. The data acquisition system used for the Neutron Wall is obsolete and should be replaced by Versa Module Euro Card Data Acquisition modules. The new scheme will be designed to include the Strip Array and Neutron Wall detectors with maximum readout efficiency, no dead time, data selection and event synchronization. The digitizer modules provide features like zero suppressed readout and overflow suppression. Zero suppression, once enabled, prevents conversion of value, which is lower than user defined threshold. Adding FPGA (field programmable gate array) cards to data acquisition provides pre- and post-algorithmic processing on data.

Heavy-ion induced two-neutron transfer reactions and the role of pairing / Reacciones de transferencia de dos neutrones inducidas por iones pesados y el papel del apareamiento

Abstract Heavy-ion induced two-neutron transfer reactions (18O,16O) at 84 MeV were studied on several targets up to high excitation energy of the residual nucleus thanks to the use of the MAGNEX magnetic spectrometer to detect the ejectiles. The obtained results indicate of the important role played by the nuclear paring.

Resumen Se estudiaron reacciones de transferencia de dos neutrones inducidas por iones pesados (18O, 16O) a 84 MeV en varios blancos hasta una alta energía de excitación del núcleo residual gracias al uso del espectrómetro magnético MAGNEX para detectar los residuos eyectados. Los resultados obtenidos indican el importante papel desempeñado por el apareamiento nuclear.

β+ decay properties of A=100 isobars / Propiedades de la desintegración β+ de isóbaros con A = 100

Abstract The estimation of spectroscopic properties of neutron-deficient nuclei in the A=100 tin mass region is needed for the understanding of the rp-process path and the experimental exploration of the nuclear landscape. In order to evaluate some spectroscopic properties of the Gamow-Teller β +decay of neutron deficient isobars of A=100, we have performed shell model calculations by means of Oxbash nuclear structure code. The jj45pn valence space used consists of nine proton and neutron orbitals. The calculations included few valence hole-proton and particle-neutronin πg9/2 and vg7/2 orbitals respectively, in 100Sn doubly magic core. Effective interaction deduced from CD-Bonn one is introduced taking into account the nuclear monopole effect in this mass region. The results are then compared with the available experimental data.

Resumen La estimación de las propiedadesespectroscópicas de los núcleosdeficientes en neutrones en la región de masas de estaño A = 100 es necesaria para la comprensióndelcaminodelproceso rp y la exploraciónexperimental de laestructura interna de los núcleos. Con el fin de evaluar algunas propiedades espectroscópicas de la desintegración β+de Gamow-Teller en los isótopos de estañodeficientes en neutrones con A = 100, hemosrealizadocálculosdelmodelo de capas mediante el código de estructuranuclear de Oxbash. El espacio de valencia jj45pn utilizado consiste en nueve orbitales de protones y neutrones. Los cálculosincluyeronpocoshueco-protóny partícula-neutrón de valencia en orbitales πg9/2 y vg7/2respectivamente, en un núcleo100Sn doblementemágico. La interacciónefectivadeducida de CD-Bonn se introduceteniendo en cuenta el efectomonopolarnuclear en estaregión de masa. Los resultados se comparanluego con los datosexperimentales disponibles.

Nuclear physics and astronomical observations of compact objects / Física nuclear y observaciones astronómicas de objetos compactos

Abstract We discuss our predictions of two astrophysics observations: neutrino emission and element abundances. We studied the emission and possible detection of neutrinos from past black hole accretion disks. We find neutrinos are copiously emitted from these sites and encourage the development of large facilities for detection. We also studied changes in the synthesis of neutron-rich elements due to the suppression of key nuclear processes. We find important changes in the element abundances due to the, previously overlooked, alpha decay.

Resumen Discutimos nuestras predicciones de dos observaciones astrofísicas: la emisión de neutrinos y las abundancias de elementos. Hemos estudiado la emisión y posible detección de neutrinos emitidos por discos de acreción alrededor de agujeros negros en el pasado. Encontramos que los neutrinos son emitidos en abundancia por discos de acreción y sugerimos el desarrollo de detectores de gran escala para mejorar su detección. También hemos estudiado los cambios en la síntesis de elementos ricos en neutrones, debido a la supresión de procesos nucleares claves. Encontramos que hay cambios importantes en la abundancia de elementos debido al decaimiento alfa.

Measurement of the neutron dose equivalent rate from a dedicated intraoperative radiation therapy accelerator / 中华放射医学与防护杂志

Objective To measure and analyze the neutron dose equivalent rate produced by an IORT accelerator with 9 and 12 MeV electron energyies,and compare them with those from a Siemens Primus linear accelerator with the same electron energy,in order to provide data reference for the risk of secondary cancer induced by radiotherapy.Methods Using the neutron detector LB6411,the neutron dose equivalent rates produced by the IORT accelerator of 9 and 12 MeV were measured on some key locations,such as the head of the accelerator,cylinder bottom,patient plane with electron energies 9 and 12 MeV.The similar measurements were also performed on the same locations on a Siemens conventional accelerator.The data were collected and analyzed and the result wer compared between the two accelerators.Results Neutron dose equivalent rates from the IORT accelerator with 9 MeV energy were (51.8±3.1),(45.5 ±1.5),(70.5 ±4.9) and (68.2±3.3) μ Sv/h near the head of the accelerator,cylinder bottom,patient plane,with 5.9％,5.4％,17.8％ and 21.5％ lower than at 12 MeV,respectively.The dose equivalent rates at the similar locations from the Siemens Primus accelerator were (277.3 ±1.2),(285.1 ±1.6),(185.1 ±1.8) and (182.8 ±2.4) μSv/h at 9 MeV,with 48.8％,47.6％,48.7％,52.2％ lower than those at 12 MeV,respectively.At the energy of 12MeV,the neutron equivalent dose rate from the IORT was lower by a factor of about 10 than for Siemens Primus accelerator.Conclusions The neutron dose equivalent rates generaged by both the IORT and the Siemens Primus are higher at 12 MeV than at 9 MeV,which would lead to an increased risk of secondary cancer to patients.The traditional medical accelerator produces much higher neutron dose equivalent rates than the intraoperative electron accelerator,for which the appropriate shielding should be takn.

Estudo sobre os teores de Tório, Urânio e Potássio nas águas superficiais e sedimento marginal do Rio Piracicaba, Minas Gerais, Brasil / Study on the levels of Th, U and K in surface water and marginal sediment of Piracicaba River, Minas Gerais, Brazil

RESUMO: Nesse estudo, o principal objetivo foi mensurar a concentração de tório, urânio e potássio aplicando a técnica da análise por Ativação Neutrônica Instrumental em dois compartimentos ambientais, águas superficiais e sedimento marginal, do rio Piracicaba, em Minas Gerais. Esse rio possui área de drenagem que inclui as regiões do Quadrilátero Ferrífero da Região do Vale do Aço, sujeitando-se a intensa ação antropogênica. As amostragens ocorreram em quatro pontos de coleta, localizados nos municípios de Fonseca, Rio Piracicaba, Nova Era e Ipatinga, nas estações seca e chuvosa. As concentrações determinadas para aqueles elementos no sedimento se apresentaram elevadas em comparação com os valores usualmente observados para o perfil geológico na região de estudo, denotando relação com o modelo de exploração econômica, notadamente com a mineração e siderurgia. Evidencia, também, a relação com a degradação do feldspato potássico e do quartzo. Na água superficial, constatou-se o incremento da concentração do tório e potássio em comparação com os valores do Conselho Nacional do Meio Ambiente (CONAMA), nº. 357/2005. Os achados desse estudo explicitaram a necessidade da adoção de medidas mitigadoras, visando a contenção dos danos ambientais.

ABSTRACT: In this study, the main objective was to measure the concentration of thorium, uranium and potassium applying the Neutron Activation Instrumental Analysis technique in two environmental compartments - surface water and marginal sediment - in river Piracicaba, Minas Gerais, Brazil. This river has a drainage area which includes the regions of the Iron Quadrangle in the Steel Valley Region, subject to intense anthropogenic action. Four collection points were sampled, being located in Fonseca, Rio Piracicaba, New Age and Ipatinga municipalities, in both the dry and rainy seasons. The concentrations detected for those elements in the sediment were high values when compared to those usually detected for the geological profile in the study area, showing a relation to the model of economic exploitation, especially with the mining and steel industries. It also highlights the connection with the degradation of potassium feldspar and quartz. In shallow water, an increase of thorium and potassium concentrations was found in accordance with values foreseen by the National Environmental Council (CONAMA) No. 357/2005. The findings in this study showed the need for the adoption of mitigating measures, in order to contain environmental damages.

Study on step accuracy measurement and dose deviation of 252 Cf neutron afterloading radiotherapy machine / 中华放射医学与防护杂志

Objective To study the step aceuracy of 252Cf neutron afterloading radiotherapy machine and the dose deviation caused by step deviation.Methods EBT3 film was used to measure the steps of the 252Cf neutron source,and then the center of each 252Cf neutron source was identified by measuring the optical density value by using the ImageJ software.Double ion chambersmethod was used to measure the dose deviation dlue to the 252 Cf neutron source position shift.Results 252 Cf neutron source step accuracy may amount to 0.01 mm using EBT3 film measurement,when 252Cf neutron source position deviation is less than 3 mm,the dose deviation is less than 2.5％.Conclusions The study on the step accuracy and position deviation of the 252Cf neutron source can provide a reference for the quality control standard of the 252Cf neutron afterloading radiotherapy machine.

Paired observation of californium-252 neutron intraluminal brachytherapy combined with external-beam radiotherapy with and without lead shielding for cervical cancer / 中华放射肿瘤学杂志

Objective To compare the efficacy between californium?252 ( 252 Cf ) neutron intraluminal brachytherapy combined with external?beam radiotherapy with lead?shielding pelvic parallel opposing field technique and non?lead?shielding four?field box technique for cervical cancer. Methods A total of 52 patients with stage Ⅱa?Ⅲb cervical squamous cell carcinoma who were admitted to our hospital from 2004 to 2007 were enrolled as subjects and paired by clinical stage, age, tumor size, and degree of anemia. The 26 pairs of patients were divided into lead?shielding pelvic parallel opposing field group (lead?shielding group) and non?lead?shielding four?field box group (non?lead?shielding group). For all patients in both groups, 252 Cf neutron brachytherapy was added in external?beam radiotherapy. The local control (LC), overall survival (OS), and disease?free survival (DFS) rates were calculated using the Kaplan?Meier method and analyzed using the log?rank test. The difference in the incidence of late complications was analyzed using the McNemar method. Results There were significant differences in 5?year LC, OS, and DFS rates between the lead?shielding group and the non?lead?shielding group (85% vs. 81%, P= 0?? 014;89% vs. 73%, P=0?? 013; 89% vs. 73%, P= 0?? 013 ). There was also significant difference in the incidence of late complications between the lead?shielding group and the non?lead?shielding group ( 12% vs. 23%, P=0?? 008). Conclusions When intraluminal brachytherapy combined with external?beam radiotherapy is used to treat cervical cancer, the centers of the front and back fields should be shielded by lead, regardless of whether the parallel opposing field technique or the four?field box technique is used.