2015年 · 第35卷第11期

Surgery is the main treatment for esophageal cancer^[1]However, up to 50% of patients have recurrence within 1 year after radical surgery^[2]and the 3-year overall survival rate generally does not exceed 10%^[3]。 Currently, there is increasing evidence that prophylactic radiotherapy or chemoradiotherapy in patients with positive lymph nodes after radical esophageal cancer surgery significantly reduces the recurrence rate and improves survival^[4,5,6,7]。 However, there is no consensus on the scope of prophylactic radiotherapy^[7,8,9,10]。 Previous studies in this group have preliminarily found that patients in the middle or upper segment do not have to irradiate the upper abdomen, and patients in the lower segment do not have to irradiate the supraclavicle^[11]However, it did not specify whether the middle or upper segment patients should be irradiated with the supraclavicle, and whether the lower segment patients should be irradiated with the upper abdomen. Therefore, the purpose of this study was to further determine the scope of prophylactic radiotherapy by comparing the distribution of the first recurrence of lymph nodes after radical resection alone in patients at different sites.

Stereotactic radiotherapy is a radical treatment for patients with early stage non-small cell lung cancer who cannot tolerate or refuse surgery^[1,2,3]。 Cyberknife-owned lung tracking system enables real-time breath tracking without implantation of gold labels for stereotactic radiotherapy of peripheral lung cancer^[4]。 The Machine Hop Count Optimization Parameter (OMU) in its planning system can minimize the total number of machine hops (MU) in the plan. Studies have shown that the volume of the low-dose area of the lungV₅Significant predictors of grade 2 or higher radiation pneumonia (RP) in patients treated with chest radiotherapy^[5]。 The purpose of this study was to investigate the effect of OMU optimization parameters on normal lung tissue volume in the design of a Cyberknife program for peripheral lung cancer.

In recent years, the utilization of nuclear energy and nuclear technology has developed steadily, and the level of safety management has been gradually improved. However, radiation accidents still occur from time to time, which have caused harm to radiological workers and public health^[1,2,3]。 In this study, 5 cases of two radiation accidents were investigated¹⁹²The Ir external irradiation personnel underwent dose estimation, clinical observation and examination, medical treatment, and follow-up six months and one year after exposure, which are reported as follows.

There are two oilfield logging companies in Henan Province, and the ionizing radiation exposed to radiation workers mainly comes from²⁴¹An Am-Be neutron source,¹³⁷Neutrons and gamma rays of Cs sealed sources, etc. The investigation and analysis of the exposure dose of such radiation workers can provide a dose basis for improving operating procedures, improving working conditions and optimizing radiation protection level. This study is based on GBZ 128-2002 Specification for Personal Monitoring of Occupational External Exposure^[1], neutron albedo with thermoluminescence (TLD) dosimeter^[2]and photon measurement methods, monitoring the individual dose of external irradiation of oilfield logging workers, investigating and dealing with suspicious results, counting the per capita annual effective dose, collective dose, monitoring rate, distribution of monitored people and collective dose distribution, analyzing the reasons why the annual effective dose of workers exceeds 5 mSv and the protection management situation, and putting forward protective measures to reduce the exposed dose.

With the rapid development of nuclear medicine, especially PET/CT and other technologies, while bringing better medical services to patients, a large amount of medical radioactive waste is inevitably generated in the process of diagnosis and treatment, and it is increasing year by year. In general, medical radioactive waste includes: radioactive materials that are no longer in use and therefore considered waste; Contaminated objects such as paper, plastic gloves and covers, counter tubes, glassware, and lotions; and the excreta of patients injected with radionuclides. In addition to such conventional wastes, wastes of variable composition may also be generated from events or accidents involving radioactive materials^[1]。 Medical radioactive waste belongs to special waste, which can not be disposed of at will even after specific activity reaches the standard of cleaning and uncontrolling^[2,3]。 The purpose of this study is to investigate several typical medical radioactive waste producing units, to understand the source and production quantity of medical radioactive waste, preparation and storage methods, and to discuss some problems in the management process.

In the process of nuclear energy development and utilization, nuclear radiation medical rescue has always attracted much attention. Establishing effective nuclear radiation medical rescue system is an important component of nuclear accident emergency rescue^[1]。 In the civil field, relevant institutions have carried out a lot of research on how to establish a nuclear radiation medical rescue system; Because that nuclear operations involved are mostly confidential, there are few reports^[2,3]And rarely seen in land nuclear armed forces. The Second Artillery Corps is an important armed force to carry out land nuclear counterattack, and the construction of nuclear radiation medical rescue system is one of the research topics that needs emphasis. Because of the particularity of the mission of the Second Artillery Corps, its nuclear radiation medical rescue system is a strong independent rescue force, which occupies an important position in the nuclear radiation rescue system of China. This paper briefly introduces the relevant experience and thinking of further strengthening the construction of nuclear radiation medical rescue system in the future.

The development of radiotherapy technology has brought about high precision, high dose, high efficacy and low injury, but at the same time there are possible human or systematic errors caused by danger^[1]。 Comprehensive dose validation is necessary to ensure the safe execution of clinical radiotherapy^[1,2]。 In vivo dosimetry (IVD) is one of the most direct and effective quality assurance methods at present^[1,3]。 The detectors used in IVD include thermoluminescence, diode, self-developing film and metal oxide semiconductor field effect transistor (MOSFET)^[4]Compared with other detectors, MOSFET is considered to be a better tool for radiotherapy IVD due to its small size, real-time reading, and simple operation^[5]。 The application of MOSFET detector in radiotherapy has been carried out abroad for many years^{[6,7,8,9,10,11,12,13,14,15,16,17,18]}At the same time, it has been commercialized, but there are few reports on the application of MOSFET detectors in radiotherapy in China. This article reviews the application of MOSFET in body dose monitoring of radiotherapy.