Objective: To provide reference for on-site medical emergency preparedness and response to nuclear facilities of our country. Methods: On the basis of laws, regulations and standards as well as our experience and research in this field. Results: To provide effective advice for on-site medical emergency preparedness and response. Conclusion:Introduce unclear accident influence, unclear accident emergency system and so on.

Objective: To design qualitative quality control testing device for portable medical endoscope optical performance. Methods:To install the mounting bracket, uniform light source and testing target, etc and integrate testing of the visual resolution, geometric distortion, color reproduction capability, the dynamic range and the brightness of the image plane on only one testing target. Results:This kind of device can observe the target by eye or monitor. Conclusion:It can realize the function of rapid, qualitative detection for clinical medical endoscope optical performance parameters.

Objective To study the relationship between occupational stress and metal health of radiation workers.Methods Totally 220 radiation workers were investigated by Chinese perceived stress scales questionnaire,Chinese health questionnaire-12,as well as questionnaire related to radiology.Results The stress score of radiation worker with senior title was 18.18 ± 6.12,which was the lowest of all 220 participants.There was positive relationship between stress score and health score (r =0.484).19.1％ of the workers sometimes felt stressed due to the danger of work.Conclusions There are some significantly correlation between occupational stress and metal disorder.More attention should be paid on the occupational stress.Positive measures such as decompression and psychological intervention will be helpful to protect physical and mental health of radiation workers.

Objective To measure the circuit time constants of 4 kinds of radiation survey meters (451P ionization chamber dosimeter,6150AD6 + 6150AD-b dose meter,FH40G + FHZ672E-10 dose meter and AT1123 dose meter) and,to discuss the formula of time response correction and its application.Methods In the condition of continuous exposure of X-ray machine,the ambient dose equivalent rates shown by survey meters were recorded.In order to get the circuits time constant,the least squares fittingmethod was used to fit the data using the time response formula of circuit having a capacitance C and a resistance R in series.Results The relative uncertainty of fitted circuit time constants was higher than 20％ except for 6150AD6 + 6150AD-b dose meter.The relative uncertainty of fitted r was 8％ for 6150AD6 + 6150AD-b dose meter.Conclusions The time required to stabilize the dosimeter readings was 8,5,3 and 2 s,respectively,for the 451P ionization chamber dosimeter,6150AD6 +6150AD-b dose meter,FH40G + FHZ672E-10 dose meter and AT1123 dose meter.The rising trend of their measured values was not fully accordance with the RC circuit time response correction formula.

Objective To use Monte Carlo method to build a shielding calculation model for the proton and heavy ion treatment room,and to provide a reliable calculation method for shielding design.Methods A Monte Carlo-based FLUKA code was adopted to build the shielding calculation model for the proton and heavy ion treatment room,and to simulate the radiation field distribution in the proton and heavy ion treatment room.The calculation model was verified through the radiation detection around the proton and heavy ions treatment room.Results The FLUKA code-based simulation results were consistent with the radiation detection.Conclusions The shielding calculation model based on FLUKA code can simulate the radiation field from proton and heavy ions.Among the secondary particles,secondary neutrons are the dominant component and the main concern of accelerator shielding design.In shielding calculation,the emphasis should be put on both beam intensity and energy.

Objective To investigate the current situation of radiation protection in nuclear medicine diagnosis workplace.Methods The study was performed in 3 hospitals in northeast,north and central of China from February to December in 2013.The γ dose rate instrument was used to detect the workplace ambient dose equivalent rate of medicine preparation,leaching,packing,injection and imaging.Individual effective dose and equivalent dose were evaluated by photoluminescent dosimeter.Results The ambient dose equivalent rate was up to 1.92 mSv/h at repacking place and 1.2 mSv/h at injection place.The ambient dose equivalent rate of patients after injection was 5.36-240 μ,Sv/h.The hand equivalent dose was 0.01-0.02 mGy.Moreover,there were problems of staff route intersection,as well as the patients after injection staying in the public area.Conclusions Radiation workers should pay more attention to individual protection,and improve the operation proficiency to shorten the operation time.Furthermore,in order to protect public from unnecessary irradiation,there should be some changes in staff route and patients administration.

Objective:To verify and discuss the consistency and applicability of the semi empirical formula and Monte Carlo simulation method in the radiation shielding calculation for high energy synchrotron radiation source.Methods:The semi empirical formula and Monte Carlo simulation were used to calculate the ambient dose equivalent outside of the shielding.Results:The ratio of Jenkins semi empirical formula result to Monte Carlo simulation result was 111%-153%. The ratio of Sakano semi empirical formula result to Monte Carlo simulation result was 201%.Conclusions:For a single shielding material, the semi empirical formula can be simple and conservative to complete the shielding calculation for high-energy electron accelerator. For a variety of shielding materials, Monte Carlo simulation method should be used.

Objective To investigate the attitude toward and perception of the risk of nuclear power plant among the public residing in vicinity of nuclear power plant,as well as the related factors.Methods A face-to-face interview on perceived radiation risks was conducted among 1408 individuals in Liangyungang City, Jiangsu Province.where the Tianwan nuclear power plant was under construction.The four groups was defined according to the distance between the residence of the subjects and the Tianwan nuclear power plant:<4 km,4- 8 km,8-30 km and 30-50 km.A was used to collect information on education,working history,religion, perception of major industries hazards especially nuclear power plant,and major factors may influence their perceptions.Ordinal logistic regression model was used to analyze the data.Results About 91.18% of the interviewee heard about the nuclear power plant,35.36% of them had knowledge about Chernobyl nuclear power plant accident,71.05% of them believed that the nuclear power plant had no negative effects on environments, 37.03% of them believed that the nuclear energy was safe.74.27% of them believed that it was necessary for China to develop nuclear energy.63.29% of them supported the construction of the nuclear power plant in local area.Ordinal logistic regression analysis revealed that the higher education,higher family annual income,male, economic benefits from the nuclear power plant construction,and trust in local government having competency to handling emergencies were positive factors;otherwise,impression on nuclear power plant of bad influences on environment and health were negative factors.An inverted U-shaped with a right tailing relationship between negative attitudes toward nuclear power plant and distance to the plant was found.Conclusions Education, gender,family annual income and expectation of economic benefit returns were the major factors influencing the perception of and attitudes toward nuclear power plant.More works needed to be done to mitigate the negative attitude of the residents in vicinity of nuclear power plant and enhance the public acceptability .

Objective To validate and discuss the time response correction formula for four types of dosimeters (6150AD6 + 6150AD-b,FH40G + FHZ672E-10,451P ionization chamber and AT1123).Methods The ambient dose equivalent rates shown by survey meters were recorded separately when X-ray emission time was 500,200,100 and 50 ms.The corrected values were obtained by the formula of circuit having a capacitance C and asistance R in series.Results Therewas no correlation between the value measured by AT1123 dosimeter and the time of irradiation.The values by other three kinds of dosimeters obviously varied with the time of irradiation.Conclusions It is not required to make the time response correction for the measured value of ATl123 dosemeter,whereas the values measured by the other three dosimeters could be corrected by the time response correction formula.

Objective To establish a simple and convenient method and study the feasibility of using gold nanoparticle composites (ssDNA-AuNPs) for colorimetric detection of gamma radiation.Methods The composites ssDNA-AuNPs were prepared by applying the ssDNA to the surface of AuNPs,and then were irradiated with gamma ray with absorbed doses of 0,5,10,20,and 30 Gy,respectively.Subsequently the color change in the solutions were observed simultaneously with absorption spectra being measured.The linear relationship between the ratio of A625/A521 in the absorption spectrum and the absorbed dose was established.Results With the increase of radiation dose,the color of the solutions changed from wine-red to blue-violet gradually,the ratio of A625/A521 in absorption spectra had excellent liner response for absorbed dose ranging from 0 to 30 Gy,and the linear equation was A625/A521 =0.020 6 + 0.303 6 E(R2 =0.991 5).Conclusions The ssDNA-AuNPs synthesized in this experiment can be successfully used for colorimetric detection of gamma absorbed dose,and a simple and convenient method for detection of gamma radiation has been newly established.