热释光剂量计测量125I粒子源植入中职业人员剂量方法研究

目的 研究用热释光剂量计(TLD)测量并计算¹²⁵I粒子源植入中职业人员器官和组织接受的吸收剂量及有效剂量方法。方法 用⁶⁰Co γ射线开展TLD稳定性等相关性能实验。用¹²⁵I粒子源照射一组TLD片,建立空气比释动能标准剂量曲线。将TLD片分别贴在粒子源植入过程中职业人员铅衣内外甲状腺等13个部位,测量平均吸收剂量,计算器官和组织的吸收剂量和有效剂量。结果 3例前列腺癌粒子源植入术中,职业人员铅衣外器官和组织吸收剂量0.02~3.80 μGy,有效剂量0.06~1.81 μSv;铅衣内最高吸收剂量2.35 μGy,有效剂量0.02 μSv,屏蔽65.9%以上γ射线。3例脑癌中,职业人员铅衣外器官和组织吸收剂量0.23~11.31 μGy,有效剂量0.88~4.07 μSv;铅衣内最高吸收剂量2.22 μGy,有效剂量0.09 μSv,屏蔽54.5%以上射线。3例肺癌中,职业人员铅衣外器官和组织吸收剂量0.03~14.78 μGy,有效剂量0.35~7.59 μSv;铅衣内最高吸收剂量4.09 μGy,有效剂量0.22 μSv,屏蔽58.4%以上射线。2例纵隔癌中,职业人员铅衣外器官和组织的吸收剂量为0.06~74.91 μGy,有效剂量0.83~17.96 μSv;铅衣内最高吸收剂量10.29 μGy,有效剂量0.50 μSv,屏蔽85%以上射线。1例卵巢癌中,职业人员铅衣外器官和组织吸收剂量0.09~14.29 μGy,有效剂量2.40~4.50 μSv;铅衣内最高吸收剂量7.77 μGy,有效剂量0.12 μSv,屏蔽33.4%以上射线。植入1例眼睛癌中,职业人员铅衣外器官和组织吸收剂量为2.20~39.84 μGy,有效剂量4.48~10.06 μSv;铅衣内最高吸收剂量5.19 μGy,有效剂量0.16 μSv,屏蔽54.6%以上射线。结论 用TLD监测粒子源植入中职业人员剂量的方法简单易行,是保护近距离植入粒子源治疗中医务人员健康的有效措施。     

Radiation dose rates from patients undergoing positron emission tomography: implications for technologists and waiting areas

Increasingly hospitals are showing an interest in developing their imaging services to include positron emission tomography (PET). There is therefore a need to be aware of the radiation doses to critical groups. To assess the effective whole-body dose received by technologists within our dedicated PET centre, each staff member was issued with a dose rate meter, and was instructed to record the time spent in contact with any radioactive source, the dose received per working day and the daily injected activity. On average each technologist administered 831 MBq per day. The mean whole-body dose per MBq injected was 0.02 μSv/MBq^–1. The average time of close contact (<2.0 m) with a radioactive source per day was 32 min. The average effective dose per minute close contact was 0.5 μSv/min^–1, which resulted in a mean daily effective dose of 14.4 μSv. No technologist received greater than 60 μSv (the current UK limit for non-classified workers) in any one day, and in general doses received were less than 24 μSv, the daily dose corresponding to the proposed new annual limit for non-classified workers of 6.0 mSv per annum. However, we recognise that the layout of nuclear medicine departments will not mirror our own. We therefore measured the instantaneous dose rates at 0.1, 0.5, 1.0 and 2.0 m from the mid-thorax on 115 patients immediately after injection, to provide estimates of the likely effective doses that might be received by technologists operating dual-headed coincidence detectionsystems, and others coming into contact in the waiting room with patients who have been injected with fluorine-18 fluorodeoxyglucose. The mean (95th percentile) dose rates measured at the four aforementioned distances were 391.7 (549.5), 127.0 (199.8), 45.3 (70.0) and 17.1 (30.0) μSv/h^–1, respectively. A number of situations have been modelled showing that, with correct planning, FDG studies should not significantly increase the effective doses to technologists. However, one possible area of concern is that, depending on the number of patients in a waiting area at any one time, accompanying persons may approach the limits set by the new UK IRR 1999 regulations for members of the public. Received 30 September and in revised form 27 December 1999     

3种常见介入诊疗中放射工作人员有效剂量的估算

目的 选取介入放射学中较常见的脑血管、心血管和肝脏介入诊疗,估算以上3种介入诊疗中放射工作人员的有效剂量.方法 通过仿真人体模型实验,了解脑血管、心血管、肝脏介入诊疗中仿真体模内组织、器官的吸收剂量,并根据ICRP 103号出版物中规定的组织权重因子估算3种介入诊疗中放射工作人员的有效剂量.结果 脑血管介入诊疗时,介入放射工作人员的有效剂量分别为高剂量组24.0μSv、中剂量组9.7μSv、低剂量组6.8 μSv;心血管介入诊疗时,放射工作人员的有效剂量分别为高剂量组36.3 μSv、中剂量组29.3 μSv、低剂量组17.8μSv;肝脏介入诊疗时,放射工作人员的有效剂量分别为高剂量组23.9 μSv、中剂量组11.3μSv、低剂量组5.5μSv.结论 心血管介入诊疗中放射工作人员高、中、低3个剂量组的有效剂量分别高于脑血管和肝脏介入诊疗时相应剂量组的有效剂量.

Abstract：

Objective To study and estimate the effective dose of interventional employees in the common cerebralvascular, cardiovascular and liver interventional diagnosis and treatment.Methods The absorbed doses of tissue or organ of anthropomorphic phantom in these three procedures were estimated by the anthropomorphic phantom experiment.The effective doses were calculated by the tissue weight factor which was given by International Commission on Radiological Protection publication 103.Results The effective doses to high, medium and low group were 24.0, 9.7,6.8 μSv for cerebralvascular interventional diagnosis and treatment, and 36.3, 29.3, 17.8 μSv for cardiovascular interventional diagnosis and treatment, and 23.9, 11.3, 5.5 μ Sv for liver interventional diagnosis and treatment, respectively.Conclusions The effective doses of high, medium and low group of interventional employees in cardiovascular interventional procedure are higher than those of cerebralvascular and liver interventional procedures.     

125Ⅰ粒子源近距离治疗前列腺癌模型的剂量学研究

目的 研究放射性125Ⅰ粒子源在治疗前列腺癌中的剂量分布,探寻治疗计划系统(TPS)优化效果的有效方法.方法 选定1个治疗计划系统,应用热释光剂量计,基于前列腺癌等效模体,模拟测量前列腺癌中的剂量分布.模拟植入共89颗125Ⅰ粒子,每个粒子的活度为1.37×107Bq(±5%).结果 各层的最大剂量为151～241 Gy,与处方剂量145 Gy的偏差在4.1%～66.0%.各层的最小剂量在101～128 Gy,与处方剂量的偏差在12%～30%.离模体边缘10 mm处正常组织的最大剂量为46～91 Gy,偏差为44%～63%.结论 该系统对实际的粒子植入治疗,评估TPS提供了实用的方法.

Abstract：

Objective To study the dose distribution of the radioactive 125Ⅰ seeds sources in the treatment of prostate cancer and also to explore the more effective method for improving treatment planning system (TPS).Methods Choose the designated TPS and use TLDs dosimeter based on a prostate cancer model.Finally stimulated measurement was focused on dose distribution in prostate cancer.The number of 125Ⅰ seed sources implanted was 89, each with 1.37 × 107 ( ± 5% ) Bq.Results Maximum dose of every layer ranged from 151 to 241 Gy, by 4.1% to 66.0% higher than the prescribed dose (145 Gy).The Minimum dose of every layer ranged from 101 to 128 Gy, by 12% to 30% higher than the prescribed dose.The maximum dose of normal tissue at 10 mm from the edge of model ranged from 46 to 91 Gy.The deviation was 44% -63% compared with the prescribed dose.Conclusions The designated TPS shows that it could be used as a practical guide for treatment of prostate cancer with the radioactive 125Ⅰ seed sources.The research methods offered by the study can provide evaluation of the TPS.     

Effective radiation dose from semicoronal CT of the sacroiliac joints in comparison with axial CT and conventional radiography

The aim of this study was to evaluate the radiation dose given by semicoronal CT of the sacroiliac joints (SIJs) in comparison with axial CT and conventional radiography. The total effective radiation doses given by serial contiguous semicoronal and axial CT, using 5-mm slices, 120 kV and 330 mAs, were determined by measurement of organ doses using an anthropomorphic Rando Alderson phantom paced with thermoluminescence dosimeters. The doses given by conventional antero-posterior (AP) and oblique projections of the SIJs were determined similarly. In a female the total effective dose by semicoronal CT was found to be more than six times lower than by axial CT and 2.5 times lower than the dose use to obtain a conventional AP radiograph, the values being 102, 678, and 255 μSv, respectively. The effective dose by semicoronal CT was only a little higher than the dose given to obtain two oblique radiographs. In a male with lead protection of the gonads the dose by semicoronal CT was four times lower than by axial CT, but higher than by conventional radiography. In conclusion, the effective dose by semicoronal CT of the SIJs is lower than by axial CT, and in females a semicoronal CT implies a lower effective radiation dose that used to obtain an AP radiograph. Electronic Publication     

中国人仿真胸部体模检测多层螺旋CT扫描组织器官剂量的研究

目的 利用中国人仿真胸部模型来测量不同噪声指数下胸部各组织器官的吸收剂量,计算有效剂量(ED)并对MSCT胸部扫描进行剂量评估.方法 对CDP-1C型中国人仿真胸部体模在CT体层解剖和X线衰减两方面进行等效性论证;通过在体模内布放热释光剂量计(TLD)来测量不同噪声水平下各组织器官的吸收剂量,并记录相应的剂量长度乘积(DLP);将两者分别换算为ED后选择单因素t检验方法进行对比研究,分析自动管电流调制(ATCM)技术时不同噪声指数胸部CT扫描的剂量水平.结果 中国人仿真胸部体模与成人CT胸部图像的结构相似.体模主要器官平均CT值为肺-788.04 HU、心脏45.64 HU、肝脏65.84 HU、脊柱254.32 HU,与成人偏差程度分别为肺0.10%、心脏3.04%、肝脏4.49%、脊柱4.36%.肝脏的平均CT值差异有统计学意义(t=-8.705,P＜0.05);肺、心脏和脊柱平均CT值与人体差异无统计学意义(t值分别为-0.752、-1.219、-1.138,P＞0.05).当噪声指数从8.5逐渐增至22.5时,DLP从393.57 mGy·cm递减至78.75 mGy·cm,各器官吸收剂量呈下降趋势(以肺为例,平均吸收剂量从22.38 mGy递减至3.66 mGy).应用DLP所计算的ED较器官吸收剂量计算的ED偏低(以噪声指数为8.5为例,两种方法的ED分别为6.69和8.77 mSv).结论 应用中国人仿真体模来进行CT剂量评估更为准确;基于ATCM技术的胸部CT扫描噪声指数设定至少应大于8.5.

Abstract：

Objective Using the Chinese anthropomorphic chest phantom to measure the absorbed dose of various tissues and organs under different noise index, and to assess the radiation dose of MSCT chest scanning with the effective dose(ED). Methods The equivalence of the Chinese anthropomorphic chest phantom(CDP-1C) and the adult chest on CT sectional anatomy and X-ray attenuation was demonstrated. The absorbed doses of various tissues and organs under different noise index were measured by laying thermoluminescent dosimeters(TLD) inside the phantom, and the corresponding dose-length products(DLP) were recorded. Both of them were later converted into ED and comparison was conducted to analyze the dose levels of chest CT scanning with automatic tube current modulation (ATCM) under different noise index. Student t-test was applied using SPSS 12.0 statistical software. Results The Phantom was similar to the human body on CT sectional anatomy. The average CT value of phantom are -788.04 HU in lung,45.64 HU in heart,65.84 HU in liver,254.32 HU in spine and the deviations are 0.10%,3.04%, 4.49% and 4.36% respectively compared to humans. The difference of average CT value of liver was statistically significant(t=-8.705,P＜0.05),while the differences of average CT values of lung, heart and spine were not significant(t value were -0.752,-1.219,-1.138,respectively and P＞0.05).As the noise index increased from 8.5 to 22.5, the DLP decreased from 393.57 mGy·cm to 78.75 mGy·cm and the organs dose declined. For example, the average absorbed dose decreased from 22.38 mGy to 3.66 mGy in lung. Compared to ED calculating by absorbed dose, the ED calculating by DLP was lower. The ED values of the two methods were 6.69 mSv and 8.77 mSv when the noise index was set at 8.5. Conclusions Application of the Chinese anthropomorphic chest phantom to carry out CT dose assessment is more accurate. The noise index should be set more than 8.5 during the chest CT scanning based on ATCM technique.     

平板DSA介入检查治疗患者的剂量调查

目的 调查平板数字减影血管造影(DSA)介入检查治疗患者的照射剂量,分析影响患者照射剂量的因素.方法 收集2009年3至6月来本院做DSA检查治疗的患者461例,手术种类包括全脑血管造影(CEA)、颅内动脉瘤弹簧圈栓塞(CAE)、肝脏动脉造影+超选化疗(SHAC)、冠状动脉造影(COA)、冠状动脉支架植入(PISI)、心脏射频消融(RFCA)、永久起搏器安装(PCPI).通过采集所有病例的剂量面积值(DAP)、累计皮肤表面人射剂量(CAK)、透视时间,采用转换因子计算有效剂量值.结果 CEA、CAE、SHAC、COA、PIST、RFCA、PCPI的有效剂量当量分别为(0.33±0.20)、(0.49±0.35)、(6.92±4.19)、(0.76±0.91)、(2.35±1.47)、(0.50±0.74)和(0.67±0.70)Sv;461例患者中超过1 Sv的达到120人次,占26%,超过10 Sv的达到10人次,均为SHAC患者.CAK分另为(0.55±0.43)、(1.34±1.11)、(0.95±0.57)、(0.32±0.31)、(0.91±0.33)、(0.16±0.22)和(0.15±0.14)Gy,CAK值超过1 Gy共为59例,占12.8%,超过2 Gy为11例,占2.4%,有2例超过3 Gy,为4.5和6.1 Gy,分别为CEA和CAE患者.结论 各项介入手术患者所受照射剂量个体差异较大.介入检查治疗患者接受的照射剂量较高,需要进行严格的监督以保证患者照射剂量得到最佳控制.

Abstract：

Objective To investigate the radiation doses for the patients undergoing interventional radiology and to analyze the dose - influencing factors.MethodsThe clinical data of 461 patients undergoing interventional radiology,including cerebral angiography ( CEA ),cerebral aneurysm embolism ( CAE ),superselective hepatic arterial chemoembolization ( SHAG ),coronary angiography ( COA ),percutaneous intracoronary stent implantation ( PIS1 ),cardiac radiofrequency catheter ablation ( RFCA ),and permanent cardiac pacemaker implantation(PCPI) were collected to observe the cumulative air kerma (CAK),dose area product (DAP),and fluoroscopy time,and effective dose was estimated using the conversion factors.Results The effective doses for CEA,CAE,SHAG,COA,PISI,RFCA,and PCPI were (0.33 ±0.20),(0.49 ±0.35),(6.92 ±4.19),(0.76 ±0.91),(2.35 ± 1.47),(0.50 ±0.74),and (0.67 ±0.70) Sv,respectively.In 126 of the 416 patients (26%),the effective doses were greater than 1 Sv,and the effective doses of 10 person-times were greater than 10 Sv,all of which were observed in the patients undergoing SHAG.The CAK values for CEA,CAE,SHAG,COA,PISI,RFCA,and PCPIwere (0.55 ±0.43),(1.34 ± 1.11),(0.95 ±0.57),(0.32 ±0.31),(0.91 ±0.33),(0.16 ±0.22),and (0.15 ±0.14) Gy,respectively.The CAK values were greater than 1 Gy in 59 of the 461 patients ( 12.8% ),greater than 2 Gy in 11 cases (2.4%) ,and greater than 3 Gy in 1 CEA cases and 1 CEA case,respectively.Conclusions There is a wide variation range in radiation dose for different procedures.As most interventional radiology procedure can result in clinically significant radiation dose to the patient,stricter dose control should be carried out.     

131I-美妥昔单抗联合动脉内化疗栓塞治疗原发性肝癌的内照射吸收剂量估算

Objective Metuximab is a specific monoclonal antibody F(ab')fragment targeted to the hepatocellular carcinoma(HCC)associated antigen of HAb18G/CD147.131I labeled metuximab has shown to be effective response on HCC in phase Ⅰ/Ⅱtrails.To evaluate the feasibility of 131I-metuximab combined with transarterial chemoembolization(TACE)is the treatment of HCC,the anthors estimated the radiation absorbed dose to organs.Methods 131I-metuximab(27.75 MBq/kg)and the mixture of anticancer drug and Lipiodol with interval 20 min later were administered to 21 patients with HCC via a transfemoral catheter.The pharmacokinetie and desimetric data were collected by means of venous blood samples.urine collections,and 4 or 5 γ-scintigraphies (SPECT) over7 d.The total amount of activity in percent of iniected activity (%ID)of main organ and the total body were calculated by regions of interest(ROI).The cumulated activities were determined from integration of the time-%ID curves using the SPSS 12.0 software.Absorbed doses to organ and red marrow were estimated according to the medical internal radiation dose (MIRD) formalism and blood-based marrow estimation with a red marrow-to-blood activity concentration ratio.The tumorto-no tumor ratio was calculated as well.Results A mean administered aetivity was 1.89 GBq per session (range 1.47-2.23 GBq).SPECT scans showed the significant accumulation of the radioconjugate in liver tumor and faint uptake in other organs until 14 d.Organ absorbed dose(n=12):the total absorbed dose to liver,spleen,thyroid,lungs,kidney and total-body was(3.19±1.01),(3.65±2.41),(3.61±2.40),(0.97±0.23),(0.96±0.35)and(0.57±1.55)Gy,with(0.55±0.09)Gy to the red marrow(n=7),respectively.From 2.88±1.11 to 1.64±0.39 were observed in tumor-to-liver ratio at 3 h to 168 h.Conclusion Internal absorbed dose estimation based on MIRD formalism is not only to establish reliable dose-response relationships for target tissue and dose-toxicity relationships for normal tissue but also to improve treatment planning in individual patient.     

Reduction of contamination risks during clinical studies with Technegas

During patient studies with the Technegas equipment in our department, we regularly detected small to considerable contaminations of the operator and in the area surrounding the apparatus. These contaminations were found to be of different origin: residual activity in the tubing from the apparatus to the patient which diffuses after deconnection, residual activity and small particles of the destroyed carbon crucible in the apparatus which are dispersed during opening of the door of the gas preparation chamber, leakage at the patient site during studies in uncooperative patients and a dysfunctioning valve inside the apparatus. To reduce the contamination risks, we made some adaptations to the apparatus. In the first place, the dysfunctioning valve was replaced. In addition, a powerful air exhaust pump with an efficient filter was installed. It was connected with (1) a newly installed transparent box in front of the door of the gas preparation chamber, (2) a dome on a flexible arm which can be positioned above the patient’s face during the examination and (3) a nipple on which the mouthpiece can be placed after the study. After these adaptations, a study showed the absence of measurable contamination on the clothing of the personnel handling the apparatus. Occasionally, considerable contamination was still measured on the gloves worn during filling of the carbon boat with generator eluate, but only small contaminations (up to 9.25 kBq) were measured on the mouthmask worn by the operator during administration of the Technegas. This results in a maximum effective dose equivalent fromactivity deposited in the lungs of 0.008 μSv per study. The total body dose of the operator from external radiation for one Technegas examination was determined to be 2 μSv. The highest dose rate was measured during filling of the crucible (0.2 mSv/h). Received 15 May and in revised form 3 June 1999     

Biokinetics and radiation doses for carbon-14 urea in adults and children undergoing the Helicobacter pylori breath test

The long-term biokinetics and dosimetry of carbon-14 were studied in nine adults and eight children undergoing carbon-14 urea breath test for Helicobacter pylori (HP) infection. The elimination of ¹⁴C via exhaled air and urine was measured with the liquid scintillation counting technique and with accelerator mass spectrometry. After the subjects had been given 110 kBq ¹⁴C-urea (children: 55 kBq) orally, samples of exhaled air were taken up to 180 days after administration and samples of urine were collected up to 40 days. Sixteen of the subjects were found to be HP-negative. In these subjects a total of 91.1%±3.9% (mean of adults and children ± standard error of the mean) of the administered ¹⁴C activity was recovered. The majority of the administered activity, 88.3%±6.2% in adults and 87.7%±5.0% in children, was excreted via the urine within 72 h after administration. A smaller fraction was exhaled. In adults 4.6%±0.6% of the activity was exhaled within 20 days and in children 2.6%±0.3%. Uncertainties in the biokinetic results are mainly due to assumptions concerning endogenous CO₂ production and urinary excretion rate and are estimated to be less than 30%. The absorbed dose to various organs and the effective dose were calculated using the ICRP model for urea and CO₂. The urinary bladder received the highest absorbed dose: in adults, 0.15±0.01 mGy/MBq and in children of various ages (7–14 years), 0.14–0.36 mGy/MBq. The findings indicate that an investigation with ¹⁴C-urea gives an effective dose to adults of 2.1±0.1 μSv (for 110 kBq) and to children of 0.9–2.5 μSv (for 55 kBq). From a radiation protection point of view, there is thus no reason for restrictions on even repeated screening investigations with ¹⁴C-urea in whole families, including children. Received 27 October 1998 and in revised form 13 January 1999     

3种介入术中工作人员的辐射剂量水平分析

目的 分析和评价临床实施较多的3种典型介入术中,工作人员的辐射剂量水平.方法 用仿真模体模拟实际诊疗情况,用热释光(TLD)元件作为测量工具,检测X射线机旁有/无防护组合时介人工作者眼晶状体、颈部及胸部的辐射剂量水平,估算其眼晶状体当量剂量和有效剂量.结果 X射线机旁有防护设施条件下,头部受照剂量减少85%～90%.脑血管介入术第一手术者眼晶状体当量剂量高于心血管和外周血管介入术,外周血管介入术第一手术者年有效剂量低于脑血管和心血管介入术.结论 介入工作者在本研究中使用的防护措施及适当的工作强度下,年有效剂量不会超过20 mSv的限值,但眼晶状体当量剂量可能会超过ICRP最新推荐的眼晶状体剂量限值(20 mSv),介入工作者应重视对眼晶状体的防护.

Abstract：

Objective To assess the level of radiation exposures of operators in three typical types of interventional fluoroscopic procedures.Methods Alderson Radiation Therapy (ART) phantom was used to stimulate the practices of diagnosis and therapy using TLDs for dose measurement.The radiation exposures of eye lens, neck, and breast were measured when the lead shielding of machine was on/off and the equivalent dose and effective dose to the eye lens were estimated.Results Radiation exposure of head was obviously reduced by 85% -90% when the lead shielding was on.The doses in different procedures were different.In cerebral angiography the dose equivalent of eye len was the highest in the three procedures.The annual effective dose for the operators was smaller in peripheral vascular interventions than that in cardiovascular interventional therapy and that in cerebral angiography.Conclusions The operators involved in intervention will receive an annual effective dose of less than 20 mSv as recommended by the ICRP under the protection conditions provided by the current study, except for eye lens.Attention should be paid to the protection of the eyes of operators.     

Preliminary safety evaluation of a cyclotron facility for positron emission tomography imaging

This work describes the design characteristics of a medical imaging centre which uses positron emission tomography, with a cyclotron for fluorine-18 and nitrogen-13 production, and which has provided experimental information on operational data recorded by area dosimetry since 1995. Doses to radiopharmacy and medical staff have been measured both in normal work and in some handling incidents. Data on radiation levels in the installation have also been obtained and related to design details and shielding. Area dosimetry was carried out using a five-stationary detector network, with a sampling rate of 2 min^–1, and by thermoluminescent dosimetry (TLD). Staff were also monitored by TLD, using extra chips for finger dosimetry and to duplicate individual whole-body dosimetry in order to measure doses in certain single operations. For normal work, average whole-body doses to radiopharmacy staff were between 0.03 and 0.28 mSv/month, wrist doses were between 0.42 and 2.67 mSv/month, and finger doses were between 1.4 and 7.7 mSv/day for the left hand and 0.8 and 2.4 mSv/day for the right hand; such variation reflects the differing expertise of staff and the role played by optimisation. Finger doses between 16 and 131 mSv were measured in handling incidents, and finger doses of 20.2 and 20.7 mSv for the left hand and 22.0 and 22.3 mSv for the right hand were measured during handling of a syringe without shielding, containing 3 GBq. For medical staff, contributions to the whole-body dose of 2.0 and 1.9 μSv/procedure were measured for injection and placing the patient on the examination couch, respectively. Dose measurement on the middle finger of the right hand gives an average of 70 μSv during the injection. The provisions regarding the shielding design have proved to be adequate and effective during a 3-year operational period. Operational doses to medical staff are comparatively low, while radiopharmacy staff are the most exposed. The finger doses in these professionals may exceed the annual limit, unless operational restrictions in daily practice are adopted. On-line area dosimetry records based on dose rate probes have proved to be effective both for monitoring radiation levels during the operation and for detecting changes in the behaviour of the facility in the irradiation process. Received 23 January and in revised form 12 April 1999     

不同剂量60Co γ 射线部分照射人离体血对染色体畸变形成的影响

目的 分析不同剂量60Co γ射线部分照射人离体血对淋巴细胞染色体畸变形成的影响.方法 用0～8 Gy(剂量率为0.35 Gy/min)60Coγ射线在37 ℃条件下照射3份离体健康人外周血标本,以0.5∶1的比例与同一供血者的未受照血混合,120 min后进行培养、制片,显微镜下分析染色体畸变(双着丝粒+着丝粒环)的变化,借此进行剂量估算.结果 各组的双着丝粒体+着丝粒环和总畸变,以及断片和单体断裂均随着剂量的增加而增加.用双着丝粒+着丝粒环进行的剂量估算,0.5～2 Gy组大于照射剂量的1/3,4～8 Gy组均接近照射剂量的1/3.结论 染色体畸变可以作为估算非均匀照射的生物学指标之一.

Abstract：

Objective To investigate the effects of 60Co γ-ray partial radiation on chromosome aberration in human peripheral blood in vitro.Methods The samples of heparinized peripheral whole blood from 3 healthy persons were exposed to 60Co γ-rays at the doses between 0 and 8 Gy with the dose rate of 0.35 Gy/min at the temperature of 37 ℃ ,and then mixed with the unirradiated blood samples of the Microscopy was used to observe the chromosome aberration double ( centromere + centromere) and the biological dose was estimated thereby.ResultsThe amounts of double centromere + centromere were increased along with the dose of irradiation in all groups.The estimated biological dose was higher than the 1/3 of the irradiation dose when the dose was between 0.5 to 2 Gy,and was close to the 1/3 of the irradiation dose when the dose was between 4 to 8 Gy.Conclusion Chromosome aberration can be used as a biomarker in estimation of uneven irradiation.     

青蒿琥酯对人宫颈癌HeLa细胞的放射增敏作用

Objective To investigate the radiosensitizing effects of artesunate on human HeLa cells of cervical cancer in vitro.Methods Hela cells were irradiated with 60Co γ-rays.The dose rate was 0.635 Gy/min and the radiation dose was 0,1,2,4,6 Gy,respectively.The anti-proliferation activities of artesunate on HeLa cells were evaluated with MTT assay,to determine the most appropriate drug concentration.The effect of radiosensitivity was observed by using clonogenic assay.The single-hit multitarget model was used to plot the HeLa cell's dose-survival curve,to calculate mean lethal dose,quasithreshold dose and sensitization enhancement rate,and to evaluate its radiosensitization effect.The apoptosis was analyzed with flow cytometry (FCM) to further test the radiation senseitization of artesunate on HeLa cells.Results The inhibition of artesunate on HeLa cells increased with concentration.In radiation group,the cell cloning efficiency were 91.67% ,82.02% ,58.60% ,25.01%,respectively,and in artesunate (2.0 μ mol/L) + radiation group,the cell cloning efficiency were 74.93% ,60.53% ,22.38% ,5.05%.In radiation group and artesunate (2.0 μmol/L) + radiation group,the mean lethal dose(D0) was 2.95 and 2.07 Gy,respectively,while the qusai-threshold dose (Dq) were 2.01 and 1.24 Gy,respectively,and SER was 1.43.Compared with 2 and 6 Gy radiation group,the apoptosis rate of drug + radiation group increased from 12.26% ,40.08% to 22.71% ,59.92%.Conclusions The inhibiting effect of artesunate on HeLa cells is concentration-dependent.Artesunate has radiosensitizing effect on HeLa cells in vitro.     

A possible method using baseline hormonal levels to prescribe the appropriate oral therapeutic radioiodine dosage for Graves' disease

Objective The purpose of this study was to retrospectively examine the correlations of hormonal ratios with radioiodine I-131 therapeutic parameters and the potentiality of prescribing the therapeutic I-131 target dosage for an individual patient with Graves' disease using baseline serum levels of thyroid hormones. Materials and methods Serum T3, T4, and FT4 levels 6 and 12 months after I-131 therapy/baseline levels (hormonal ratios) were calculated for a total of 68 therapeutic courses in 57 patients with Graves' disease. The therapeutic parameters were absorbed dose (Gy), dose concentration (μCi/g) and oral dose (mCi). Linear regression analysis was performed for correlating hormonal ratios (X) and therapeutic parameters (Y). Results Significant (P < 0.05) negative correlations of the hormonal ratios were observed with absorbed dose (R −0.50 for T3, −0.61 for T4, and −0.46 for FT4 at 6 months, and −0.29 for T3, −0.44 for T4 at 12 months) and dose concentration (R −0.57 for T3, −0.58 for T4, and −0.49 for FT4 at 6 months and −0.27 for T3, −0.27 for T4 at 12 months), but not with oral dose at 6 months and 12 months or the absorbed dose and dose concentration for FT4 at 12 months. The correlations were higher at 6 months than at 12 months and in serum T4 than in serum T3 and FT4. The formulae for serum T4 at 6 months were as follows: Y (Gy) = 109 − 53X and Y (μCi/g) = 109 − 52X. Conclusions These results suggest that the hormonal ratios are significantly correlated with the absorbed dose and dose concentration. The formulae for serum T4 at 6 months may serve to prescribe the individual oral dosage for Graves' disease, although the correlation coefficients are about −0.6.     

Are restrictions to behaviour of patients required following fluorine-18 fluorodeoxyglucose positron emission tomographic studies?

The clinical use of positron emission tomography (PET) is expanding rapidly in most European countries. It is likely therefore that patients receiving the tracer fluorine-18 fluorodeoxyglucose (¹⁸FDG) will be discharged to come into contact with family members, members of the public and ward staff. There are few direct measurements on which to base any recommendations with regard to radiation protection, and so we have measured the dose rates from patients undergoing clinical PET examinations in our centre. Seventy-five patients who underwent whole-body and brain ¹⁸FDG PET examinations were studied. Dose rates were measured at 0.1, 0.5, 1.0 and 2.0 m from the mid thorax on leaving the department. The median administered activity was 323 MBq with a 95th percentile value of 360 MBq. The median dose rates measured at the four distances were 90.0, 35.0, 14.0 and 5.0 μSv h^–1 (the median dose rates per unit administered activity at 2 h post injection were 0.31, 0.11, 0.04 and 0.02 μSv h^–1 MBq^–1). The corresponding 95th percentile values were 174.0, 69.0, 29.0 and 7.5 μSv h^–1 (0.43, 0.2, 0.08 and 0.03 μSv h^–1 MBq^–1). A number of social situations were modelled and an annual dose limit of 1 mSv was used to determine whether restrictive behavioural advice was required. In the case of nursing staff on wards a value of 6 mSv was regarded as the annual limit, which translates to a daily limit of approximately 24 μSv. There is no need for restrictive advice for patients travelling by public or private transport when they leave the department 2 h after the administration of ¹⁸FDG. Similarly, there is no need for restrictive advice with regard to their contact with partners, work colleagues or children of any age, although it should be stressed that children should not accompany the patient to the scanning department. The only possible area of concern is in an oncology ward, where patients may be regularly referred for PET investigations and other high activity radionuclide studies and are partially helpless. Even in this area, however, it is unlikely that a nurse would receive a daily dose of more than 24 μSv. We conclude that there is no need for restrictive advice for patients undergoing ¹⁸FDG PET studies given the current administered activities. Received 27 July and in revised form 25 September 1998     

Computed tomography dose optimisation in cystic fibrosis:A review

Cystic fibrosis(CF)is the most common autosomal recessive disease of the Caucasian population worldwide,with respiratory disease remaining the most relevant source of morbidity and mortality.Computed tomography(CT)is frequently used for monitoring disease complications and progression.Over the last fifteen years there has been a six-fold increase in the use of CT,which has lead to a growing concern in relation to cumulative radiation exposure.The challenge to the medical profession is to identify dose reduction strategies that meet acceptable image quality,but fulfil the requirements of a diagnostic quality CT.Dose-optimisation,particularly in CT,is essential as it reduces the chances of patients receiving cumulative radiation doses in excess of 100 m Sv,a dose deemed significant by the United Nations Scientific Committee on the Effects of Atomic Radiation.This review article explores the current trends in imaging in CF with particular emphasis on new developments in dose optimisation.     

10种介入诊疗程序中患者的辐射剂量调查

目的 调查研究介入诊疗程序中患者的受照剂量,评估其放射诊疗风险.方法 利用配置有符合IEC 60601-2标准的穿透型电离室的飞利浦Allura Xper FD20 DSA系统,收集记录10种介入诊疗程序共198例患者的剂量参数,估算出可供评估皮肤损伤的最高皮肤剂量及有效剂量.结果 累计透视时间范围为2.1～80.9 min,摄影帧数范围为15～678帧,剂量面积乘积范围为11～825 Gy·cm2,累计剂量范围为24～3374 mGy.有16例患者最高皮肤剂量超过1 Gy,79例患者有效剂量大于20 mSv.结论 有部分病例的最高皮肤剂量超过了皮肤损伤阈值,所以对患者的放射防护应给予足够的重枧.

Abstract：

Objective To investigate radiation dose to the patients undergoing interventional radiology and make radiation risk assessment.Methods Data was collected on 198 instances of 10 interventional radiology procedures by using Philips Allura Xper FD20 DSA, which was equipped with the transparent ionization chamber system in compliance with IEC 60601-2.Patient peak skin dose and effective dose were estimated.Results Cumulative fluoroscopy time was 2.1 - 80.9 min, and number of images monitored for PSD were above 1 Gy and 79 cases monitored for E were above 20 mSv.Conclusions Substantial number of cases exceeded the dose threshold for erythema.Due attention should be paid to radiation protection of patients.     

秦山核电站运行对上海环境放射性影响评价

Objective To study the effect on the environmental radioactivity level and the health of the residents in Shanghai when Qinshan Nuclear Power Station(QNPS) has been in normal operational condition for 17 years. Methods The field monitoring and the sampling analytical method were used for monitoring the radioactivity level in outdoor environment, drinking water, food and soil. Results The outdoor natural radiation level and the radioactivity level in the sample of the environmental media were on the normal background level. There was no distinct change in the environmental radiation level of Jinshan Area when QNPS was in normal operational condition. The radioactivity level in the environmental media was far lower than the limit values specified by the national standard GB. The effective dose of the outdoor natural external exposure for the residents is about 0.102 mSv/a and the effective dose of the internal exposure from the artificial radionuclides 90Sr and 137Cs in food for the residents is about 0.488 μSv/a. Conclusions There is no effect of the radioactive contamination on the environmental radioactivity level and the health of the residents in Shanghai when QNPS has been in normal operational condition for 17 years.