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目的 探讨90Y树脂微球治疗在临床应用中的放射防护措施。方法 模拟90Y树脂微球治疗手术流程,通过监测术前药物分装准备、药物转运、术中药物操作和输注、术后患者住院观察各个阶段周围剂量当量率水平,分析临床应用中所应采取的放射防护措施。结果 活性室周围剂量当量率水平为0.12~0.42 μSv/h,通风橱周围剂量当量率为1.04~3.32 μSv/h。数字减影血管造影(DSA)室在90Y+DSA扫描时最高为0.78 μSv/h,在99Tcm+DSA时最高为 0.36 μSv/h; 透视防护区在90Y药物时在第一术者位155 cm高度为13.19 μSv/h,而在90Y+DSA扫 描时最高为80 cm高度处315.01 μSv/h。第二术者位在90Y药物时最高为155 cm高度为6.28 μSv/h, 90Y+DSA 扫描时最高为155 cm高度处291.03 μSv/h。患者病房周围剂量当量率为0.11~0.58 μSv/h。 结论 核医学科及介入室等原有屏蔽措施能够满足90Y树脂微球治疗的放射防护要求,但仍需根据实际情况进行科学评估,同时应加强药物操作中的放射防护及表面污染处理措施。 相似文献
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目的 对我国核医学诊断工作场所辐射防护现状进行调查.方法 2013年2—12月期间,在东北、华中和华北地区分别选择1家三甲医院,用γ剂量率仪巡测核医学诊断制药、淋洗、分装、注射、扫描过程中工作场所周围剂量当量率,光致发光剂量计测量放射工作人员个人有效剂量和当量剂量.结果 在放射性药物分装、注射和受检者摆位等操作环节中周围剂量当量率较高, 分装时最高达1.92 mSv/h,注射时距针管5 cm处剂量率最高达1.2 mSv/h,受检者体表30 cm处剂量率范围为5.36~240 μSv/h,某医院护士手部当量剂量为0.01~0.02 mGy,部分工作场所存在人员路线交叉及注射后受检者停留在公众区域的现象.结论 核医学实践中放射工作人员应加强个人防护,提高操作熟练程度以缩短作业时间,应优化放射工作人员出入路线,加强注射后受检者的管理,以免公众人员受到不必要的照射. 相似文献
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18F-FDG PET显像中受检者周围人员的辐射剂量监测 总被引:7,自引:0,他引:7
目的 为1 8F 脱氧葡萄糖 (FDG)PET显像过程中工作和陪护人员的临床辐射防护提供参考数据。方法 用辐射剂量仪分别测量 30例工作人员在注射室、显像室的剂量当量率及受检者注射1 8F FDG后即刻、1和 2h距前胸 0 1、0 5、1 0、2 0m的剂量当量率 ,计算每例检查每一步操作的剂量当量和各工作场所工作人员的年剂量当量。结果 工作人员每例各步操作平均个人剂量当量为药品分装 :左手 (30 0± 8 0 ) μSv,右手 (6 0± 1 5 ) μSv ,全身 (0 5± 0 1) μSv;注射 :手部 (3 0 0± 0 75 )μSv,全身 (1 2 7± 0 2 0 ) μSv ;摆位和采集 ,结束采集共 (9 9± 1 4 ) μSv;密切接触的陪护人员为 (310±91) μSv。各工作场所工作人员的累计年剂量当量分别为 :药品分装及注射 :左手 (16 6 3± 4 4 1)mSv,右手 (6 4 5± 1 2 3)mSv ,全身 (1 18± 0 15 )mSv;显像采集 :全身 (4 99± 0 70 )mSv。结论 通过现有防护设施和方法 ,工作人员和陪护人员的受照剂量均未超过国家辐射安全标准 (GBSS)关于职业及公众个人年剂量限值。 相似文献
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RDS111型回旋加速器辐射剂量监测与防护 总被引:1,自引:0,他引:1
目的监测回旋加速器运行过程中产生的辐射水平及其与靶电流之间的关系,为相关人员的防护提供参考.方法用剂量仪分别测量美国CTI RDS111型回旋加速器在靶电流为40μA时生产11C、13N、15O、18F 4种核素在大厅内外的γ和中子剂量率及不同靶电流下的剂量当量率,并计算相关人员可能的年剂量当量.结果回旋加速器大厅内除1个点外,其余各处剂量当量率均小于15 μSv/h,大厅外周围环境则均小于0.5 μSv/h.相关人员可能的年剂量当量小于1.04mSv.线性拟合示,剂量当量率与束流强度呈正比.结论正常情况下,相关人员吸收剂量均未超过国家安全标准中关于职业人员(20 mSv)和公众个人(5 mSv)的年剂量当量限值. 相似文献
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目的探讨分化型甲状腺癌(DTC)清甲治疗后诊断性131I SPECT/CT全身显像中, 患者服131I后对周围的辐射剂量及其变化规律, 为辐射安全评价和职业防护研究提供依据。方法采用方便抽样方法, 回顾性分析2021年6至12月在联勤保障部队第九八〇医院行诊断性131I SPECT/CT全身显像的20例患者[男性5例、女性15例, 年龄(45.7±11.7)岁, 范围24.0~65.0岁]。采用X、γ剂量率仪分别测量患者服131I后胸前体表不同时间(2、24、48、72、96 h)、距离胸前体表不同距离(1.0、2.0、3.0 m)的辐射剂量率, 采用热释光探测器分别测量患者服131I后第1~4天的辐射当量剂量。结果患者服131I后2 h, 胸前体表的辐射剂量率最高[186.12(135.52~201.01)μSv/h], 且随着服131I后时间的延长和距胸前体表距离的增加, 辐射剂量率均明显下降;服131I后96 h以上胸前体表的辐射剂量率, 以及任何时间距离胸前体表3.0 m处的辐射剂量率均可达到本底辐射水平。患者服131I后, 第1天对周围的辐射当量剂量为(1.19± 0.28)... 相似文献
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目的研究患者接受90Y树脂微球选择性内放射治疗(SIRT)后48 h内所排泄尿液中90Y的放射性活度, 为术后患者排泄物的管理提供建议。方法收集3名患者在术后0~24 h和24~48 h两个时间段内排泄的尿液, 并对尿液中的90Y放射性活度进行检测和分析。结果 3名患者术后0~24 h和24~48 h尿液中的90Y放射性活度排泄量分别为(1 266±258)kBq/GBq和(140±106)kBq/GBq, 90Y放射性活度浓度分别为(640±113)kBq/L和(53±12)kBq/L。结论 90Y树脂微球治疗术后肝癌患者0~24 h排泄尿液中的90Y放射性活度比24~48 h高。术后患者可通过增加排泄尿量的方式来加速排出体内游离的90Y;患者住院期间的排泄物应按照HJ 1188-2020《核医学辐射防护与安全要求》的要求处理。 相似文献
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本文报道了广东阳江高本底地区6名、对照地区8名人尸体的骨226Ra、226Ra的浓度以及部分居民内脏器官中。210Po、210Pb的浓度。结果轰明阳江高本底地区和对照地区居民骨镭-226、镭-228的浓度分别为29.9pCi/kg, 26.9pCi/kgl 8.7pCi/kg, 8.2pCi/kg.由此估算出阳江高本底地区屠民骨中226Ra、228Ra的负薄璧及对骨衬、骨髓所产生的剂量当量分别为对照地区民民的3.4倍, 3.3倍。两地区居民内脏器官中210Po、210Pb的测定分析铡数较少但仍看出, 高本底地区均明显高于对照地区. 相似文献
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目的 为了解天然放射性核素226Ra、228Ra、210Pb与210Po在水生物及食物链中转移和蓄积情况。方法 定点采集养殖水产品及栖息环境中水与底质沉积物, 按不同的实验需要, 每个鲜样分别剥取肉, 骨(壳),鳞片和胃肠。烹饪样品, 洗净、称重、清炖, 熟后分离出骨(壳),余为食物。样品分别测定226Ra、228Ra、210Pb和210Po含量。数据按统计学要求处理, 配对数据, 作了配对显着性检验。结果 226Ra、228Ra和210Pb主要沉积于骨(壳)中, 浓集系数为102~103,肉中为100~102.210Po主要蓄积在水生物胃肠中, 浓集系数在102~104,鱼类胃肠与贝类肉中可达104.水产食品烹饪加工过程226Ra、228Ra和210Pb在食物链中转移不明显, 经配对显着性检验, 差异无显着性(P0.05);然而210Po在淡水鱼类和虾类中转移是明显的, 肉配对检验有非常显着性差别(P<0.01).结论水生物对226Ra、228Ra、210Pb和210Po有很强浓集能力。 相似文献
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Castillo AX Pérez-Malo M Isaac-Olivé K Mukhallalati H González EC Berdeguez MT Díaz NC 《Nuclear medicine and biology》2010,37(8):935-942
The performance of a system composed of an organic cation exchanger (Dowex 50Wx8) and a chelating agent (EDTA) previously described for the successful production of (90)Y via a (90)Sr/(90)Y generator is assessed under dynamic conditions. In an attempt to overcome the established limitation of ion-exchange resins for the separation of subcurie quantities of activity, (90)Y is repeatedly isolated from an 11.8-GBq (320 mCi) (90)Sr cow using a three-column tandem arrangement. The high recovery and radionuclidic purity obtained for (90)Y and the parameters of the separation (time, eluant concentration, pH and flow rate range) strongly suggest that Ci quantities of (90)Y can be handled satisfactorily by the ion-exchange method. No replacement or treatment of the cow, low waste generation and (90)Sr losses less than 0.1% after each run were observed during the present study which, in combination with the low cost of this resin, may result in an attractive alternate method for the production of large quantities of (90)Y. 相似文献
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SummaryThe influence of diet or its ingredients on 141Ce absorption and retention was investigated in six-day-old rats. Animals were fed over 8 h with cow's milk, rat diet or a mixture of rat diet ingredients (fish meal, sunfiower meal, alfalfa, cane molasses and premix) labelled with 141Ce. Whole-body radioactivity was determined in a double crystal scintillation counter every 24 h over a six-day period. Gut, liver, kidney and femur retention and cerium distribution in the gut was determined at the end of the experiment. Compared to milk diet, administration of rat diet or ingredients caused respectively 3 and 7·5 times lower whole body retention. Carcass retention was reduced by rat diet or ingredients 2–3 times and intestinal retention 3 and 8 times respectively. Irrespective of the dietary treatment the main site of cerium intestinal retention was the ileum. Our present results indicate that some compounds of rat diet might be considered as a means of reducing cerium absorption and intestinal retention in the very young. 相似文献
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Mauro L. Bonardi Luigi Martano Flavia Groppi Marco Chinol 《Applied radiation and isotopes》2009,67(10):1874-1877
90Y is one of the most useful radionuclides for radioimmunotherapeutic applications and has a half-life (t1/2=64.14 h) suitable for most therapeutic applications, beta particles of high energy and decays to a stable daughter. It is significant that 90Y is available conveniently and inexpensively from a radionuclide “generator” by decay of its parent, 90Sr. Nevertheless, current and planned clinical applications with [90Y] labelled compounds employ activity levels that cannot be readily obtained from an in-house generator, but from commercial sources. We have evaluated Eichrom's Sr-resin, either as an “in-house” generator or as a fast QC method for analysis of 90Y solutions.In particular, for the development as a generator, we investigated the percentage of the radio-Sr in the first 8 M HNO3 eluate: in this fraction the concentration of 90Sr must be smaller than 10−5% (recommendations of the International Commission on Radiological Protection). For evaluation as a rapid QC method, we analyzed the concentration of 90Y in all the fractions containing “only” radio-Sr: 90Y should not be present in these eluates. After the collection of β− and γ spectra and analysis of them, we concluded that commercial Sr-resin minicolumn cannot give us the results expected; we developed an in-house system loaded with 4 mL of Sr-resin which gave better results as a generator and a rapid QC method. 相似文献
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Helisch A Förster GJ Reber H Buchholz HG Arnold R Göke B Weber MM Wiedenmann B Pauwels S Haus U Bouterfa H Bartenstein P 《European journal of nuclear medicine and molecular imaging》2004,31(10):1386-1392
Purpose For the internal radiotherapy of neuroendocrine tumours, the somatostatin analogue DOTATOC labelled with 90Y is frequently used [90Y-DOTA-Phe1-Tyr3-octreotide (SMT487-OctreoTher)]. Radiation exposure to the kidneys is critical in this therapy as it may result in renal failure. The aim of this study was to compare cumulative organ and tumour doses based upon dosimetric data acquired with the chemically identical 86Y-DOTA-Phe1-Tyr3-octreotide (considered as the gold standard) and the commercially available 111In-pentetreotide.Methods The cumulative organ and tumour doses for the therapeutic administration of 13.32 GBq 90Y-DOTA-Phe1-Tyr3-octreotide (three cycles, each of 4.44 GBq) were estimated based on the MIRD concept (MIRDOSE 3.1 and IMEDOSE). Patients with a cumulative kidney dose exceeding 27 Gy had to be excluded from subsequent therapy with 90Y-DOTA-Phe1-Tyr3-octreotide, in accordance with the directives of the German radiation protection authorities.Results The range of doses (mGy/MBq 90Y-DOTA-Phe1-Tyr3-octreotide) for kidneys, spleen, liver and tumour masses was 0.6–2.8, 1.5–4.2, 0.3–1.3 and 2.1–29.5 (86Y-DOTA-Phe1-Tyr3-octreotide), respectively, versus 1.3–3.0, 1.8–4.4, 0.2–0.8 and 1.4–19.7 (111In-pentetreotide), with wide inter-subject variability. Despite renal protection with amino acid infusions, estimated cumulative kidney doses in two patients exceeded 27 Gy.Conclusion Compared with 86Y-DOTA-Phe1-Tyr3-octreotide, dosimetry with 111In-pentetreotide overestimated doses to kidneys and spleen, whereas the radiation dose to the tumour-free liver was underestimated. However, both dosimetric approaches detected the two patients with an exceptionally high radiation burden to the kidneys that carried a potential risk of renal failure following radionuclide therapy. 相似文献
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Gedik GK Uğur O Atilla B Pekmezci M Yildirim M Seven B Varoğlu E 《Annals of nuclear medicine》2006,20(3):183-188
OBJECTIVES: Radionuclide synovectomy is a reliable therapy in patients with chronic synovitis. However, radiation doses delivered to non-target organ systems due to leakage of radioactive material from the articular cavity are an important disadvantage of this procedure. In this study we compared extraarticular leakage values of the 3 commonly used radiopharmaceuticals; 90Y-citrate, 90Y-silicate and 186Re-sulfide colloid. MATERIALS AND METHODS: Thirty-five patients with persistent synovitis were enrolled in the study. Twenty-two hemophilic, 8 rheumatoid arthritis and 5 patients with pigmented villonodular synovitis were studied. 90Y labeled silicate and citrate were used for knee joints and 186Re-sulfide for intermediate sized joints. Radiocolloid leakage values were evaluated using a gamma camera with 20% window centered over the bremsstrahlung photopeak of 90Y and a respective window over the 137 keV photopeak of 186Re. Regions of interest were drawn over the injection site, the regional lymph nodes and the background areas. Leakage of radiocolloid was calculated by dividing the counts/pixel in the regional lymph node area to the counts/pixel in the injection site. RESULTS: No visible leakage was observed. The median leakage values calculated for 90Y-citrate, 90Y-silicate and 186Re-sulfide were found as 1.9%, 2.4% and 2.7%, respectively. The difference between the variability of leakage values was not statistically significant (p > 0.05). CONCLUSION: There was no significant difference in terms of extraarticular leakage between 9Y-citrate, 9Y-silicate and 186Re-sulfide radiocolloids. 相似文献
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In an attempt to visualize folate receptors that overexpress on many cancers, [18F]-fluorobenzene and pyridinecarbohydrazide-folate/methotrexate conjugates ([18F]-1, [18F]-2-folates and [18F]-8, [18F]-9-MTXs) were synthesized by the nucleophilic displacement reactions using ethyl-trimethylammonium-benzoate and pyridinecarboxylate precursors. The intermediates ethyl [18F]-fluorinated benzene and pyridine esters were reacted with hydrazine to produce the [18F]-fluorobenzene and pyridinecarbohydrazides, followed by coupling with N-hydroxysuccinimide-folate/MTX. Radiochemical yields were greater than 80% (decay corrected), with total synthesis time of less than 45 min. Radiochemical purities were always greater than 97% without high-performance liquid chromatography purification. These synthetic approaches hold considerable promise as rapid and simple method for the radiofluorination of folate derivatives with high radiochemical yield in short synthesis time. In vitro tests on KB cell line showed that significant amount of the radioconjugates were associated with cell fractions, and in vivo characterization in normal Balb/c mice revealed rapid blood clearance of these radioconjugates with excretion predominantly by the urinary and partially by the hepatobiliary systems. Biodistribution studies in nude mice bearing human KB cell line xenografts demonstrated significant tumor uptake and favorable biodistribution profile for [18F]-2-folate over the other conjugates. The uptake in the tumors was blocked by excess coinjection of folic acid, suggesting a receptor-mediated process. Micro-positron emission tomography images of nude mice bearing human KB cell line xenografts confirmed these observations. These results demonstrate that [18F]-2-folate may be useful as molecular probe for detecting and staging of folate receptor-positive cancers, such as ovarian cancer and their metastasis as well as monitoring tumor response to treatment. 相似文献
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Comparison of [18F]FDG-PET and L-3[123I]-iodo-alpha-methyl tyrosine (I-123 IMT)-SPECT in primary lung cancer 总被引:2,自引:0,他引:2
Willkomm P Bangard M Guhlke S Sartor J Bender H Gallkowski U Reichmann K Biersack HJ 《Annals of nuclear medicine》2002,16(7):503-506
OBJECTIVE: The aim of this study was to evaluate L-3[123I]-iodo-alpha-methyl tyrosine (IMT)-SPECT and FDG-PET in pulmonary lesions suspected to be lung cancer. METHODS: Whole body PET (measured transmission corrected emission scans) was performed 45 minutes after i.v. injection of 222-370 MBq (6-10 mCi) 18F-FDG on a Siemens PET scanner (ECAT EXACT 47) including 5-6 bed positions. 123I-IMT-SPECT (chest) was performed after injection of 370 MBq (10 mCi) with a dual head camera (Picker Prism 2000) and commercially available reconstruction algorithms. Ten patients (6 male and 4 female) with suspected lung cancer were investigated. The results were compared to histological findings after surgery or bronchoscopic biopsies and CT. RESULTS: 123I-IMT-SPECT and FDG-PET were able to detect all 9 cases of lung cancer (1-8 cm in diameter). One case was true negative. Both imaging methods were true positive with respect to mediastinal lymph node metastases in one patient. The tumor/background ratio was higher with PET (8.20 vs. 2.84). CONCLUSION: Despite the limited number of patients it may be concluded that IMT-SPECT as well as FDG-PET are suited to correctly diagnose lung cancer. Nevertheless, FDG-PET, if available, seems to be better suited because of the higher tumor/background ratio and better resolution. 相似文献
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Takashi Tanaka Fumitoshi Tago Su-Ping Fang Noriko Shimura 《International journal of radiation biology》2013,89(10):731-740
Purpose: MRL-lpr/lpr mice, a model for various autoimmune diseases, were repeatedly irradiated with 0.5 Gy of γ-rays, and changes in their autoimmune manifestations were investigated.Materials and methods: MRL-lpr/lpr mice at 13 weeks of age were maintained in plastic cages and exposed whole-body to 0.5 Gy γ-ray irradiation from a 137Cs source 5 times per week for 4 weeks, from the time they were 13 weeks old until they reached 17 weeks old. Changes of autoimmune manifestations were examined 3 weeks later at the 20th week.Results: Splenomegaly, lymphadenopathy, and proteinuria in MRL-lpr/lpr mice were clearly ameliorated by a total dose of 10 Gy (0.5 Gy/day×5 days/week for 4 weeks). Histologically severe disease-specific damage to the kidney and the salivary gland, i.e., glomerulonephritis and sialoadenitis, was also improved after irradiation. CD3+ CD4? CD8? CD45R/B220+ T cell numbers, which proliferate abnormally in MRL-lpr/lpr mice, were significantly decreased by the irradiation, possibly through induction of apoptosis. The elevated NO2? and NO3? (NOx?) production by macrophages of MRL-lpr/lpr mice was lowered by the irradiation. The irradiation also prolonged the life span of MRL-lpr/lpr mice. These phenomena may contribute to the amelioration of autoimmune manifestations in MRL-lpr/lpr mice exposed to repeated small-doses of γ-rays.Conclusions: Repeated small-dose γ-ray exposure ameliorates the autoimmune manifestations in MRL-lpr/lpr model mice. 相似文献