质子加速器放射治疗场所活化核素所致人员受照剂量估算与分析

目的 了解质子加速器放射治疗场所空气活化产物可能致工作人员的受照剂量水平,为治疗场所的防护设计和人员的放射防护提供技术基础。方法 以PROTEUS235型质子治疗系统为例,分析质子加速器运行时场所空气中可能产生的主要活化核素,估算工作场所内活化核素的放射性活度浓度及其所致人员的受照剂量。结果 在质子加速器厅内,活化核素¹⁵O的放射性活度浓度最高,为4.1×10^-2Bq ·cm^-3;¹³N、⁴¹Ar和¹¹C依次为3.3×10^-2、6.2×10^-3和2.0×10^-2Bq ·cm^-3。在质子束治疗室内,上述核素放射性活度浓度约为加速器厅内的5%。工作人员在停束后5和30 min进入质子加速器厅内,因外照射可能受到的年有效剂量分别小于1和0.1 mSv;在质子治疗停束后即刻进入治疗室,因空气活化所致年有效剂量为1.3～2.0 mSv,而在停束后5和15 min进入时分别为0.7～1.2和0.3～0.6 mSv。结论 质子加速器治疗场所空气中活化核素所致人员受照剂量不容忽视,应主要考虑活化核素¹⁵O、¹³N、⁴¹Ar、¹¹C所致外照射对工作人员造成的剂量贡献,并采取必要的防护措施。     

60Coγ射线照射对人血小板功能的影响

以不同剂量的⁶⁰Coγ射线照射富含血小板血浆后,检测其代谢及释放产物的变化⁶⁰Coγ射线照射剂量达5Gy时,血小板表面活化标记蛋白GMP-140分子的表达显着增多,且随剂量的增加而增高,血浆内血小板TxB₂的产生及释放当剂量为2.5Gy时就呈显着升高,γ射线剂量大于5Gy时,血浆内vWF的浓度显着升高；结果提示；⁶⁰Coγ射线照射剂量达5 Gy后,可激活体外的血小板,导致后者代谢旺盛。内容物释放增多。     

北京地区天然本底辐射水平及所致公众剂量评价

本文报道了北京地匮天然辐射豫所致公众剂量的大小、构成和方式。其中来自宇宙射线(电离)雨地表γ辐射的外照射剂量为0.77mSv·a^-1。;通过食入和吸入进入人体内昀放射性核素形成的内照射总计1.66mSv·a^-1。天然辐射内照射源自的80%(全部天然辐射源的55%)来自吸入²²²Rn和托²²⁰Rn的短寿命子体。天然辐射源产生的北京地区公众人均年有效剂量当量为2.43mSv·a^-1,当前北京居民年集体有效剂量当量为2.39×10⁴man·Sv·a^-1。     

环境样品中放射性核素γ谱分析的比对

为了对用γ谱仪分析环境样品中的放射性核素含量进行质量控制,组织了第二次卫生部系统及有关单位的γ谱分析环境样品的比对工作.本文介绍了这次比对的方法,方式、数据处理、定值方法及十二个实验室分析三个不同填充密度的土壤样品及二个河泥样品中的²³⁸U、²²⁶Ra、²³²Th、⁴⁰K¹³⁷Cs和¹³⁴Cs等放射性核素含量的测量结果,还分析了各实验室测量数据的精确度,有86%左右的测量分析数据与参考值在±20%以内符合,只有个别实验室由于系统误差较大,影响了测量结果的准确性.     

水样品放射性核素γ能谱分析的比对与评价

目的 通过在重点实验室间开展γ能谱测量分析比对活动,改进水样品的γ能谱分析技术。方法 参加中国计量科学研究院组织的水样品中γ能谱测量分析比对。样品中²³⁸U、 ²²⁶Ra、²⁰⁸Tl、²²⁸Ac、⁴⁰K、²⁴¹Am、¹³⁷Cs、⁶⁰Co被检出。为分析比对结果,2015年又采用新制备的水标准源重新进行了效率刻度,并且采用了1台新购进的γ能谱仪（BE5030）重新测量了比对样品。结果 比对样品3次测量结果与主导实验室参考值的分析比较,发现采用γ能谱仪（BE5030）测量分析的结果较好,特别是天然核素结果,与参考值的最大E_n值仅为0.71。结论 宽能高纯锗γ能谱仪（BE5030）在天然放射性核素的测量分析方面优势明显,并且由于其探测器的结构特点,使得其在低能区本底干扰更少。此次比对改进了本实验室样品测量分析的准确性,取得了良好的效果。     

222Rn-220Rn累积探测器参加日本组织的国际比对结果分析

目的 通过参加国际比对,提高²²²Rn和²²⁰Rn累积测量的水平,保证测量的质量。方法 将本实验室的LD-P型²²²Rn-²²⁰Rn探测器寄往日本放射线医学综合研究所(National Institute of Radiological Science,NIRS),参加²²²Rn-²²⁰Rn累积探测器的国际比对。²²²Rn比对在NIRS的标准²²²Rn室进行,按暴露量分低、中、高3个水平;²²⁰Rn比对在NIRS的²²⁰Rn室进行,也分低、中、高3个水平。暴露结束后将探测器寄回本实验室进行蚀刻、分析,然后把测量结果报给NIRS,最后NIRS将暴露的参考值反馈回本实验室。结果 LD-P探测器²²²Rn比对测量低、中、高3个暴露水平的测量值与参考值的相对偏差(RPD)分别为-13.8%、-14.4% 和-17.1%;²²⁰Rn比对测量低、中、高3个暴露水平的测量值与参考值的RPD分别为-14.4%、 8.9%和-3.2%。结论 本次比对LD-P探测器²²²Rn和²²⁰Rn的测量结果均在NIRS规定的RPD为20%的一级标准范围内。     

中日γ能谱分析土壤样品中放射性核素的比对

目的 通过开展γ能谱测量分析比对活动,检验比对样品的采集、制备、测量和分析全过程,以促进放射性核素γ能谱测量分析技术的发展。方法 由中国疾病预防控制中心辐射防护与核安全医学所采集和制备环境土壤样品,比对各方分别对两个土壤样品中的²¹⁴Pb、²¹⁴Bi、²⁰⁸Tl、²²⁸Ac、⁴⁰K和¹³⁷Cs 6个核素进行测量和分析。根据3个实验室约定测量结果的评定标准,利用各实验室上报的活度浓度和总不确定度数据计算测量结果评价变量(En)值。结果 每两个实验室间计算的En值均小于1,3个实验室的结果均为可接受的结果。结论 各比对方的测量结果在一定范围内是一致的。本次比对既检验了比对方实验室的核素分析水平,又促进了本实验室样品制备中均匀性检验能力的提高。     

测量125I放射性活度的相加峰符合法

本文介绍测量¹²⁵I放射性活度的相加峰符合法。通过测量¹²⁵I衰变放射的27.5kevx射线飘135.5keVγ 射线单一峰计数率及这两种射线相加峰计数率,可准确的计算出¹²⁵I源的放射性活泼。本法与测量¹²⁵I活度的相对法比较,具有使用方便,不需要对计算系统进行刻度,以及测量结果几乎不受样品源体积、源在探测器中的位置和样品源容器类型的影响等优点,是核医学和辐射防护中测量¹²⁵I放射性活度的较为理想的一种方法。     

硼中子俘获治疗的加速器中子源7Li(p,n)7Be的中子特性研究

目的 通过研究质子加速器 ⁷Li(p,n)⁷Be 反应的中子特性,为研究和制作适用于硼中子俘获治疗(BNCT)的加速器中子源提供基础数据。方法 加速质子使其轰击Li靶后产生中子;通过金属箔活化法,测量中子与In箔发生阈值反应后放出的γ射线;然后计算出In箔的放射性活度、加速器反应后放出中子的注量和反应的微分截面。结果 质子加速轰击Li靶后,在不同方向产生不同能量和注量的中子。加速器电压分别为3.0、2.8和2.6 MV,出射中子与入射质子束的方向一致时, ⁷Li(p,n)⁷Be 反应的微分截面约为50 mb/mr;夹角为60°时,反应的微分截面减小到30 mb/mr左右。由于部分中子与其他金属原子等发生弹性散射而射向后方,提高了这一范围内In箔的比放射性活度,影响了其微分截面的准确性。结论 用金属箔活化法测定中子简便易行,可同时测得多个方向的中子分布,但需对中子与其他金属弹性散射产生的影响进行进一步的研究; ⁷Li(p,n)⁷Be 反应后发射出的中子经慢化后,能得到适于BNCT治疗的热中子和超热中子;若作为BNCT的中子源,加速器的质子束流需达到10 mA。     

0～15MeV中子诱发239Pu裂变产额能量关系的评价研究

目的 研究0～15 MeV中子诱发 ²³⁹Pu 裂变产物的累积产额随入射中子能量变化的关系。方法 使用加权平均和ZOTT评估的方法对裂变产物核的累积产额实验数据进行评价推荐,通过SPCC程序拟合和多模式模型理论首次得出产额能量关系。结果 评价推荐了0～15 MeV中子诱发 ²³⁹Pu 裂变的 ⁸⁵Kr^m 、 ⁸⁷Kr 、 ⁸⁸Kr 和 ¹³⁸Xe 4个重要气体产物核的累积产额数据,给出了产额能量关系曲线。评价后的数据与国际上ENDF/B-VII、JENDL-3.1、JEF-2.2和CENDL-2等数据库的推荐数据进行了比较,使相关数据得以更新和补充。理论计算结果可以在定性上与实验拟合曲线进行比较。结论 ⁸⁷Kr 和 ⁸⁸Kr 的累积产额随能量增加呈上升趋势,而 ⁸⁵Kr^m 和 ¹³⁸Xe 呈现直线型的关系曲线。多模式理论计算结果可以定性地反映实验拟合曲线的趋势。     

Production of large quantities of 90Y by ion-exchange chromatography using an organic resin and a chelating agent

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.     

人体中的镭-226、镭-228、钋-210、铅-210

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.}     

Comparison of extraarticular leakage values of radiopharmaceuticals used for radionuclide synovectomy

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.     

Rapid determination of Sr impurities in freshly “generator eluted” Y for radiopharmaceutical preparation

⁹⁰Y is one of the most useful radionuclides for radioimmunotherapeutic applications and has a half-life (t_1/2=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.     

226Ra 228Ra 210Pb和210Po在水生生物及食物链中转移规律的探讨

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。     

Scintigraphic findings of MALT lymphoma of the thyroid

Mucosa-associated lymphoid tissue (MALT) lymphoma has been established as a distinct entity among non-Hodgkin's lymphomas, and the most common primary site is the stomach. We describe scintigraphic findings in a patient with MALT lymphoma of the thyroid. A 71-year-old woman with Hashimoto's thyroiditis suffered from rapid cervical swelling, and ultrasonography and CT revealed a thyroid nodule. The nodule showed accumulation of 99mTc pertechnetate comparable to the surrounding thyroid tissue, mimicking a benign nodule. Both 67Ga and 201Tl imaging visualized the lesion as an increased uptake area. After radiotherapy, abnormally increased uptake disappeared on 67Ga images, which predicted a favorable outcome. MALT lymphoma of the thyroid may be visualized as a warm nodule on 99mTc pertechnetate scintigraphy.     

Rapid synthesis and in vitro and in vivo evaluation of folic acid derivatives labeled with fluorine-18 for PET imaging of folate receptor-positive tumors

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.     

Development of a modular system for the synthesis of PET [C]labelled radiopharmaceuticals

[¹¹C]labelled radiopharmaceuticals as N-[¹¹C]methyl-choline ([¹¹C]choline), l-(S-methyl-[¹¹C])methionine ([¹¹C]methionine) and [¹¹C]acetate have gained increasing importance in clinical PET and for the routine production of these radiopharmaceuticals, simple and reliable modules are needed to produce clinically relevant radioactivity. On the other hand, flexible devices are needed not only for the routine synthesis but also for more complex applications as the development of new tracers. The aim of this work was the adaptation of an Eckert Ziegler modular system for easy routine synthesis of [¹¹C]choline, [¹¹C]methionine and [¹¹C]acetate using components that account for straightforward scaling up and upgrades.     

Radiobiological Issues in the Anomalous Enhanced Effect of Low-dose-rate Fission-spectrum Neutrons: Reply to Letter to the Editor by G. W. Barendsen

Summary

The 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.     

Pre-therapeutic dosimetry and biodistribution of 86Y-DOTA-Phe1-Tyr3-octreotide versus 111In-pentetreotide in patients with advanced neuroendocrine tumours

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.