Computerized control system for administration of the radioisotope use

An on-line computer system for administration of the radioisotope use has been developed. This system consists of a multi-job type host computer and two sets of personal computers with identification card-readers. The personal computers are employed as terminal devices for radioisotope users. By the use of an identification card, entrance and leaving times are recorded automatically. Furthermore, an easy operation of the personal computer permits users to access to the information of their registered radioisotopes, such as nuclides, chemical forms, updated activities, storage locations, and history of usage. A recording sheet on which those data are printed is provided from the personal computer. After the use of radioisotopes, users can record their data on the recording sheets. These records are used as the input data to this system to update the data of the used radioisotopes. Owing to the concise format of the recording sheet and various sorting programs developed in present work, this system enables us to grasp the exact flow of the radioisotopes from purchase to disposal. Out-put data from high-speed kanji printer can provide many important books which are legally requested to be kept for administration of the radioisotope use.     

The South African national Accelerator centre: particle therapy and isotope production programmes

The National Accelerator Centre (NAC) provides facilities for basic and applied research, radioisotope production and particle therapy. To date, 851 patients have been treated on the 66 MeV p + Be isocentric neutron therapy unit while 191 patients have been treated (mainly for intracranial conditions) on the 200 MeV horizontal proton beam facility. A variety of radioisotopes such as ⁶⁷Ga, ⁸¹Rb/⁸¹Kr, ¹¹¹In, ¹²³I, and ²⁰¹Tl are produced on a regular weekly basis, and more than 1000 consignments of radiopharmaceuticals prepared from these radioisotopes are supplied to more than 30 hospitals and private practices throughout South Africa each year. Some non-medical radioisotopes are also produced.     

分子印迹聚合物在抗生素残留测定中的应用

抗生素的滥用及残留对生物体和环境造成极大危害,其含量低、种类多、基质复杂,通常需要进行样品前处理结合色谱分析以实现灵敏测定。分子印迹聚合物（MIPs）能选择性识别、有效富集目标分析物并消除干扰,已广泛用于抗生素的样品前处理中。该文对MIPs制备中面临的挑战进行了总结;对2016年以来抗生素MIPs的固相萃取应用进行了综述和展望,主要包括固相萃取、分散固相萃取、磁固相萃取、基质固相分散萃取、固相微萃取、搅拌棒吸附萃取。此外,该文重点介绍了抗生素MIPs的印迹新策略,如多模板、多功能单体、虚拟模板、刺激响应、亲水性印迹等。最后,该文对抗生素MIPs的制备和前处理应用进行了展望。     

Sequential separation by HDEHP of carrier-free101,105,106Rh,103,104,105,106,110,112Ag and104,105,107,109,111Cd produced in alpha-particle activated palladium

Carrier free^101,105,106Rh,^{103,104,105,106,110,112}Ag and^{104,105,107,109,111}Cd radioisotopes were produced simultaneously by -particle irradiation of palladium target material in a variable energy cyclotron. The radioisotopes produced were extracted and separated from the activated target by LLX using HDEHP as liquid cation exchanger. With the help of -ray spectrometry the presence of several radioisotopes in the activated target matrix and their purity at each step of the separation was confirmed.     

Producing radioisotopes in power reactors

The demand of radioisotopes is rising due to wide-ranging applications in industry, agriculture, medicine and in research. Two sources of artificial radioisotopes are accelerators and reactors. The reactor offers large volume for irradiation, simultaneous irradiation of different samples and economy of production, whereas accelerators are generally used to produce those isotopes which can not be produced by reactor. Radioisotope production started on a significant scale in several countries with the commissioning of research reactors starting from the late 1950s. The period from 1950 to 1970 saw construction of a large number of research reactors with multiple facilities. After 1980, because of the decommissioning of many old ones, the number of operating reactors has been steadily decreasing. The research reactors used for radioisotope production could be broadly classified into swimming pool type and tank type reactors. CANDU power reactors currently produce many millions of curies per year of ⁶⁰Co for MDS Nordion’s use in industry and commerce. Studies related to production of other isotopes in power reactors have also been performed. Indeed, while a very few reactors have come online in the past decade, many more have been retired or may retire in coming years. After failure of MAPLE project, there has been unwillingness to built new reactors. Activism and politics has made it so difficult to build new reactors that we are left to use only the reactors we inherited from a nuclear era. Many design considerations and requirements for the production of isotopes in power reactors must be assessed, such as; operator and public safety, minimum impact on station efficiency and reactor operations, shielding requirements during reactor operation with target adjusters and removal of the target adjusters from core, transportation within the station, and finally the processing and shipment off-site. Use of power reactors for isotope production is reviewed.     

Separation of carrier-free 111In, 116,117Te and 116,116m,117Sb from a 11B-induced silver target

Heavy-ion activation with ~55 MeV ¹¹B beam on silver target leads to the production of carrier-free ¹¹¹In, ^116,117Te and ^116,116m,117Sb radioisotopes in the target matrix. Liquid-liquid extraction, using Aliquat-336 and trioctylamine (TOA) as liquid anion exchangers in HNO₃ and HCl medium, respectively, and di-(2-ethylhexyl)phosphoric acid (HDEHP) as liquid cation exchanger in ammoniacal medium was used to investigate the separation of the produced radioisotopes from the bulk target matrix.     

Separation of 103Pd from Rh and Ag by the macroporous AG MP-1 anion exchange resin in Ag targets

A radiochemical process is reported for the production of ¹⁰³Pd from Ag targets for use in brachytherapy. The procedure, which is based on anion exchange chromatography, separates Pd from a large amount of target material (16 g Ag), as well as Rh radioisotopes (mainly ¹⁰¹Rh and ¹⁰⁰Rh), which are produced from decays of their Pd parents. The AG MP-1 anion exchange resin was used for the process. For elution of Rh and Ag, 3M nitric acid solution was used and 5% ammonia solution was used to elute the Pd. The average recovery of Pd was 97.4%. An elution curve for Pd was set up and a panel for the radiochemistry designed and installed in a hot cell.     

离子液体固定化材料在固相萃取中的应用研究进展

离子液体是由阴、阳离子组成的低温熔融盐,几乎没有蒸汽压,具有稳定性好、溶解能力强、结构可设计、导电性好等优良性能。离子液体作为一种广受关注的新型“绿色溶剂”,具有代替传统有机溶剂的潜力,其制备方法和应用范围研究日趋完善和多样,已广泛应用于催化化学、光电化学、材料化学和分析化学等领域。离子液体通过功能化导向设计后,可以将羟基、氨基、羧基、氰基等活性基团键合在离子液体结构上,促使其更加易于与目标分子通过生成π-π键、氢键、离子键和范德华力等而产生相互作用,更加易于发生固定化反应。将离子液体负载到固体载体材料进行固定化后,新型材料既可以减少离子液体的流失,同时保留了离子液体和固体载体的独特性能,具有富集效率高、吸附容量高、稳定性好、识别位点多、萃取选择性强、离子液体利用率高等特点,近年来,在有机小分子固相萃取分离研究中应用广泛。该文从离子液体与硅胶、分子筛、分子印迹聚合物、氧化石墨烯、磁性材料等固体载体的固定化研究情况入手,综述了离子液体固定化材料在固相萃取分离中的应用情况,涉及的目标分离物质包括生物碱类、黄酮类、多酚类等天然活性成分,以及常见药物分子、有机农药等有机小分子化合物,系统地介绍了离子液体与多种载体固定化的性质、应用和分离机制。离子液体的引入,增加了复合材料的活性位点分布和吸附容量,离子液体固定化材料的吸附效率与离子液体种类、吸附材料用量、样品溶液浓度、吸附温度、pH值、洗脱溶剂类型、用量及流速等因素有关。该文探讨了离子液体结构相对单一、相关基础理论研究相对薄弱、复杂基质萃取程度不理想等问题,并提出相应的解决思路,以期为离子液体固定化材料在复杂基质中目标分子分离分析方面的应用提供借鉴和参考。     

Recovery of hafnium radioisotopes from a proton irradiated tantalum target

The^178m2Hf nucleus, with its long half-life (31 y) and high-spin isomeric state (16⁺) is desired for new and exotic nuclear physics studies. The Los Alamos Radioisotope Program irradiated a kilogram of natural tantalum at the Los Alamos Meson Physics Facility in early 1981. After fifteen years of decay, this target was ideal for the recovery of^178m2Hf. There was more than a millicurie of^178m2Hf produced during this irradiation and there has been a sufficient period of time for most of the other hafnium radioisotopes to decayed away. Traditionally, separation techniques for recovering hafnium isotopes from tantalum targets employ solvent extractions with reagents that are considered hazardous. These techniques are no longer condoned because they generate a mixed-waste (radioactive and hazardous components) that can not be treated for disposal. In this paper we describe a new and unique procedure for the recovery of hafnium radioisotopes from a highly radioactive, proton irradiated, tantalum target using reagents that do not contribute a hazardous waste component.     

Separation of (203)Pb by ion-exchange chromatography on chelex 100 after production of (203)Pb by the Pb(p, xn)(203)Bi--> EC.beta+ (203)Pb nuclear reaction

Bismuth radioisotopes, produced by 50-MeV proton bombardment of a lead target in a cyclotron, are separated from the lead target material by ion-exchange chromatography on a column containing 5.0 ml of Chelex 100. After a decay period of 24 hr, the (203)Pb formed in situ is eluted from the column and then separated from (200)Tl and (201)Tl on a second ion-exchange column containing 0.5 ml of Chelex 100. Separations are sharp and carrier-free (203)Pb is obtained.     

Immobilised gold nanostars in a paper-based test system for surface-enhanced Raman spectroscopy

Paper-based SERS active substrates were prepared adsorbing spherical and star-shaped gold nanoparticles on a standard filter paper support. Besides the deposition conditions, morphological parameters of the particles were found to strongly affect the enhancer properties of the substrates. The developed substrate was tested regarding surface homogeneity as well as in the quantitative analysis of malachite green, – a well documented Raman reporter dye – and proved to be capable also to detect the oxidation products of apomorphine, a well-known drug molecule used in Parkinson's disease. This material is simple to prepare, easy to handle and dispose and as such it could be a perfect target for further development of a new family of mass-produced, cheap solid SERS substrates.     

Waste minimization in the Los Alamos Medical Radioisotope Program

Since the mid-1970s the Los Alamos Medical Radioisotope Program has been irradiating target materials to produce and recover radioisotopes for applications in medicine, environmental science, biology, physics, materials research, and other disciplines where radiotracers find utility. By necessity, the chemical processing of targets and the isolation of radioisotopes generates radioactive waste materials. In recent years there have been federal mandates requiring us to discontinue the use of hazardous materials and to minimize radioactive waste volumes. As a result, substantial waste reduction measures have been introduced at the irradiation facility, in processing approaches, and even in the ways the product isotopes are supplied to users.     

Solid targets for 99mTc production on medical cyclotrons

Recent disruptions in the molybdenum-technetium generator supply chain prompted a review of non-reactor based production methods for both ⁹⁹Mo and ^99mTc. Small medical cyclotrons (E _p ~ 16–24 MeV) are capable of producing Curie quantities of ^99mTc from isotopically enriched ¹⁰⁰Mo using the ¹⁰⁰Mo(p,2n)^99mTc reaction. Unlike most other metallic target materials for routine production of medical radioisotopes, molybdenum cannot be deposited by reductive electroplating from aqueous salt solutions. To overcome this issue, we developed a new process for solid molybdenum targets based on the electrophoretic deposition of fine ¹⁰⁰Mo powder onto a tantalum plate, followed by high temperature sintering. The targets obtained were mechanically robust and thermally stable when irradiated with protons at high power density.     

Recent developments in the manufacture of 173lutetium targets

To better model nuclear processes there is an interest in measuring neutron capture cross sections of lanthanide radioisotopes. A natural hafnium target was irradiated with 100 meV protons at the Los Alamos Isotope Production Facility at the Los Alamos Neutron Science Center (LANSCE) to produce neutron poor lutetium radioisotopes. After irradiation, the target was allowed to cool to allow shorter lived lutetium isotopes to decay. This left predominately ¹⁷³Lu with small amounts of ¹⁷⁴Lu. The hafnium target was then chemically processed to isolate the lanthanide fraction through ion exchange techniques. Recent efforts have focused on the separation of lanthanide species to produce an elementally pure lutetium product, the manufacture of small high density lutetium targets, and neutron capture cross section measurements.     

Use of a heterogeneous isotope exchange method for preparation of rose bengal labelled by radioisotopes of iodine

A new method of preparation of rose bengal labelled by radioisotopes of iodine has been developed. The method is based on heterogeneous isotope exchange between rose bengal absorbed on a solid carrier and electrophilic species of radioiodine in HCl solutions. Low specific activity solutions can be used in the method. The method can also be used for preparation of other labelled derivatives of diiodofluorescein.     

Electrophoresis and detection of tin-labeled DNAs on open-faced gels.

Alternative protocols are necessary for the use of polyacrylamide gel electrophoresis in genome scale sequencing and mapping studies. The use of radioisotopes and manual gel reading will have to be replaced with a flexible labeling system that can be detected at levels similar or to better than radioisotopes but allows automated, high-speed detection. Labeling with stable isotopes is such an alternative. These nondecaying isotopes have the potential to be detected in sub-attomole quantities, despite being surrounded by the gel matrix, due to the high selectivity and sensitivity of resonance-ionization spectroscopy coupled with a mass spectrometer. In this study the detection limits of sputter-initiated resonance ionization spectroscopy (SIRIS) are investigated using thin, open-faced polyacrylamide gels supported by plastic. This system allows reproducibility and flexibility in the choice of gel size and buffer system since the gel can be cast, washed free of polymerization by-products, dried, and stored until use. Various concentrations of an Sn-labeled oligomer were run on these gels and loads of 5 femtomoles/mm could be detected on a 240 microns thick gel. Gels as thin as 60 microns lower the detectable concentration loads to 1 femtomole/mm. The limiting factor is tin contamination in the gel which, if reduced, will further increase detection. Polymerase chain reaction (PCR) products can also be labeled and detected using Sn isotopes, which could prove useful in mapping studies. Also presented are techniques which will facilitate resolution of these PCR products on open-faced gels by employing discontinuous buffers systems and DNA mobility modifiers.     

Copper complexes of bis(thiosemicarbazones): from chemotherapeutics to diagnostic and therapeutic radiopharmaceuticals

The molecules known as bis(thiosemicarbazones) derived from 1,2-diones can act as tetradentate ligands for Cu(II), forming stable, neutral complexes. As a family, these complexes possess fascinating biological activity. This critical review presents an historical perspective of their progression from potential chemotherapeutics through to more recent applications in nuclear medicine. Methods of synthesis are presented followed by studies focusing on their potential application as anti-cancer agents and more recent investigations into their potential as therapeutics for Alzheimer's disease. The Cu(II) complexes are of sufficient stability to be used to coordinate copper radioisotopes for application in diagnostic and therapeutic radiopharmaceuticals. Detailed understanding of the coordination chemistry has allowed careful manipulation of the metal based properties to engineer specific biological activities. Perhaps the most promising complex radiolabelled with copper radioisotopes to date is Cu(II)(atsm), which has progressed to clinical trials in humans (162 references).     

The use of radionuclides for the determination of adsoroption isotherms of volatile chlorides

It is demonstrated that gas-solid chromatography is a useful method for the investigation of the adsorption, properties of inorganic compounds at temperatures up to 1100 K. The use of radioisotopes enables the application of this method to extreme small concentrations and surface areas. Adsorption entropies and enthalpies for various chlorides on a quartz glass surface are presented, as well as several other adsorption data of inorganic chlorides. The possibility to use data obtained by this method for the optimization of separations is shown.     

Automated production of 64Cu prepared by 18?MeV cyclotron

⁶⁴Cu (T_1/2?=?12,7?h, ??^? 37,1?%, ??⁺ 17,9?%, EC 41?%) is a useful radioisotopes for positron emission tomography radiopharmaceutical. We used the reaction route ⁶⁴Ni(p,n)⁶⁴Cu for the ⁶⁴Cu preparation. A basic disadvantage of this route, a high price of the enriched target material, was eliminated by using very simple recycling procedure. Compact solid target irradiation system was installed at the end of the external beam line of the IBA Cyclone 18/9 cyclotron. In this paper, the irradiation of ⁶⁴Ni target and separation of ⁶⁴Cu from a target material is described. The separation was achieved by anion exchange chromatography with HCl as a elution solution. The distribution ratio for different HCl concentrations on Bio-Rad AG1-X8 and elution profile of ⁶⁴Cu were investigated. ⁶⁴Cu production rate for 100?mg ⁶⁴Ni of 99.09?% purity (ISOFLEX) on gold target was 104?MBq/??Ah. The activity of the product was checked by ionisation chamber (Curiementor), gamma spectrometry using a HPGe detector and liquid scintillation counting using the triple-to-double coincidence ratio method. The separation process of ⁶⁴Cu was made in a home-made separation module.     

Charged particle activation analysis coupled with X-ray counting

A survey is given on the analytical use of X-ray emitting radioisotopes produced by charged particle activation. Thirty-nine proton and deuteron reactions were considered on twentysix elements (34≤Z≤82). Thick target yields and sensitivity estimates are presented. The features and limitations of this method and the scope of non-destructive and destructive determinations are discussed. The main interest of this approach is to open an avenue for trace analysis with simplified data acquisition and reduction.