Radiochemical separation of actinides for their determination in environmental samples and waste products

Energy Technology Data Exchange (ETDEWEB)

Gleisberg, B [Nuclear Engineering and Analytics Rossendorf, Inc. (VKTA), Dresden (Germany)

1997-03-01

The determination of low level activities of actinides in environmental samples and waste products makes high demands on radiochemical separation methods. Artificial and natural actinides were analyzed in samples form the surrounding areas of NPP and of uranium mines, incorporation samples, solutions containing radioactive fuel, solutions and solids resutling from the process, and in wastes. The activities are measured by {alpha}-spectrometry and {gamma}-spectrometry. (DG)

The study of radiochemical separation methods on gaseous Fission product krypton-88

International Nuclear Information System (INIS)

Yang Zhihong; Zhang Shengdong; Yang Lei; Ding Youqian; Sun Hongqing; Ma Peng

2012-01-01

Half-life of krypton-88 is 2.84 hours, high fission yields and a relatively large gamma branching ratio is had. The gas is short-lived fission products in burnup measurements. Only New fission products can extract from extraction in gas of fissile irradiation target. But krypton-88 with krypton-85, krypton-87, xenon -135, and xenon-138 is coexisted together, thus radiochemical separation must quickly taken. selected the irradiation time is 1-2 hours and cooling time is best 2 hours for sample preparation, krypton and xenon were separated using activated carbon adsorption, the ratio of krypton and xenon were measured by gamma spectroscopy. Then according to the ratio of krypton-85 and xenon-125 count rate coefficient around separation were calculated yield of krypton and decontamination factor of xenon and the final the yield of krypton-85 is calculated. (authors)

Development of radiochemical separation method for determination of toxic elements in biological samples

International Nuclear Information System (INIS)

Maihara, V.A.; Vasconcellos, M.B.A.; Favaro, D.I.T.; Armelin, M.J.A.

1990-01-01

In order to determine Hg, Sb, As and Se in biological materials by neutron activation analysis, a radiochemical separation was developed. The chemical separation procedure used was based on the digestion of the irradiated sample in a mixture of H NO 3 and H 2 SO 4 in a teflon bomb, at 130 0 C for 1 to 4 hours. After the dissolution of organic matter, Hg and Sb were retained by a Dowex 2-X8 resin column in 6 M HCl. The effluent was passed through a TDO, tin dioxide column which retains As and Se in 3 M HCl medium. Radioactive tracers of these elements were used to determine the yields of the separation process. Certified reference materials were analyzed to check the precision and accuracy of the method. (author)

Development of a radiochemical separation method for toxic elements determination from biologic samples

International Nuclear Information System (INIS)

Malhara, V.A.; Vasconcellos, M.B.A.; Favaro, D.I.T.; Armelin, M.J.A.

1990-01-01

In order to determine Hg, Sb, As and Se in biological materials by neutron activation analysis, a radiochemical separation was developed. The chemical separation procedure used was based on the digestion of the irradiated sample in a mixture of HNO 3 and H 2 SO 4 in a teflon bomb, at 130 0 C for 1 to 4 hours. After the dissolution of organic matter, Hg and Sb were retained by a Dowex 2-XB resin column in 6M HCI. The efluent was passed through a TDO, tin dioxide column which retains As and Se in 3M HCI medium. Radioactive tracers of these elements were used to determine the yields of the separation process. Certified reference materials were analyzed to check the precision and accuracy of the method. (author)

Radiochemical separations of hafnium, tantalum, and germanium from tungsten and selenium irradiated by 14 MeV neutrons

International Nuclear Information System (INIS)

Blachot, J.; Benabed, A.; Herment, J.; Monnand, E.

1968-01-01

Radiochemical separations of Hf, Ta and Ge from W and Se respectively, after 14 MeV-neutron irradiation. A new isotope: 79 Ge with a half-live of 50 ± 5 s and emitter of a 230 keV γ transition is observed. (authors) [fr

Radiochemical separation of cadmium-109

International Nuclear Information System (INIS)

Egamediev, S.; Mukhtarov, A.; Nurbaeva, D.; Rakhmanov, A.

2006-01-01

Full text: Cadmium-109 has a half-life of 461.9 days and decays by electron capture to 109 Ag with the emission of 88 keV γ-ray (3.79%) along with the characteristic X-ray from the K level of Ag, with energy of 22.5 keV. This radionuclide has found widespread use as a photon source in x-ray fluorescence analysis devices employed in industry for numerous applications such as the direct determination of gold in ores, the analysis of metals and identification of steels. Other applications range from its use as an electron source for measurement of densities of air-pollution samples, to tracer studies in mushrooms and mice and rats. In the nuclear medicine field there is growing interest in employing 109 Cd in a 109 Cd/ 109mA g generator, as an alternative to other biomedical generators of ultra short-lived gamma emitters. There are several methods for the production of 109 Cd in literature: 1. Bombardment of silver cyclotron target via 109 Ag(d,2n) 109 Cd reaction with 16 MeV deuterons. 2. Bombardment of natural silver target via 109 Ag(p,n) 109 Cd reaction with 14 MeV protons. 3. Proton bombardment of natural indium target with 96 MeV protons. 4. Irradiation of enriched 107 Ag target in high-flux nuclear reactor at neutron flux 2x10 15 n·cm -2 ·s -1 via 107 Ag(n,γ) 108 Ag → 108 Cd (n,γ) 109 Cd reaction. 5. Irradiation of enriched 108 Cd target in nuclear reactor at neutron flux 1x10 14 n·cm -2 ·s -1 via 108 Cd (n,γ) 109 Cd reaction. The production of 109 Cd with proton beam via 109 Ag(p,n) 109 Cd reaction is ideal for the cyclotron U-150, since it is not required the change of the regime for the machine functioning. Because of its relatively long half-life the time required for separation is also not an important factor, but its use as an X-ray source requires a very high radiochemical purity. In the present work we studied two methods for separation of 109 Cd from model solution of silver targets. First method is based on precipitation of silver as

Some problems concenrning the use of automated radiochemical separation systems in destructive neutron activation analysis

International Nuclear Information System (INIS)

Nagy, L.G.; Toeroek, G.

1977-01-01

The present state of a long term program is reviewed. It was started to elaborate a remote controlled automated radiochemical processing system for the neutron activation analysis of biological materials. The system is based on wet ashing of the sample followed by reactive desorption of some volatile components. The distillation residue is passed through a series of columns filled with selective ion screening materials to remove the matrix activity. The solution is thus ''stripped'' from the interfering radioions, and it is processed to single-elements through group separations using ion-exchange chromatographic techniques. Some special problems concerning this system are treated. (a) General aspects of the construction of a (semi)automated radiochemical processing system are discussed. (b) Comparison is made between various technical realizations of the same basic concept. (c) Some problems concerning the ''reconstruction'' of an already published processing system are outlined. (T.G.)

Utility of reversed phase high performance liquid chromatography for on-line yield determination of radiochemical separations: Studies with cobalt

International Nuclear Information System (INIS)

Subramanian, S.; Woittiez, J.R.W.

1993-01-01

This article indicates the potentials of high performance liquid chromatography (HPLC) as a radiochemical technique for multielement separation of neutron irradiated samples. The focus lies on the convenience to use the detector signal of the eluted components to indicate the chemical yield of the analyte, which has often proved to be a crucial step in radiochemical separations. Two signals have been utilized. The UV signal of the metal-ligand complexes separated by reversed phase HPLC and the radioactive response as a result of sample irradiation of carrier-tracer addition. Change in ratio is discussed between the two signals, if any, for a specific sample. Losses of metal as much as 65% were simulated and corrected using the individual UV response. The method promises improved accuracy for elemental analysis despite losses suffered during the various chemical steps. The procedure omits the necessity of additional analytical steps for yield determination. The present article aims at the chromatographic part of the study. Cobalt as cobalt diethyldithiocarbamate has been used to demonstrate the viability of the concept. The separation was developed on c C18 reverse phase analytical column and optimized on a semi preparative one

Radiochemical analysis of phosphorus in milk samples

International Nuclear Information System (INIS)

Oliveira, R.M. de; Cunha, I.I.L.

1991-01-01

The determination of phosphorus in milk samples by thermal neutron activation analysis employing radiochemical separation is described. The radiochemical separation consists of the simultaneous irradiation of samples and standards, dissolution of the milk samples in a perchloric acid and nitric acid mixture, addition of zinc hold-back carrier, precipitation of phosphorus as ammonium phospho molybdate (A.M.P.) and sample counting in a Geiger-Mueller detector. The analysis sources of error were studied and the established method was applied to phosphorus analyses in commercial milk samples. (author)

Obtention process of phosphorus 32 starting from commercial sulfur and design and construction of the radiochemical separation prototype

International Nuclear Information System (INIS)

Duarte A, C.; Alanis M, J.; Gutierrez R, C.

2002-01-01

In this work an obtention process of phosphorus 32 ( 32 P) in orthophosphoric acid form (H 3 32 PO 4 ) is described starting from commercial sulfur. Also the design and construction of the experimental prototype used in the radiochemical separation and their results in three tests carried out is reported. (Author)

Radiochemical studies of some preparation methods for phosphorus

International Nuclear Information System (INIS)

Loos-Neskovic, C.; Fedoroff, M.

1983-01-01

Various methods of radiochemical separation were tested for the determination of phosphorus in metals and alloys by neutron activation analysis. Classical methods of separation revealed some defects when they were applied to this problem. Methods using liquid extraction gave low yields and were not reproducible. Methods based on precipitation gave better results, but were not selective enough in most cases. Retention on alumina was not possible without preliminary separations. Authors studied a new radiochemical separation based on the extraction of elemental phosphorus in the gaseous phase after reduction at high temperature with carbon. Measurements with radioactive phosphorus showed that the extraction yield is better than 99%. (author)

Cyclotron production, radiochemical separation and quality control of platinum radiotracers for toxicological studies

International Nuclear Information System (INIS)

Bonardi, M.; Birattari, C.; Groppi, F.; Arginelli, D.; Gini, L.; Gallorini, M.

1998-01-01

The increasing concentration of Pt, Pd and Rh in the environment is mainly due to the release of these elements from the catalytic converters of the motorvehicles. This situation makes it necessary to carry out metallotoxicological experiments on both cell cultures and laboratory animals, in order to assess their impact on living organisms after a Long Term and Low Level Exposure (LLE). Both nuclear reactions nat Ir(p,xn) and nat Os(α,xn) were investigated in the energy range up to 45 MeV for protons and 38 MeV for alpha-particles, in order to optimize the irradiation parameters for the production of 188,189,191 Pt. Several sets of thin- and thick-target excitation functions were determined experimentally by cyclotron irradiation at both Milano and Ispra cyclotrons. This paper reports the irradiation parameters studied and adopted and two radiochemical procedures for the separation of radio-Pt from an Os target, as well as from ruthenium, iridium and gold impurities. These procedures were used to obtain very high specific activity Pt radionuclides in No Carrier Added (NCA) form. Radionuclidic, radiochemical and chemical purity measurements were carried out by the use of several techniques like γ-spectrometry, ion-exchange radio-chromatography, atomic absorption spectrometry and neutron activation analysis. (author)

Radiochemical analysis of military nuclear facilities

International Nuclear Information System (INIS)

Bayramov, A.A.; Bayramova, S.M.

2012-01-01

Full text : Radiochemical Analysis is a branch of analytical chemistry comprising an aggregate of methods for qualitatively determining the composition and content of radioisotopes in the products of transformations. Safety and minimization of radiation impact on human and environment are important demand of operation of Military Nuclear Facilities (MNF). In accordance of recommendations of International Commission on Radiological Protection there are next objects of radiochemical analysis: 1) potential sources of radiochemical pollution; 2) environment (objects of environment, human environment including buildings, agricultural production, water, air et al.); 3) human himself (determination of dose from external and internal radiation, chemical poisoning). The chemical analysis can be carried out using, for example, the Gas Chromatography instrument whish separates chemical mixtures and identifies the components at a molecular level. It is one of the most accurate tools for analyzing environmental samples. The Gas Chromatography works on the principle that a mixture will separate into individual substances when heated. The heated gases are carried through a column with an inert gas (such as helium). As the separated substances emerge from the column opening, they flow into the Mass Spectrometry. Mass spectrometry identifies compounds by the mass of the analyte molecule. Newly developed portable Gas Chromatography and Mass Spectrometry are techniques that can be used to separate volatile organic compounds and pesticides. Other uses of Gas Chromatography, combined with other separation and analytical techniques, have been developed for radionuclides, explosive compounds such as royal demolition explosive and trinitrotoluene, and metals. So, based on the many years experience of operation of dangerous MNF, in concordance with norms of radiation and chemical safety it was considered that the tasks of the radiochemical analysis of Military Nuclear Facilities include

Determination of thorium in native gold by radiochemical neutron activation analysis

International Nuclear Information System (INIS)

Liu, Y.; Kraehenbuehl, U.

1995-01-01

Thorium concentrations in 11 native gold samples from different sources, e.g. placer gold, vein and lode gold were determined. Thorium was determined by radiochemical separation and measurement of protactinium from irradiated native gold samples. The chemical yield of the separation procedures is 90%. Other elements were measured by gamma-ray spectroscopy. The radiochemical separation procedures described in this work make accurate determination of Th concentrations in native gold at picogram concentrations possible. (orig.)

Automation of column-based radiochemical separations. A comparison of fluidic, robotic, and hybrid architectures

Energy Technology Data Exchange (ETDEWEB)

Grate, J.W.; O' Hara, M.J.; Farawila, A.F.; Ozanich, R.M.; Owsley, S.L. [Pacific Northwest National Laboratory, Richland, WA (United States)

2011-07-01

Two automated systems have been developed to perform column-based radiochemical separation procedures. These new systems are compared with past fluidic column separation architectures, with emphasis on using disposable components so that no sample contacts any surface that any other sample has contacted, and setting up samples and columns in parallel for subsequent automated processing. In the first new approach, a general purpose liquid handling robot has been modified and programmed to perform anion exchange separations using 2 mL bed columns in 6 mL plastic disposable column bodies. In the second new approach, a fluidic system has been developed to deliver clean reagents through disposable manual valves to six disposable columns, with a mechanized fraction collector that positions one of four rows of six vials below the columns. The samples are delivered to each column via a manual 3-port disposable valve from disposable syringes. This second approach, a hybrid of fluidic and mechanized components, is a simpler more efficient approach for performing anion exchange procedures for the recovery and purification of plutonium from samples. The automation architectures described can also be adapted to column-based extraction chromatography separations. (orig.)

Radiochemical methods to enhance efficiency of α-spectral measurements

International Nuclear Information System (INIS)

Silkina, G.P.; Artem'ev, O.I.

2001-01-01

The paper describes possible ways to improve a plutonium radiochemical separation technique developed in the Khlopin Radium Institute and modify it to account for the site-specific features of samples from the former Semipalatinsk test site (STS) and enhance the alpha spectrometry efficiency.The paper describes possible ways to improve a plutonium radiochemical separation technique developed in the Khlopin Radium Institute and modify it to account for the site-specific features of samples from the former Semipalatinsk test site (STS) and enhance the alpha spectrometry efficiency. (author)

Radiochemical determination and separation or total radium, 226Ra and 224Ra; Analisis Radioquimico de Radio total, Radio-226 y Radio-224

Energy Technology Data Exchange (ETDEWEB)

Suarez, J A; Gonzalez, J A; Pablo, M A. de

1987-07-01

Radiochemical purification and separation of radium has been carried out and the determination of total radium solubilized in aqueous samples has been studied assuming that all the alpha emitters of the sample have their origin in the 226Ra and elements of its desintegration chain. Also, the activities of 22Ra and 226 Ra have been evaluated separately doing a measurement after the chemical separation of the radium and another one 10 days after. (Author) 9 refs.

From SRAFAP to SISAK - rapid chemical separations in nuclear research

International Nuclear Information System (INIS)

Herrmann, G.

1988-10-01

The author gives an overview of rapid radiochemical separations, starting from the early experiments done by Rutherford up to the very sophisticated recoil fragment separations by fast on-line methods as an attempt to produce superheavy elements. Main emphasis is given to developments during the last decades and the extensive work performed by collaborators of the Nuclear Chemistry Institute at the University of Mainz. (RB)

Mercury determination in geological samples using radiochemical separation

International Nuclear Information System (INIS)

Goncalves, Cristina; Favaro, Deborah I.T.

1997-01-01

In this work, a radiochemical procedure is presented to increase the neutron activation analysis sensitivity. After irradiation, geological reference materials - Buffalo River Sediment (BRS- - NIST SRM 2704), Lake Sediment (BCR - CRM 280) and GXR-5 (USGS - AEG) - were leached with aqua regia in a Parr bomb placed in a domestic microwave oven and then bismuth diethyl dithiocarbamate was used to pre concentrate mercury by solvent extraction. This procedure eliminates the interference from 279 keV Se-75 photopeak and background radiation from 511 keV Cu-64 photopeak. (author). 15 refs., 2 figs., 1 tab

Radiochemical separation and effective dose estimation due to ingestion of 90Sr

International Nuclear Information System (INIS)

Ilic, Z.; Vidic, A.; Deljkic, D.; Sirko, D.; Zovko, E.; Samek, D.

2009-01-01

Since 2007. Institute for Public Health of Federation of Bosnia and Herzegovina-Radiation Protection Centre, within the framework of monitoring of radioactivity of environment carried out measurement of specific activity of 90 Sr content in selected food and water samples. The paper described the methods of measurement and radiochemical separation. Presented results, as average values of specific activity of 90 Sr, were used for estimation of effective dose due to ingestion of 90 Sr for 2007. and 2008. Estimated effective dose for 2007. due to ingestion of 90 Sr for adults was 1,36 μSv and 2,03 μSv for children (10 year old), and for 2008. 0,67 μSv (adults) and 1,01 μSv (children 10 year old). Estimated effective doses for 2007. and 2008. are varied because of different average specific activity radionuclide 90 Sr in selected samples of food, their number, species and origin. (author) [sr

Radiochemical neutron activation analysis of gold in geochemical samples

International Nuclear Information System (INIS)

Zilliacus, R.

1983-01-01

A fast method for the radiochemical neutron activation analysis of gold in geochemical samples is described. The method is intended for samples having background concentrations of gold. The method is based on the dissolution of samples with hydrofluoric acid and aqua regia followed by the dissolution of the fluorides with boric acid and hydrochloric acid. Gold is then adsorbed on activated carbon by filtrating the solution through a thin carbon layer. The activity measurements are carried out using a Ge(Li)-detector and a multichannel analyzer. The chemical yields of the separation determined by reirradiation vary between 60 and 90%. The detection limit of the method is 0.2 ng/g gold in rock samples. USGS standard rocks and exploration reference materials are analyzed and the results are presented and compared with literature data. (author)

Procedural and developmental aspects of a multielement automatic radiochemical machine, applied to neutron irradiated biomedical samples

International Nuclear Information System (INIS)

Iyengar, G.V.

1976-06-01

This report is intended to serve as a practical guide, elaborately describing the working details and some developmental work connected with an automatic multielement radiochemical machine based on thermal neutron activation analysis using ion exchange and partition chromatography. Some of the practical aspects and personal observations after much experience with this versatile multielement method, applied to investigate the elemental composition of different biomedical matrices, are summarized. Standard reference materials are analyzed, and the data are presented with a set of gamma-spectra obtained before and after chemical separation into convenient groups suitable for gamma spectroscopy. The samples analyzed included various human and animal tissues, body fluids, IAEA biological standard reference materials, and samples from the WHO/IAEA project on 'Trace elements in relation to cardiovascular diseases'. Simplified modifications of the radiochemical processing, suitable for fast and routine analysis of clinical samples have also been discussed. (orig.) [de

Development of a rapid radiochemical procedure for the separation of /sup 235m/U from 239Pu

International Nuclear Information System (INIS)

Attrep, M. Jr.; Efurd, D.W.; Roensch, F.R.

1987-01-01

We have developed a rapid radiochemical procedure for the isolation and purification of /sup 235m/U (t/sub 1/2/ = 26 minutes) from 239 Pu samples up to 250 mg. Purpose of developing the procedure was to measure the thermal neutron fission cross section of the isomeric meta state of 235 U. We used rapid small-scale anion exchange columns that absorbed uranium in concentrated HBr but did not absorb plutonium. Uranium was easily eluted with very dilute HF. The separation time required 25 to 35 minutes. We were able to attain a separation factor of uranium from plutonium of approximately 1 x 10 10 with samples ranging from 1 x 10 10 to 3 x 10 11 . The ratio of the fission cross sections for the meta to ground state was measured to be 1.42. 4 figs., 1 tab

Green methods for the radiochemical separations of no-carrier-added 61Cu, 62Zn from 7Li irradiated cobalt target

International Nuclear Information System (INIS)

Moumita Maiti; Kaustab Ghosh; Susanta Lahiri

2015-01-01

A nat Co target was irradiated with 47 MeV 7 Li beam to produce no-carrier-added 61 Cu, 62 Zn in the target matrix. Two new green radiochemical methods were developed for separation of 61 Cu and 62 Zn from the target matrix, (i) liquid-liquid extraction (LLX) technique using room temperature ionic liquid (RTIL) 1-butyl-3-methylimidazolium hexafluorophosphate ([C 4 mim][PF 6 ]) and ammonium pyrrolidinedithiocarbamate (APDC) (ii) adsorption on calcium alginate beads. (author)

Radiochemical determination of zirconium by inductively coupled plasma mass spectrometry (ICPMS)

International Nuclear Information System (INIS)

Oliveira, Thiago C.; Oliveira, Arno Heeren de

2013-01-01

The zirconium isotope 93 Zr is a long-lived pure β-particle-emitting radionuclide thus occurring as one of the radionuclides found in nuclear reactors. It's produced from 235 U fission and from 92 Zr neutron activation. Due to its long half-life, 93 Zr is one of the interest radionuclides for assessment studies performance of waste storage or disposal. Measurement of 93 Zr is difficult owing to its trace level concentration and its low activity in nuclear wastes and further because its certified standards are not frequently available. The aim of this work was to apply a selective radiochemical separation methodology for 93 Zr determination in nuclear waste and analyze it by Inductively Coupled Plasma Mass Spectrometry (ICPMS). To set up the zirconium radiochemical separation procedure, a zirconium tracer solution was used in order to follow the zirconium behavior during the radiochemical separation. A tracer solution containing the main interferences, Ba, Co, Eu, Fe, Mn, Nb, Ni, Sr, and Y was used in order to verify the decontamination factor during separation process. The limit of detection of 0,039 ppb was obtained for zirconium standard solutions by ICPMS. Then, the protocol will be applied to low level waste (LLW) and intermediate level waste (ILW) from nuclear power plants. (author)

Development of Radiochemical Separation Technology

Energy Technology Data Exchange (ETDEWEB)

Lee, Eil Hee; Kim, K. W.; Yang, H. B. (and others)

2007-06-15

This project of the second phase was aimed at the development of basic unit technologies for advanced partitioning, and the application tests of pre-developed partitioning technologies for separation of actinides by using a simulated multi-component radioactive waste containing Am, Np, Tc, U and so on. The goals for recovery yield of TRU, and for purity of Tc are high than 99% and about 99%, respectively. The work scopes and contents were as follows. 1). For the development of basic unit technologies for advanced partitioning. 1. Development of technologies for co-removal of TRU and for mutual separation of U and TRU with a reduction-complexation reaction. 2. Development of extraction system for high-acidity co-separation of An(+3) and Ln(+3) and its radiolytic evaluation. 3. Synthesis of extractants for the selective separation of An(+3) and its relevant extraction system development. 4. Development of a hybrid system for the recovery of noble metals and its continuous separation tests. 5. Development of electrolytic system for the decompositions of N-NO3 and N-NH3 compounds to nitrogen gas. 2). For the application test of pre-developed partitioning technologies for the separation of actinide elements in a simulated multi-component solution equivalent to HLW level. 1. Co-separation of Tc, Np and U by a (TBP-TOA)/NDD system. 2. Mutual-separation of Am, Cm and RE elements by a (Zr-DEHPA)/NDD system. All results will be used as the fundamental data for the development of advanced partitioning process in the future.

Hanford radiochemical site decommissioning demonstration program

International Nuclear Information System (INIS)

Nelson, D.C.

1971-01-01

A program is proposed for the innovation, development, and demonstration of technologies necessary to decommission the Hanford radiochemical plant area to the extent that the sites can have unrestricted public access. The five tasks selected for development and demonstration of restoration techniques were restoration of a burial ground, decommissioning of a separations plant, restoration of a separations plant waste interim storage tank farm, restoration of a liquid disposal area, and disposal of large contaminated equipment. Process development requirements are tabulated and discussed. A proposed schedule and estimated costs are given

Separation procedure for the determination of Ag, Cd, Hg and Zn in biological material by radiochemical neutron activation analysis

Energy Technology Data Exchange (ETDEWEB)

Haas, H F; Krivan, V

1986-05-01

A simple separation procedure for the determination of Ag, Au, Cd, Hg and Zn in biological material by radiochemical neutron activation analysis was developed. It enables the separation of the indicator radionuclides sup(110m)Ag, /sup 198/Au, /sup 115/Cd, /sup 203/Hg and /sup 65/Zn in a group with yields >99% and is well suited for the separation of /sup 203/Hg from /sup 75/Se and /sup 65/Zn from /sup 46/Sc. The separation of these radionuclides is often necessary because of the occurrence of instrumental interferences in the instrumental neutron activation analysis. Simultaneously, the limits of detection for Ag, Au and Cd can significantly be improved. The method is based on the decomposition of the sample in the mixture of HNO/sub 3//HCl/H/sub 2/O/sub 2/ and on the separation of Ag, Au, Cd, Hg and Zn on Dowex 1X8 from a sample solution being 1.5 M with HCl. The applicability of this method is demonstrated by the analysis of lichens and several kinds of fungi. For the experimental conditions used, the limits of detection are of the order of magnitude of 10 ng/g.

Trace analysis measurements in high-purity aluminium by means of radiochemical neutron and proton activation analysis

International Nuclear Information System (INIS)

Egger, K.P.

1987-01-01

The aim of the study consisted in the development of efficient radiochemical composite processes and activation methods for the multi-element determination of traces within the lower ng range in high-purity aluminium. More than 50 elements were determined with the help of activation with reactor neutrons; the selective separation of matrix activity (adsorption with hydrated antimony pentoxide) led to a noticeable improvement of detectability, as compared with instrumental neutron activation analysis. Further improvements were achieved with the help of radiochemical group separations in ion exchangers or with the help of the selective separation of the pure beta-emitting elements. Over 20 elements up to high atomic numbers were determined by means of activating 13 MeV protons and 23 Me protons. In this connection, improvements of the detection limit by as a factor of 10 were achieved with radiochemical separation techniques, as compared with pure instrumental proton activation analysis. (RB) [de

Proceedings of the Tripartite Seminar on Nuclear Material Accounting and Control at Radiochemical Plants

International Nuclear Information System (INIS)

1999-01-01

The problems of creation and operation of nuclear materials (NM) control and accounting systems and their components at radiochemical plants were discussed in seminar during November 2-6 of 1998. There were 63 Russian and 25 foreign participants in seminar. The seminar programme includes following sessions and articles: the aspects of State NM control and accountancy; NM control and accounting in radiochemical plants and at separate stages of reprocessing of spent nuclear fuel and irradiated fuel elements of commercial reactors; NM control and accountancy in storage facilities of radiochemical plants; NM control and accounting computerization, material balance assessment, preparation of reports; qualitative and quantitative measurements in NM control and accounting at radiochemical plants destructive analysis techniques [ru

Innovation in metrology: fast automated radiochemical separation and measurement for strontium 89 and 90

Energy Technology Data Exchange (ETDEWEB)

Augeray, C.; Galliez, K.; Mouton, M.; Tarlette, L.; Loyen, J.; Fayolle, C.; Gleizes, M. [Institut de Radioprotection et de Surete Nucleaire - IRSN (France)

2014-07-01

Measuring radioactivity in the food and for radiological monitoring of the environment around Nuclear Facilities or mining sites requires the quantification of the radioactive isotopes present in the different compartments (liquids or solids), especially of the beta emitters. Strontium 89 and 90, both pure beta emitters are radioactive isotopes of interest. Because of their toxicity and the similarity of their chemical and physical behavior with calcium, these elements may be found through the food chain. After the Fukushima accident, the necessity of quantifying quickly radioactive isotopes such as strontium 89 and 90 appeared. The technique we are going to present concerns the determination of the activity concentration of strontium 89 and 90 in water, according to the {sup 89}Sr/{sup 90}Sr ratio. It consists of two stages: the chemical separation by ionic chromatography and the measurement of the activity concentration of strontium 89 and 90 by Cerenkov Effect. The automated separation has been developed and allows isolating the isotopes of strontium in particular the radioactive ones: strontium 89 and 90. The separation can be done within one hour. It was realized from the adaptation of existing analytical chemistry equipments with on-line couplings. The protocol of separation is based on the use of ions exchange columns of Ionic chromatography not as a separation and measurement technique of the cation but only as a separation technique. At the release time of the ion to be quantified, a fraction collector allows its recovery. The test portion is then analyzed with a liquid scintillation counter (LSC). The activity concentration is measured by Cerenkov Effect on a quenched sample. The quenching is realized by applying a thin colored film on the sample vial. This color quench is used to make strontium 90 counts disappear on the LS spectrum. This way, only yttrium 90 ingrowth and strontium 89 decay are measured (E{sup 90}Sr < E{sup 89}Sr < E{sup 90}Y

The analytical of radiochemical purity of tumor receptor imaging agent 99Tcm-octreotide

International Nuclear Information System (INIS)

Wang Xufu; Zuo Shuyao; Shao Wenbo; Wang Guoming; Sun Jianwen; Zhang Qin

2003-01-01

The radiochemical purity of tumor receptor imaging agent 99 Tc m -octreotide is measured by High Pressure Liquid Chromatography (HPLC) and two systems of chromatography combining method of silver stain. The results show that the radiochemical purity of 98 Tc m -octreotide measured by both methods are effective and correct. It can separate 99 Tc m -octreotide from other radioactive compositions correctly and effectively

RAPID AUTOMATED RADIOCHEMICAL ANALYZER FOR DETERMINATION OF TARGETED RADIONUCLIDES IN NUCLEAR PROCESS STREAMS

International Nuclear Information System (INIS)

O'Hara, Matthew J.; Durst, Philip C.; Grate, Jay W.; Egorov, Oleg; Devol, Timothy A.

2008-01-01

Some industrial process-scale plants require the monitoring of specific radionuclides as an indication of the composition of their feed streams or as indicators of plant performance. In this process environment, radiochemical measurements must be fast, accurate, and reliable. Manual sampling, sample preparation, and analysis of process fluids are highly precise and accurate, but tend to be expensive and slow. Scientists at Pacific Northwest National Laboratory (PNNL) have assembled and characterized a fully automated prototype Process Monitor instrument which was originally designed to rapidly measure Tc-99 in the effluent streams of the Waste Treatment Plant at Hanford, WA. The system is capable of a variety of tasks: extraction of a precise volume of sample, sample digestion/analyte redox adjustment, column-based chemical separations, flow-through radiochemical detection and data analysis/reporting. The system is compact, its components are fluidically inter-linked, and analytical results can be immediately calculated and electronically reported. It is capable of performing a complete analytical cycle in less than 15 minutes. The system is highly modular and can be adapted to a variety of sample types and analytical requirements. It exemplifies how automation could be integrated into reprocessing facilities to support international nuclear safeguards needs

New radiochemical methods for determination of 237Np a 241Pu using extraction chromatography (Presentation)

International Nuclear Information System (INIS)

Strisovska, J.

2013-01-01

Thesis was focused on the development of a new methodology for the separation of anthropogenic transuranium radionuclides 237 Np a 241 Pu from different kinds of matrices. The analytical methods used in this study were based on extraction chromatography and were optimized according to the sample type. The proposed radiochemical procedure is a combination of two algorithms, which represent the separation of radionuclides by using extraction chromatographic sorbents TEVA resin and TRU resin supplied by Eichrom Technologies LLC. 239 Np a 237 Np were selectively captured on sorbent TEVA resin in oxidation state 4+. TRU resin was used for purification of plutonium fraction from interfering americium radionuclide. 242 Pu and 239 Np radionuclides as tracers have been used to monitor the radiochemical yields of separation. Before every radiochemical separation tracer radionuclide 239 Np was obtained by separation from the parent radionuclide 2 43 Am, which is in radioactive equilibrium to 239 Np. The average yield of chemical separation was 69,3% for 239 Np at 277 keV energy line and 65,9% at 228 keV energy line. The NPL AH-B08069 (2008) samples which consist of the mixture of alpha-radionuclides were used for the modification and optimization of separation method used for separation of Np and Pu in model samples. This method provided high radiochemical yields of 239,240 Pu (95,0 ± 3,5)% and 237 Np (87,9 ± 3,0)%.. Reliability of the method was verified by applying our modified separation procedures on reference materials IAEA-375 and IAEA-414 supplied by International Atomic Energy Agency. A good agreement between the results is obtained by this procedure and the certified values were found. Samples of contaminated soils from the area of Nuclear power plant A-1 Jaslovske Bohunice which is stored temporarily before disposal were analyzed using developed separation procedure. Specific activity of investigated radionuclides was determined in these samples. (author)

Rapid Radiochemical Methods for Asphalt Paving Material ...

Science.gov (United States)

Technical Brief Validated rapid radiochemical methods for alpha and beta emitters in solid matrices that are commonly encountered in urban environments were previously unavailable for public use by responding laboratories. A lack of tested rapid methods would delay the quick determination of contamination levels and the assessment of acceptable site-specific exposure levels. Of special concern are matrices with rough and porous surfaces, which allow the movement of radioactive material deep into the building material making it difficult to detect. This research focuses on methods that address preparation, radiochemical separation, and analysis of asphalt paving materials and asphalt roofing shingles. These matrices, common to outdoor environments, challenge the capability and capacity of very experienced radiochemistry laboratories. Generally, routine sample preparation and dissolution techniques produce liquid samples (representative of the original sample material) that can be processed using available radiochemical methods. The asphalt materials are especially difficult because they do not readily lend themselves to these routine sample preparation and dissolution techniques. The HSRP and ORIA coordinate radiological reference laboratory priorities and activities in conjunction with HSRP’s Partner Process. As part of the collaboration, the HSRP worked with ORIA to publish rapid radioanalytical methods for selected radionuclides in building material matrice

Radiochemical studies on the separation of iodine-131 and radioiodination of some organic compounds

International Nuclear Information System (INIS)

Mohamed, M.A.I.

2010-01-01

its retardation factor (R f ). The second technique is the purification of the labeled compounds by means of high pressure liquid chromatography (HPLC). On the reverse phase RP-18, column eluted with an appropriate solvent where each compound is identified by its retention time (R t ).Chapter III :It deals with the idea of separation of iodine-131 from tellurium targets using the dry distillation method. The factors affecting the production and separation of 131 I were studied such as the oven temperature; the distillation time and the sodium hydroxide concentration, the following flow sheet summarizes the production process. The quality control tests were carried out on the final product (Na 131 I). They were 99.9%, 98.7% for radionuclidic purity and radiochemical purity, respectively and the chemical purity of Te in the final radioiodine was 0.8μg/ml.

Critical evaluation of the determination of zirconium and hafnium by instrumental and radiochemical neutron activation analysis

International Nuclear Information System (INIS)

Burger, Mario; Kraehenbuehl, Urs

1991-01-01

Neutron activation analysis (instrument or radiochemical) is suitable for the determination of zirconium and hafnium in samples of geochemical origin only when sufficient attention is paid to inter-fering nuclides. The size of the necessary correction for INAA depends on the composition of the sample; this problem is discussed. The radio-chemical technique which is recommended involves separation of the samples, precipitations and anion-exchange separation. Results are given for various standard reference materials and for meteorites. (author). 12 refs.; 1 fig.; 9 tabs

Kit preparation of 153Sm-EDTMP and factors affecting radiochemical purity and stability

International Nuclear Information System (INIS)

Ferro-Flores, G.; Tendilla, J.I.; Lopez-Gomez, M.A.; Aguilar-Hernandez, F.; Gonzalez-Zavala, M.A.; Parades-Gutierrez, L.; Avila-Ramirez, E.

1996-01-01

A fast kit method was developed for the production of 153 Sm-EDTMP in two steps avoiding the use of nitric acid, evaporation and sterilization of the final solution by autoclave. Methods of analysis for the determination of chemical and radiochemical purity in the radiopharmaceutical solution were established. Factors affecting radiochemical purity and stability of the complex as the molar ratio of EDTMP/Sm, concentration of phosphate buffer and neutralization of EDTMP prior kit preparation were also analyzed. The use of this radiopharmaceutical in rabbits and patients showed selective skeletal uptake. (author). 5 refs., 4 figs., 3 tabs

Trace determination of uranium and thorium in biological samples by radiochemical neutron activation analysis

International Nuclear Information System (INIS)

Benedik, Ljudmila; Repinc, Urska; Byrne, Anthony R.; Stegnar, Peter

2002-01-01

Radiochemical neutron activation analysis (RNAA) is an excellent method for determining uranium and thorium; it offers unique possibilities for their ultratrace analysis using selective radiochemical separations. Regarding the favourably sensitive nuclear characteristics of uranium and of thorium with respect to RNAA, but the different half-lives of their induced nuclides, two different approaches were used. In the first approach uranium and thorium were determined separately via 239 U, 239 Np and 233 Pa. In the second approach these elements were 239 239 233 determined simultaneously in a single sample using U and/or Np and Pa. Isolation of induced nuclides was based on separation by extraction and/or anion exchange chromatography. Chemical yields were measured in each sample aliquot using added 235 U, 238 Np and 231 Pa radioisotopic tracers. (author)

Determination of Sr, Ba, Rb, and Cs in biological reference materials using a radiochemical NAA group separation procedure

International Nuclear Information System (INIS)

Mizera, J.; Randa, Z.

2008-01-01

Strontium, barium, rubidium, and cesium in selected, predominantly biological, reference materials (NIST 1515, 1547, 1549, 1566a, 1571, 1577b, 2704, CTA-OTL-1, and Bowen's Kale) were determined using neutron activation analysis (NAA) in two different analytical modes - instrumental NAA with epithermal neutrons (ENAA), and NAA with radiochemical group separation of Sr-Ba and Rb-Cs (RNAA). The ENAA mode was based on long-term (5 h) irradiation of samples in a Cd shielding. The RNAA procedure was based on long-term (20 h) irradiation of samples, their decomposition / dissolution by alkaline-oxidative fusion, and precipitation of Sr and Ba sulfates, and sorption of Rb and Cs onto ammonium phosphomolybdate (APM). Both methods provided element contents in the analyzed reference materials consistent with certified and/or literature values. (author)

A radiochemical technique for the determination of mercury in drinking water

International Nuclear Information System (INIS)

Ahmad, S.; Chaudhri, M.S.; Qureshi, I.H.

1982-01-01

A radiochemical method for the separation and determination of mercury in drinking water has been developed. The radionuclides of mercury formed after neutron irradiation of the sample were separated by liquid/liquid extraction using PAN and TBA mixture in chloroform from aqueous nitric acid medium. Quantitative extraction of mercury was achieved in a single step and the equilibrium was attained within five minutes. (orig.)

11th radiochemical conference

International Nuclear Information System (INIS)

Prasil, Z.

1987-01-01

The conference met in four sesions which discussed: Separation methods, Radioanalytical methods, Labelled compounds and Miscellaneous. The first session discussed extraction methods, ion exchange and chromatographic separation of radioisotopes. The second session heard papers on the application of these methods, e.g., in geochemistry, on the use of radioactive tracers in radiochemical analysis and the use of activation analysis in the determination of trace elements. The third session heard papers on the preparation of labelled organic compounds with isotopes 3 H, 14 C, radioiodine and 32 P, on the preparation of RIA kits and on the chemistry and radiopharmacology of technetium compounds. The other contributions which could not be heard in any of the three sessions discussed, e.g., the preparation of elements on the cyclotron and microtron, the production of a new 99m Tc-generator, the participation of the IAEA in processing low- and medium-level radioactive wastes, etc. (E.S.)

Evaluation of radiochemical data usability

International Nuclear Information System (INIS)

Paar, J.G.; Porterfield, D.R.

1997-04-01

This procedure provides a framework for implementation of radiochemical data verification and validation for environmental remediation activities. It has been developed through participation of many individuals currently involved in analytical radiochemistry, radiochemical validation, and validation program development throughout the DOE complex. It should be regarded as a guidance to use in developing an implementable radiochemical validation strategy. This procedure provides specifications for developing and implementing a radiochemical validation methodology flexible enough to allow evaluation of data useability for project-specific Data Quality Objectives (DQO). Data produced by analytical methods for which this procedure provides limited guidance are classified as open-quotes non-routineclose quotes radionuclides and methods, and analyses by these methods may necessitate adoption of modified criteria from this procedure

On the methodology of radiochemical neutron activation analysis of noble metals

International Nuclear Information System (INIS)

Chai, C.F.; Ma, S.L.; Mao, X.Y.; Liao, K.N.; Liu, W.C.

1986-01-01

Two different radiochemical procedures were developed: chelate ion resin exchange and amine solvent extraction. Two kinds of new Chinese chelate resins (NANKAI-3926 and BEI-5) and a new long-chain primary amine N 1923 were compared with Srafion NMRR and the tertiary amine N 235 in absorption performance of noble metals, respectively. Influences of various experimental conditions, e.g. sample digestion, acidity, equilibrium time, as well as elution of noble metals, on analytical sensitivity and chemical yield were discussed. Combining with neutron activation, the radiochemical separation procedures developed were used to determine the noble metal contents in the geological samples from Permina/Triassic boundary in South China. (author)

14th radiochemical conference. Booklet of abstracts

International Nuclear Information System (INIS)

2002-03-01

The contributions dealt with the following topics: Radionuclides in the environment, radioecology; Nuclear analytical methods; Chemistry of actinide and trans-actinide elements; Ionizing radiation in science, technology, and arts and cultural heritage preservation; Production and application of radionuclides; Separation methods, speciation; Chemistry of nuclear fuel cycle, radiochemical problems in nuclear waste management; and Nuclear methods in medicine, radiopharmaceuticals, and radiodiagnostics, labelled compounds. Of the verbal and poster presentation, 192 have been input to INIS. (P.A.)

Present status of radiochemical double β decay study (238U)

International Nuclear Information System (INIS)

Chevallier, A.; Chevallier, J.; Escoubes, B.; Schulz, N.; Sens, J.C.; Madic, C.; Maillard, C.

1989-01-01

The reasons for which the 238 U is a suitable candidate for the β β decay processes are explained. The strategy adopted for the radiochemical separation of the 234 U is given. A chemical system based on extraction chromatography is applied. The Pu IV breakthrough curves obtained at 40C during 238 Pu/ 238 U separation cycles are presented. A short description of the chromatographic facility is given. The solution adopted for the low background α spectrometer is explained

Electrochemistry as a basis for radiochemical generator systems

International Nuclear Information System (INIS)

Bentley, G.E.; Steinkruger, F.J.; Wanek, P.M.

1984-01-01

Ion exchange and solvent extraction techniques have been used extensively as the basis for radiochemical generators exploiting the differences in absorption behavior between the parent nuclide and its useful daughter nuclide. Many parent/daughter pairs of nuclides have sufficiently different polarographic half wave potentials so that their electrochemical behavior may be exploited for rapid separation of the daughter from the parent with minimal contamination of the product with the parent isotope

Cadmium determination in biological samples using neutron activation analysis with radiochemical separations

International Nuclear Information System (INIS)

Munoz A, Luis; Gras R, Nuri

2005-01-01

Chile has 7500 km of coastline on the Southern Pacific ocean,with about 4500 km of continental coastline that contains a variety of different geographical zones.This variety means that there is a great diversity of marine resources such as fish, shellfish and seaweeds. The utilization of these resources has been increasing in recent years making this sector an economically important one. The catch as of May 2002 came to 1.9 million tons and exports of the different species amounted to US$611.5 million as of April.But this important economic resource is being threatened by the technical demands imposed by importing countries, mainly the specific requirements for sanitary certification for fishery export products, depending on the markets of destination. The chemical element cadmium is one of the most strictly controlled elements due some shellfish accumulate a large amount of this element and to its high toxicity. The Chilean standard's analytical procedures for cadmium determination in hydro biological products, which must be met by laboratories that certify and control these products for export, are now being evaluated. Through its Chemical Metrology Unit, the Chilean Nuclear Energy Commission is strongly supporting this sector by preparing the secondary reference or control materials, and it has developed and implemented nuclear analytical methods for the certification of these materials, which will be used mostly in collaborative studies. This work describes the methodology developed for the determination of cadmium in biological samples, particularly in shellfish and fish. The method is based on neutron activation analysis with radiochemical separations, using the radioisotopes 115 Cd and 115m In, generated in the samples by bombarding with neutrons in a nuclear reactor. The samples were digested at 110 o C with H 2 SO 4 and H 2 O 2 and then the radioactive cadmium element was separated from the other elements present in the samples using a Bio Rad AG 2-X8

Collected radiochemical and geochemical procedures

Energy Technology Data Exchange (ETDEWEB)

Kleinberg, J [comp.

1990-05-01

This revision of LA-1721, 4th Ed., Collected Radiochemical Procedures, reflects the activities of two groups in the Isotope and Nuclear Chemistry Division of the Los Alamos National Laboratory: INC-11, Nuclear and radiochemistry; and INC-7, Isotope Geochemistry. The procedures fall into five categories: I. Separation of Radionuclides from Uranium, Fission-Product Solutions, and Nuclear Debris; II. Separation of Products from Irradiated Targets; III. Preparation of Samples for Mass Spectrometric Analysis; IV. Dissolution Procedures; and V. Geochemical Procedures. With one exception, the first category of procedures is ordered by the positions of the elements in the Periodic Table, with separate parts on the Representative Elements (the A groups); the d-Transition Elements (the B groups and the Transition Triads); and the Lanthanides (Rare Earths) and Actinides (the 4f- and 5f-Transition Elements). The members of Group IIIB-- scandium, yttrium, and lanthanum--are included with the lanthanides, elements they resemble closely in chemistry and with which they occur in nature. The procedures dealing with the isolation of products from irradiated targets are arranged by target element.

Fast analysis procedure of radiochemical coordinat uptake for methotrexate

International Nuclear Information System (INIS)

Caston, J.D.; Kamen, B.A.

1976-01-01

Under this invention, a radio-chemical analysis is submitted to determine the concentration of methotrexate or its equivalents in analysis in a biological medium. The amounts taken up of the labelled compound and the known concentrations of the unlabelled compound to be determined are radio-isotopically related to a first system containing a pre-determined amount of the labelled compound and a pre-determined amount of the unlabelled compound. In a second system, identical to the first, save that the sample of the biological medium to be analyzed takes the place of the unlabelled compound, the amount of labelled compound taken up is determined radio-isotopically. The concentration of the compound in the sample is then determined by correlation of the labelled compound uptake determined in the second system with the relation determined in the first system. The radio-isotopic relations and determinations may be made by direct and sequential analytical techniques [fr

Open Probe fast GC-MS - combining ambient sampling ultra-fast separation and in-vacuum ionization for real-time analysis.

Science.gov (United States)

Keshet, U; Alon, T; Fialkov, A B; Amirav, A

2017-07-01

An Open Probe inlet was combined with a low thermal mass ultra-fast gas chromatograph (GC), in-vacuum electron ionization ion source and a mass spectrometer (MS) of GC-MS for obtaining real-time analysis with separation. The Open Probe enables ambient sampling via sample vaporization in an oven that is open to room air, and the ultra-fast GC provides ~30-s separation, while if no separation is required, it can act as a transfer line with 2 to 3-s sample transfer time. Sample analysis is as simple as touching the sample, pushing the sample holder into the Open Probe oven and obtaining the results in 30 s. The Open Probe fast GC was mounted on a standard Agilent 7890 GC that was coupled with an Agilent 5977A MS. Open Probe fast GC-MS provides real-time analysis combined with GC separation and library identification, and it uses the low-cost MS of GC-MS. The operation of Open Probe fast GC-MS is demonstrated in the 30-s separation and 50-s full analysis cycle time of tetrahydrocannabinol and cannabinol in Cannabis flower, sub 1-min analysis of trace trinitrotoluene transferred from a finger onto a glass surface, vitamin E in canola oil, sterols in olive oil, polybrominated flame retardants in plastics, alprazolam in Xanax drug pill and free fatty acids and cholesterol in human blood. The extrapolated limit of detection for pyrene is Open Probe fast GC-MS is demonstrated in the analysis of heroin in its street drug powder. The use of Open Probe with the fast GC acting as a transfer line is demonstrated in <10-s analysis without separation of ibuprofen and estradiol. Copyright © 2017 John Wiley & Sons, Ltd. Copyright © 2017 John Wiley & Sons, Ltd.

Radiochemical procedures for determination of selected members of the uranium and thorium series

International Nuclear Information System (INIS)

Smithson, G.L.

1979-01-01

The radiochemical procedures contained in this manual are adaptations of those developed and published by many radiochemists. In many cases the identity of the originator is not clear and usually modifications in the original procedure have been made by subsequent workers. Nearly all of the basic radiochemical techniques and separations in use today were developed during the Manhattan Project and can be found in U.S.A.E.C. reports published from 1945 to 1953. This manual contains methods for the determination of Pb-210, Po-210; Ra-226, Ra-228, Th-228, Th-230 and Th-232. (auth)

A Simple Apparatus for Fast Ion Exchange Separations

Energy Technology Data Exchange (ETDEWEB)

Samsahl, K

1964-09-15

An apparatus suitable for very fast ion exchange group separations in radiochemistry has been elaborated. The apparatus which consists of a system of glass tubes with pistons driven by the same force, allows the exact adjustment of influent solutions to a long series of ion-exchange columns. The practical application of the apparatus to the simultaneous separation of six groups of trace elements in the neutron activation analysis of biological material is described.

A Simple Apparatus for Fast Ion Exchange Separations

International Nuclear Information System (INIS)

Samsahl, K.

1964-09-01

An apparatus suitable for very fast ion exchange group separations in radiochemistry has been elaborated. The apparatus which consists of a system of glass tubes with pistons driven by the same force, allows the exact adjustment of influent solutions to a long series of ion-exchange columns. The practical application of the apparatus to the simultaneous separation of six groups of trace elements in the neutron activation analysis of biological material is described

Comparison of alkali fusion and acid digestion methods for radiochemical separation of Uranium from dietary samples

International Nuclear Information System (INIS)

Kamesh Viswanathan, B.; Arunachalam, Kantha D.; Sathesh Kumar, A.; Jayakrishana, K.; Shanmugamsundaram, H.; Rao, D.D.

2014-01-01

Several methods exist for separation and measurement of uranium in dietary samples such as neutron activation analysis (NAA), alpha spectrometric determination, inductively coupled plasma mass spectrometry (ICP-MS) and fluorimetry. For qualitative determination of activity, NAA and alpha spectrometry are said to be superior to evaluate the isotopes of uranium ( 238 U, 234 U and 235 U). In case of alpha spectrometry, the samples have to undergo radiochemical analysis for separation from other elements for uranium detection. In our studies, uranium was determined in food matrices by acid digestion (AD) and alkali fusion (AF) methods. The recovery yield of uranium in food matrices was compared in order to get consistent yield. The average activity levels of 238 U and 234 U in food samples were calculated based on recovery yield of 232 U in the samples. The average recovery of 232 U in AD method was 22 ± 8% and in AF method, it was 14.9 ± 1.3%. The spread is more in AD method than the AF method from their mean. The lowest recovery of 232 U was found in AF method. This is due to the interference of other elements in the sample during electroplating. Experimental results showed that the uranium separation by AD method has better recovery than the AF method. The consistency in recovery of 232 U was better for AF method, which was lower than the AD method. However, overall for both the methods, the recovery can be termed as poor and need rigorous follow up studies for consistently higher recoveries (>50%) in these type of biological samples. There are reports indicating satisfactory recoveries of around 80% with 232 U as tracer in the food matrices

Radiochemical problems of radiation chemical synthesis in n, γ-field of nuclear reactor

International Nuclear Information System (INIS)

Mironov, V.P.; Frejdus, N.V.; Bugaenko, L.T.; Kalyazin, E.P.; Petryaev, E.P.

1981-01-01

A wide applicability of products of radiation chemical synthesis (RCS), using n, γ-irradiation, is limited by possible contamination of the latter with long-lived radioactive isotopes of chemical elements included in the composition of the reagent and compounds syntesized (chemically non-separable radionuclides - CNR). A technique of the determination of the limit accumulation CNR on the basis of radiation chemical parameters of the synthesis (radiation-chemical yield, the dose rate absorbed, singleness of purpose of RCS etc.) and radiochemical parameters of formation and accumulation of CNR (radiochemical yields of CNR in the products of radiolysis, neutron fluence, the reagent purity etc.) is suggested. The radiochemical evaluation of CNR accumulation (tritium and carbon-14), formed at the expense of activation with neutrons of chemical elements of water and organic substances, consisting of hydrogen, carbon and oxygen has shown that at relatively low yields of final products (> or approximately 3 molecules/100 eV) no accumulation of radionuclides in concentrations reaching the average admissible concentration takes place [ru

Blind speech separation system for humanoid robot with FastICA for audio filtering and separation

Science.gov (United States)

Budiharto, Widodo; Santoso Gunawan, Alexander Agung

2016-07-01

Nowadays, there are many developments in building intelligent humanoid robot, mainly in order to handle voice and image. In this research, we propose blind speech separation system using FastICA for audio filtering and separation that can be used in education or entertainment. Our main problem is to separate the multi speech sources and also to filter irrelevant noises. After speech separation step, the results will be integrated with our previous speech and face recognition system which is based on Bioloid GP robot and Raspberry Pi 2 as controller. The experimental results show the accuracy of our blind speech separation system is about 88% in command and query recognition cases.

Low temperature radio-chemical energy conversion processes

International Nuclear Information System (INIS)

Gomberg, H.J.

1986-01-01

This patent describes a radio-chemical method of converting radiated energy into chemical energy form comprising the steps of: (a) establishing a starting chemical compound in the liquid phase that chemically reacts endothermically to radiation and heat energy to produce a gaseous and a solid constituent of the compound, (b) irradiating the compound in its liquid phase free of solvents to chemically release therefrom in response to the radiation the gaseous and solid constituents, (c) physically separating the solid and gaseous phase constituents from the liquid, and (d) chemically processing the constituents to recover therefrom energy stored therein by the irradiation step (b)

A Fast Radiochemical Method for the Determination of Some Essential Trace Elements in Biology and Medicine

International Nuclear Information System (INIS)

Samsahl, K.

1964-12-01

A method has been developed for the determination with neutron-activation analysis of the following trace elements in soft biological tissues: Br, Ca, Cl, Cu, K, Mg, Mn, Mo, Na, P, Sr and Zn. The method consists in performing a short-term irradiation of the samples with a high thermal neutron flux, followed by fast chemical separations and gamma-spectrometric measurements. The chemical separations and the measurements of short-lived nuclides from a run are finished within 70 min, after the end of irradiation

A Fast Radiochemical Method for the Determination of Some Essential Trace Elements in Biology and Medicine

Energy Technology Data Exchange (ETDEWEB)

Samsahl, K

1964-12-15

A method has been developed for the determination with neutron-activation analysis of the following trace elements in soft biological tissues: Br, Ca, Cl, Cu, K, Mg, Mn, Mo, Na, P, Sr and Zn. The method consists in performing a short-term irradiation of the samples with a high thermal neutron flux, followed by fast chemical separations and gamma-spectrometric measurements. The chemical separations and the measurements of short-lived nuclides from a run are finished within 70 min, after the end of irradiation.

Radiolabeling, quality control and radiochemical purity assessment of 99mTc-HYNIC-TOC

International Nuclear Information System (INIS)

Melero, Laura T.U.H.; Araujo, Elaine B.; Mengatti, Jair

2009-01-01

Somatostatine receptors are widely expressed by several tumors, especially of the neuroendocrine origin. In vivo images of these tumors using radiolabeled somatostatine analogues became a useful clinical tool in oncology. The aim of this work was the radiolabeling of the somatostatine analogue HYNIC-TOC with 99mTc as well as the evaluation of the radiochemical stability and quality control of labeled complex. 99mTc-HYNIC-TOC was produced by labeling conditions using 20 μg of peptide, 20 mg of tricine and 10 mg of EDDA as coligands, 1110 MBq of 99mTc (99Mo-99mTc IPEN-TEC generator) and 15 μg of SnCl 2 .2H 2 O. The reaction proceeds for 10 minutes at boiling water bath. Radiochemical purity of labeled preparation was evaluated by different chromatographic systems: ITLC-SG in methanol:ammonium acetate (1:1); TLC-SG in sodium citrate buffer 0.1 N pH 5.0 and methylethylketone, and HPLC employing column C-18, 5 μm, 4.6 mm x 250 mm, UV (220 nm), radioactivity detectors, 1 mL/minute flow of acetonitrile and trifluoroacetic acid solution 0.1 %. Labeled compound has been found radiochemically stable for 5 hours and radiochemical purity was higher than 90 %. The thin layer chromatographic systems enabled the separation of radiochemical species presented in the labeled mixture as well as HPLC system. The labeling procedure studied resulted in high radiochemical yield and easy preparation. Future works include the preparation of a lyophilized reagent to make feasible the preparation of 99mTc-HYNIC-TOC at nuclear medicine services in order to study the clinical potential of the radiopharmaceutical in diagnostic and staging of neuroendocrine tumors. (author)

ARCA II - a new apparatus for fast, repetitive HPLC separations

International Nuclear Information System (INIS)

Schaedel, M.; Bruechle, W.; Jaeger, E.; Schimpf, E.; Kratz, J.V.; Scherer, U.W.; Zimmermann, H.P.

1989-04-01

The microcomputer controlled Automated Rapid Chemistry Apparatus, ARCA, is described in its newly designed version for the study of chemical properties of element 105 in aqueous solutions. This improved version, ARCA II, is adapted to the needs of fast and repetitive separations to be carried out in a chemically inert automated micro high performance liquid chromatography system. As an example, the separation of several group IIIB, IVB, and VB elements in the system triisooctylamine/hydrochloric acid within 30 s is demonstrated. Furthermore, a new method for the fast preparation of samples for α-particle spectroscopy by evaporation of the aqueous effluent with an intense light source is presented. (orig.)

Determination of radiochemical purity using gas chromatography

International Nuclear Information System (INIS)

1975-01-01

The concepts of chromatography, gas chromatography, activity, radiochemical impurity are defined; the procedure of the application of gas chromatography for detecting radiochemical purity of substances is standardized. (E.F.)

Radiochemical analysis of chlorine-36

International Nuclear Information System (INIS)

Rodriguez, M.; Pina, G.; Lara, E.

2006-01-01

The radioactive chlorine isotope, 36 Cl, decays with a half-life of 3x10 5 years by emitting a beta particle (98 %) and by electron capture. The aim of this paper is to propose a radiochemical separation method of 36 Cl from the other beta-gamma emitters present in low and medium radioactive wastes such as spent ion exchange resins and evaporator concentrates, that arise from Nuclear Power Plants and particularly in the wastes that come from decommissioning activities of graphite reactors, in order to provide data for 36 Cl inventory calculations. The separation method proposed is based on an oxidation technique where chlorine is trapped by NaOH. 36 Cl beta emissions are measured by liquid scintillation counting by the dual label technique in order to avoid the contamination produced by 14 C which is also trapped by NaOH and which is the main contaminant present in graphite samples. The sensitivity of this method is sufficient to achieve the needed thresholds for the radiological characterization of the radioactive materials to which this method can be applied. (author)

The role of high performance liquid chromatography in radiochemical/radiopharmaceutical synthesis and quality assurance

International Nuclear Information System (INIS)

Boothe, T.E.; Emran, A.M.

1990-01-01

The usefulness of HPLC in all areas of radiopharmaceutics has been demonstrated in numerous laboratories, particularly in the development of in-house radiopharmaceuticals for SPECT and PET. HPLC continues to be a powerful tool in preparation and quality assurance (QA) as illustrated in such areas as chemical and radiochemical identification; product separation and isolation; preparative scale purification; and specific activity determination. A review of established HPLC techniques in radiopharmaceutics will be presented. Examples from the literature as well as newer applications will be used in an attempt to assess and define the present-day role of HPLC in the preparation of radiochemicals and radiopharmaceuticals with emphasis on QA

Application of the spectrometric and radiochemical techniques in analyzing environmental samples from the Bulgarian Black Sea region

International Nuclear Information System (INIS)

Veleva, B.S.; Mungov, G.; Galabov, N.; Kolarova, M.; Guenchev, T.

1999-01-01

Development of the appropriate methods and techniques for marine and atmospheric radioactivity measurements in the NIMH-BAS during the last 5 years is presented. Approaches for pre-concentration of the radionuclides from the atmosphere and sea water samples followed with reliable radiochemical methods for radionuclides separation and low level counting are discussed. Dissolved radiocesium concentrations measured in a period of time starting in 1993 show some decrease with years and spatial variations probably due to the hydrophysical features of the sampling sides - the lower measured concentrations during 1995 and 1998 correspond to the lower salinity. Application of the radiochemical separation of Plutonium, Thorium, 90 Sr and Americium on the samples from the Bulgarian Black Sea coastal region is reported. (author)

Effects of colchicine on the intestinal transport of endogenous lipid. Ultrastructural, biochemical, and radiochemical studies in fasting rats

International Nuclear Information System (INIS)

Pavelka, M.; Gangl, A.

1983-01-01

The involvement of microtubules in the transepithelial transport of exogenous lipid in intestinal absorptive cells has been suggested. Using electronmicroscopic, biochemical, and radiochemical methods, researchers have studied the effects of the antimicrotubular agent colchicine on the intestinal mucosa and on the intestinal transport of endogenous lipid of rats in the fasting state. After colchicine treatment, the concentration of triglycerides in intestinal mucosa of rats fasted for 24 h doubled, and electron microscopic studies showed a striking accumulation of lipid particles in absorptive epithelial cells of the tips of jejunal villi. These findings suggest that colchicine interferes with the intestinal transepithelial transport of endogenous lipoproteins. Additional studies, using an intraduodenal pulse injection of [ 14 C]linoleic acid, showed that colchicine does not affect the uptake of fatty acids by intestinal mucosa. However, it had divergent effects on fatty acid esterification, enhancing their incorporation into triglycerides relative to phospholipids, and caused a significant accumulation of endogenous diglycerides, triglycerides, and cholesterol esters within the absorptive intestinal epithelium. Detailed ultrastructural and morphometric studies revealed a decrease of visible microtubules, and a displacement of the smooth and rough endoplasmic reticulum and Golgi apparatus. Furthermore, it is shown that after colchicine treatment, microvilli appear at the lateral plasma membrane of intestinal absorptive cells, a change not previously reported to our knowledge. Thus, our study shows that colchicine causes significant changes in enterocyte ultrastructure and colchicine perturbs the reesterification of absorbed endogenous fatty acids and their secretion in the form of triglyceride-rich lipoproteins from the enterocyte

A Fast Radiochemical Method for the Determination of Some Essential Trace Elements in Biology and Medicine

Energy Technology Data Exchange (ETDEWEB)

Samsahl, K

1966-02-15

An anion-exchange method based on fast selective sorption steps from mixtures of sulfuric, hydrobromic, and hydrochloric acid solutions has been developed for the separation of five different groups of radioactive trace elements in neutron-irradiated biological material. The separations are performed automatically with a simple proportioning pump apparatus. The apparatus allows the exact adjustment of influent solutions to the series of ion-exchange columns. The practical application of the method is described in detail. The successful use of the method is practically independent on the level of Na activity present in the sample.

Fifty years of radiochemical tracers

International Nuclear Information System (INIS)

Evans, E.A.

1992-01-01

During the past 50 years radiochemical tracers, usually in the form of isotopically labelled organic compounds, have been essential tools to further advance our knowledge at the frontiers of a great variety of scientific developments in the life sciences. This plenary lecture reviews necessarily selected highlights in the synthesis and applications of such radiochemical tracers. Included are examples where important advances, made possible by using radiochemicals, have contributed to improving the quality of life on this planet. The principal radioisotopes involved, 14 C, 3 H, 35 S, 32 P, 125 I, are all relatively safe to handle and are commercially available at maximum theoretical specific activity (carrier free). The compounds labeled with these radioisotopes are used in many fields of research which include biosynthesis and biotechnology studies, cell biology, drug metabolism, clinical research and environmental applications, and are briefly reviewed. (author). 55 refs

Radiochemical assay for determination of dihydropyrimidinase activity using reversed-phase high-performance liquid chromatography

NARCIS (Netherlands)

van Kuilenburg, A. B.; van Lenthe, H.; van Gennip, A. H.

1999-01-01

A radiochemical assay was developed to measure the activity of dihydropyrimidinase (DHP) in human liver homogenates. The method is based on the separation of radiolabeled dihydrouracil from N-carbamyl-beta-alanine by HPLC with on-line detection of radioactivity combined with detection of 14CO2 by

Radiochemical neutron activation analysis for trace elements of basic ingredients of pan

International Nuclear Information System (INIS)

Zaidi, J.H.; Arif, M.; Fatima, I; Qureshi, I.H.

2002-01-01

Extensive use of pan, by one-tenth of world's population, entails the evaluation of trace element contents in its ingredients. Radiochemical neutron activation analysis (RNAA) was developed and successfully employed to determine the concentration of 36 trace elements (essential, toxic and nonessential) in its four basic ingredients, leaf of betel pepper, betel nut, catechu and lime. The radiochemical separation methodology has significantly improved the detection limits of most of these elements due to suppression of Compton background. Base-line values of certain toxic and essential elements in these ingredients is provided. The daily intake of essential and toxic elements through pan was estimated and compared with the recommended values. The cumulative intake of Mn is four times higher than the recommended value and that of toxic elements is well below the tolerance limits. (author)

13th Radiochemical Conference. Booklet of Abstracts

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-04-01

The Conference included the following sessions: (i) Opening plenary presentations (6 contributions); (ii) Chemistry of natural radionuclides, discovery of radium and polonium (6 verbal presentations + 5 poster presentations); (iii) Radionuclides in the environment, radioecology (29 + 48); (iv) Activation analysis and other radioanalytical methods (36 + 49); (v) Ionizing radiation in science and technology (12 + 12); (vi) Chemistry of actinide and trans-actinide elements (11 + 14); (vii) Separation methods, speciation (18 + 41); (viii) Production and application of radionuclides (14 + 29); and (ix) Radiochemical problems in nuclear waste management (12 + 22). The majority of verbal presentations has been input to INIS, mostly in the form of the full authors` abstracts. (P.A.)

13th Radiochemical Conference. Booklet of Abstracts

International Nuclear Information System (INIS)

1998-04-01

The Conference included the following sessions: (i) Opening plenary presentations (6 contributions); (ii) Chemistry of natural radionuclides, discovery of radium and polonium (6 verbal presentations + 5 poster presentations); (iii) Radionuclides in the environment, radioecology (29 + 48); (iv) Activation analysis and other radioanalytical methods (36 + 49); (v) Ionizing radiation in science and technology (12 + 12); (vi) Chemistry of actinide and trans-actinide elements (11 + 14); (vii) Separation methods, speciation (18 + 41); (viii) Production and application of radionuclides (14 + 29); and (ix) Radiochemical problems in nuclear waste management (12 + 22). The majority of verbal presentations has been input to INIS, mostly in the form of the full authors' abstracts. (P.A.)

Radiolabeling, quality control and radiochemical purity assessment of {sup 99m}Tc-HYNIC-TOC

Energy Technology Data Exchange (ETDEWEB)

Melero, Laura T.U.H.; Araujo, Elaine B.; Mengatti, Jair [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2009-07-01

Somatostatine receptors are widely expressed by several tumors, especially of the neuroendocrine origin. In vivo images of these tumors using radiolabeled somatostatine analogues became a useful clinical tool in oncology. The aim of this work was the radiolabeling of the somatostatine analogue HYNIC-TOC with 99mTc as well as the evaluation of the radiochemical stability and quality control of labeled complex. 99mTc-HYNIC-TOC was produced by labeling conditions using 20 {mu}g of peptide, 20 mg of tricine and 10 mg of EDDA as coligands, 1110 MBq of 99mTc (99Mo-99mTc IPEN-TEC generator) and 15 {mu}g of SnCl{sub 2}.2H{sub 2}O. The reaction proceeds for 10 minutes at boiling water bath. Radiochemical purity of labeled preparation was evaluated by different chromatographic systems: ITLC-SG in methanol:ammonium acetate (1:1); TLC-SG in sodium citrate buffer 0.1 N pH 5.0 and methylethylketone, and HPLC employing column C-18, 5 {mu}m, 4.6 mm x 250 mm, UV (220 nm), radioactivity detectors, 1 mL/minute flow of acetonitrile and trifluoroacetic acid solution 0.1 %. Labeled compound has been found radiochemically stable for 5 hours and radiochemical purity was higher than 90 %. The thin layer chromatographic systems enabled the separation of radiochemical species presented in the labeled mixture as well as HPLC system. The labeling procedure studied resulted in high radiochemical yield and easy preparation. Future works include the preparation of a lyophilized reagent to make feasible the preparation of 99mTc-HYNIC-TOC at nuclear medicine services in order to study the clinical potential of the radiopharmaceutical in diagnostic and staging of neuroendocrine tumors. (author)

Growth of a manganese nodule from Peru Basin: a radiochemical anatomy

International Nuclear Information System (INIS)

Reyss, J.L.; Lemaitre, N.; Marchig, V.; Southon, J.R.; Nelson, D.E.; Vogel, J.S.

1985-01-01

Attempts have been made to study the entire growth history of a manganese nodule from the northern part of Peru Basin in the Pacific using radiochemical profiles of 230 Th/ 232 Th, 227 Th/ 230 Th and 10 Be/ 9 Be. Combined with the observations on Fe-Mn contents and textural variation, the radiochemical data indicate that the nodule grew more or less concentrically throughout most of its existence since it formed 1.5 my ago, receiving Mn from both bottom water and pore water. This condition appeared to have changed about 180 ky ago when the growth became asymmetric in that the top and bottom sides became fixed in their relative positions on the sea floor. Since then, the bottom side accreted with a fast rate of close to 200 mm/my, apparently fueled by the supply of diagenetically remobilized Mn in pore water from the sediment substrate. In the meantime, the topside accumulated at about 6 mm/my, a value which is in the normal range for deep-sea nodules having their Mn supplied from the hydrogenous source. (author)

Radiochemical Separation and Quantification of Tritium in Metallic Radwastes Generated from CANDU Type NPP - 13279

Energy Technology Data Exchange (ETDEWEB)

Ahn, H.J.; Choi, K.C.; Choi, K.S.; Park, T.H.; Park, Y.J.; Song, K. [Korea Atomic Energy Research Institute, P.O. Box 105, Yuseong, Daejeon, 305-330 (Korea, Republic of)

2013-07-01

As a destructive quantification method of {sup 3}H in low and intermediate level radwastes, bomb oxidation, sample oxidation, and wet oxidation methods have been introduced. These methods have some merits and demerits in the radiochemical separation of {sup 3}H radionuclides. That is, since the bomb oxidation and sample oxidation methods are techniques using heating at high temperature, the separation methods of the radionuclides are relatively simple. However, since {sup 3}H radionuclide has a property of being diffused deeply into the inside of metals, {sup 3}H which is distributed on the surface of the metals can only be extracted if the methods are applied. As an another separation method, the wet oxidation method makes {sup 3}H oxidized with an acidic solution, and extracted completely to an oxidized HTO compound. However, incomplete oxidized {sup 3}H compounds, which are produced by reactions of acidic solutions and metallic radwastes, can be released into the air. Thus, in this study, a wet oxidation method to extract and quantify the {sup 3}H radionuclide from metallic radwastes was established. In particular, a complete extraction method and complete oxidation method of incomplete chemical compounds of {sup 3}H using a Pt catalyst were studied. The radioactivity of {sup 3}H in metallic radwastes is extracted and measured using a wet oxidation method and liquid scintillation counter. Considering the surface dose rate of the sample, the appropriate size of the sample was determined and weighed, and a mixture of oxidants was added to a 200 ml round flask with 3 tubes. The flask was quickly connected to the distilling apparatus. 20 mL of 16 wt% H{sub 2}SO{sub 4} was given into the 200-ml round flask through a dropping funnel while under stirring and refluxing. After dropping, the temperature of the mixture was raised to 96 deg. C and the sample was leached and oxidized by refluxing for 3 hours. At that time, the incomplete oxidized {sup 3}H compounds were

Radiochemical study on preparation and quality control of 1-125/1-131 labelled some organic compounds for medical uses

International Nuclear Information System (INIS)

El-azoney, K.M.S.E.

1997-01-01

The main objective of this thesis is to investigate the optimum condition for the radioiodination of some organic compounds which find wide applications in nuclear medicine. Iodine-131 (T 1 /2= 8.04 d) which is of great importance in the field, are used for this purpose. long chain fatty acids such as 16-Bromo-hexadecanoic (16-brHDA) and -phenyl -fatty acids such as 15-p-iodophenyl pentadecanoic acid (p-IPPA) will be used as model substrates. 1- Labelling of 16-Br-HDA with Na 131 I. Labelling of 16-BrHDA will be investigated via the non-isotopic exchange between 16-Br HDA and Na 131 I to give 16- 131 IHDA. In order to obtain a high radiochemical yield with high radiochemical purity for the product 16- 131 IHDA, simple and fast methods will be followed. The influence of reagents concentrations, time, temperature, solvents and four quaternary ammonium salts as phase transfer catalysts with only one crown ether will be studied. The determination of reaction velocities and activation energies of catalysed systems was effected and compared with results on the dry state system. 2- Labelling of p-Ipa with Na 131 I. Radioiodination of 15-p-iodophenyl pentadecanoic acid is investigated by the nucleophilic substitution reaction via the isotopic exchange between p-Ipa and Na 131 I. As with 16-BrHDA, factors affecting the labelling yield such as reagent concentrations, solvents, reaction time, temperature and catalyst, is examine. The effect of different temperatures on the radiochemical yield of P- 131 Ipa is studied to determine the activation energy of the exchange reaction. Because of the necessity to separate the iodinated products from the starting materials, high performance liquid chromatographic techniques were applied for this purpose. 3.15 figs., 3.2 tabs., 179 refs

Radiochemical solar neutrino experiments

International Nuclear Information System (INIS)

Rich, R.; Spiro, M.

1993-01-01

This review covers the three presently running radiochemical solar neutrino experiments, namely the Chlorine, SAGE, and GALLEX experiments. The focus of the review is on a discussion of statistical consistency checks of the available data. The chlorine radiochemical experiment is conceptually simple and shows no strong indication of any statistical anomalies. It still forms the basis of the solar neutrino problem. Each of the two gallium experiments show internal statistical consistency. SAGE's recent preliminary results are consistent with the published GALLEX results. If this convergence is confirmed by a more definitive analysis, this would suggest that the combined result of the two gallium experiments, SAGE and GALLEX, be used for comparisons with theoretical expectations. 5 refs., 15 figs

Radiochemical separation of Tb-149 after tandem accelerator production

International Nuclear Information System (INIS)

Sarkar, S.R.

1996-01-01

Full text: Terbium-149 is produced by the heavy ion induced reaction of the type 142 Nd( 12 C,5n) 149 Dy→ 149 Tb. This work concerns the separation of terbium from neodymium target, and other lanthanides produced by secondary reactions on neodymium target. Firstly, anion-exchange separation is carried out at room temperature using acid-alcohol media (90% methanol-10% 5M nitric acid) as eluent. But the separation is not satisfactory. To achieve satisfactory separation, cation exchange separation is performed under pressure at room temperature using 0.1 6M α-hydroxyisobutyric acid of pH 5 as eluent. The pressure is exerted from a nitrogen gas cylinder. The simplicity and efficacy of this method for the separation of terbium are discussed in comparison with the commercially available high performance liquid chromatography system

Proceedings of the Tripartite Seminar on Nuclear Material Accounting and Control at Radiochemical Plants; Trudy trekhstoronnego seminara Uchet i kontrol' yadernykh materialov na radiokhimicheskikh ustanovkakh

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-07-01

The problems of creation and operation of nuclear materials (NM) control and accounting systems and their components at radiochemical plants were discussed in seminar during November 2-6 of 1998. There were 63 Russian and 25 foreign participants in seminar. The seminar programme includes following sessions and articles: the aspects of State NM control and accountancy; NM control and accounting in radiochemical plants and at separate stages of reprocessing of spent nuclear fuel and irradiated fuel elements of commercial reactors; NM control and accountancy in storage facilities of radiochemical plants; NM control and accounting computerization, material balance assessment, preparation of reports; qualitative and quantitative measurements in NM control and accounting at radiochemical plants destructive analysis techniques.

Radiochemical methodologies applied to analytical characterization of low and intermediate level wastes from nuclear power plants

International Nuclear Information System (INIS)

Monteiro, Roberto Pellacani G.; Júnior, Aluísio Souza R.; Kastner, Geraldo F.; Temba, Eliane S.C.; Oliveira, Thiago C. de; Amaral, Ângela M.; Franco, Milton B.

2017-01-01

The aim of this work is to present radiochemical methodologies developed at CDTN/CNEN in order to answer a program for isotopic inventory of radioactive wastes from Brazilian Nuclear Power Plants. In this program some radionuclides, 3 H, 14 C, 55 Fe, 59 Ni, 63 Ni, 90 Sr, 93 Zr, 94 Nb, 99 Tc, 129 I, 235 U, 238 U, 238 Pu, 239 + 240 Pu, 241 Pu, 242 Pu, 241 Am, 242 Cm e 243 + 244 Cm, were determined in Low Level Wastes (LLW) and Intermediate Level Wastes (ILW) and a protocol of analytical methodologies based on radiochemical separation steps and spectrometric and nuclear techniques was established. (author)

Safety assessment for TA-48 radiochemical operations

International Nuclear Information System (INIS)

1994-08-01

The purpose of this report is to document an assessment performed to evaluate the safety of the radiochemical operations conducted at the Los Alamos National Laboratory operations area designated as TA-48. This Safety Assessment for the TA-48 radiochemical operations was prepared to fulfill the requirements of US Department of Energy (DOE) Order 5481.1B, ''Safety Analysis and Review System.'' The area designated as TA-48 is operated by the Chemical Science and Technology (CST) Division and is involved with radiochemical operations associated with nuclear weapons testing, evaluation of samples collected from a variety of environmental sources, and nuclear medicine activities. This report documents a systematic evaluation of the hazards associated with the radiochemical operations that are conducted at TA-48. The accident analyses are limited to evaluation of the expected consequences associated with a few bounding accident scenarios that are selected as part of the hazard analysis. Section 2 of this report presents an executive summary and conclusions, Section 3 presents pertinent information concerning the TA-48 site and surrounding area, Section 4 presents a description of the TA-48 radiochemical operations, and Section 5 presents a description of the individual facilities. Section 6 of the report presents an evaluation of the hazards that are associated with the TA-48 operations and Section 7 presents a detailed analysis of selected accident scenarios

Testing the radiochemical purity of radiopharmaceuticals: application to 99mTc-HMPAO

International Nuclear Information System (INIS)

Ait Ben Ali, S.; Darsin, D.; Rizzo, N.; Lours, S.; De Beco, V.; Dumont, A.; Goudou-Sinha, C.; Izembart, M.; Jourdain, J.R.; Lemercier, V.; Linsker, S.; Moati, F.; Piketty, M.L.; Schlageter, M.H.; Moretti, J.L.

1997-01-01

The low stability of 99m Tc-HMPAO imposes to carry out the quality testing within the 15 minutes following the preparation. This study has the aim of comparing different methods of radiochemical purity determination (RP) of this radiopharmaceutical in order to validate a fast, reproducible, feasible technique, capable of separating the primary lipophilic 99m Tc-HMPAO (I) of impurities: hydrophilic secondary complex (II), TcO 4 - , reduced and halyards Tc. The reference technique associating two thin-layer chromatographies (TLC), 'C1' and 'C2', has been compared with a TLC 'W' technique and with liquid-liquid extraction 'E' technique: C1 - stationary phase, ITLC Silica gel/mobile phase, Butanone-2; C2 - stationary phase, ITLC Silica gel/mobile phase, 0.9% NaCl; W - stationary phase, Papier Whatman n o 1/mobile phase, Ether; E - extraction with ethyls acetate /0.9% NaCl (1/1 v/v). The 'C1' chromatography allows isolating the reduced Tc and the complex II, the 'C2' chromatography does the same with TcO 4 - but it requires too long techniques (20 min.). The 'W' and 'E' techniques are rapid, reproducible and allow to separate the complex I from the other impurities without discrimination. However, as their results depend upon the deposited quantity of sampling, an optimization and standardization of the techniques are necessary. A forth technique by chromatography on Sep-Pak column is to be evaluated

Radiochemical Analysis Methodology for uranium Depletion Measurements

Energy Technology Data Exchange (ETDEWEB)

Scatena-Wachel DE

2007-01-09

This report provides sufficient material for a test sponsor with little or no radiochemistry background to understand and follow physics irradiation test program execution. Most irradiation test programs employ similar techniques and the general details provided here can be applied to the analysis of other irradiated sample types. Aspects of program management directly affecting analysis quality are also provided. This report is not an in-depth treatise on the vast field of radiochemical analysis techniques and related topics such as quality control. Instrumental technology is a very fast growing field and dramatic improvements are made each year, thus the instrumentation described in this report is no longer cutting edge technology. Much of the background material is still applicable and useful for the analysis of older experiments and also for subcontractors who still retain the older instrumentation.

Radiochemical Processing Laboratory (RPL)

Data.gov (United States)

Federal Laboratory Consortium — The Radiochemical Processing Laboratory (RPL)�is a scientific facility funded by DOE to create and implement innovative processes for environmental clean-up and...

radiochemical study on the medically and technology radionuclides of some lanthanides

International Nuclear Information System (INIS)

Aglan, H.A.E.

2010-01-01

In this work, trials for the production of the medically and technologically interesting 139 Ce and 142 Pr radionuclides through cyclotron irradiations using protons and alpha particles were studied. The radiochemical separation of no-carrier-added cerium from proton irradiated lanthanum was studied by solvent extraction using DEE, TBP and TPPO, the latter reagent being employed for the first time for separation of radio cerium from bulk of lanthanum. Distribution coefficients of cerium and lanthanum were investigated as a function of equilibrium time and HNO 3 concentration. A mixture of 0.05 M K 2 Cr 2 O 7 and 0.1 M H 2 SO 4 was used as an oxidizing agent to improve the separation efficiency of cerium. A comparative study of the three extractants released that DEE is the best for separation of cerium from bulk of lanthanum oxide. The target was prepared by pressing. The production of 139 Ce of high radionuclidic and chemical purity via irradiation of lanthanum oxide target at MGC-20 cyclotron with protons of energy 14.5 is described. The experimental yield was found to be 153 kBq/μAh .The adsorption behaviour of La/Ce system on Dowex 50W-X8 in different media, namely, nitric acid, acetate buffer and citrate buffer was studied as a function of the concentration of nitric acid and buffer ph. In addition, in cation-exchange column chromatography experiments, three different eluants, namely, citrate buffer of ph 5.5, 0.1 M EDTA and 0.2 M α-HIBA, were employed for separation of Ce (III) from La (III). The optimum conditions for improvement of radiochemical separation of no-carrier-added 139 Ce from proton irradiated lanthanum were applied using the most suitable chelating agent 0.2 M α-HIBA. The purification of 139 Ce from macro amount of La (III) was done using two columns in a sequence. The experimental yield was found to be 200 kBq/μAh.

Analysis of the radiochemical purity of 18F-FDG by HPLC

International Nuclear Information System (INIS)

Chen Liguang; Tang Anwu; He Shanzhen; Chen Yulong

2001-01-01

The radiochemical purity (RCP) of 18 F-FDG is analyzed by HPLC. Eighty-five percent acetonitrile is used as the eluting solution. Carbon hydrate column is used as separation column. The t R of 18 F - is 6.50 min and 18 F-FDG is 9.00 min. HPLC take less time and has higher sensitivity than TLC for the same sample at the same time. So HPLC excels TLC in analyzing RCP of 18 F-FDG

Application of the radiochemical - and the direct gamma ray spectrometry method to the burnup determination of irradiated uranium oxide

International Nuclear Information System (INIS)

Cunha, I.I.L.

1979-01-01

The burn up of natural U 3 O 8 that occurs by the action of thermal neutrons was determined, using the radioisotopes 144 Ce, 137 Cs, 103 Ru, 106 Ru and 95 Zr as monitors. The determination of the burn up was made using both destructive and non-destructive methods. In the non-destructive method, the technique of direct gamma-ray spectrometry was used and the radioisotopes mentioned were simultaneously counted in a Ge-Li detector. In the radiochemical method the same radioisotopes were isolated one from the other and from all other fission products before counting. The solvent extraction technique was used for the radiochemical separation of uranium, cerium, cesium and ruthenium. To separate zirconium and niobium, adsorption in silica-gel was used. The extraction agent employed to isolate cesium was dipycrilamine and for the separation of the other radioisotopes Di-(2-Ethyl Hexyl) Phosphoric acid (HDEHP) was used. (Author) [pt

Radiochemical procedures and techniques

International Nuclear Information System (INIS)

Flynn, K.

1975-04-01

A summary is presented of the radiochemical procedures and techniques currently in use by the Chemistry Division Nuclear Chemistry Group at Argonne National Laboratory for the analysis of radioactive samples. (U.S.)

Radiochemical schemes of obtaining 89Sr and 90Y radionuclides

International Nuclear Information System (INIS)

Usarov, Z. O.

2010-03-01

Key words: strontium-89, yttrium-90, extraction and extraction-chromatographic purification of radionuclides, radiopharmaceuticals. Subjects of research: strontium-89 and yttrium-90 radionuclides and their chloride forms. Purpose of work is developing of radiochemical technologies on obtaining of 89 Sr and 90 Y on the WWR-SM reactor with high radionuclide purity. Methods of research: extraction and extraction-chromatographic methods of radionuclides separation, beta- and gamma-spectrometric methods of activity measuring. The results obtained and their novelty: Were determined the conformity to laws of Y and Sr distribution in two-phase systems TBP-HNO 3 , TBP-NH 4 NO 3 , TBP-HCI, HDEHP-NO 3 , HDEHP-NH 4 NO 3 and HDEHP-HCI. Were determined the conformity to laws of Y and Sr distribution in systems with craun ethers DB-18K-6 and DTBDB-18K-6 from water solutions of HNO 3 . Radiochemical technologies on obtaining of 89 Sr and 90 Y radionuclides including radiochemical process of yttrium target with using the systems TBP-HNO 3 and HDEHP/Teflone were developed. Practical value: the radiochemical technology of obtaining 89 Sr with high radionuclide purity was developed. The method of preparation a chloride compound of 89 SrCl 2 which is used as a drug form for preparation of 89 Sr- 'Metastron' was developed. The relatively simple method of on the way obtaining 90 Y in the reactor with high radionuclidic purity that is useful for follow using in medical practice was offered. Degree of embed and economic effectivity: the developed technologies have approbation in manufacturing conditions in Radiopreparat Enterprise of INP AS RU and were offered for receiving of domestic preparations against of import foreign analogues. The statement about using the invention by obtained patent is attached to dissertation. Field of application: the received results will be introduced in manufacture at Radiopreparat Enterprise of INP AS RU for receiving of domestic preparations

Methods for training radiochemical technicians at ORNL

International Nuclear Information System (INIS)

Parrott, J.R.; Nicol, R.G.

The training of personnel to carry out radiochemical operations at ORNL is a formidable and recurrent task since programs are constantly shifting. It is essential that provisions be made for the routine retraining of these personnel if they are to make effective contributions on a continuing basis. Training methods are described that have emerged as a result of thirty years experience in a variety of radiochemical pilot-plant programs. Emphasis is placed on training programs for technicians for the 233 U Processing Facility since essentially all aspects of radiochemical operations are encountered in this facility. These programs have included operations performed in glove boxes, hot-cell manipulator work handling high-neutron-emitting isotopes, and the entire spectrum of remote solvent extraction operations. (U.S.)

Radiochemical stability of radiopharmaceutical preparations

International Nuclear Information System (INIS)

Martins, Patricia de A.; Silva, Jose L. da; Ramos, Marcelo P.S.; Oliveira, Ideli M. de; Felgueiras, Carlos F.; Herrerias, Rosana; Zapparoli Junior, Carlos L.; Mengatti, Jair; Fukumori, Neuza T.O.; Matsuda, Margareth M.N.

2011-01-01

The 'in vitro' stability studies of the radiopharmaceutical preparations are an essential requirement for routine practice in nuclear medicine and are an important parameter for evaluating the quality, safety and efficacy required for the sanitary registration of pharmaceutical products. Several countries have published guidelines for the evaluation of pharmaceutical stability. In Brazil, the stability studies should be conducted according to the Guide for Conducting Stability Studies published in the Resolution-RE n. 1, of 29th July 2005. There are also for radiopharmaceutical products, two specific resolutions: RDC-63 regulates the Good Manufacturing Practices for Radiopharmaceuticals and RDC-64 provides the Registration of Radiopharmaceuticals, both published on the 18th December 2009. The radiopharmaceutical stability is defined as the time during which the radioisotope can be safely used for the intended purpose. The radiochemical stability can be affected by a variety of factors, including storage temperature, amount of radioactivity, radioactive concentration, presence or absence of antioxidants or other stabilizing agents. The radiochemical stability studies must be established under controlled conditions determined by the effective use of the product. The aim of this work was to evaluate the radiochemical stability of labeled molecules with 131 I, 123 I, 153 Sm, 18 F, 51 Cr, 177 Lu and 111 In as well as 67 Ga and 201 Tl radiopharmaceuticals. Radiochemical purity was evaluated after production and in the validity period, with the maximum activity and in the recommended storage conditions. The analyses were carried out by thin-layer silica gel plate, paper chromatography and gel chromatography. The experimental results showed to be in accordance with the specified limits for all the analysed products. (author)

Obtention process of phosphorus 32 starting from commercial sulfur and design and construction of the radiochemical separation prototype; Proceso de obtencion de fosforo-32 a partir de azufre comercial y diseno y construccion del prototipo de separacion radioquimica

Energy Technology Data Exchange (ETDEWEB)

Duarte A, C.; Alanis M, J.; Gutierrez R, C. [Instituto Nacional de Investigaciones Nucleares, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

2002-07-01

In this work an obtention process of phosphorus 32 ({sup 32} P) in orthophosphoric acid form (H{sub 3}{sup 32}PO{sub 4}) is described starting from commercial sulfur. Also the design and construction of the experimental prototype used in the radiochemical separation and their results in three tests carried out is reported. (Author)

Radiochemical Solar Neutrino Experiments - Successful and Otherwise

International Nuclear Information System (INIS)

Hahn, R.L.

2008-01-01

Over the years, several different radiochemical systems have been proposed as solar neutrino detectors. Of these, two achieved operating status and obtained important results that helped to define the current field of neutrino physics: the first solar-neutrino experiment, the Chlorine Detector ( 37 Cl) that was developed by chemist Raymond Davis and colleagues at the Homestake Mine, and the subsequent Gallium ( 71 Ga) Detectors that were operated by (a) the SAGE collaboration at the Baksan Laboratory and (b) the GALLEX/GNO collaborations at the Gran Sasso National Laboratory. These experiments have been extensively discussed in the literature and in many previous International Neutrino Conferences. In this paper, I present important updates to the results from SAGE and GALLEX/GNO. I also review the principles of the radiochemical detectors and briefly describe several different detectors that have been proposed. In light of the well-known successes that have been subsequently obtained by real-time neutrino detectors such as Kamiokande, Super-Kamiokande, SNO, and KamLAND, I do not anticipate that any new radiochemical neutrino detectors will be built. At present, only SAGE is still operating; the Chlorine and GNO radiochemical detectors have been decommissioned and dismantled

Radiochemical solar neutrino experiments, 'successful and otherwise'

International Nuclear Information System (INIS)

Hahn, Richard L

2008-01-01

Over the years, several different radiochemical systems have been proposed as solar neutrino detectors. Of these, two achieved operating status and obtained important results that helped to define the current field of neutrino physics: the first solar-neutrino experiment, the Chlorine Detector ( 37 Cl) that was developed by chemist Raymond Davis and colleagues at the Homestake Mine, and the subsequent Gallium ( 71 Ga) Detectors that were operated by (a) the SAGE collaboration at the Baksan Laboratory and (b) the GALLEX/GNO collaborations at the Gran Sasso National Laboratory. These experiments have been extensively discussed in the literature and in many previous International Neutrino Conferences. In this paper, I present important updates to the results from SAGE and GALLEX/GNO. I also review the principles of the radiochemical detectors and briefly describe several different detectors that have been proposed. In light of the well-known successes that have been subsequently obtained by real-time neutrino detectors such as Kamiokande, Super-Kamiokande, SNO, and KamLAND, I do not anticipate that any new radiochemical neutrino detectors will be built. At present, only SAGE is still operating; the Chlorine and GNO radiochemical detectors have been decommissioned and dismantled.

Continuous radiochemical analysis of fission products in a nuclear reactor water coolant

International Nuclear Information System (INIS)

Moskvin, L.N.; Zakharov, L.K.; Leont'ev, G.G.; Mel'nikov, V.A.; Orlenkov, I.S.; Slutskij, G.K.

1975-01-01

Method for continuous radiochemical analysis of I, Cs, Ba, Sr and Ce isotopes in a reactor water heat-transfer agent was developed. A continuous two-dimensional chromatographic process of complex mixtures separation of substances proved to be feasible on several parallel sorbent layers, which moved at constant velocities and separated by stationary intermediate collectors. Tests on model solutions containing I, Ce, Cs and Ba isotopes and on heat-carrier samples showed quantitative separation of elements. The results were indicative of a basic possibility of using multisorbent chromatographs for continuous control of multicomponent mixtures, particularly for control of radioactive fission product compositions in water heat-transfer agents in nuclear power plants. A diagram is shown for a two-dimensional chromatographic separation of a multicomponent mixture. Also shown is a flow chart of an installation for continuous control of iodine and cesium isotope activities

Radiochemicals

International Nuclear Information System (INIS)

1980-01-01

In this catalogue those radioactive chemicals for research are listed which are produced by the Radiochemical Centre Amersham and our laboratories at Brunswick. The dates given for each product can understandably only be limited within the framework of such a catalogue. Additional dates and references to application technique can be obtained from us any time. Our programme is continually updated by new products. If a compound not listed in the catalogue should be required we ask for inquiry. Our working team for special syntheses will try to produce it according to our possibilities and our requirements. (orig.) [de

RADCHEM - Radiochemical procedures for the determination of Sr, U, Pu, Am and Cm

Energy Technology Data Exchange (ETDEWEB)

Sidhu, R. [Inst. for Energy Technology (Norway)

2006-04-15

An accurate determination of radionuclides from various sources in the environment is essential for assessment of the potential hazards and suitable countermeasures both in case of accidents, authorised release and routine surveillance. Reliable radiochemical separation and detection techniques are needed for accurate determination of alpha and beta emitters. Rapid analytical methods are needed in case of an accident for early decision-making. The objective of this project has been to compare and evaluate radiochemical procedures used at Nordic laboratories for the determination of strontium, uranium, plutonium, americium and curium. To gather detailed information on the procedures in use, a questionnaire regarding various aspects of radionuclide determination was developed and distributed to all (sixteen) relevant laboratories in the Nordic countries. The response and the procedures used by each laboratory were then discussed between those who answered the questionnaire. This report summaries the findings and gives recommendation on suitable practice. (au)

RADCHEM - Radiochemical procedures for the determination of Sr, U, Pu, Am and Cm

International Nuclear Information System (INIS)

Sidhu, R.

2006-04-01

An accurate determination of radionuclides from various sources in the environment is essential for assessment of the potential hazards and suitable countermeasures both in case of accidents, authorised release and routine surveillance. Reliable radiochemical separation and detection techniques are needed for accurate determination of alpha and beta emitters. Rapid analytical methods are needed in case of an accident for early decision-making. The objective of this project has been to compare and evaluate radiochemical procedures used at Nordic laboratories for the determination of strontium, uranium, plutonium, americium and curium. To gather detailed information on the procedures in use, a questionnaire regarding various aspects of radionuclide determination was developed and distributed to all (sixteen) relevant laboratories in the Nordic countries. The response and the procedures used by each laboratory were then discussed between those who answered the questionnaire. This report summaries the findings and gives recommendation on suitable practice. (au)

Radiochemical determination of 210 Pb and 226Ra in petroleum sludges and scales

International Nuclear Information System (INIS)

Araujo, Andressa Arruda de

2005-01-01

The oil extraction and production, both onshore and offshore, can generate different types of residues, such as sludge, that is deposited in the water/oil separators, valves and storage tanks and scales, which form i the inner surface of ducts and equipment. Analyses already carried out through gamma spectrometry indicated the existence of high radioisotope concentration. However, radionuclides emitting low-energy gamma-rays, such as 210 Pb, are hardly detected by that technique. Consequently, there is a need to test alternative techniques to determine this and other radionuclides from the 238 U series. This work, therefore, focuses on the radiochemical determination of the concentration of 210 Pb, and 226 Ra in samples of sludge and scale from the oil processing stations of the UN-SEAL, a PETROBRAS unit responsible for the exploration and production of petroleum in Sergipe and Alagoas. The sludge and scale samples went through a preliminary process of extraction of oil, in order to separate the solid phase, where the largest fraction of the radioactivity is concentrated. After oil removal, the samples were digested using alkaline fusion as an option for dissolution. Finally, their activity concentration was determined for the samples of sludge and scales, using and alternative radiochemical method, which is based on ionic exchange. The activity concentration found for 210 Pb varied from 1,14 to 507,3 kBq kg -1 . The values for 226 Ra were higher, varying from 4,36 to 3.445 kBq kg -1 . The results for 226 Ra were then compared with the ones found for the same samples of sludge and scales using gamma spectrometry. The results of the comparison confirm the efficiency of the methodology used int hi work, that is, radiochemical determination by means of ionic exchange. (author)

Radiochemical analysis of a wide range of 131I activities in water and milk using well-type germanium detector

International Nuclear Information System (INIS)

Xin Li; Bradt, C.J.; Umme-Farzana Syed; Abdul Bari; Torres, M.A.; Kimi Nishikawa; Khan, A.J.; Menia, T.A.; Semkow, T.M.; University at Albany, State University of New York, Rensselaer, NY

2017-01-01

We report a study of a fast radiochemical method to determine the activity of 131 I via the radiochemical recovery obtained with a 129 I tracer. Previous methods were valid for low levels of 131 I activities. In the new method, we developed a correction using the 29.7-keV X-ray peak from Xe, taking into consideration that this peak originates from both and 131 I decay. This enables quantitation of high levels of 131 I activity. Furthermore, for a very high 131 I activity, one can use the 39.6-keV gamma peak which is unique to 129 I. Combining both approaches enables quantitation of 131 I activities up to 200 times that of the 129 I recovery tracer. (author)

Fast and effective determination of strontium-90 in high volumes water samples

International Nuclear Information System (INIS)

Basarabova, B.; Dulanska, S.

2014-01-01

A simple and fast method was developed for determination of 90 Sr in high volumes of water samples from vicinity of nuclear power facilities. Samples were taken from the environment near Nuclear Power Plants in Jaslovske Bohunice and Mochovce in Slovakia. For determination of 90 Sr was used solid phase extraction using commercial sorbent Analig R Sr-01 from company IBC Advanced Technologies, Inc.. Determination of 90 Sr was performed with dilute solution of HNO 3 (1.5-2 M) and also tested in base medium with NaOH. For elution of 90 Sr was used eluent EDTA with pH in range 8-9. To achieve fast determination, automation was applied, which brings significant reduction of separation time. Concentration of water samples with evaporation was not necessary. Separation was performed immediately after filtration of analyzed samples. The aim of this study was development of less expensive, time unlimited and energy saving method for determination of 90 Sr in comparison with conventional methods. Separation time for fast-flow with volume of 10 dm 3 of water samples was 3.5 hours (flow-rate approximately 3.2 dm 3 / 1 hour). Radiochemical strontium yield was traced by using radionuclide 85 Sr. Samples were measured with HPGe detector (High-purity Germanium detector) at energy E φ = 514 keV. By using Analig R Sr-01 yields in range 72 - 96 % were achieved. Separation based on solid phase extraction using Analig R Sr-01 employing utilization of automation offers new, fast and effective method for determination of 90 Sr in water matrix. After ingrowth of yttrium samples were measured by Liquid Scintillation Spectrometer Packard Tricarb 2900 TR with software Quanta Smart. (authors)

The radiochemical purity of radiotracers as the criterion of their usefulness in investigations of hydrocarbons distillation

International Nuclear Information System (INIS)

Kolaczkowski, M.

1976-01-01

Among numerous analytic techniques of separation and analysis of radioactive products gas radiochromatography has proved to be particularly suitable. Organic bromides labelled with 82 Br-radionuclide are investigated. The analytic gas chromatographs equipped with appropriately constructed radiochromatographic attachments are used. The results of radiochemical purity determination of radiotracers are compared for various techniques. (author)

Radiochemical procedure for the determination of plutonium isotopes in powdered milk

International Nuclear Information System (INIS)

Taddei, M.H.T.; Silva, N.C.

2006-01-01

A radiochemical procedure for the determination of alpha-emitting isotopes of plutonium in powdered milk is proposed. The procedure involves sample dissolution (by HNO 3 and HClO 4 ), separation by ionic-exchange resin, electrodeposition and alpha-spectroscopy. In order to determine the chemical recovery, 242 Pu was employed as a tracer. A reference material (Marine Sediment IAEA 135) was analyzed to validate such procedure, and to show its reliability. Afterwards, some powdered milk, produced for international trade, was analyzed and chemical recovery was found to be around 95%. (author)

Radioactive preparations. Determination of radiochemical purity by thin-layer chromatography

International Nuclear Information System (INIS)

1986-01-01

The standard sets the data which must be attached to every sample, and the equipment, chemicals and auxiliary substances used in the determination of radiochemical purity of substances by chromatography. Described are preparation of the sample, the procedure of sample deposition, the development, drying and detection of the radioactive preparation. The qualitative and quantitative assessment of the radiochromatogram is described as are the calculation of radiochemical purity and the determination of the reproducibility of measurement of radiochemical purity of radioactive preparations. (E.S.)

Radiochemical methodologies applied to analytical characterization of low and intermediate level wastes from nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Monteiro, Roberto Pellacani G.; Júnior, Aluísio Souza R.; Kastner, Geraldo F.; Temba, Eliane S.C.; Oliveira, Thiago C. de; Amaral, Ângela M.; Franco, Milton B., E-mail: rpgm@cdtn.br, E-mail: reisas@cdtn.br, E-mail: gfk@cdtn.br, E-mail: esct@cdtn.br, E-mail: tco@cdtn.br, E-mail: ama@cdtn.br, E-mail: francom@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

2017-07-01

The aim of this work is to present radiochemical methodologies developed at CDTN/CNEN in order to answer a program for isotopic inventory of radioactive wastes from Brazilian Nuclear Power Plants. In this program some radionuclides, {sup 3}H, {sup 14}C, {sup 55}Fe, {sup 59}Ni, {sup 63}Ni, {sup 90}Sr, {sup 93}Zr, {sup 94}Nb, {sup 99}Tc, {sup 129}I, {sup 235}U, {sup 238}U, {sup 238}Pu, {sup 239}+{sup 240}Pu, {sup 241}Pu, {sup 242}Pu, {sup 241}Am, {sup 242}Cm e {sup 243}+{sup 244}Cm, were determined in Low Level Wastes (LLW) and Intermediate Level Wastes (ILW) and a protocol of analytical methodologies based on radiochemical separation steps and spectrometric and nuclear techniques was established. (author)

Determination of selenium in roasted beans coffee samples consumed in Algeria by radiochemical neutron activation analysis method

International Nuclear Information System (INIS)

Messaoudi, Mohammed; Begaa, Samir; Hamidatou, Lylia; Salhi, M'hamed

2018-01-01

The essential trace element selenium is a focus of attention due to its effects on human health, there being consequences of both its deficiency and excess. Due to the ultra-trace content of selenium, the neutron activation analysis method (NAA) is difficult to apply. We therefore made use of the radiochemical neutron activation analysis (RNAA) to determine Se at low level concentrations in several consumed food items in Algeria. A radiochemical procedure based on liquid-liquid separation was established in our laboratory. In this research we focused on the determination of selenium in two species of coffee: Arabica and Robusta. The accuracy of the method was assessed by analyzing the certified reference material NIST-SRM 1573a (tomato leaves). The results obtained show a selenium variation from 0.025 to 0.052 μg/g in coffee beans and an average yield of the separation of about 85%. The results of this study were compared with those obtained with samples from Brazilian, Caribbean, Indian and Kenyan coffee beans.

Use of new composite materials for the determination of Cu, Cd, Mo, As, and Sb in biological samples by radiochemical neutron activation analysis

Czech Academy of Sciences Publication Activity Database

Lučaníková, M.; Kučera, Jan; Šebesta, F.; John, J.

2006-01-01

Roč. 269, č. 2 (2006), s. 463-468 ISSN 0236-5731 R&D Projects: GA ČR(CZ) GA203/04/0943 Institutional research plan: CEZ:AV0Z10480505 Keywords : radiochemical neutron activation analysis * separation using composite materials Subject RIV: CB - Analytical Chemistry, Separation Impact factor: 0.509, year: 2006

Burn-up determination of irradiated uranium oxide by means of direct gama spectrometry and by radiochemical method

International Nuclear Information System (INIS)

Cunha, I.I.L.; Nastasi, M.J.C.; Lima, F.W.

1981-09-01

The burn-up of thermal neutrons irradiated U 3 O 8 (natural uranium) samples has been determined by using both direct gamma spectrometry and radiochemical methods and the results obtained were compared. The fission products 144 Ce, 103 Ru, 106 Ru, 137 Cs and 95 Zr were chosen as burn-up monitors. In order to isolate the radioisotopes chosen as monitors, a radiochemical separation procedure has been established, in which the solvent extraction technique was used to separate cerium, cesium and ruthenium one from the other and all of them from uranium. The separation between zirconium and niobium and of both elements from the other radioisotopes and uranium was accomplished by means of adsorption on a silica-gel column, followed by selective elution of zirconium and of niobium. When use was made of the direct gamma-ray spectrometry method, the radioactivity of each nuclide of interest was measured in presence of all others. For this purpose use was made of gamma-ray spectrometry and of a Ge-Li detector. Comparison of burn-up values obtained by both methods was made by means of Student's 't' test, and this showed that results obtained in each case are statistically equal. (Author) [pt

Radiochemical neutron activation analysis of zirconium and zirconium-niobium alloys

International Nuclear Information System (INIS)

Tashimova, F.A.; Sadikov, I.I.; Salimov, M.

2004-01-01

Full text: Zirconium and zirconium-niobium alloys are used on nuclear technology, as fuel cladding of nuclear reactors. Their nuclear-physical, mechanical and thermophysical properties are influenced them matrix and impurity composition, therefore determination of matrix and impurity content of these materials is a very important task. Neutron activation analysis is one from multielemental and high sensible techniques that are widely applied in analysis of high purity materials. Investigation of nuclear-physical characteristics of zirconium has shown that instrumental variant NAA is unusable for analysis due to high radioactivity of a matrix. Therefore it is necessary carrying out radiochemical separation of impurity radionuclides from matrix. Study of the literature datum have shown, that zirconium and niobium are very well extracted from muriatic solution with 5% tributyl phosphineoxide (TBPO) solution in toluene and 0,75 M solution of di-2-ethyl hexyl phosphoric acid (HDEHP) in cyclohexanone. Investigation of these elements extraction in these systems has shown that more effective and selective separation of matrix radionuclides is achieved in HDEHP-3M HCI system. This system is also extracted and hafnium, witch is an accompanying element of zirconium and its high content prevented determination of other impurity elements in sample. Therefore we used extraction system HDEHP-3M HCl for analysis of zirconium and zirconium-niobium alloys in chromatographic variant. By measurement of distribution profile of a matrix and of elution curve of determined elements is established, that for effective separation of impurity and matrix radionuclides there is enough chromatographic column with diameter 1 cm and height of a sorbent layer 7 cm, thus volume of elute, necessary for complete elution of determinate elements is 35-40 ml. On the basis of the carried out researches the technique of radiochemical NAA of high purity zirconium and zirconium-niobium alloy, which allows to

Radiochemical analysis of radio-nuclides in sea water collected near Bikini Atoll

Energy Technology Data Exchange (ETDEWEB)

Miyake, Y; Sugiura, Y

1955-01-01

A radiochemical analysis of sea water containing fission materials collected near Bikini Atoll in June, 1954, was performed. The sea water was boiled with hydrochloric acid, iron and lanthanum salts each 5 mg as Fe and La were added to it. They were precipitated as hydroxide, which was dissolved in hydrochloric acid and ferric chloride was extracted with ethyl ether. The remaining solution was evaporated to dryness and the residue was dissolved in hydrochloric acid. Using the latter solution the group separation was done with cation exchanger resins.

Determination of heavy metal pollutants such as Hg, Zn, Se, Cd, and Cu in aquatic environment of Thana Creek by radiochemical thermal neutron activation analysis

International Nuclear Information System (INIS)

khan, S.Z.; Shah, P.K.; Ramani Rao, V.; Turel, Z.r.; Haldar, B.C.

1984-01-01

A rapid method has been developed for the radiochemical separation of Cu, As, Se, Hg, and Zn from thermal neutron irradiated environmental samples. The concentration of the elements in the environmental samples has been ascertained by radiochemical neutron activation analysis. The accuracy, precision and sensitivity of the method has been determined. The results of the analysis indicates the location of maximum pollution of the aquatic environment and the extent of pollution in the 5 locations of Thana Creek. 1 reference, 3 tables

Instrumentation for chemical and radiochemical monitoring in nuclear power plants

International Nuclear Information System (INIS)

Nordmann, F.; Ballard, G.

2009-01-01

This article details the instrumentation implemented in French nuclear power plants for the monitoring of chemical and radiochemical effluents with the aim of limiting their environmental impact. It describes the controls performed with chemical automata for the search for drifts, anomalies or pollution in a given circuit. The operation principles of the different types of chemical automata are explained as well as the manual controls performed on samples manually collected. Content: 1 - general considerations; 2 - objectives of the chemical monitoring: usefulness of continuous monitoring with automata, transmission to control rooms and related actions, redundancy of automata; 3 - instrumentation and explanations for the main circuits: principle of chemical automata monitoring, instrumentation of the main primary circuit, instrumentation of the main secondary circuit, instrumentation of the tertiary circuit, preparation of water makeup (demineralized water), other loops, instrumentation for effluents and environment monitoring, measurement principles of chemical automata, control and maintenance of chemical automata; 4 - manual controls after sampling; 5 - radiochemical monitoring: automatized radiochemical measurements, manual radiochemical measurements; 6 - conclusion

Present status and perspective of radiochemical analysis of radionuclides in Nordic countries

DEFF Research Database (Denmark)

Hou, Xiaolin; Olsson, Mattias; Togneri, Laura

2016-01-01

Radiochemical analysis plays a critical role in the determination of pure beta and alpha emitting radionuclides for environmental monitoring, radioecology, decommissioning, nuclear forensics and geological dating. A remarkable development on radiochemical analysis has been achieved in the past...... of radionuclides, especially in Nordic countries; some requirements from nuclear industries and research organizations, as well as perspectives on the development of radiochemical analysis are discussed....

Radiochemical and instrumental neutron activation analysis - recent trends

International Nuclear Information System (INIS)

Dams, R.

1990-01-01

Recent trends of radiochemical and instrumental neutron activation analysis are discussed. Novel developments include the application of cyclic and pulsed activation, better energy resolution with hyperpure germanium detectors, and use of pulse processing systems allowing extremely high count rates of very short-lived isotopes. Further development is anticipated in the field of speciation in biological and environmental studies. Radiochemical methods have led to accurate determinations at the ng/g level. A promising future is expected for neutron activation techniques. (orig.)

15th radiochemical conference: Booklet of abstracts and conference programme

International Nuclear Information System (INIS)

John, J.; Benes, P.; Kucera, J.; Havela, L.; Bartonicek, B.; Vobecky, M.; Krizova, V.; Kopicka, K.; Prasil, Z.

2006-04-01

The conference was structured as follows: Opening plenary lectures (6 lectures); Topic 1 - radionuclides in the environment, radioecology (22 verbal presentations (VPs), 23 poster presentations (PPs)); Topic 2 - nuclear analytical methods (22 VPs, 32 PPs); Topic 3 - chemistry of actinide and transactinide elements (8 VPs, 10 PPs); Topic 4 - radiation chemistry (9 VPs, 5 PPs); Topic 5 - production and application of radionuclides (17 VPs, 6 PPs); Topic 6 - separation methods, speciation (21 VPs, 23 PPs); Topic 7 - chemistry of nuclear fuel cycle, radiochemical problems in nuclear waste management (20 VPs, 16 PPs); Topic 8 - nuclear methods in medicine, radiopharmaceuticals, and radiodiagnostics, labelled compounds (8 VPs, 7 PPs); and Panels (2 introductions). (P.A.)

Fast Mechanically Driven Daughter Cell Separation Is Widespread in Actinobacteria.

Science.gov (United States)

Zhou, Xiaoxue; Halladin, David K; Theriot, Julie A

2016-08-30

Dividing cells of the coccoid Gram-positive bacterium Staphylococcus aureus undergo extremely rapid (millisecond) daughter cell separation (DCS) driven by mechanical crack propagation, a strategy that is very distinct from the gradual, enzymatically driven cell wall remodeling process that has been well described in several rod-shaped model bacteria. To determine if other bacteria, especially those in the same phylum (Firmicutes) or with similar coccoid shapes as S. aureus, might use a similar mechanically driven strategy for DCS, we used high-resolution video microscopy to examine cytokinesis in a phylogenetically wide range of species with various cell shapes and sizes. We found that fast mechanically driven DCS is rather rare in the Firmicutes (low G+C Gram positives), observed only in Staphylococcus and its closest coccoid relatives in the Macrococcus genus, and we did not observe this division strategy among the Gram-negative Proteobacteria In contrast, several members of the high-G+C Gram-positive phylum Actinobacteria (Micrococcus luteus, Brachybacterium faecium, Corynebacterium glutamicum, and Mycobacterium smegmatis) with diverse shapes ranging from coccoid to rod all undergo fast mechanical DCS during cell division. Most intriguingly, similar fast mechanical DCS was also observed during the sporulation of the actinobacterium Streptomyces venezuelae Much of our knowledge on bacterial cytokinesis comes from studying rod-shaped model organisms such as Escherichia coli and Bacillus subtilis Less is known about variations in this process among different bacterial species. While cell division in many bacteria has been characterized to some extent genetically or biochemically, few species have been examined using video microscopy to uncover the kinetics of cytokinesis and daughter cell separation (DCS). In this work, we found that fast (millisecond) DCS is exhibited by species in two independent clades of Gram-positive bacteria and is particularly prevalent

A radiochemical NAA method for the determination of tin, barium, copper and antimony- role of tin as an indicator for gun shot residues

International Nuclear Information System (INIS)

Chattopadhyay, N.; Basu, A.K.; Tripathi, A.B.R.; Rao, M.S.; Anil Kumar, S.; Parthasarathy, R.; Mathur, P.K.

1998-01-01

Metallic tin being present as impurity and hardening agent of lead bullet/shot, is expected to play an important role in forensic ballistics in matching of bullet lead specimens for establishment of commonness of origin and also as an additional parameter for characterisation of Gun Shot Residue (GSR). 121 Sn is a suitable radioisotope for quantification of the element at ppm level if it is separated in highest radiochemical purity. A sequential Radiochemical Neutron Activation Analysis (RNAA) procedure for its simultaneous determination along with trace levels of Ba, Cu and Sb has been developed and its applications in forensic science are described. (author)

Radiochemical verification and validation in the environmental data collection process

International Nuclear Information System (INIS)

Rosano-Reece, D.; Bottrell, D.; Bath, R.J.

1994-01-01

A credible and cost effective environmental data collection process should produce analytical data which meets regulatory and program specific requirements. Analytical data, which support the sampling and analysis activities at hazardous waste sites, undergo verification and independent validation before the data are submitted to regulators. Understanding the difference between verification and validation and their respective roles in the sampling and analysis process is critical to the effectiveness of a program. Verification is deciding whether the measurement data obtained are what was requested. The verification process determines whether all the requirements were met. Validation is more complicated than verification. It attempts to assess the impacts on data use, especially when requirements are not met. Validation becomes part of the decision-making process. Radiochemical data consists of a sample result with an associated error. Therefore, radiochemical validation is different and more quantitative than is currently possible for the validation of hazardous chemical data. Radiochemical data include both results and uncertainty that can be statistically compared to identify significance of differences in a more technically defensible manner. Radiochemical validation makes decisions about analyte identification, detection, and uncertainty for a batch of data. The process focuses on the variability of the data in the context of the decision to be made. The objectives of this paper are to present radiochemical verification and validation for environmental data and to distinguish the differences between the two operations

Automated radiochemical processing for clinical PET

International Nuclear Information System (INIS)

Padgett, H.C.; Schmidt, D.G.; Bida, G.T.; Wieland, B.W.; Pekrul, E.; Kingsbury, W.G.

1991-01-01

With the recent emergence of positron emission tomography (PET) as a viable clinical tool, there is a need for a convenient, cost-effective source of the positron emitter-labeled radiotracers labeled with carbon-11, nitrogen-13, oxygen-15, and fluorine-18. These short-lived radioisotopes are accelerator produced and thus, require a cyclotron and radiochemistry processing instrumentation that can be operated 3 in a clinical environment by competant technicians. The basic goal is to ensure safety and reliability while setting new standards for economy and ease of operation. The Siemens Radioisotope Delivery System (RDS 112) is a fully automated system dedicated to the production and delivery of positron-emitter labeled precursors and radiochemicals required to support a clinical PET imaging program. Thus, the entire RDS can be thought of as an automated radiochemical processing apparatus

Development of a radiochemical neutron activation analysis procedure for determination of rhenium in biological and environmental samples at ultratrace level

Czech Academy of Sciences Publication Activity Database

Kučera, Jan; Byrne, A. R.; Mizera, Jiří; Lučaníková, M.; Řanda, Zdeněk

2006-01-01

Roč. 269, č. 2 (2006), s. 251-257 ISSN 0236-5731 R&D Projects: GA ČR(CZ) GA203/04/0943 Institutional research plan: CEZ:AV0Z10480505 Keywords : radiochemical neutron activation analysis * rhenium * biological and environmental samples Subject RIV: CB - Analytical Chemistry, Separation Impact factor: 0.509, year: 2006

Methods for training radiochemical technicians at ORNL

International Nuclear Information System (INIS)

Parrott, J.R.; Nicol, R.G.

1975-01-01

The training of personnel to carry out radiochemical operations at ORNL is a formidable and recurrent task since repetitive, production-type operations are not involved, and programs are constantly shifting. It is essential that provisions be made for the routine retraining of personnel if they are to make effective contributions on a continuing basis. The present training methods have emerged as a result of thirty years experience in a variety of radiochemical pilot-plant programs. These programs have included operations performed in glove boxes, hot-cell manipulator work handling high-neutron-emitting isotopes, and the entire spectrum of remote solvent extraction operations. Present methods of training and the results obtained are summarized

Radiochemical measurement of mass transport in sodium

International Nuclear Information System (INIS)

Cooper, M.H.; Chiang, S.H.

1976-01-01

Mass transport processes in the sodium coolant of Liquid Metal Fast Breeder Reactors (LMFBRs) are significant in determining rates of corrosion and deposition of radioactive nuclides from the fuel cladding, deposition and cold trapping of fission products from defect or failed fuel, carbon and nitrogen redistribution in the containment materials, and removal of impurities by cold trapping or hot trapping. Mass transport between rotating, concentric cylinders in molten sodium has been investigated using a unique radiochemical method. Long-lived (33 year) cesium-137, dissolved in the sodium, decays radioactively emitting a beta to barium-137m, which decays with a short half-life (2.6 minutes) emitting a gamma. Cesium is weakly adsorbed and remains in solution, while the barium is strongly adsorbed on the stainless steel surfaces. Hence, by measuring the barium-137m activity on movable stainless steel surfaces, one can calculate the mass transport to that surface. Mass transfer coefficients in sodium measured by this method are in agreement with published heat transfer correlations when the effect of the volumetric mass source is taken into account. Hence, heat transfer correlations can be confidently utilized by analogy in estimating mass transfer in liquid-metal systems

Radiochemical neutron activation analysis based multi-elemental analysis of high purity gallium

International Nuclear Information System (INIS)

Tashimova, F.A.; Sadikov, I.I; Salimov, M.I.; Zinov'ev, V.G.

2006-01-01

Full text: Gallium is one of the widely used materials in semiconductor and optoelectronics industry. Gallium is used to produce infrared detectors, piezoelectric sensors, high- and low-temperature transistors for space and defense technology. One of the most important requirements for semiconductor materials of gallium compounds is an excessive high purity for layers and films. Information on impurities (type of an impurity, concentration, character of distribution) is important as for better understanding of the physical and chemical processes taking place in formed semiconductor structures and for the 'know-how' of devices on their basis. The object of this work is to develop radiochemical neutron activation technique for analysis of high purity gallium. Irradiation of 0.1 g of gallium sample in neutron flux of 5·10 13 cm -2 s -1 for 5 hours will result in induced activity of more than 10 8 Bq, due to 72 Ga radionuclide, half-life of which is 14.1 hours. Therefore to perform instrumental NAA of gallium long period (10 day) cooling is required, and high sensitive determination of elements producing short- and long-lived radionuclides (T 1/2 72 Ga. We have studied the behavior of gallium in extraction-chromatographic system 'TBP-HCl'. The experiments have shown that higher factor of distribution (D) and capacity on gallium can be achieved when 'TBP-4M HCl' system is used. However more than 10 trace elements have high D and thus they cannot be separated from 72 Ga. To resolve the problem and increase the number of separated trace elements we have used preliminary satisfaction of chromatographic column with tellurium, which has D higher than the most of elements in 'TBP-4M HCl' system and thus suppresses extraction of elements. Distribution profile of gallium along the column and elution curve of 25 trace elements have been measured. Chemical yields of separated elements measured by using radiotracers are more than 93%. On the basis of the carried out researches

Separation and study of nuclides far from beta stability and search for new regimes of nuclear stability

International Nuclear Information System (INIS)

Skarestad, M.

1977-01-01

In radiochemical separations progress has been made in developing both discontinuous and continuous separation techniques. Outstanding examples of fast, discontinuous separations have been reported from the University of Mainz where chemical separations are performed on a subsecond time scale. However, when experiments have to be performed repeatedly, a continuous separation process delivering a steady source of short-lived species is more appropriate. Such separations are accomplished in the on-line operating solvent extraction system SISAK. The combination of this separation technique with a Gas Jet Recoil Transport (GJRT) system makes it possible to adapt the separation system to different irradiation facilities. The performance of SISAK has been illustrated through the study of short-lived rare-earth isotopes, using conventional gamma-ray spectroscopy. Following some initial test experiments at a 14 MeV neutron generator in Gothenburg the SISAK system was installed at a Philips PW 5320 neutron generator situated in the Dept. of Nuclear Chemistry, Univ. of Oslo in 1972. In the following two years the main effort was devoted to the development of the experimental separation technique although some physics results were obtained in this period. In 1974 the SISAK system was combined with a GJRT arrangement and installed at the Mainz TRIGA reactor. (JIW)

Determination of radiochemical purity and pharmacokinetic parameters of sup(99m)Tc-sulphur colloid and sup(99m)Tc-tin colloid

International Nuclear Information System (INIS)

Jovanovic, V.; Konstantinovska, D.; Milivojevic, K.; Bzenic, J.

1981-01-01

Labelling yield and radiochemical purity, higher than 95%, of sup(99m)Tc-colloid preparations were determined by using the paper chromatography method. Less than 3% of labelled citric acid, added to the preparation as a buffer solution, has been found in sup(99m)Tc-sulphur colloid. High radiochemical purity and optimum size of colloid particles has also been proved by biodistribution studies on experimental animals. The analysis performed has shown that more than 50% of sup(99m)Tc-colloid preparations excreted by urine is sup(99m)TcO - , the remaining past 50% being protein bound sup(99m)Tc. Biological half-time of excretion of the fast phase is the same for both preparations, i.e. 10 min, while for the slow component it is 120 min in sup(99m)Tc-S-colloid and 160 min in sup(99m)Tc-Sn colloid. (orig.) [de

Determination of trace amounts of uranium in silicate materials by means of neutron activation analysis involving rapid radiochemical separation

International Nuclear Information System (INIS)

Ebihara, M.; Tomura, Kenji; Masutani, M.

1987-01-01

Uranium is determined in silicate materials such as standard rocks and a meteorite by radiochemical neutron activation analysis. The gamma-ray intensity of 239 U was measured with a planar type pure germanium detector system. The obtained data are mostly consistent with the literature values. Compared with a non-destructive method, the present method was found to improve the sensitivity by at least a factor of ten. Several errors which might be involved in the authors' RNAA procedures were examined and their degrees were evaluated. (author)

Radiochemical purity determination by paper chromatography 2

International Nuclear Information System (INIS)

1975-01-01

The standard relates to the determination of radiochemical impurities in labelled compounds using paper chromatography. The basic terms are given as is the description of procedure and evaluation of chromatograms. (E.S.)

Fast Mechanically Driven Daughter Cell Separation Is Widespread in Actinobacteria

Directory of Open Access Journals (Sweden)

Xiaoxue Zhou

2016-08-01

Full Text Available Dividing cells of the coccoid Gram-positive bacterium Staphylococcus aureus undergo extremely rapid (millisecond daughter cell separation (DCS driven by mechanical crack propagation, a strategy that is very distinct from the gradual, enzymatically driven cell wall remodeling process that has been well described in several rod-shaped model bacteria. To determine if other bacteria, especially those in the same phylum (Firmicutes or with similar coccoid shapes as S. aureus, might use a similar mechanically driven strategy for DCS, we used high-resolution video microscopy to examine cytokinesis in a phylogenetically wide range of species with various cell shapes and sizes. We found that fast mechanically driven DCS is rather rare in the Firmicutes (low G+C Gram positives, observed only in Staphylococcus and its closest coccoid relatives in the Macrococcus genus, and we did not observe this division strategy among the Gram-negative Proteobacteria. In contrast, several members of the high-G+C Gram-positive phylum Actinobacteria (Micrococcus luteus, Brachybacterium faecium, Corynebacterium glutamicum, and Mycobacterium smegmatis with diverse shapes ranging from coccoid to rod all undergo fast mechanical DCS during cell division. Most intriguingly, similar fast mechanical DCS was also observed during the sporulation of the actinobacterium Streptomyces venezuelae.

Radiochemical analysis for nuclear waste management in decommissioning

International Nuclear Information System (INIS)

Hou, X.

2010-07-01

The NKS-B RadWaste project was launched from June 2009. The on-going decommissioning activities in Nordic countries and current requirements and problems on the radiochemical analysis of decommissioning waste were discussed and overviewed. The radiochemical analytical methods used for determination of various radionuclides in nuclear waste are reviewed, a book was written by the project partners Jukka Lehto and Xiaolin Hou on the chemistry and analysis of radionuclide to be published in 2010. A summary of the methods developed in Nordic laboratories is described in this report. The progresses on the development and optimization of analytical method in the Nordic labs under this project are presented. (author)

Radiochemical analysis for nuclear waste management in decommissioning

Energy Technology Data Exchange (ETDEWEB)

Hou, X. (Technical Univ. of Denmark, Risoe National Lab. for Sustainable Energy. Radiation Research Div., Roskilde (Denmark))

2010-07-15

The NKS-B RadWaste project was launched from June 2009. The on-going decommissioning activities in Nordic countries and current requirements and problems on the radiochemical analysis of decommissioning waste were discussed and overviewed. The radiochemical analytical methods used for determination of various radionuclides in nuclear waste are reviewed, a book was written by the project partners Jukka Lehto and Xiaolin Hou on the chemistry and analysis of radionuclide to be published in 2010. A summary of the methods developed in Nordic laboratories is described in this report. The progresses on the development and optimization of analytical method in the Nordic labs under this project are presented. (author)

Use of tetracycline as complexing agent in radiochemical separations

International Nuclear Information System (INIS)

Saiki, M.; Nastasi, M.J.C.; Lima, F.W.

1981-01-01

The use of the antibiotic agent tetracycline (TC) for analytical purposes in solvent extraction procedures is presented. Individual extraction curves for the lanthanides, zinc, scandium, uranium, thorium, neptunium and protactinium were obtained. Separation of those elements from one another, and of uranium from selenium, bromine, antimony, barium, tantalum and tungsten was carried out. In all cases benzyl alcohol was the diluent used to dissolve tetracycline hydrochloride. Sodium chloride was used as supporting electrolyte for the lanthanide separations and sodium perchlorate for the other elements mentioned. Stability or formation constants for the lanthanide complexes as well as for thorium complex with tetracycline were determined by using the methods of average number of ligands, the limiting value (for thorium), the two parameters and the weighted least squares. For the lanthanides, the stability constants of the complexes Ln(TC) 3 go from 9.35+-0.22 for lanthanum up to 10.84+-0.11 for lutetium. For the Th(TC) 4 complex the formation constant is equal to 24.6+-0.3. Radioisotopes of the respective elements were used as tracers for the determinations. (author)

Studies on the radiochemical separation of Ga(III) from Zn(II)

International Nuclear Information System (INIS)

Chirayil, Viju; Vimalnath, K.V.; Jagadeesan, K.C.; Thakare, S.V.; Dhami, P.S.; Jagesia, Poonam; Dakshinamoorthy, A.

2007-01-01

The 67 Ga, produced in cyclotron from zinc target is widely used in tumor imaging in the form of gallium citrate. A method to separate gallium from zinc is developed using cation exchange chromatography. Reactor produced 65 Zn and 72 Ga were used to study the separation characteristics for further applicability in cyclotron production of 67 Ga. Zinc forms a stable cationic complex with NH 3 , whereas, Gallium forms anionic gallate (Ga(OH) 4 )- at pH 9.3. Zinc is quantitatively taken up by the cation exchange resin (Tulsion T-42) in NH 4 + form, thus effecting a simple rapid one step separation between Zn and Ga. (author)

Method of determination of radiochemical purity of gallium-67 citrate injection

International Nuclear Information System (INIS)

Wang Quanji

1985-01-01

A simple method is used to compare the effect of five developing agents on the radiochemical purity of neutral products of 67 GaCit and on Rsub(f) values. Two preferable developing agents are recommended as suitable for the identification of 67 GaCit injection in its production. The effect of six pH values of different developing agents on radiochemical purity, Rsub(f) and chromatogram are compared for the neutral products. The results of the experiments show that the ascending paper chromatography with 1:2:4 pyridine/ethanol/water and 85:15 methanol/water is preferable for the determination of the radiochemical purity of 67 GaCit. The other developing agents also can be used if there are not any impurities except gallium radioisotopes

Reliability of pulse waveform separation analysis: effects of posture and fasting.

Science.gov (United States)

Stoner, Lee; Credeur, Daniel; Fryer, Simon; Faulkner, James; Lambrick, Danielle; Gibbs, Bethany Barone

2017-03-01

Oscillometric pulse wave analysis devices enable, with relative simplicity and objectivity, the measurement of central hemodynamic parameters. The important parameters are central blood pressures and indices of arterial wave reflection, including wave separation analysis (backward pressure component Pb and reflection magnitude). This study sought to determine whether the measurement precision (between-day reliability) of Pb and reflection magnitude: exceeds the criterion for acceptable reliability; and is affected by posture (supine, seated) and fasting state. Twenty healthy adults (50% female, 27.9 years, 24.2 kg/m) were tested on six different mornings: 3 days fasted, 3 days nonfasted condition. On each occasion, participants were tested in supine and seated postures. Oscillometric pressure waveforms were recorded on the left upper arm. The criterion intra-class correlation coefficient value of 0.75 was exceeded for Pb (0.76) and reflection magnitude (0.77) when participants were assessed under the combined supine-fasted condition. The intra-class correlation coefficient was lowest for Pb in seated-nonfasted condition (0.57), and lowest for reflection magnitude in the seated-fasted condition (0.56). For Pb, the smallest detectible change that must be exceeded in order for a significant change to occur in an individual was 2.5 mmHg, and for reflection magnitude, the smallest detectable change was 8.5%. Assessments of Pb and reflection magnitude are as follows: exceed the criterion for acceptable reliability; and are most reliable when participants are fasted in a supine position. The demonstrated reliability suggests sufficient precision to detect clinically meaningful changes in reflection magnitude and Pb.

A radiochemical procedure for the determination of Po-210 in environmental samples

International Nuclear Information System (INIS)

Godoy, J.M.; Schuettelkopf, H.

1980-07-01

A radiochemical procedure for the determination of Po-210 in environmental samples was developed. Soil, sediments, filter materials, plants, water and food samples can be analyzed for Po-210. Wet ashing is achieved with HNO 3 + H 2 O 2 or HCl + HNO 3 . To separate disturbing substances, a coprecipitation with Te is used for sample materials containing silica. Po-210 deposition from HCl solution on Ag platelets with other sample materials is possible directly. Deposited Po-210 is counted by α-spectrometry. For chemical yield determination Po-208 is added, yields range between 60% and 100%. A lower detection limit of about 0,002 pCi Po-210/sample is achievable. (orig./HP) [de

Improving the radiochemical purity determination of 123I-labeled metaiodobenzylguanidine

International Nuclear Information System (INIS)

Luciana Carvalheira; Paulo Bechara Dutra; Paula Fernandes de Aguiar

2014-01-01

The HPLC method originally applied at the Nuclear Engineering Institute (IEN) for the radiochemical purity determination of 123iodine labeled m-iodobenzylguanidine ( 123 I-mIBG) takes 18.5 min. The final product release also depends on this result, and to facilitate this stage, we aimed to decrease this analysis time. We also intended to use fewer toxic compounds, if feasible. The optimization approach used herein was a combination of factorial and mixture designs to study simultaneously the selected variables. Analysis time, resolution and chromatograms aspect were the measured responses. The qualitative analysis of these responses provided the best chromatographic separation conditions that were 52 mM KH 2 PO 4 in a solution of ethanol and water (1:1), applying a flow rate of 0.50 mL min -1 and C18 column (4.6 × 250 mm, 5 μm). These optimum conditions not only decreased the analysis time in 61 %, but also allowed the reduction of mobile phase toxicity. To assure reliable data, method validation was performed for these conditions. The method has proved its specificity, the detection limit found was 3.70 × 10 -4 MBq mL -1 and the quantification limit has corresponded to 1.11 × 10 -3 MBq mL -1 . Repeatability and intermediate precision has not exceeded 3 and 5 %, respectively, and the accuracy has matched the interval of 95-105 %. This new method has been routinely applied in the radiochemical purity determination of 123 I-mIBG at IEN. (author)

The magnetic monopole and the separation between fast and slow magnetic degrees of freedom.

Science.gov (United States)

Wegrowe, J-E; Olive, E

2016-03-16

The Landau-Lifshitz-Gilbert (LLG) equation that describes the dynamics of a macroscopic magnetic moment finds its limit of validity at very short times. The reason for this limit is well understood in terms of separation of the characteristic time scales between slow degrees of freedom (the magnetization) and fast degrees of freedom. The fast degrees of freedom are introduced as the variation of the angular momentum responsible for the inertia. In order to study the effect of the fast degrees of freedom on the precession, we calculate the geometric phase of the magnetization (i.e. the Hannay angle) and the corresponding magnetic monopole. In the case of the pure precession (the slow manifold), a simple expression of the magnetic monopole is given as a function of the slowness parameter, i.e. as a function of the ratio of the slow over the fast characteristic times.

The magnetic monopole and the separation between fast and slow magnetic degrees of freedom

International Nuclear Information System (INIS)

Wegrowe, J-E; Olive, E

2016-01-01

The Landau–Lifshitz–Gilbert (LLG) equation that describes the dynamics of a macroscopic magnetic moment finds its limit of validity at very short times. The reason for this limit is well understood in terms of separation of the characteristic time scales between slow degrees of freedom (the magnetization) and fast degrees of freedom. The fast degrees of freedom are introduced as the variation of the angular momentum responsible for the inertia. In order to study the effect of the fast degrees of freedom on the precession, we calculate the geometric phase of the magnetization (i.e. the Hannay angle) and the corresponding magnetic monopole. In the case of the pure precession (the slow manifold), a simple expression of the magnetic monopole is given as a function of the slowness parameter, i.e. as a function of the ratio of the slow over the fast characteristic times. (paper)

Investigation of the 168Hf electron capture decay using fast radiochemical separation

International Nuclear Information System (INIS)

Trubert, D.; Hussonnois, M.; Brillard, L.; Barci, V.; Ardisson, G.; Szeglowski, Z.; Constantinescu, O.

1995-01-01

The (EC + β + ) decay of 168 Hf, produced by the 156 Gd ( 16 O,4n) reaction, has been studied, with high efficiency HPGe coaxial detectors, using on-line measurements carried out with the RACHEL setup, built to investigate the chemical properties of transactinide elements. Off-line measurements were also carried out using catcher collection technique. Energies and intensities of 119 γ-lines are reported among which only two were known in the earlier study of Chu and Reednick. The 168 Lu level scheme built on the basis of single and γ-γ coincidence measurements, allows the interpretation of more than 79 γ-transitions, between 38 excited states reported for the first time. (orig.)

Comparison of different thin layer detection techniques to determine the radiochemical purity of radiopharmaceuticals

International Nuclear Information System (INIS)

Hammermaier, A.; Reich, E.; Boegl, W.

1985-01-01

Ten radiopharmaceuticals frequently used in clinical treatment were examined as to their radiochemical purity by paper and thin layer chromatography or electrophoresis, respectively. It is known that radiochemical impurities may result in an unnecessary exposure of the patients to be examined. Other than determining the radiochemical purity of several radiopharmaceuticals, a comparison of the different measuring methods of distributing activity on radiochromatograms or electropherograms is intended by this study. For this, the activity distribution in the developed radiochromatograms was assessed by four different measuring methods (TLC-linear analyzer, TLC-scanner with NaI(Tl) detector, TLC-scanner with gas flow counter and NaI(Tl) well-typ counter). As shown by the above analysis, only the TLC-linear analyzer and the NaI(Tl) well-typ counter (measurement of chromatograms or electropherograms cut into strips) are generally suitable methods for determining the radiochemical purity of radiochemicals, the TLC-scanner with gas flow counter is usable in most cases, while TLC-scanner with NaI(Tl) detector is yielding unsatisfactory results. (orig.) [de

Radiochemical studies on nuclear fission at Trombay

Indian Academy of Sciences (India)

227Ac to 245Cm were determined by radiochemical methods which involved ... foil, followed by direct γ counting using high resolution Ge(Li) detector was also ... the stiffness to mass asymmetric distortion decreases on either side of lead.Also ...

Radiochemical applications of insoluble sulfate columns. Analytical possibilities in the field of the fission product solutions

International Nuclear Information System (INIS)

Barrachina, M.; Sauvagnac, R.

1962-01-01

In this paper we go on with our study of the heterogeneous ion-isotopic exchange in column. At present, we apply it to determine the radiochemical composition of the raw solutions used in the industrial recuperation of the long-lived fission products. The separation of the radioelements contained in these solutions is carried out mainly by making use of small columns, 1-3 cm height, of BaSO 4 or SrSO 4 , under selected experimental conditions. These columns behave like a special type of inorganic exchangers, working by absorption or by ion-isotopic exchange depending on the cases,a nd they provide the means for the selective separation of several important fission products employing very small volumes of fixing and eluting solutions. (Author) 11 refs

Radiochemical synthesis of etomoxir

Energy Technology Data Exchange (ETDEWEB)

Abbas, Hafiz G. [Institute of Nuclear Medicine and Oncology (INMOL), New Campus Road, Lahore (Pakistan); Yunus, M. [University of the Punjab, New Campus Road, Lahore (Pakistan); Feinendegen, Ludwig E., E-mail: feinendegen@gmx.ne [Department of Nuclear Medicine, Heinrich-Heine University Duesseldorf, Wannental 45, 88131 Lindau (Germany)

2011-02-15

Sodium 2-{l_brace}6-(4-chlorophenoxy)hexyl{r_brace}oxirane-2-carboxylate (Etomoxir) inhibits transport of fatty acids via the carnitine shuttle into mitochondria of muscle cells and prevents long chain fatty acids from providing energy through {beta}-oxidation especially for muscle contraction. The objective of this synthesis is to develop a method for radioiodination of Etomoxir in order to explore its potential in diagnostic metabolic studies and molecular imaging. Thus, a method is described for the radiochemical synthesis and purification of ethyl 2-{l_brace}6-(4-[{sup 131}I]iodophenoxy)hexyl{r_brace}oxirane-2-carboxylate (3) and 2-{l_brace}6-(4-[{sup 131}I]iodo-phenoxy)hexyl{r_brace}oxirane-2-carboxylic acid (4). For the synthesis of these new agents, ethyl 2-{l_brace}6-(4-bromophenoxy)hexyl{r_brace}oxirane-2-carboxylate (1) and 2-{l_brace}6-(4-bromophenoxy)hexyl{r_brace}oxirane-2-carboxylic acid (2) were refluxed with [{sup 131}I]NaI in the presence of anhydrous acetone at a temperature of 80 {sup o}C and 90 {sup o}C for a period of 3-4 hours, respectively. The method of radiolabeling, based on the nucleophilic exchange reaction, resulted in a radiochemical yield of 43% and 67% for compounds 3 and 4, respectively. This paper reports on the labeling of etomoxir with radioiodine as {sup 124}I labeled etomoxir may be of great importance in molecular imaging.

Radiochemical methods

International Nuclear Information System (INIS)

Geary, W.J.

1986-01-01

This little volume is one of an extended series of basic textbooks on analytical chemistry produced by the Analytical Chemistry by Open Learning project in the UK. Prefatory sections explain its mission, and how to use the Open Learning format. Seventeen specific sections organized into five chaptrs begin with a general discussion of nuclear properties, types, and laws of nuclear decay and proceeds to specific discussions of three published papers (reproduced in their entirety) giving examples of radiochemical methods which were discussed in the previous chapter. Each section begins with an overview, contains one or more practical problems (called self-assessment questions or SAQ's), and concludes with a summary and a list of objectives for the student. Following the main body are answers to the SAQ's, and several tables of physical constants, SI prefixes, etc. A periodic table graces the inside back cover

Radiochemical separation of mostly short-lived neutron activation products

Czech Academy of Sciences Publication Activity Database

Kučera, Jan; Kameník, Jan; Povinec, P. P.

2017-01-01

Roč. 311, č. 2 (2017), s. 1299-1307 ISSN 0236-5731. [1st International Conference on Radioanalytical and Nuclear chemistry (RANC). Budapest, 10.04.2016-15.04.2016] R&D Projects: GA ČR(CZ) GBP108/12/G108 Institutional support: RVO:61389005 Keywords : determination * Vanadium * Iodine * Manganese * Silicon * Mercury * Selenium * Th-232 anad U-238 * SuperNEMO experiment Subject RIV: CB - Analytical Chemistry, Separation OBOR OECD: Analytical chemistry Impact factor: 1.282, year: 2016

Safety and Waste Management for SAM Radiochemical Methods

Science.gov (United States)

The General Safety and Waste Management page offers section-specific safety and waste management details for the radiochemical analytes included in EPA's Selected Analytical Methods for Environmental Remediation and Recovery (SAM).

Decontamination and decommission of a radiochemical laboratory building complex

International Nuclear Information System (INIS)

Zoubek, Norbert

2008-01-01

Full text: Handling of unsealed radioactive substances for research and development purposes in chemical or pharmaceutical industries or research centres as well as production of radioactive substances (e.g. for applications in nuclear medicine or industry) requires operation of special radiochemical laboratories. In general, operation of radiochemical laboratories is strongly regulated by the government and national authorities. The operator needs a permit related to radiological protection. In general, technical requirements for such facilities are very high. To ensure high safety standards with respect to the employees and the environment, several radiological protection measures have to be taken. These measures (for example special shielding or ventilation and waste water systems) depend on various factors, e.g. activity in use, kind of nuclides, chemical properties and volatility of substances. In order to close-down such radiochemical laboratories some radiological protection measures have to be maintained to ensure protection of both humans and the environment induced by possible residual contaminations within the facility including technical inventory. However, a later reuse of the facility as a non-radioactive facility requires removal of all radioactive contamination with respect to national regulation. Resulting radioactive wastes have to be disposed of under control of competent authorities. Based on the experience of a decontamination and decommission project for a former radiochemical laboratory complex, the main steps necessary to release such a facility are discussed. Analytical aspects of initial conditions, necessary organisational structures within the project, resources needed estimation and exploration of the radiological situation in the laboratory, elaboration of a measuring strategy and decontamination methods as well as different waste disposal routes in relation to different waste types are reported. (author)

Hanford Environmental Restoration data validation process for chemical and radiochemical analyses

International Nuclear Information System (INIS)

Adams, M.R.; Bechtold, R.A.; Clark, D.E.; Angelos, K.M.; Winter, S.M.

1993-10-01

Detailed procedures for validation of chemical and radiochemical data are used to assure consistent application of validation principles and support a uniform database of quality environmental data. During application of these procedures, it was determined that laboratory data packages were frequently missing certain types of documentation causing subsequent delays in meeting critical milestones in the completion of validation activities. A quality improvement team was assembled to address the problems caused by missing documentation and streamline the entire process. The result was the development of a separate data package verification procedure and revisions to the data validation procedures. This has resulted in a system whereby deficient data packages are immediately identified and corrected prior to validation and revised validation procedures which more closely match the common analytical reporting practices of laboratory service vendors

Proceedings of DAE-BRNS biennial symposium on emerging trends in separation science and technology

International Nuclear Information System (INIS)

Pathak, P.N.; Mohapatra, P.K.; Goswami, A.

2012-01-01

The symposium on emerging trends in separation science and technology was held during 27 February -1 March, 2012. An attempt has been made to cover a wide range of topics in the symposium including design and synthesis of solvents/resins, development of separation equipment's, separation the nuclear fuel cycle, emerging separation technologies, electrochemical and pyrochemical separations, treatment of industrial effluents, isotope separations, membrane science and technology, radiochemical separations, water treatment and recycling, bioremediation and speciation. Papers relevant to INIS are indexed separately

Advanced Aqueous Separation Systems for Actinide Partitioning

Energy Technology Data Exchange (ETDEWEB)

Nash, Kenneth L.; Clark, Sue; Meier, G Patrick; Alexandratos, Spiro; Paine, Robert; Hancock, Robert; Ensor, Dale

2012-03-21

One of the most challenging aspects of advanced processing of spent nuclear fuel is the need to isolate transuranium elements from fission product lanthanides. This project expanded the scope of earlier investigations of americium (Am) partitioning from the lanthanides with the synthesis of new separations materials and a centralized focus on radiochemical characterization of the separation systems that could be developed based on these new materials. The primary objective of this program was to explore alternative materials for actinide separations and to link the design of new reagents for actinide separations to characterizations based on actinide chemistry. In the predominant trivalent oxidation state, the chemistry of lanthanides overlaps substantially with that of the trivalent actinides and their mutual separation is quite challenging.

Application of radiochemical separation procedures to environmental and biological materials

Energy Technology Data Exchange (ETDEWEB)

Eakins, J D [UKAEA Atomic Energy Research Establishment, Harwell. Environmental and Medical Sciences Div.

1984-06-15

The measurement of low levels of radionuclides in environmental and biological materials often depends on separation of the nuclide of interest from a bulky matrix containing interfering radioelements. In such case, however sophisticated and elegant the counting technique, the quality of the final data will

Automated radiochemical synthesis and biodistribution of [11C]l-α-acetylmethadol ([11C]LAAM)

International Nuclear Information System (INIS)

Sai, Kiran Kumar Solingapuram; Fan, Jinda; Tu, Zhude; Zerkel, Patrick; Mach, Robert H.; Kharasch, Evan D.

2014-01-01

Long-acting opioid agonists methadone and l-α-acetylmethadol (LAAM) prevent withdrawal in opioid-dependent persons. Attempts to synthesize [ 11 C]-methadone for PET evaluation of brain disposition were unsuccessful. Owing, however, to structural and pharmacologic similarities, we aimed to develop [ 11 C]LAAM as a PET ligand to probe the brain exposure of long-lasting opioids in humans. This manuscript describes [ 11 C]LAAM synthesis and its biodistribution in mice. The radiochemical synthetic strategy afforded high radiochemical yield, purity and specific activity, thereby making the synthesis adaptable to automated modules. - Highlights: • Radiochemical synthesis of opioid [ 11 C]l-α-acetylmethadol (LAAM) described for the first time. • High radiochemical yield, purity and specific activity. • Easily reproducible and adaptable synthesis to any C-11 automated modules. • [ 11 C]LAAM utility as a PET radiopharmaceutical for assessing brain penetration

Planning for maintenance in radiochemical facilities [Paper No.: VB-2

International Nuclear Information System (INIS)

Balasubramanian, G.R.

1981-01-01

Reprocessing facilities in the earlier stages of development were planned mainly based on the concept of direct maintenance in view of the inherent advantage of man-machine interface and initial savings in the investment costs. With the mechanical processes finding a firm place in head-end operation and increase in down time necessary for elaborate decontamination efforts even for a minor modification has led to the review of the concept. For the same reason, the recent plants are based on the concept of harmonious blend of both direct and remote maintenance. The paper describes the planning needed from consideration of various aspects related to such concepts of maintenance during different phases of such type of facilities, highlighting some of the tools and special equipments to be developed for this purpose. A brief description of recent development in the field of remote maintenance is also given. Though the basic hot facility of reference is the one of reprocessing fast reactor fuels, the concepts and systems discussed are equally applicable to other radiochemical and radiometallurgical facilities also. (author)

Comparison of two selective separation method for 93Zr by using TRU and TEVA resins

International Nuclear Information System (INIS)

Oliveira, Thiago C.; Oliveira, Arno Heeren de

2011-01-01

The zirconium isotope 93 Zr is a long-lived pure β-particle-emitting radionuclide produced from 235 U fission and from neutron activation of the stable isotope 92 Zr and thus occurring as one of the radionuclides found in nuclear reactors. Due to its long half life, 93 Zr is one of the radionuclides of interest for the performance of assessment studies of waste storage or disposal. Measurement of 93 Zr is difficult owing to its trace level concentration and its low activity in nuclear wastes and further because its certified standards are not frequently available. The aim of this work was to compare two radiochemical procedure based on selective extraction using an anion-exchange chromatography, TRU and TEVA resins, in order to separate zirconium from the matrix and to analyze it by liquid scintillation spectrometry technique. To set up the radiochemical separation procedure for zirconium, a tracer solution of 95 Zr and its 724.19 keV γ-ray measurements by γ - spectrometry were used in order to follow the behavior of zirconium during the radiochemical separation. A tracer solution of 55 Fe, the main interference in the LSC measurements, was used in order to verify the decontamination factor during the separation process. The limit of detection of the 0.05 Bq 1 -1 was obtained for 55 Fe standard solutions by using a sample:cocktail ratio of 3:17 mL for Optiphase Hisafe 3 cocktail. (author)

Miniaturized chromatographic radiochemical procedure for 131I - MIBG

International Nuclear Information System (INIS)

Barboza, M.F. de; Pereira, N.S. de; Colturato, M.T.; Silva, C.P.G. da.

1989-12-01

Different solvents were used in paper chromatographic methods to obtain the best system in routine radiochemical control for 131 I-MIBG produced at IPEN-CNEN/SP. The dates were compared with those obtained with eletrophoresis method in buffer acetate, pH=4.5, 350V, during 40 minutes. The stability of the labeled compound store under 4 0 C was studied during 15 days. Miniaturized chromatographic procedures were established using Whatman 3MM (8x1cm) and n-butanol-:acetic acid: water (S:2:1) as a solvent. the Rf values were: 0.3 (I - ) and 1.0 (MIBG). The radiochemical purity was 99.3 and 99.2% (first day) obtained with eletrophoresis and miniaturized chromatographic procedures, respectively and, 84.7% after 15 days of its preparation. It is a rapid, practical and reproductive method. (author) [pt

Automated ion-exchange system for the radiochemical separation of the noble metals

International Nuclear Information System (INIS)

Parry, S.J.

1980-01-01

Ion-exchange separation is particularly suitable for mechanisation and automated ion exchange has been applied to the activation analysis of biological and environmental samples. In this work a system has been designed for experimental studies, which can be adapted for different modes of operation. The equipment is based on a large-volume sampler for the automatic presentation of 500 ml of liquid to a sampling probe. The sample is delivered to the ion-exchange column by means of a peristaltic pump. The purpose of this work was to automate a procedure for separating the noble metals from irradiated geological samples, for neutron-activation analysis. The process of digesting the rock sample is carried out manually in 30 min and is not suited to unattended operation. The volume of the resulting liquid sample may be 100 ml and so the manual separation step may take as long as 1.25 h per sample. The reason for automating this part of the procedure is to reduce the separation time for a group of five samples and consequently to improve the sensitivity of the analysis for radionuclides with short half-lives. This paper describes the automatic ion-exchange system and the ways in which it can be used. The mode of operation for the separation of the noble metals is given in detail. The reproducibility of the system has been assessed by repeated measurements on a standard reference matte. (author)

Synthesis of N-[methyl-11C]hydromorphone by using multivariate strategies for optimization of radiochemical yields

International Nuclear Information System (INIS)

Rimland, Annika; Bergson, Goeran; Obenius, Ulf; Sjoeberg, Stefan; Langstroem, Bengt

1987-01-01

The synthesis of N-[methyl- 11 C]hydromorphone has been performed by using [ 11 C]methyl iodide and desmethyl hydromorphone in a mixture of dimethylsulphoxide and dimethylformamide as solvent. Optimization of the radiochemical yield by varying the reaction conditions was performed by using multivariate strategies. The labelled hydromorphone was obtained in 72% radiochemical yield in the alkylation reaction with [ 11 C]-methyl iodide, counted from the end of the [ 11 C]methyl iodide synthesis. N-[Methyl- 11 C]hydromorphone was obtained as a ready injectable pharmaceutical solution with a total synthesis time of 40 min and in a 10% total radiochemical yield, with a radiochemical purity > 99.5%, according to HPLC analysis. (author)

Devising of the method for the determination of small and very small amounts of cadmium in biological materials by radiochemical version of neutron activation analysis

International Nuclear Information System (INIS)

Dybczynski, R.; Samczynski, Z.

1996-01-01

The newly modified version of the method for the determination of cadmium in biological materials by radiochemical NAA based on selective post irradiation separation of Cd using ion exchange rasin Retardion 11A8 is presented. The conditions necessary for the selective retaining of Cd on the column exploiting both anionic and cationic ion exchange function of the resin have been discussed. Depending on the composition of the external solution, cadmium existing in the form of either anionic chloride complexes or cationic amine species is taken up by quaternary ammonium or carboxylate functional groups, respectively while accompanying elements are eluted. The elaborated method was further verified by determine Cd content in several certified biological reference materials using neutron activation analysis. The ion exchange separation procedure assures very high radiochemical purity of the cadmium fraction. Decontamination factors obtained for Mo, Sb, Na, Zn, Co, Sc amounted to 10 3 - 10 6 . Detection limit for Cd was 0.5 μg kg -1 . Analytical results show good agreement with the certified values. (author). 10 refs, 7 figs, 1 tab

A radiochemical assay for biotin in biological materials

International Nuclear Information System (INIS)

Hood, R.L.

1975-01-01

A radiochemical assay for biotin is described. The assay was sensitive to one nanogram and simple enough for routine biotin analyses. The assay yielded results which were comparable to those obtained from a microbiological assay using Lactobacillus plantarum. (author)

Sorption technique of separation of thallium-201 from proton-irradiated thallium

International Nuclear Information System (INIS)

Deptula, Cz.; Zajtseva, N.G.; Mikolaevskij, S.; Khalkin, V.A.

1989-01-01

A sorption technique is developed for radiochemical separation of thallium-201 from proton-irradiated targets of metallic thallium. The technique consists in separation of 201 Pb and 201 Tl in the column with ammonium 12-molybdophosphate fixed in the matrix of porous Teflon (AMP-sorbent). The chemical yield of radiothallium is 98 %, the duration of chemical procedures is 2.5-3 hours. 21 refs.; 1 fig.; 1 tab

The determination of the radiochemical purity of 99Tcm-DTPA-HSA injection

International Nuclear Information System (INIS)

Yin Guangrong; Zhang Yan

1996-01-01

A simple, rapid analytical method of radiochemical purity for the 99 Tc m -DTPA-HSA injection is established. 99 Tc m (VII), 99 Tc m (IV) and labelled compound 99 Tc m -DTPA-HSA are separated by two systems of paper chromatography on Whatman No.1. The solvent of the system A is 85% methanol and that of the system B is water-95% alcohol-ammonium hydroxide (volume ratio is 5:2:1). 90 Tc m (IV) and labelled compound are located at the origin, while R f of 99 Tc m (VII) is about 0.4-0.5 in the system A. R f of 99 Tc m (VII) and labelled compound are about 0.7-0.8, while 99 Tc m (IV) is located at the origin in the system B

Determination of individual rare earth elements in Vietnamese monazite by radiochemical neutron activation analysis

International Nuclear Information System (INIS)

Nguyen Van Suc; Nguyen Mong Sinh

1993-01-01

Radiochemical neutron activation analysis (RNAA) has been applied for determination of rare earth elements (REE) in Vietnamese monazite. The chemical separation procedure used is based on the chromatographic elution of rare earth groups, after the separation of 233 Pa(Th) in irradiated monazite samples by coprecipitation with MnO 2 , the rare earth elements were retained by Biorad AG1 x 8 resin column in 10% 15.4M HNO 3 -90% methanol solution. The elution of heavy rare earth (HREE) and middle rare earth (MREE) groups was carried out with 10% 1M HNO 3 - 90% methanol and 10% 0.05M HNO 3 -90% methanol solution, respectively; while the light rare earths (LREE) were eluted from the column by 0.1M HNO 3 solution. The accuracy of the method was checked by the analysis of granodiorite GSP-I and the rare earth values were in good agreement. (author) 7 refs.; 3 tabs

Application of radiochemical determination methods in cleanability research of building materials

International Nuclear Information System (INIS)

Maeaettae, Jenni; Kymaelaeinen, Hanna-Riitta; Sjoeberg, Anna-Maija

2011-01-01

During recent years increasing effort has been made to modify surface properties with easy-to-clean or self-cleaning characteristics, and concomitantly there is a need to be able to quantify cleanability. Methodology is a complex issue, including aspects of selection and characterization of the surface materials, the soiling materials (contaminants), soiling and cleaning methods, and the detection methods. Different biological, chemical, physical and visual methods have been included in studies of surface cleanability. One challenge has been to obtain quantitative information about soiling. The radiochemical methods, gamma spectrometry (NaI(Tl)-crystal) and liquid scintillation counting, have been shown to be suitable for evaluating cleanability of different surface materials and different soiling material types, providing quantitative information about the amount of soiling material both on and beneath the surface. Due to the different labelled soiling components, the interaction of the surface with different soiling material types can be evaluated. Radiochemical methods have unique benefits particularly for examining porous materials and surfaces. However, they are suitable only for highly controlled studies because of the hazards. Different features and details of radiochemical methods are discussed with the view to aid planning of future cleanability studies. - Highlights: → Radiochemical methods can be used for cleanability studies. → These methods give quantitative information about the amount of soiling material. → These methods are suitable particularly for examining porous materials. → These methods are suitable for highly controlled studies because of the hazards.

Radiochemicals in biomedical research

International Nuclear Information System (INIS)

Evans, E.A.; Oldham, K.G.

1988-01-01

This volume describes the role of radiochemicals in biomedical research, as tracers in the development of new drugs, their interaction and function with receptor proteins, with the kinetics of binding of hormone - receptor interactions, and their use in cancer research and clinical oncology. The book also aims to identify future trends in this research, the main objective of which is to provide information leading to improvements in the quality of life, and to give readers a basic understanding of the development of new drugs, how they function in relation to receptor proteins and lead to a better understanding of the diagnosis and treatment of cancers. (author)

Remote-controlled module-assisted synthesis of O-(2-[18F]fluoroethyl)-L-tyrosine as tumor PET tracer using two different radiochemical routes

International Nuclear Information System (INIS)

Wang Mingwei; Yin Duanzhi; Zhang Lan; Zhou Wei; Wang Yongxian

2006-01-01

The positron-emitter fluorine-18 labeled amino acid O-(2-[ 18 F]fluoroethyl)-L-tyrosine ([ 18 F]FET) has shown very promising perspectives for brain tumor diagnosis with positron emission tomography (PET). There have been two existing preparation routes of [ 18 F]FET named direct nucleophilic radiofiuorination of protected L-tyrosine and radiofiuoroallcylation of unprotected L-tyrosine, respectively. A general module was designed specifically for the routine synthesis of [ 18 F]FET, which could be suitable for the present two chemical methods with simple modifications. The fluorinated intermediates and the final product were separated and purified using solid phase extraction (SPE) on the Sep-Pak silica plus cartridge instead of the time-consuming high performance liquid chromatography (HPLC) procedures. The total synthesis time was about 50-60 rain with good radiochemical yield (about 20-40%, no-decay-corrected) and good radiochemical purity (more than 97%) for both the synthetic methods. (authors)

Fast Monaural Separation of Speech

DEFF Research Database (Denmark)

Pontoppidan, Niels Henrik; Dyrholm, Mads

2003-01-01

a Factorial Hidden Markov Model, with non-stationary assumptions on the source autocorrelations modelled through the Factorial Hidden Markov Model, leads to separation in the monaural case. By extending Hansens work we find that Roweis' assumptions are necessary for monaural speech separation. Furthermore we...

Determination of mercury in ppb level by activation analysis and chemical separation

International Nuclear Information System (INIS)

Requejo, C.S.

1983-02-01

A method for determining mercury in steel samples was developed. Activation analysis using thermal neutrons, followed by radiochemical separations to eliminate 75 Se interferences, were applied. Sixty hours after the end of the irradiation, the samples were processed and distillation of mercury and selenium bromides were carried out. Selenium was separated as an element and mercury sulfide was precipitaded. The chemical separation procedure was tested by using a tracer technique; the recovery yield was 99,2% + - 2,7%. (C.L.B.) [pt

Evaluation of radiochemical purities of some radiopharmaceuticals in Shiraz Namazi teaching hospital

Directory of Open Access Journals (Sweden)

Hossein Sadeghpour

2015-03-01

Full Text Available Many radiopharmaceuticals, as a special group of drugs, are eventually prepared at the nuclear medicine departments of the hospitals. Therefore, their quality control procedures such as sterility tests, radionuclide, radiochemical and chemical purity should be carried out in the hospitals. In this study, radiochemical purity for more than 300 preparations of three different radiopharmaceutical formulations from commercial kits were tested using instant thin layer chromatography. The formulations 99mTc-DTPA, 99mTc-MDP and 99mTc-MIBI were obtained from Pars Isotope Co. Several paper chromatographic systems including standard and factory recommended thin layer chromatography systems were used in this study. In addition different equipments for detection of radioactivity in paper chromatography like gamma camera and dose calibrator were used. The results showed that the most observed impurities were hydrolyzed reduced technetium (HR-Tc. There were no significant differences between calculated 99mTc-MIBI radiochemical purities when the radioactive detection device was gamma camera instead of dose calibrator. In case of 99mTc-DTPA and 99mTc-MDP, there were significant differences in detection of HR-Tc. On the contrary, no significant differences in free pertechnetate were observed when package insert procedures for quality control were used instead of those recommended in the references. Finally, we observed that the package insert procedures for quality control can offer higher radiochemical purities.

Current studies of biological materials using instrumental and radiochemical neutron activation analysis

International Nuclear Information System (INIS)

Fardy, J.J.; McOrist, G.D.; Farrar, Y.J.

1985-01-01

Instrumental neutron activation analysis still remains the preferred option when analysing the trace element distribution in a wide rage of materials by neutron activation analysis. However, when lower limits of detection are required or major interferences reduce the effectiveness of this technique, radiochemical neutron activation analysis is applied. This paper examines the current use of both methods and the development of rapid radiochemical techniques for analysis of the biological materials, hair, cow's milk, human's milk, milk powder, blood and blood serum

Radiochemical neutron activation analysis of high pure palladium and platinum by ion exchange chromatography

International Nuclear Information System (INIS)

Sadikov, I.I.; Zinov'ev, V.G.; Sadikova, Z.O.; Salimov, M.I.

2006-01-01

Full text: The palladium and platinum are widely used for jewel manufacture because of their beautiful white color. However the most part of these metals are widely adopted in the world as catalysts. Many works on analytical chemistry of platinum group elements published during last years are devoted to determination of platinum and palladium in other materials. There are no articles on analysis technique of the palladium and platinum purity published during last 20 years. Available publications are very old and are published till 70th of the last century, and implement chemical and spectral methods. At the same time, the palladium and platinum are very suitable for NAA. Therefore the purpose of our research was development of high-sensitivity and multielement techniques of radiochemical neutron activation analysis of a high pure palladium and platinum. Research of nuclear characteristics of palladium and platinum has shown that radioactive nuclides with different yields are formed under the reactor neutrons. 109 , 111 , 111m Pd, 109m , 111 Ag, 191 , 197 , 199 Pt, 199 Au are the most important among them. 109Pd separation factor is equal to 1*10 5 at palladium analysis, whereas 197 Pt and 199 Au separation factor is equal to 1*10 4 at the platinum analysis every other day after irradiation. Palladium and platinum can be separated by precipitation, extraction and ion exchange methods. For separation of radioactive nuclide of the matrix elements from the impurity elements we used ion exchange chromatography system Dowex-1x8 - 1 M HNO 3 for palladium and Dowex-1x8 - 0.1 M HNO 3 for platinum. At the HNO 3 acid concentrations variation from 0,1 M to 1 M more then 25 elements have distribution factors less than 1 and 10 elements have distribution factors 5 while matrix elements have distribution factors higher than 100. It allows an effective separation of these elements from palladium and platinum. Optimum sizes of the chromatographic column and the column effluent

Artificial receptor-functionalized nanoshell: facile preparation, fast separation and specific protein recognition

Science.gov (United States)

Ouyang, Ruizhuo; Lei, Jianping; Ju, Huangxian

2010-05-01

This work combined molecular imprinting technology with superparamagnetic nanospheres as the core to prepare artificial receptor-functionalized magnetic nanoparticles for separation of homologous proteins. Using dopamine as a functional monomer, novel surface protein-imprinted superparamagnetic polydopamine (PDA) core-shell nanoparticles were successfully prepared in physiological conditions, which could maintain the natural structure of a protein template and achieved the development of molecularly imprinted polymers (MIPs) from one dimension to zero dimension for efficient recognition towards large biomolecules. The resultant nanoparticles could be used for convenient magnetic separation of homologous proteins with high specificity. The nanoparticles possessed good monodispersibility, uniform surface morphology and high saturation magnetization value. The bound amounts of template proteins measured by both indirect and direct methods were in good agreement. The maximum number of imprinted cavities on the surface of the bovine hemoglobin (Hb)-imprinted nanoshell was 2.21 × 1018 g - 1, which well matched their maximum binding capacity toward bovine Hb. Both the simple method for preparation of MIPs and the magnetic nanospheres showed good application potential in fast separation, effective concentration and selective biosensing of large protein molecules.

Artificial receptor-functionalized nanoshell: facile preparation, fast separation and specific protein recognition

Energy Technology Data Exchange (ETDEWEB)

Ouyang, Ruizhuo; Lei Jianping; Ju Huangxian, E-mail: jpl@nju.edu.cn, E-mail: hxju@nju.edu.cn [Key Laboratory of Analytical Chemistry for Life Science (Education Ministry of China), Department of Chemistry, Nanjing University, Nanjing 210093 (China)

2010-05-07

This work combined molecular imprinting technology with superparamagnetic nanospheres as the core to prepare artificial receptor-functionalized magnetic nanoparticles for separation of homologous proteins. Using dopamine as a functional monomer, novel surface protein-imprinted superparamagnetic polydopamine (PDA) core-shell nanoparticles were successfully prepared in physiological conditions, which could maintain the natural structure of a protein template and achieved the development of molecularly imprinted polymers (MIPs) from one dimension to zero dimension for efficient recognition towards large biomolecules. The resultant nanoparticles could be used for convenient magnetic separation of homologous proteins with high specificity. The nanoparticles possessed good monodispersibility, uniform surface morphology and high saturation magnetization value. The bound amounts of template proteins measured by both indirect and direct methods were in good agreement. The maximum number of imprinted cavities on the surface of the bovine hemoglobin (Hb)-imprinted nanoshell was 2.21 x 10{sup 18} g{sup -1}, which well matched their maximum binding capacity toward bovine Hb. Both the simple method for preparation of MIPs and the magnetic nanospheres showed good application potential in fast separation, effective concentration and selective biosensing of large protein molecules.

Northern Marshall Islands Radiological Survey: a quality-control program for a radiochemical analyses

International Nuclear Information System (INIS)

Jennings, C.D.; Mount, M.E.

1983-08-01

More than 16,000 radiochemical analyses were performed on about 5400 samples of soils, vegetation, animals, fish, invertebrates, and water to establish amounts of 90 Sr, 137 Cs, 241 Am, and plutonium isotopes in the Northern Marshall Islands. Three laboratories were contracted by Lawrence Livermore National Laboratory to perform the radiochemical analyses: Environmental Analysis Laboratory (EAL), Richmond, California; Eberline Instrument Corporation (EIC), Albuquerque, New Mexico; and Laboratory of Radiation Ecology (LRE), University of Washington, Seattle, Washington. The analytical precision and accuracy were monitored by regularly including duplicate samples and natural matrix standards in each group of about 100 samples analyzed. Based on the duplicates and standards, over 83% of the radiochemical analyses in this survey were acceptable - 97% of the analyses by EAL, 45% of the analyses by EIC, and 98% of the analyses by LRE

Feasibility studies to assess the use of 236Pu as a radiochemical yield monitor in bioassay samples

International Nuclear Information System (INIS)

Sawant, P.D.; Kalsi, P.C.

2007-01-01

Various plutonium compounds are handled in nuclear facilities of BARC. Hence, there is a possibility of occupational workers getting exposed to Pu. In vitro bioassay monitoring in which Pu is separated by chemical procedures from excreta samples and estimated by alpha-spectrometry, is the method of choice for the evaluation of internal dose to the occupational workers handling Pu. However, this method requires a suitable Pu tracer for reducing the uncertainties due to chemical yield in the separation, electro-deposition and counting efficiency. 242 Pu is commonly used as a tracer but due to its non-availability, efforts were made earlier to indigenously synthesis 236 Pu by proton irradiation of 237 Np in BARC-TIFR pelletron facility. The present study, reports the feasibility of using 236 Pu as a radiochemical yield monitor (tracer) in bioassay samples. (author)

The publication lapse of papers in Radiochemical and Radioanalytical Letters

International Nuclear Information System (INIS)

Braun, T.; Nagydiosi-Kocsis, Gy.

1982-01-01

The time needed for passing through journal editorial and publication processing has been examined for the papers published in Radiochemical and Radioanalytical Letters for the years 1969-1981. (author)

Comparison of two selective separation method for {sup 93}Zr by using TRU and TEVA resins

Energy Technology Data Exchange (ETDEWEB)

Oliveira, Thiago C.; Oliveira, Arno Heeren de, E-mail: tco@cdtn.b, E-mail: heeren@nuclear.ufmg.b [Universidade Federal de Minas Gerais (DEN/UFMG), Belo Horizonte, MG (Brazil). Dept. de Engenharia Nuclear; Monteiro, Roberto Pellacani G., E-mail: rpgm@cdtn.b [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

2011-07-01

The zirconium isotope {sup 93}Zr is a long-lived pure {beta}-particle-emitting radionuclide produced from {sup 235}U fission and from neutron activation of the stable isotope {sup 92}Zr and thus occurring as one of the radionuclides found in nuclear reactors. Due to its long half life, {sup 93}Zr is one of the radionuclides of interest for the performance of assessment studies of waste storage or disposal. Measurement of {sup 93}Zr is difficult owing to its trace level concentration and its low activity in nuclear wastes and further because its certified standards are not frequently available. The aim of this work was to compare two radiochemical procedure based on selective extraction using an anion-exchange chromatography, TRU and TEVA resins, in order to separate zirconium from the matrix and to analyze it by liquid scintillation spectrometry technique. To set up the radiochemical separation procedure for zirconium, a tracer solution of {sup 95}Zr and its 724.19 keV {gamma}-ray measurements by {gamma} - spectrometry were used in order to follow the behavior of zirconium during the radiochemical separation. A tracer solution of {sup 55}Fe, the main interference in the LSC measurements, was used in order to verify the decontamination factor during the separation process. The limit of detection of the 0.05 Bq 1{sup -1} was obtained for {sup 55}Fe standard solutions by using a sample:cocktail ratio of 3:17 mL for Optiphase Hisafe 3 cocktail. (author)

Motion-based, high-yielding, and fast separation of different charged organics in water.

Science.gov (United States)

Xuan, Mingjun; Lin, Xiankun; Shao, Jingxin; Dai, Luru; He, Qiang

2015-01-12

We report a self-propelled Janus silica micromotor as a motion-based analytical method for achieving fast target separation of polyelectrolyte microcapsules, enriching different charged organics with low molecular weights in water. The self-propelled Janus silica micromotor catalytically decomposes a hydrogen peroxide fuel and moves along the direction of the catalyst face at a speed of 126.3 μm s(-1) . Biotin-functionalized Janus micromotors can specifically capture and rapidly transport streptavidin-modified polyelectrolyte multilayer capsules, which could effectively enrich and separate different charged organics in water. The interior of the polyelectrolyte multilayer microcapsules were filled with a strong charged polyelectrolyte, and thus a Donnan equilibrium is favorable between the inner solution within the capsules and the bulk solution to entrap oppositely charged organics in water. The integration of these self-propelled Janus silica micromotors and polyelectrolyte multilayer capsules into a lab-on-chip device that enables the separation and analysis of charged organics could be attractive for a diverse range of applications. © 2015 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.

Investigation of short-lived neutron-rich palladium and silver isotopes after fast chemical separation from fission fragments

International Nuclear Information System (INIS)

Bruechle, W.

1976-01-01

In this paper, chemical separation processes are described permitting fast and neat isolation of short-lived palladium and silver nuclides from fusion product mixtures. The process for palladium is based on the stability of palladium diethyldithiophosphate. From fission products of the reactions 238 U(n,f) and 249 Cf(nth,f), the following palladium niclides could be studied for the first time by gamma spectroscopy: 1.66 min 113 Pd, 2.45 min 114 Pd, 29 sec sup(115a)Pd, 54 sec sup(115b)Pd, 12.5 sec 116 Pd. 113 Pd could also be indentified according to the reaction 116 Cd(n,α) 113 Pd. The separation of silver is based on the fast isotopic exchange on AgCl. With this process, the following nuclides have been separated from fission product mixtures and studied by gamma spectroscopy: 70 sec sup(113m)Ag, 5.0 sec 114 Ag, 19.2 sec sup(115m)Ag, 2.65 min sup(116g)Ag, 10.5 sec sup(116m)Ag, 1.3 min sup(117g)Ag, 6.0 sec sup(117m)Ag, 4.0 sec 118 Ag. (orig./WL) [de

Separation of gallium and actinides in plutonium nuclear materials by extraction chromatography

International Nuclear Information System (INIS)

Eitrheim, E.S.; Knight, A.W.

2015-01-01

Analysis of stable gallium in nuclear materials has applications in nuclear fuel characterization and nuclear forensics. The use of positron-emitting gallium isotope 68 Ga as a tracer for Ga recoveries for analyses in materials containing actinides was explored. A radiochemical method for the separation of Ga, Pu, U, Th, and Am using commercially-available extraction chromatography resins was developed and evaluated. The method effectively allows precise determination of Ga yield (97 ± 3 %) in the analysis of stable Ga (spike recovery 101 ± 1 %) and radioactive Pu (radiochemical yield, 82 ± 10 %; spike recovery, 96 ± 3 %), while also providing pure elemental fractions of other actinides relevant to materials encountered in the analysis Pu-containing materials. (author)

Radionuclide separation and processing for recycle or disposal

International Nuclear Information System (INIS)

Allen, W.O.; Morrey, J.R.; Fryberger, T.B.; Wolf, S.M.; Lien, S.C.T.

1992-01-01

The U.S. Department of Energy (DOE) Office of Technology Development (OTD) is sponsoring research and development on advanced radiochemical separations, at a modest level, with the long-term goals of reducing the volume of deep geologic repository-disposed waste and the toxicity of low-level waste disposed as cement grout in a near-surface vault. This will help reduce overall environmental risks and the cost of waste management. (author)

Scientific and technical conference. Problems and horizons of development of chemical and radiochemical control in nuclear energetics. Collection of summaries of reports

International Nuclear Information System (INIS)

2001-01-01

During scientific and technical conference on problems of development of chemical and radiochemical control in nuclear energetics following themes were considered: the problems of methodological and instrumental assurance of chemical and radiochemical control at working nuclear power plants and nuclear energetic units; modern conceptions of automation systems construction of chemical and radiochemical control on the basis of intellectual measuring channels; the ways of decision of generally system problems of organization and management of chemical and radiochemical control using computed technologies; the problems of certification of chemical and radiochemical methods of measuring in nuclear energetics [ru

Radiochemical analysis of the Bikini ashes

Energy Technology Data Exchange (ETDEWEB)

Ishibashi, M; Shigematsu, T; Ishida, T

1954-01-01

The following nuclides were detected in the Bikini ashes by radiochemical procedures: /sup 45/Ca, /sup 89/Sr, /sup 91/Y, /sup 95/Zr, /sup 103/Ru, /sup 144/Pr, and /sup 237/U. The ion-exchange method was used for analysis of contaminated rain water which fell on the Kyoto area on May 16, 1954 from which the presence of /sup 89/Sr, /sup 95/Zr, and /sup 140/Ba, was detected. Rare earths seemed also to be present.

Fast gradient HPLC/MS separation of phenolics in green tea to monitor their degradation.

Science.gov (United States)

Šilarová, Petra; Česlová, Lenka; Meloun, Milan

2017-12-15

The degradation of catechins and other phenolics in green tea infusions were monitored using fast HPLC/MS separation. The final separation was performed within 2.5min using Ascentis Express C18 column (50mm×2.1mm i.d.) packed with 2μm porous shell particles. Degradation was studied in relation to the temperature of water (70, 80, 90°C) and the standing time of the infusion (up to 6h). Along with chromatographic separation, the antioxidant properties of the infusions were monitored using two spectrophotometric methods. During staying of green tea infusion, the degradation of some catechins probably to gallic acid was observed. Finally, the influence of tea bag storage on antioxidant properties of green tea was evaluated. Rapid degradation of antioxidants after 3weeks was observed. The principal component analysis, factor analysis and discriminant analysis were used for the statistical evaluation of obtained experimental data. Copyright © 2017 Elsevier Ltd. All rights reserved.

Monoterpene separation by coupling proton transfer reaction time-of-flight mass spectrometry with fastGC.

Science.gov (United States)

Materić, Dušan; Lanza, Matteo; Sulzer, Philipp; Herbig, Jens; Bruhn, Dan; Turner, Claire; Mason, Nigel; Gauci, Vincent

2015-10-01

Proton transfer reaction mass spectrometry (PTR-MS) is a well-established technique for real-time analysis of volatile organic compounds (VOCs). Although it is extremely sensitive (with sensitivities of up to 4500 cps/ppbv, limits of detection monoterpenes, which belong to the most important plant VOCs, still cannot be distinguished so more traditional technologies, such as gas chromatography mass spectrometry (GC-MS), have to be utilised. GC-MS is very time consuming (up to 1 h) and cannot be used for real-time analysis. Here, we introduce a sensitive, near-to-real-time method for plant monoterpene research-PTR-MS coupled with fastGC. We successfully separated and identified six of the most abundant monoterpenes in plant studies (α- and β-pinenes, limonene, 3-carene, camphene and myrcene) in less than 80 s, using both standards and conifer branch enclosures (Norway spruce, Scots pine and black pine). Five monoterpenes usually present in Norway spruce samples with a high abundance were separated even when the compound concentrations were diluted to 20 ppbv. Thus, fastGC-PTR-ToF-MS was shown to be an adequate one-instrument solution for plant monoterpene research.

Determination of isotopic ratios of osmium and ruthenium in meteorites by pretreatment and radiochemical neutron activation analysis

International Nuclear Information System (INIS)

Chinfang Chai; Yongzhong Liu; Xueying Mao

1996-01-01

The isotopic abundance ratios of 190 Os/ 184 Os and 96 Ru/ 102 Ru for the metal phases of the Jilin and Taonan stone meteorites were determined by pretreatment and radiochemical neutron activation analysis. All experimental factors affecting Os and Ru isotopic ratios were discussed, including sampling, standard, irradiation, separation and counting. The statistical errors of measurements for the 199 Os/ 184 Os ratio can be controlled within 1%. The experimental results indicate that the statistically significant anomalies of the 190 Os/ 184 Os and 96 Ru/ 102 Ru ratios have not been found relative to the terrestrial Os and Ru standards. (author). 6 refs., 1 fig., 5 tabs

Imaging Scanner Usage in Radiochemical Purity Test

International Nuclear Information System (INIS)

Norhafizah Othman; Yahaya Talib; Wan Hamirul Bahrin Wan Kamal

2011-01-01

Imaging Scanner model BIOSCAN AR-2000 has been used in the radiochemical purity test for the product of Mo-99/ Tc-99m generator. Result from this test was produced directly where the percentage of pertechnetate was calculated based on width peak area by thin layer chromatography. This paperwork will explain the function, procedure, calibration of the instrument and discussed the advantages compared to the previous method. (author)

Rapid chemical separations

CERN Document Server

Trautmann, N

1976-01-01

A survey is given on the progress of fast chemical separation procedures during the last few years. Fast, discontinuous separation techniques are illustrated by a procedure for niobium. The use of such techniques for the chemical characterization of the heaviest known elements is described. Other rapid separation methods from aqueous solutions are summarized. The application of the high speed liquid chromatography to the separation of chemically similar elements is outlined. The use of the gas jet recoil transport method for nuclear reaction products and its combination with a continuous solvent extraction technique and with a thermochromatographic separation is presented. Different separation methods in the gas phase are briefly discussed and the attachment of a thermochromatographic technique to an on-line mass separator is shown. (45 refs).

Rapid separation of individual rare-earth elements from fission products

International Nuclear Information System (INIS)

Baker, J.D.; Gehrke, R.J.; Greenwood, R.C.; Meikrantz, D.H.

1980-01-01

A microprocessor-controlled radiochemical separation system has been developed to rapidly separate rare-earth elements from gross fission products. The system is composed of two high performance liquid chromatography columns coupled in series by a stream-splitting injection valve. The first column separates the rare-earth group by extraction chromatography using dihexyldiethylcarbamylmethylenephosphonate (DHDECMP) adsorbed on Vydac C 8 resin. The second column isolates the individual rare-earth elements by cation exchange using Aminex A-9 resin with α-hydroxyisobutyric acid (α-HIBA) as the eluent. With this system, fission-product rare-earth isotopes with half-lives as short as three minutes have been studied

Minicomputer system for radiochemical analysis by coincidence spectrometry

International Nuclear Information System (INIS)

Brauer, F.P.; Fager, J.E.

1979-01-01

Minicomputer-based coincidence analysis methods have been developed for use in performing radiochemical analysis by high-resolution x- and gamma-ray coincidence spectrometry. This paper describes the data-acquisition and analysis methods develolped for qualitative and quantitative analyses of coincidence spectrometric data. Data-acquisition capabilities include both direct multiparameter pulse-height analysis and buffered list-mode acquisition

Slifers revisited: a method for determining yields independent of radiochemical measurements

International Nuclear Information System (INIS)

Rambo, J.T.

1976-01-01

It would be very desirable if an independent method other than radiochemical measurement were available to determine the yields of low-yield events in the alluviums and tuffs of areas 2, 9, and 10 at the Nevada Test Site. The successful application of slifers to the measurement of yields from high-yield events suggests that under some conditions they may also be usable with low-yield events. This view is supported by the evidence discussed here, which is based on direct experience with slifer yield measurements for low-yield events in porous media. Suggested methods for improving slifer yield determinations and a method for determining yields independent of radiochemical measurements are offered

Statistical processing of technological and radiochemical data

International Nuclear Information System (INIS)

Lahodova, Zdena; Vonkova, Kateřina

2011-01-01

The project described in this article had two goals. The main goal was to compare technological and radiochemical data from two units of nuclear power plant. The other goal was to check the collection, organization and interpretation of routinely measured data. Monitoring of analytical and radiochemical data is a very valuable source of knowledge for some processes in the primary circuit. Exploratory analysis of one-dimensional data was performed to estimate location and variability and to find extreme values, data trends, distribution, autocorrelation etc. This process allowed for the cleaning and completion of raw data. Then multiple analyses such as multiple comparisons, multiple correlation, variance analysis, and so on were performed. Measured data was organized into a data matrix. The results and graphs such as Box plots, Mahalanobis distance, Biplot, Correlation, and Trend graphs are presented in this article as statistical analysis tools. Tables of data were replaced with graphs because graphs condense large amounts of information into easy-to-understand formats. The significant conclusion of this work is that the collection and comprehension of data is a very substantial part of statistical processing. With well-prepared and well-understood data, its accurate evaluation is possible. Cooperation between the technicians who collect data and the statistician who processes it is also very important. (author)

The use of robots for automation in the radiochemical laboratory

International Nuclear Information System (INIS)

Huddleston, J.

1988-01-01

The use of robotic systems for automated processes such as overnight operations, procedures involving radiation hazards in radiochemical laboratories is discussed. Particular reference is made to their use in analytical problems. Their flexibility is emphasised. (U.K.)

Radiochemical procedure and quantitative determination of the activation product, 63Ni, in environmental soft water samples with high Ca and Mg phosphate concentration

International Nuclear Information System (INIS)

Jordan, N.; Michel, H.; Barci-Funel, G.; Barci, V.

2008-01-01

Nickel-63 is a low energy beta-emitter needing a radiochemical separation before β-counting. Several papers described the separation and the detection of 63 Ni in environmental samples. The method used in our work was first developed by SKWARZEC and HOLM. The main steps of this separation are the selective precipitation of nickel with dimethylglyoxime (DMG) and the use of the non-sorption of nickel on anion resin in hydrochloric acid solutions. In this paper, a new step is added to eliminate high quantities of calcium and magnesium phosphate disturbing the iron hydroxide precipitation step. The procedure has been applied to soft water samples: sediments, plants and fishes. The chemical yields are 60, 70 and 20%, respectively. The detection limit of 63 Ni by liquid scintillation spectrometer is 10 mBq. (author)

Abyssal sediment erosion from the Central Indian Basin: Evidence from radiochemical and radiolarian studies

Digital Repository Service at National Institute of Oceanography (India)

Banakar, V.K.; Gupta, S.M.; Padmavati, V.K.

) 167-173 167 Elsevier Science Publishers B.V., Amsterdam Letter Section Abyssal sediment erosion in the Central Indian Basin: Evidence from radiochemical and radiolarian studies V.K. Banakar, S.M. Gupta and V.K. Padmavathi National Institute... of Oceanography, Dona-Paula, Goa-403 004, India (Revision accepted September 17, 1990) ABSTRACT Banakar, V.K., Gupta, S.M. and Padmavathi, V.K., 1991. Abyssal sediment erosion from the Central Indian Basin: Evi- dence from radiochemical and radiolarian studies...

Assessment of radiochemical purity of [18F]fludeoxyglucose by high pressure liquid chromatography (HPLC)

International Nuclear Information System (INIS)

Lacerda, Aline E.; Silva, Juliana B.; Silveira, Marina B.; Ferreira, Soraya Z.

2011-01-01

The quality control of [ 18 F]fludeoxyglucose ( 18 FDG) has received attention due to its increasing clinical use. Although the quality requirements of 18 FDG are established in various pharmacopoeia, the suitability of all testing methods used should be verified under actual conditions of use and documented. The aim of this study was to develop a high pressure liquid chromatography (HPLC) method for radiochemical purity evaluation of 18 FDG, based on pharmacopoeia references, and to verify its suitability for routine quality control in our centre. HPLC analysis was performed with an Agilent HPLC. 18 FDG and impurities were separated on an anion-exchange column by isocratic elution with 0.1 M NaOH as the mobile phase. Detection was accomplished with refractive index and NaI (Tl) scintillation detectors. The flow rate of the mobile phase was set at 0.8 mL/min and the column temperature was kept at 35 deg C. Specificity, linearity, precision and robustness were assessed to verify if the method was adequate for its intended purpose. Retention time of 18 FDG was not affected by the presence of other components of the formulation and a good peak resolution was achieved. The analytical curve of 18 FDG was linear, with a correlation coefficient value of 0.9995. Intraday repeatable precision, reported as the relative standard deviation, was 0.11%. Analytical procedure remained unaffected by small variations in mobile phase flow rate. Results evidenced that HPLC is suitable for radiochemical purity evaluation of 18 FDG, considering operational conditions of our laboratory. (author)

Method Development of Cadmium Investigation in Rice by Radiochemical Neutron Activation Analysis

International Nuclear Information System (INIS)

Promsawad, Arunee; Pareepart, Ratirot; Laoharojanaphand, Sirinart; Arunee, Kongsakpaisal

2007-08-01

Full text: A radiochemical neutron activation analysis for the determination of cadmium was investigated. A chemical separation of cadmium utilized ion exchange chromatography of a strong basic anion-exchange resin BIO-RAD 1X 8 (Chloride form). The adsorbing medium of 2M HCl was found to be the most suitable among the concentration attempted (2, 4, 6, 8 and 10M HCl) and the eluent for desorption of the cadmium from column was 8M NH 3 solution. A chemical yield of 95% was found. The method has been evaluated by analyzing certified reference materials with 0.5.g/g (SRM 1577b, Bovine Liver) and 2.48.g/g (SRM 1566b, Oyster Tissue) cadmium. The agreement of the result with certified values is within 92% for Bovine Liver and 96% for Oyster Tissue. The method developed was applied to determine the cadmium concentrations in contaminated Thai rice. It was found that the cadmium concentrations ranged from 7.4 to 578.9 ppb

Production, study and use of short-lived nuclides in pure and applied nuclear research

International Nuclear Information System (INIS)

Bjoernstad, T.

1986-01-01

The thesis which is based on 17 published papers, reports on the on-line performance of the fast radiochemical separation system SISAK, technical devlopment in the preparation of sources for beta-particles and neutrons, and on important SISAK system improvements concerning liquid hold-up time. It further reports on the development of new production targets at ISOLDE for 600 MeV proton and 910 MeV 3 He-particle irradiations, on tests with a heavy ion beam of 1 GeV 12 C-particles, and on the present availability of mass-separated beams of the halogen elements through new ion source development. Some results from nuclear spectroscopic studies of nuclides in selected mass regions when using such new or improved techniques are given. Examples of techniques for practical application of short-lived nuclides in radiochemical analysis and for radiochemical production for medical purposes are presented

Evaluation of the separation and purification of 227Th from its decay progeny by anion exchange and extraction chromatography

International Nuclear Information System (INIS)

Ivanov, P.I.; Collins, S.M.; Es, E.M. van; García-Miranda, M.; Jerome, S.M.; Russell, B.C.

2017-01-01

Thorium-227 is currently undergoing evaluation as a potential radionuclide for targeted cancer therapy, and as such a high chemical purity of the material is required. To establish a reliable procedure for radiochemical isolation of 227 Th from the parent 227 Ac and decay progeny, which includes the radiotherapeutic 223 Ra, the performance of three different separation schemes based on ion-exchange and extraction chromatography have been evaluated. The results suggest that both ion exchange and extraction chromatographic techniques can be successfully used for the separation of 227 Th from its decay progeny, however extraction chromatographic resins demonstrate favourable performance in terms of Th recovery and purification from radionuclide impurities. - Highlights: • Development of a radiochemical separation of 227 Th from residual 227Ac as well as from decay progeny. • Evaluation of ion-exchange and extraction chromatography techniques. • TEVA resin demonstrates favourable performance in terms of Th recovery and purification. • Developed method is applicable to both nuclear medicine and environmental analysis.

Testing the radiochemical purity of radiopharmaceuticals: application to {sup 99m}Tc-HMPAO; Controle de la purete radiochimique des radiopharmaceutiques: application au {sup 99m}Tc-HMPAO

Energy Technology Data Exchange (ETDEWEB)

Ait Ben Ali, S.; Darsin, D.; Rizzo, N.; Lours, S.; De Beco, V.; Dumont, A.; Goudou-Sinha, C.; Izembart, M.; Jourdain, J.R.; Lemercier, V.; Linsker, S.; Moati, F.; Piketty, M.L.; Schlageter, M.H.; Moretti, J.L. [Groupe de travail `Radiopharmaceutique - Ile de France` (France)

1997-12-31

The low stability of {sup 99m}Tc-HMPAO imposes to carry out the quality testing within the 15 minutes following the preparation. This study has the aim of comparing different methods of radiochemical purity determination (RP) of this radiopharmaceutical in order to validate a fast, reproducible, feasible technique, capable of separating the primary lipophilic {sup 99m}Tc-HMPAO (I) of impurities: hydrophilic secondary complex (II), TcO{sub 4}{sup -}, reduced and halyards Tc. The reference technique associating two thin-layer chromatographies (TLC), `C1` and `C2`, has been compared with a TLC `W` technique and with liquid-liquid extraction `E` technique: C1 - stationary phase, ITLC Silica gel/mobile phase, Butanone-2; C2 - stationary phase, ITLC Silica gel/mobile phase, 0.9% NaCl; W - stationary phase, Papier Whatman n{sup o} 1/mobile phase, Ether; E - extraction with ethyls acetate /0.9% NaCl (1/1 v/v). The `C1` chromatography allows isolating the reduced Tc and the complex II, the `C2` chromatography does the same with TcO{sub 4}{sup -} but it requires too long techniques (20 min.). The `W` and `E` techniques are rapid, reproducible and allow to separate the complex I from the other impurities without discrimination. However, as their results depend upon the deposited quantity of sampling, an optimization and standardization of the techniques are necessary. A forth technique by chromatography on Sep-Pak column is to be evaluated

Ga2O for target, solvent extraction for radiochemical separation and SnO2 for the preparation of a 68Ge/68Ga generator

International Nuclear Information System (INIS)

Aardaneh, K.; Walt, T.N. van der

2006-01-01

The target for the production of 68 Ge consists of a disc of gallium suboxide, Ga 2 O, with a 19 mm diameter. The suboxide was primarily prepared by repeatedly mixing metallic Ga and Ga 2 O 3 at 700 deg C. The target (2.4 g) was quite stable under a long-time irradiation with a 34 MeV proton beam at a current of ∼80 μA. The dissolution of the target was performed using 12M sulphuric acid solution, assisted with the dropwise addition of 30% H 2 O 2 solution, and took less than 4 hours. A solvent extraction method, using a 9M H 2 SO 4 - 0.3M HCl/CCl 4 system, was employed for the radiochemical separation of 68 Ge from Ga and Zn radionuclides, while 0.05M HCl was used for the back extraction of 68 Ge from the organic phase. The 68 Ge obtained in the dilute HCl was directly loaded onto a column containing either a hydrous tin dioxide or a crystalline tin dioxide, obtained by calcinations of the hydrous oxide at 450, 700, and 900 deg C. The calcinated hydrous tin dioxide at 900 deg C showed the highest crystallinity and highest 68 Ga elution yield and was selected for use in the generator. The 68 Ga elution from the column generator packed with 2 g of tin dioxide, using 3 ml of 1M HCl, and yielded an average of 65%. The breakthrough of 68 Ge was 6.1 x 10 -4 %. (author)

Radiochemical search for neutron-rich isotopes of element 107

International Nuclear Information System (INIS)

Schaedel, M.

1987-01-01

Recent mass calculations have indicated that there is a region of deformed nuclei around neutron number N=162 that is especially stable against spontaneous fission. Barrier heights of about 5 MeV for Z = 107 nuclides can be extrapolated. To search for new, neutron-rich isotopes of element 107 in radiochemical experiments with 254 Es as a target an on-line chemical separation of element 107 (EKA-Rhenium), especially from the actinide elements is needed. An on-line gas-phase chemistry was developed with the homolog Re based on the volatility of the oxide which is transported in an O 2 containing atmosphere along a temperature gradient in a quartz tube and is condensed onto a thin Ta coated Ni-foil. The authors applied this technique in two series of experiments with their rotating wheel on-line gas-phase chemistry apparatus at the 88-inch cyclotron where they irradiated 254 Es as a target with 93 MeV and 96 MeV 16 O ions to search for 266 107. The assignment of the observed alpha events between 8 and 9 MeV to possibly (1) non actinide contaminants like 212 Po, (2) known isotopes of heavy elements like 261 105, or (3) a new isotope will be discussed

Influence of Storage Temperature on Radiochemical Purity of 99mTc-Radiopharmaceuticals.

Science.gov (United States)

Uccelli, Licia; Boschi, Alessandra; Martini, Petra; Cittanti, Corrado; Bertelli, Stefania; Bortolotti, Doretta; Govoni, Elena; Lodi, Luca; Romani, Simona; Zaccaria, Samanta; Zappaterra, Elisa; Farina, Donatella; Rizzo, Carlotta; Giganti, Melchiore; Bartolomei, Mirco

2018-03-15

The influence of effective room temperature on the radiochemical purity of 99m Tc-radiopharmaceuticals was reported. This study was born from the observation that in the isolators used for the preparation of the 99m Tc-radiopharmaceuticals the temperatures can be higher than those reported in the commercial illustrative leaflets of the kits. This is due, in particular, to the small size of the work area, the presence of instruments for heating, the continuous activation of air filtration, in addition to the fact that the environment of the isolator used for the 99m Tc-radiopharmaceuticals preparation and storage is completely isolated and not conditioned. A total of 244 99m Tc-radiopharmaceutical preparations (seven different types) have been tested and the radiochemical purity was checked at the end of preparation and until the expiry time. Moreover, we found that the mean temperature into the isolator was significantly higher than 25 °C, the temperature, in general, required for the preparation and storage of 99m Tc-radiopharmaceuticals. Results confirmed the radiochemical stability of radiopharmaceutical products. However, as required in the field of quality assurance, the impact that different conditions than those required by the manufacturer on the radiopharmaceuticals quality have to be verified before human administration.

Separation of heavier rare earths from neutron irradiated uranium targets

International Nuclear Information System (INIS)

Bhargava, V.K.; Rao, V.K.; Marathe, S.G.; Sahakundu, S.M.; Iyer, R.H.

1978-01-01

A radiochemical method is described for the separation of heavier rare earths from the fission of uranium. The method is particularly suitable for the separation of low yield (10sup(-5)%-10sup(-7)%), highly asymmetric rare earth fission products viz. sup(179,177)Lu, sup(175)Yb, sup(173)Tm, sup(172,171)Er, sup(167)Ho and sup(161,160)Tb in the neutron induced fission of natural and depleted uranium targets. Additional separation steps have been incorporated for decontamination from sup(239)Np (an activation product) and sup(93-90)Y (a high fission-yield product) which show similar chemical behaviour to rare earths. Separation of individual rare earths is achieved by a cation exchange method performed at 80 deg C by elution with α-hydroxyisobutyric acid (α-HIBA). (author)

The Northern Marshall Islands radiological survey: A quality control program for radiochemical and gamma spectroscopy analysis

International Nuclear Information System (INIS)

Kehl, S.R.; Mount, M.E.; Robison, W.L.

1995-09-01

From 1979 to 1989, approximately 25,000 Post Northern Marshall Islands Radiological Survey (PNMIRS) samples were collected, and over 71,400 radiochemical and gamma spectroscopy analyses were performed to establish the concentration of 90 Sr, 137 Cs, 241 Am, and plutonium isotopes in soil, vegetation, fish, and animals in the Northern Marshall Islands. While the Low Level Gamma Counting Facility (B379) in the Health and Ecological Assessment (HEA) division accounted for over 80% of all gamma spectroscopy analyses, approximately 4889 radiochemical and 5437 gamma spectroscopy analyses were performed on 4784 samples of soil, vegetation, terrestrial animal, and marine organisms by outside laboratories. Four laboratories were used by Lawrence Livermore National Laboratory (LLNL) to perform the radiochemical analyses: Thermo Analytical Norcal, Richmond, California (TMA); Nuclear Energy Services, North Carolina State University (NCSU); Laboratory of Radiation Ecology, University of Washington (LRE); and Health and Ecological Assessment (HEA) division, LLNL, Livermore, California. Additionally, LRE and NCSU were used to perform gamma spectroscopy analyses. The analytical precision and accuracy were monitored by including blind duplicates and natural matrix standards in each group of samples analyzed. On the basis of reported analytical values for duplicates and standards, 88% of the gamma and 87% of the radiochemical analyses in this survey were accepted. By laboratory, 93% of the radiochemical analyses by TMA; 88% of the gamma-ray spectrometry and 100% of the radiochemistry analyses by NCSU; 89% of the gamma spectroscopy and 87% of the radiochemistry analyses by LRE; and 90% of the radiochemistry analyses performed by HEA's radiochemistry department were accepted

Mortality coefficients among personnel of radiochemical plants of open-quotes Mayakclose quotes-Combine for 40-year period of observation

International Nuclear Information System (INIS)

Koshurnikova, N.A.; Komleva, N.S.; Baisogolov, G.D.

1993-01-01

The results of the epidemiological research, conducted among the personnel of the radiochemical plants of open-quotes Mayakclose quotes. Combine are as follows: during the 40-year-period of observation the mortality rate from all and separate causes, except age, is lower, than the expected one, which is calculated on the basis of the National Statistics. Oncological mortality rate is reliably higher, than the expected one, which is conditioned by the high frequency of lung cancer and leucaemia. Internal α-irradiation plays the leading role in the induction of lung cancer, and the increase of mortality rate from leukemia is closely connected with external γ-irradiation

Investigations of radiochemical methods for the platinum group metals for NAA

International Nuclear Information System (INIS)

Tredoux, M.

A radiochemical procedure for the determination of the platinum group metals and gold is outlined in this report. The sample is irradiated, treated with acids and passed through anion-exchange columns before being determined by gamma spectrometry

Rapid, radiochemical-ligand binding assay for methotrexate

International Nuclear Information System (INIS)

Caston, J.D.

1976-01-01

A radiochemical ligand binding assay for methotrexate is provided. A binder factor comprising a partially purified dihydrofolic acid reductase preparation is employed. The binder factor is conveniently prepared by homogenizing a factor containing animal organ such as liver, and extracting with isotonic saline and ammonium sulfate. A binder cofactor, NADPH 2 , is also employed in the binding reaction. The procedure contemplates both direct and sequential assay techniques, and it is not interfered with by vast excesses of many natural folate derivatives. 12 claims, 6 drawing figures

RADIOCHEMICAL YIELDS OF GRAFT POLYMERIZATION REACTIONS OF CELLULOSE

Energy Technology Data Exchange (ETDEWEB)

Arthur, Jr, J C; Blouin, F A

1963-12-15

The preparation of radioinduced graft polymers of cotton cellulose, while retaining the fibrous nature and high molecular weight of the cellulose, depended primarily on the radiochemical yields of cellulose reactions and of graft polymerization reactions. Yields of the initial major molecular changes in cellulosic polymer indicated that, in the case of scission of the molecule and carboxyl group formation, chain reactions were not initiated by radiation; however, in the case of carbonyl group formation chain reactions were initiated but quickly terminated. Generally, experimental procedures, used in graft polymerization reactions, were: simultaneous irradiation reactions, that is, application of monomers or solutions of monomers to cellulose or chemically modified celluloses, then irradiation; and post-irradiation reactions, that is, irradiation of cellulose or chemically modified celluloses, then after removal from the field of radiation, contacting the irradiated cellulose with monomer. Some of the most important factors influencing the radiochemical yields of graft polymerization reactions, of styrene and acrylonitrile onto cellulose were: concentration of monomer in treating solution; solvent; ratio of monomer solution to cellulose; prior chemical modification of cellulose; and absence of oxygen, particularly in post-irradiation reactions. Experimental data are presented, and the direct and indirect effects of Co/sup 60/ gamma radiation on these reactions are discussed. (auth)

Standardization of equations for radiochemical calculations

International Nuclear Information System (INIS)

Danahy, R.J.; Dugan, T.A.; Tomlinson, F.K.; Jones, H.W.

1994-01-01

In mid 1993, the Fernald Environmental Restoration Management Corporation (FERMCO), with USEPA approval implemented a project quality assurance plan containing performance-based specifications for radiochemical sample analyses conducted in support of the Fernald site remediation activities. FERMCO's initial approach to acquiring performance-based radioanalytical services was to provide limited guidance regarding equations for computation of the quantities required in each analysis report. It became evident that there was a significant divergence of opinion on how to compute some very basic radiochemical quantities. The use of a standardized set of equations was needed in order to ensure comparability of data from different laboratories. In a remediation project of this magnitude, use of multiple laboratories is a virtual necessity. Consequently comparability of data becomes an extremely important issue. A critical issue in the Remedial Investigation/Feasibility Study (RI/FS) phase of the dean up project is to avoid the occurrence of excessive false positive sample results. Such results could lead to unnecessary clean up and significant additional cost. This paper describes the specific formulas FERMCO is currently using to define such quantities as net sample count rate, sample radionuclide concentration, radiometric tracer and gravimetric carrier recovery. Equations have also been produced to define the uncertainty in each of the above quantities. Equations for the Total Propagated Uncertainty (TPU) and for a sample-specific Minimum Detectable Concentration (MDC) have also been specified. Generalized equations have been reformulated to address the specific conditions which apply to the analysis of FERMCO samples. In particular, FERMCO requires results which have been corrected for the radioactivity in the blank while in other instances, sample results without blank correction are required

A comparison of the radiochemical stability of different iodine-131 labelled metaiodobenzylguanidine formulations for therapeutic use

International Nuclear Information System (INIS)

Wafelman, A.R.; Beijnen, J.H.; Hoefnagel, C.A.; Maes, R.A.A.

1994-01-01

The results of a stability study of three commercially available formulations of [ 131 I]MIBG for therapeutic use and an unstabilized formulation, stored under various conditions, are presented. The stability was followed for 20 days. In all formulations tested, free [ 131 I]iodide, formed by radiolysis, was the most important radiochemical impurity. The pharmaceutical formulation with the largest amount of stabilizer was radiochemically - but not chemically -most stable. (author)

Impact of calibration errors on CMB component separation using FastICA and ILC

Science.gov (United States)

Dick, Jason; Remazeilles, Mathieu; Delabrouille, Jacques

2010-01-01

The separation of emissions from different astrophysical processes is an important step towards the understanding of observational data. This topic of component separation is of particular importance in the observation of the relic cosmic microwave background (CMB) radiation, as performed by the Wilkinson Microwave Anisotropy Probe satellite and the more recent Planck mission, launched on 2009 May 14 from Kourou and currently taking data. When performing any sort of component separation, some assumptions about the components must be used. One assumption that many techniques typically use is knowledge of the frequency scaling of one or more components. This assumption may be broken in the presence of calibration errors. Here we compare, in the context of imperfect calibration, the recovery of a clean map of emission of the CMB from observational data with two methods: FastICA (which makes no assumption of the frequency scaling of the components) and an `Internal Linear Combination' (ILC), which explicitly extracts a component with a given frequency scaling. We find that even in the presence of small calibration errors (less than 1 per cent) with a Planck-style mission, the ILC method can lead to inaccurate CMB reconstruction in the high signal-to-noise ratio regime, because of partial cancellation of the CMB emission in the recovered map. While there is no indication that the failure of the ILC will translate to other foreground cleaning or component separation techniques, we propose that all methods which assume knowledge of the frequency scaling of one or more components be careful to estimate the effects of calibration errors.

Thorium base fuels reprocessing at the L.P.R. (Radiochemical Processes Laboratory) experimental plant

International Nuclear Information System (INIS)

Almagro, J.C.; Dupetit, G.A.; Deandreis, R.A.

1987-01-01

The availability of the LPR (Radiochemical Processes Laboratory) plant offers the possibility to demonstrate and create the necessary technological basis for thorium fuels reprocessing. To this purpose, the solvents extraction technique is used, employing TBP (at 30%) as solvent. The process is named THOREX, a one-cycle acid, which permits an adequate separation of Th 232 and U 233 components and fission products. For thorium oxide elements dissolution, the 'chopp-leach' process (installed at LPR) is used, employing a NO 3 H 13N, 0.05M FH and 0.1M Al (NO 3 ) 3 , as solvent. To adapt the pilot plant to the flow-sheet requirements proposed, minor modifications must be carried out in the interconnection of the existing decanting mixers. The input of the plant has been calculated by Origin Code modified for irradiations in reactors of the HWR type. (Author)

Rapid radiochemical ion-exchange separation of iodine from tellurium: a novel radioiodine-132 generator

Energy Technology Data Exchange (ETDEWEB)

Abrao, A

1975-01-01

Tellurium ions form a soluble cationic complex with thiourea in acid medium. The cationic tellurium-thiourea species is strongly absorbed on a cationic ion exchanger. The retention of tellurium on the resin enables many interesting separation schemes for tellurium from various ions. With special interest, the separation of iodine from tellurium was studied. An efficient and convenient iodine-132 generator is described, in which the radio-iodine is eluted with water or 9 g/1 NaCl, when desired.

Application of mercury cathode electrolysis to fission-product separation

International Nuclear Information System (INIS)

Besson, A.; Prigent, Y.; Van-Kote, F.

1969-01-01

A method involving controlled potential mercury cathode electrolysis has been developed to separate fission products. It allows the radiochemical determination of Ag, Cd, Pd, Rh, Ru, Sn, Te, Sb and Mo from solutions of fission products highly concentrated in mineral salts. The general procedure consists in three main steps: electrolytic amalgam generation, destruction of amalgams and ultimate purification of elements by other means. Electrolytic operations last about five hours. Chemical yields lie between 10 per cent and 70 per cent. (authors) [fr

Fast Breeder Reactor studies

International Nuclear Information System (INIS)

Till, C.E.; Chang, Y.I.; Kittel, J.H.; Fauske, H.K.; Lineberry, M.J.; Stevenson, M.G.; Amundson, P.I.; Dance, K.D.

1980-07-01

This report is a compilation of Fast Breeder Reactor (FBR) resource documents prepared to provide the technical basis for the US contribution to the International Nuclear Fuel Cycle Evaluation. The eight separate parts deal with the alternative fast breeder reactor fuel cycles in terms of energy demand, resource base, technical potential and current status, safety, proliferation resistance, deployment, and nuclear safeguards. An Annex compares the cost of decommissioning light-water and fast breeder reactors. Separate abstracts are included for each of the parts

Fast Breeder Reactor studies

Energy Technology Data Exchange (ETDEWEB)

Till, C.E.; Chang, Y.I.; Kittel, J.H.; Fauske, H.K.; Lineberry, M.J.; Stevenson, M.G.; Amundson, P.I.; Dance, K.D.

1980-07-01

This report is a compilation of Fast Breeder Reactor (FBR) resource documents prepared to provide the technical basis for the US contribution to the International Nuclear Fuel Cycle Evaluation. The eight separate parts deal with the alternative fast breeder reactor fuel cycles in terms of energy demand, resource base, technical potential and current status, safety, proliferation resistance, deployment, and nuclear safeguards. An Annex compares the cost of decommissioning light-water and fast breeder reactors. Separate abstracts are included for each of the parts.

Observations on the radiochemical control of radiopharmaceuticals at tajoura nuclear research center (TNRC)

International Nuclear Information System (INIS)

Abuzwida, M.A.; Saad, M.A.; Elmagrahi, H.; Elghanodi, Y.

1998-01-01

Production of radioisotopes for the radiopharmaceutical purposes is the main task of Tajoura nuclear center. During the analysis of the 131 I- radioactive solution which was produced using the so-called dry method, the following has been observed : in order to reduce the cost and the time of analytical cycle or time used for the radiochemical purity (RCP), a spot test has been used to indicate the position of the radioactivity in the chromatogram rather than using autoradiographing or the x-ray films. This method was based on the reaction between I 2 and starch to give a blue color at different R f values I 2 is liberated by I - oxidation (H 2 O 2 ) or by IO - 3 reaction with SCN - in the presence of HCl. A simple and fast test for the estimation of the content in the radioactive sample has been elaborated.This method was based on the reduction of Te (IV) or (VI) to Te metal using SnCI 2 in a alkaline media. The detection limit of the elaborated method was found to be 131 I- buffer solution, and 16.0 m S for Na CI saline solution were obtained

Assessment of radiochemical purity of [{sup 18}F]fludeoxyglucose by high pressure liquid chromatography (HPLC)

Energy Technology Data Exchange (ETDEWEB)

Lacerda, Aline E.; Silva, Juliana B.; Silveira, Marina B.; Ferreira, Soraya Z., E-mail: radiofarmacoscdtn@cdtn.b [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil). Unidade de Pesquisa e Producao de Radiofarmacos

2011-07-01

The quality control of [{sup 18}F]fludeoxyglucose ({sup 18}FDG) has received attention due to its increasing clinical use. Although the quality requirements of {sup 18}FDG are established in various pharmacopoeia, the suitability of all testing methods used should be verified under actual conditions of use and documented. The aim of this study was to develop a high pressure liquid chromatography (HPLC) method for radiochemical purity evaluation of {sup 18}FDG, based on pharmacopoeia references, and to verify its suitability for routine quality control in our centre. HPLC analysis was performed with an Agilent HPLC. {sup 18}FDG and impurities were separated on an anion-exchange column by isocratic elution with 0.1 M NaOH as the mobile phase. Detection was accomplished with refractive index and NaI (Tl) scintillation detectors. The flow rate of the mobile phase was set at 0.8 mL/min and the column temperature was kept at 35 deg C. Specificity, linearity, precision and robustness were assessed to verify if the method was adequate for its intended purpose. Retention time of {sup 18}FDG was not affected by the presence of other components of the formulation and a good peak resolution was achieved. The analytical curve of {sup 18}FDG was linear, with a correlation coefficient value of 0.9995. Intraday repeatable precision, reported as the relative standard deviation, was 0.11%. Analytical procedure remained unaffected by small variations in mobile phase flow rate. Results evidenced that HPLC is suitable for radiochemical purity evaluation of {sup 18}FDG, considering operational conditions of our laboratory. (author)

Diaphragms obtained by radiochemical grafting in PTFE

International Nuclear Information System (INIS)

Nenner, T.; Fahrasmane, A.

1984-01-01

Diaphragms for alkaline water electrolysis are prepared by radiochemical grafting of PTFE fabric with styrene, which is later on sulfonated, or with acrylic acid. The diaphragms obtained are mechanically resistant to potash at temperatures up to 200 0 C, but show some degrafting, which limits the lifetime. The sulfonated styrene group has been found to be more stable in electrolysis than the acrylic acid. In both cases, the incorporation of a cross-linking agent like divinyl benzene improves the lifetime of the diaphragms. Electrolysis during 500 hours at 120 0 C and 10 kAm 2 could be performed. (author)

Rapid radiochemical methods for preparation of sup(99m)Tc labelled compounds

International Nuclear Information System (INIS)

Narasimhan, D.V.S.; Banodkar, S.M.; Kothari, K.; Mani, R.S.

1981-01-01

Several inorganic and organic compounds incorporating sup( 99 m)Tc are being extensively used for imaging various body organs. The preparation of these sup( 99 m)Tc compounds with the necessary purity requirements is carried out by controlled reduction of sup( 99 m)Tc-pertechnetate using Sn(II) ions as the reducing agent followed by complexation with various active ingredients. The authors here present procedures developed at Radiopharmaceuticals Section of BARC for preparing sup( 99 m)Tc-diphosphonate, sup( 99 m)Tc-glucoheptonate, sup( 99 m)Tc-albumin microspheres and sup( 99 m)Tc-phytate with high radiochemical purity. The paper also describes procedures for the preparation of freeze-dried kits for single step preparation of these compounds. The paper also describes the authors' experience with various analytical procedures for the determination of radiochemical purity of these preparations. (author)

LA-ICP-MS for Trace Analysis of Long-Lived Radionuclides in Solid Non-conducting Radioactive Waste Samples

International Nuclear Information System (INIS)

Becker, J.S.; Gastel, M.; Tenzler, D.; Dietze, H.J.

1999-01-01

The characterization of radioactive waste materials from nuclear reactors for recycling and final storage requires fast, sensitive and precise analytical methods, which are able to determine long-lived radionuclidic ultra traces in a short time. For the determination of long-lived α and β ray-emitting nuclides besides the classical radiochemical methods which are mostly include time-consuming radiochemical separation procedures, to an increasing extent inductively coupled plasma mass spectrometry (ICP-MS) has been used successfully as a powerful trace, ultra trace and isotopic analytical method for the determination of long-lived radionuclides in aqueous solutions [1-3

Radiochemical and biological control of metaiodobenzyl-guanidine (MIBG) labeled with 131I

International Nuclear Information System (INIS)

Barboza, M.R.F.F. de; Muramoto, E.; Colturato, M.T.; Silva Valente Goncalves, R. da; Pereira, N.P.S. de; Almeida, M.A.T.M. de; Silva, C.P.G. da.

1988-07-01

This study shows the standardization of the radiochemical control of MIBG - 131 I in eletrophoretic system and also the biological control in Wistar rat for a period of time, not longer than 60 minutes after tracer administration. (author) [pt

Analytical and radiochemical methods in the stability study of the MIBI-Sm

International Nuclear Information System (INIS)

Isaac, M.; Leyva, R.; Gamboa, R.; Turino, D.

1997-01-01

99mT c-MIBI is a radiopharmaceutical imaging agent useful for assessing myocardial perfusion. This paper presents the stability results obtained in the radiochemical purity and others parameters in the quality control of 5 batch during more than 2 years

Determination of phosphorus in metals by neutron activation and chemical separation as hydride

International Nuclear Information System (INIS)

Rouchaud, J.C.; Fedoroff, M.

1993-01-01

Phosphorous at trace levels alters the properties of metals and alloys. Its determination was investigated by radiochemical neutron activation analysis. Separation by solvent extraction or by evolution as P 0 showed to be neither selective nor quantitative in presence of a metallic matrix. Therefore, a new method of separation by reduction to phosphorous hydride followed by liquid scintillation counting was investigated. This method is quantitative in the case of non-radioactive iron doped with radioactive phosphorus. At present, the separation is not quantitative for irradiation iron samples, owing probably to hot atom or radiation effects. A detection limit of 0.002 μg is expected. (author) 10 refs.; 1 fig.; 3 tabs

The synthesis of [O-methyl-{sup 11}C]venlafaxine: a non-classical, fast-acting antidepressant

Energy Technology Data Exchange (ETDEWEB)

Gee, A.D.; Gjedde, A. [Aarhus Univ. Hospital, PET Center, Aarhus (Denmark); Smith, D.F. [Aarhus Univ. Psychiatric Hospital, Inst. for Biological Psychiatry, Risskov (Denmark)

1997-01-01

As part of our program to develop PET tracers for the 5-HT reuptake site, venlafaxine, a non-classical, fast-acting antidepressant, was selected as a candidate for labelling with {sup 11}C for in vivo evaluation. [O-methyl-{sup 11}C]venlafaxine was produced by the alkylation of O-desmethyl venlafaxine with [{sup 11}C]methyl iodide followed by HPLC purification and formulation. Radiochemically pure [O-methyl-{sup 11}C]venlafaxine was obtained in a 30 {+-} 5% decay corrected radiochemical yield and a specific activity > 50 GBq/{mu}mol(1.4 Ci/{mu}mol) at the end of synthesis. For a typical production starting with 46 GBq (1.3 Ci) [{sup 11}C]CO{sub 2}, 5.2 GBq (140 mCi) [O-methyl-{sup 11}C]venlafaxine was obtained as a sterile, formulated solution in a synthesis time of 30 min (counted from EOB). (Author).

OPERATIONAL EXPERIENCE: UPGRADED MPC AND A SYSTEMS FOR THE RADIOCHEMICAL PLANT OF THE SIBERIAN CHEMICAL COMBINE

International Nuclear Information System (INIS)

RODRIGUEZ, C.; GOLOSKOKOV, I.; FISHBONE, L.; GOODEY, K.; LOOMIS, M.; CRAIN, B. JR.; LARSEN, R.

2003-01-01

The success of reducing the risk of nuclear proliferation through physical protection and material control/accounting systems depends upon the development of an effective design that includes consideration of the objectives of the systems and the resources available to implement the design. Included among the objectives of the design are facility characterization, definition of threat, and identification of targets. When considering resources, the designer must consider funds available, rapid low-cost elements, technology elements, human resources, and the availability of resources to sustain operation of the end system. The Siberian Chemical Combine (SCC) is a multi-function nuclear facility located in the Tomsk region of Siberia, Russia. Beginning in 1996, SCC joined with the United States Department of Energy (US/DOE) Material Protection, Control, and Accounting (MPC and A) Program to develop and implement MPC and A upgrades for the Radiochemical, Chemical Metallurgical, Conversion, Uranium Enrichment, and Reactor Plants of the SCC. At the Radiochemical Plant the MPC and A design and implementation process has been largely completed for the Plutonium Storage Facility and related areas of the Radiochemical Plant. Design and implementation of upgrades for the Radiochemical Plant include rapid physical protection upgrades such as bricking up of doors and windows, and installation of security-hardened doors. Rapid material control and accounting upgrades include installation of modern balances and bar code equipment. Comprehensive MPC and A upgrades include the installation of access controls to sensitive areas of the Plant, alarm communication and display (AC and D) systems to detect and annunciate alarm conditions, closed circuit (CCTV) systems to assess alarm conditions, central and secondary alarm station upgrades that enable security forces to assess and respond to alarm conditions, material control and accounting upgrades that include upgraded physical

Radiochemical regularities of migration mobility of Chernobyl' discharge radionuclides

International Nuclear Information System (INIS)

Skorobogat'ko, E.P.; Rybalko, S.I.

1992-01-01

Data on the radionuclude (RN) migration in environment later the Chernobyl' accident are generalized. Introduction of fallout of the radioactive discharge into environment causes necessity to account and to study different factors of geochemical and physicochemical character determining further RN behaviour in the medium. For a well-founded forecast of the behaviour it is necessity to use a complex of radiochemical and physicochemical research, lying in the base of radiation monitoring of environment. 1 refs

Separation of iodine-131 from water using isotopic exchange with iodine-starch compound

International Nuclear Information System (INIS)

Ignatov, V.P.; Kolomejtseva, I.V.

1990-01-01

Conditions of iodine isotopic exchange with iodine-starch compound (ISC) were studied with the aim of compound utilizatoin for radioactive iodine separation from solution. It is shown that in pH range from 2 to 7 the degree of iodine extraction and coefficient of its distribution practically do not depend on pH, at pH>7 ISC destruction (decolorizing) starts and iodine extraction decreases. Rapid method of iodine separation from solution is suggested. The method can be used in radiochemical techniques. The degree of extraction equals 80 %, a higher degree of extraction can not be achieved owing to ISC formation peculiarities

Application of radiochemical method under radioecological situation study in locations of radioactive wastes damping in shallow gulfs of the Novaya Zemlya Archipelago

International Nuclear Information System (INIS)

Stepanets, O.V.; Borisov, A.P.; Komarevskij, V.M.; Ligachev, A.N.; Solov'eva

2005-01-01

Results of works carried out on the 'Boris Petrov Academician' research ship on burial locations examination of submarine potential hazardous objects in the Kara Sea and in the Stepovoj, Abrosimov and Stivol'ka gulfs are cited. Comprehensive radioecological studies in the damping locations of solid radioactive wastes in the Novaya Zemlya Archipelago conducted in 2002-2004 with application of radio-chemical methods for certain radionuclides determination in the samples of bottom sediments and water in the immediate vicinity from the submerged objects are allowing to revealing the objective picture of man-caused contamination of water environment near submerged objects and by the gulfs water area. The studies uniting instrumental tools of acoustic search and visual objects inspection, opportunity of sampling of bottom sediments and near bottom water in the object vicinity and away from it with subsequent analysis of selected samples by the method of direct gamma-spectroscopy and radio-chemical concentration of certain radionuclides are permitting to obtain the statistically assisted data set on special concentrations of cesium, strontium, cobalt, plutonium radionuclides in a water layer and bottom sediments. Obtained results with taking into account of hydrological conditions allow to explain the peculiarities of radioactivity distribution in separate water areas

Radiochemical determination of {sup 210} Pb and {sup 226}Ra in petroleum sludges and scales; Determinacao radioquimica de {sup 210} Pb e {sup 226}Ra em borras e incrustacoes de petroleo

Energy Technology Data Exchange (ETDEWEB)

Araujo, Andressa Arruda de

2005-07-01

The oil extraction and production, both onshore and offshore, can generate different types of residues, such as sludge, that is deposited in the water/oil separators, valves and storage tanks and scales, which form i the inner surface of ducts and equipment. Analyses already carried out through gamma spectrometry indicated the existence of high radioisotope concentration. However, radionuclides emitting low-energy gamma-rays, such as {sup 210} Pb, are hardly detected by that technique. Consequently, there is a need to test alternative techniques to determine this and other radionuclides from the {sup 238} U series. This work, therefore, focuses on the radiochemical determination of the concentration of {sup 210}Pb, and {sup 226} Ra in samples of sludge and scale from the oil processing stations of the UN-SEAL, a PETROBRAS unit responsible for the exploration and production of petroleum in Sergipe and Alagoas. The sludge and scale samples went through a preliminary process of extraction of oil, in order to separate the solid phase, where the largest fraction of the radioactivity is concentrated. After oil removal, the samples were digested using alkaline fusion as an option for dissolution. Finally, their activity concentration was determined for the samples of sludge and scales, using and alternative radiochemical method, which is based on ionic exchange. The activity concentration found for {sup 210}Pb varied from 1,14 to 507,3 kBq kg{sup -1}. The values for {sup 226}Ra were higher, varying from 4,36 to 3.445 kBq kg{sup -1}. The results for {sup 226}Ra were then compared with the ones found for the same samples of sludge and scales using gamma spectrometry. The results of the comparison confirm the efficiency of the methodology used int hi work, that is, radiochemical determination by means of ionic exchange. (author)

Studies on some Indian paints for radiochemical plants

International Nuclear Information System (INIS)

Mahesh Kumar, V.V.; Srinivasan, R.; Natarajan, R.

1996-01-01

The choice of paints in areas subjected to contamination and radiation in nuclear installation need special attention. The types of generic coatings are examined with reference to these requirements. Among those examined, certain types of epoxy paints are found to be attractive for these applications. Samples of epoxy paints obtained from some Indian manufacturers are tested for their suitability. Decontaminability and radiation resistance properties are also evaluated with special reference to radiochemical plants. Important specifications for such applications are listed. This report summarizes the results of these studies. (author)

Fast, on the spot preparation of pure [99mTc] TRODAT-1

International Nuclear Information System (INIS)

Toth, G.; Koernyei, J.; Pavics, L.; Csiszar, M.; Szakonyi, Z.; Fueloep, F.

2002-01-01

Full text: Based on our experience a reliable preparation of the known dopamine transporter imaging agent, [ 99m Tc]TRODAT-1 could only be performed by including purification step, independently whichever published labeling method was tried. The aim of our study was to find an easy, on the spot preparation technique ensuring a stable radiochemical purity over 95 %. The precursor compound was prepared according the literature. Two series of one vial kits were aseptically prepared using 100 and 50 micrograms of free ligand. Reconstitution of the vials were carried out with 1 - 3 GBq [ 99m Tc]pertechnetate ( 100 o C, 30 min). The crude reaction mixtures were applied onto a preconditioned C 18-SepPak Light cartridge (Waters). After washing the solid phase with 15 ml of 1:50 ethanol / saline, the radioactive complex was eluted with 1 ml of 1:1 ethanol / saline solution. The separation efficiencies were monitored by dose calibrator measurements, while the radiochemical purity was determined by HPLC. All of the recorded HPLC radio-chromatograms exhibited three different peaks in the unpurified reaction mixture: peak-1 was identified as a mixture of hydrophilic technetium complexes, peak-2 was assumed as decomposition product of peak-3 ([ 99m Tc]TRODAT-1 diastereomers). It was found for both series of kits that the ratio of impurity peaks (peak-1 and 2) was increased with rising the 99m Tc activity over 1.5 GBq. Using activities below this limit, the peak ratios indicated individual features for each series. Higher ligand concentration resulted about 1:1 ratio of peak-1 and peak-2 while the amount of peak-3 was between 65 % to 95 %. The total amount of impurity peaks were significantly higher (40 to 60 %) for lower ligand concentration, but peak-2 was negligible (1 - 2 %) in this case. With introducing C18-SepPak purification step we were able to remove peak-1 completely from both series of reaction mixtures while the amount of peak-2 had been increased slightly only. The

Neutron activation analysis of ultrabasis rock by Ge(Li) γ-ray spectrometry and group separation

International Nuclear Information System (INIS)

Chen Baoguan; Yuan Ling; Fang Chanmeng

1986-01-01

The analytical procedure for determination of 21 elements in two ultrabasis rock samples with Ge(Li) gamma-ray spectrometry and group separation was described. 8 elements including Cr, Fe, Co, Sc, Mn, Na, Cl and Br have been directly determined by INAA. 13 elements including La, Ce, Nd, Sm, Gd, Eu, Tb, Ho, Tm, Yb, Lu, Zn and Cs have been determined by radiochemical separation. The samples of international standard AGV-1 (Andesite) have also been analyzed. The agreement of the results with the values proposed by F.J.Flanagan is satisfactory

A rapid radiochemical ion-exchange separation of iodine from tellurium: a novel radioiodine-132 generator

International Nuclear Information System (INIS)

Abrao, A.

1975-01-01

Tellurium ions form a soluble cationic complex with thiourea in acid medium. The cationic tellurium-thiourea species is strongly absorbed on a cationic ion exchanger. The retention of tellurium on the resin enables many interesting separation schemes for tellurium from various ions. With special interest, the separation of iodine from tellurium was studied. An efficient and convenient iodine-132 generator is described, in which the radio-iodine is eluted with water or 9 g/1 NaCL, when desired

A radio-high-performance liquid chromatography dual-flow cell gamma-detection system for on-line radiochemical purity and labeling efficiency determination

DEFF Research Database (Denmark)

Lindegren, S; Jensen, H; Jacobsson, L

2014-01-01

In this study, a method of determining radiochemical yield and radiochemical purity using radio-HPLC detection employing a dual-flow-cell system is evaluated. The dual-flow cell, consisting of a reference cell and an analytical cell, was constructed from two PEEK capillary coils to fit into the w...

Preparation, radiochemical purity control and stability of 99mTc-mertiatide (Mag-3)

International Nuclear Information System (INIS)

Van Hemert, F.J.; Schimmel, K.J.M.; Van Eck-Smit, B.L.F.; Van Lenthe, H.

2005-01-01

Scintigraphic image analysis of 99m Tc-mertiatide (Mag-3, mercaptoacetyltriglycine) clearance provides the determination of the blood flow, the tubular transit time and the excretion as well from both kidneys. Radiopharmaceutical routine recommends a radiochemical purity control before administration of the product to a patient. The main objective of this study is to develop a Mag-3 labeling procedure that fits better than the previous one in our daily routine production of radiopharmaceuticals. Increasing proportions of 99m Tc-Mag-3 were measured during the heating and cooling steps of the Mag-3 labeling procedure. High performance liquid chromatography (HPLC) analysis was used to confirm the results of a rapid radiochemical quality control assay on standard instant thin-layer chromatography-silica gel (ITLC-SG) paper. The reconstitution time takes 20-25 minutes from the harvest of pertechnetate to a ready-for-use calibrated patient syringe. The HPLC profile of 99m Tc-Mag-3 including its minor impurities remains unchanged for 24-48 hours after reconstitution. The application of a programmable Peltier-directed device for heating/cooling provides a better control of the temperature course. The procedure proposed fully meets the labeling criteria recommended by the supplier and can be performed with a minimum of attention within a time-span that we formerly needed for solely the radiochemical purity control assay. Moreover, 99m Tc-Mag-3 prepared in this way seems to be considerably more stable than mentioned in the manufacturer's instructions. (author)

Low-level simultaneous determination of As and Sb in standard reference materials using radiochemical neutron activation analysis with isotopic 77As and 125Sb tracers

International Nuclear Information System (INIS)

Byrne, A.R.

1987-01-01

The aim of the present work was to develop an older method used in our laboratory based on selective solvent extraction of As and Sb as their iodides with toluene, and by the use of the radioisotopic tracers 77 As and 125 Sb, to improve the accuracy by better control of the radiochemical yields. 77 As was produced for each sample run by concurrent irradiation of a few mg of GeO 2 followed by a rapid separation of 77 As from 77 Ge. The radiochemically purified sample fraction containing 76+77 As and 122+125 Sb was counted on a Ge detector in good geometry. The γ-lines of the four nuclides do not mutually interfere so that a combined measurement of As and Sb may be made. The method was applied to IAEA Milk Powder A-11, Animal Muscle H-4, Bowen's Kale and some other SRMs. The results obtained are discussed in the light of literature measurements. From present and previous results, together with data by Heydorn, the presently accepted value for As in Bowen's Kale of 140 ngxg -1 may be 20% too high. (orig.)

Rapid and sensitive enzymatic-radiochemical assay for the determination of triglycerides

International Nuclear Information System (INIS)

Khoo, J.C.; Miller, E.; Goldberg, D.I.

1987-01-01

An enzymatic-radiochemical method suitable for the determination of triglyceride levels of cells in culture is described. The method is based on the enzymatic hydrolysis of triglycerides to free fatty acids which then complex with 63 Ni. The method is rapid, accurate, and inexpensive. The procedure extends the sensitivity of triglyceride measurement to as low as 0.25 nanomoles

Separation process of 99Mo from 132Te using thiourea as a complex agent. Application to the separation of 99Mo from fission products

International Nuclear Information System (INIS)

Mestnik, S.A.C.; Silva, C.P.G. da

1986-01-01

A radiochemical method has been developed to separate 99 Mo from 13 2Te both produced in the fission of 235 U. The method is based on the formation of a cationic complex of tellurium with thiourea in acid medium which is retained on the cationic exchange resin (Dowex 50W-X8, 100-200 mesh) while the molyhdenum does not form such complex and passes through. The experimental results show that the retention of Te-thiourea complex on the resin is (98,3 +- 1,1) %. (Author) [pt

Determination of 210Pb and 210Po in water samples

International Nuclear Information System (INIS)

Ayranov, M.; Tosheva, Z.; Kies, A.

2004-01-01

Lead-210 and Polonium-210 are naturally occurring members of the Uranium-238 decay series. They could be found in various environmental samples, such as groundwater, fish and shellfish, contributing an important component of the human natural radiation background. For this reason the development of a fast, reproducible and sensitive method for determination of 210 Pb and 210 Po is of a great concern. The aims of our study were to adopt procedures for radiochemical separation of these radionuclides and radioanalytical methods for their determination. The combination of electrochemical deposition, co-precipitation and extraction chromatography gives the opportunity for fast and effective radiochemical separation of the analytes. Polonium was spontaneously plated on copper disk from the stock solution. Lead was co-precipitated with Fe(OH) 3 and further purified by extraction chromatography on Sr Spec columns. Alpha spectra of polonium were collected on Canberra PIPS detectors with 900 mm 2 active surface. The activities of lead were determined by LSC (Gardian Wallac Oy). The minimum detectable activities for sample size 1000 mL and chemical yield of 88 % for the polonium and 85 % for the lead are presented. The proposed method proved to be fast, accurate and reproducible for routine determination of lead and polonium in environmental water samples. (authors)

The use of cuprous iodide as a precipitation matrix in the radiochemical determination of 131I in milk

International Nuclear Information System (INIS)

McCurdy, D.E.; Mellor, R.A.; Lambdin, R.W.; McLain, M.E. Jr.

1980-01-01

As a result of the implementation of the As Low As is Reasonably Achievable philosophy to the nuclear power industry, recent U.S. Nuclear Regulatory Commission requirements have prompted high sensitivity radiochemical analysis for the measurement of 131 I in milk. The most recognized and commonly employed technique incorporates costly palladium iodide as the final precipitate in the radiochemical purification of the iodine chemical species. The procedure presented in this paper outlines the many advantages of using cuprous iodide as the final precipitate. These include lower cost per analysis, consistent recoveries, better precipitate matrix and good self absorption characteristics. Typical lower limit of detection values and operating characteristics obtained for high sensitivity β-γ analysis as well as gas proportional counting and a comparison of radiochemical and Ge(Li) spectrometric results for environmental samples collected during a recent Chinese weapons fallout incident are presented. (author)

III Scientific-technical conference. Problems and outlooks for development of chemical and radiochemical control in atomic energetics (Atomenergoanalytics-2005). Summaries of reports

International Nuclear Information System (INIS)

2005-01-01

Summaries of reports of the III Scientific-technical conference: Problems and outlooks for development of chemical and radiochemical control in atomic energetics (Atomenergoanalytics-2005) are presented. The conference performed 20-22 September, 2005, in Sosnovyj Bor. Problems of methodical, instrumental and metrological supply of chemical, radiochemical and radiometric control at active NPP and NPU, modern concepts of construction of automated systems of chemical and radiometric control in the atomic energetics, directions for the decision of questions in organization and conducting of chemical and radiochemical control of water-chemical regimes of NPP and NPU are discussed [ru

Mixing and sampling tests for Radiochemical Plant

International Nuclear Information System (INIS)

Ehinger, M.N.; Marfin, H.R.; Hunt, B.

1999-01-01

The paper describes results and test procedures used to evaluate uncertainly and basis effects introduced by the sampler systems of a radiochemical plant, and similar parameters associated with mixing. This report will concentrate on experiences at the Barnwell Nuclear Fuels Plant. Mixing and sampling tests can be conducted to establish the statistical parameters for those activities related to overall measurement uncertainties. Density measurements by state-of-the art, commercially availability equipment is the key to conducting those tests. Experience in the U.S. suggests the statistical contribution of mixing and sampling can be controlled to less than 0.01 % and with new equipment and new tests in operating facilities might be controlled to better accuracy [ru

On-line separation of Pu(III) and Am(III) using extraction and ion chromatography

International Nuclear Information System (INIS)

Jernstroem, J.; Lehto, J.; Betti, M.

2007-01-01

An on-line method developed for separating plutonium and americium was developed. The method is based on the use of HPLC pump with three analytical chromatographic columns. Plutonium is reduced throughout the procedure to trivalent oxidation state, and is recovered in the various separation steps together with americium. Light lanthanides and trivalent actinides are separated with TEVA resin in thiocyanate/formic acid media. Trivalent plutonium and americium are pre-concentrated in a TCC-II cation-exchange column, after which the separation is performed in CS5A ion chromatography column by using two different eluents. Pu(III) is eluted with a dipicolinic acid eluent, and Am(III) with oxalic acid eluent. Radiochemical and chemical purity of the eluted plutonium and americium fractions were ensured with alpha-spectrometry. (author)

Advanced system for separation of rare-earth fission products

International Nuclear Information System (INIS)

Baker, J.D.; Gehrke, R.J.; Greenwood, R.C.; Meikrantz, D.H.

1982-01-01

A microprocessor-controlled radiochemical separation system has been further advanced to separate individual rare-earth elements from mixed fission products in times of a few minutes. The system was composed of an automated chemistry system fed by two approximately 300 μg 252 Cf sources coupled directly by a He-jet to transport the fission products. Chemical separations were performed using two high performance liquid chromatography columns coupled in series. The first column separated the rare-earth group by extraction chromatography using dihexyldiethylcarbamoylmethylphosphonate (DHDECMP) adsorbed on Vydac C 8 resin. The second column isolated the individual rare-earth elements by cation exchange chromatography using Aminex A-9 resin with α-hydroxyisobutyric acid (α-HIBA) as the eluent. Significant results, which have been obtained to date with this advanced system, are the identification of several new neutron-rich rare-earth isotopes including 155 Pm (T=48+-4 s) and 163 Gd (T=68+-3 s). In addition, a half-life of 41+-4 s is reported for 160 Eu. (author)

Automation of radiochemical analysis by flow injection techniques. Am-Pu separation using TRU-resinTM sorbent extraction column

International Nuclear Information System (INIS)

Egorov, O.; Washington Univ., Seattle, WA; Grate, J.W.; Ruzicka, J.

1998-01-01

A rapid automated flow injection analysis (FIA) procedure was developed for efficient separation of Am and Pu from each other and from interfering matrix and radionuclide components using a TRU-resin TM column. Selective Pu elution is enabled via on-column reduction. The separation was developed using on-line radioactivity detection. After the separation had been developed, fraction collection was used to obtain the separated fractions. In this manner, a FIA instrument functions as an automated separation workstation capable of unattended operation. (author)

Simple and fast fabrication of superhydrophobic metal wire mesh for efficiently gravity-driven oil/water separation.

Science.gov (United States)

Song, Botao

2016-12-15

Superhydrophobic metal wire mesh (SMWM) has frequently been applied for the selective and efficient separation of oil/water mixture due to its porous structure and special wettability. However, current methods for the modification of metal wire mesh to be superhydrophobic suffered from problems with respect to complex experimental procedures or time-consuming process. In this study, a very simple, time-saving and single-step electrospray method was proposed to fabricate SMWM and the whole procedure required about only 2min. The morphology, surface composition and wettability of the SMWM were all evaluated, and the oil/water separation ability was further investigated. In addition, a commercial available sponge covered with SMWM was fabricated as an oil adsorbent for the purpose of oil recovery. This study demonstrated a convenient and fast method to modify the metal wire mesh to be superhydrophobic and such simple method might find practical applications in the large-scale removal of oils. Copyright © 2016 Elsevier Ltd. All rights reserved.

A radiochemical analyses of metastudtite and leachates from spent fuel

International Nuclear Information System (INIS)

McNamara, Bruce K.; Hanson, Brady D.; Buck, Edgar C.; Soderquist, Chuck Z.

2004-01-01

Immersion of commercial spent nuclear fuel (CSNF) in deionized water produced two novel corrosion products after a two-year contact period. Another unexpected result was that suspensions of aggregates were observed to form at the air-water interface for each of five samples. These solids were characterized, by SEM and XRD to be nearly pure metastudtite (UO4-2H2O); while the corrosion present on the surface of the fuel itself was determined to be studtite (UO4-2H2O). The occurrence of the floating phase prompted a radiochemical analysis of these solids. This chemical analysis was a unique opportunity to study the relatively pure corrosion phase for incorporation of radionuclides. The analysis indicated that high concentration of 90Sr, 137Cs, 99Tc, and that lower concentrations 237Np, 238, 239Pu and 243, 244Cm had partitioned with the air-water interface aggregates. The concentrations of 241Am were two orders of magnitude lower than the expected inventory in the suspended solids. The radiochemical analyses of the several leachate samples provide preliminary solubility data for the hydrogen peroxide leaching of CSNF and these data are compared to leaching of the same fuel in J-13 and deionized waters. The extent of fuel dissolution in these media are discussed

Triphenyl phosphine oxide as a substoichiometric radiochemical reagent: Determination of thallium

International Nuclear Information System (INIS)

Reddy, P.C.; Polaiah, B.; Rangamannar, B.

1991-01-01

A rapid radiochemical method has been developed for the determination of microgram amounts of thallium based on the substoichiometric extraction of its ocmplex with triphenylphosphine oxide into benzene from 6 M sulphuric acid. 10-90 μg of thallium was determined with an average error of 2.06%. The effect of diverse metal ions on the extraction was studied. (orig.)

Determination of the radiochemical purity of phosphorus-32 and tritium-labeled diisopropylphosphorofluoridate (DFP)

International Nuclear Information System (INIS)

Christopher, R.E.; Sheppard, G.

1975-01-01

A method is described for the determination of the radiochemical purity of labeled diisopropylphosphorofluoridate (DFP), based on the irreversible inhibition reaction with the enzyme α-chymotrypsin. The nature of the impurities in commercially available 32 P- and 3 H-labeled DFP is discussed

Radiochemical syntheses further radiopharmaceuticals for positron emission tomography and new strategies for their production

CERN Document Server

Kilbourn, Michael R; Kilbourn, Michael R

2015-01-01

This book describes methods and procedures for preparing PET radiopharmaceuticals, and highlights new methods for conducting radiochemical reactions with carbon-11 (C11) and fluorine-18 (F18), which are two of the most commonly used radionuclides in positron emission tomography (PET) imaging.     Provides reliable methods for radiochemical syntheses and reactions, including all essential information to duplicate the procedure     Eliminates the time-consuming process of searching journal articles and extracting pertinent details from lengthy experimental sections or supporting information     Focuses on an emerging and important area for pharmaceutical and medical applications     Encompasses technical, regulatory, and application aspects     Includes solid-phase radiochemistry, transition-metal catalyzed radiochemistry, microfluidics, click chemistry, green radiochemistry and new strategies for radiopharmaceutical quality control.

An overview of the status of radiochemical analysis in Hungary

International Nuclear Information System (INIS)

Solymosi, J.; Toth, G.

1994-01-01

This overview covers the following activities at radioanalytical laboratories in Hungary: tracer techniques and their applications; some important new results; radioimmunoassay; x-ray emission analysis and x-ray fluorescence analysis, Moessbauer-spectroscopy and their applications in various fields of science and technology; neutron activation analysis; radiochemical analysis for nuclear power plant applications activities in various laboratories; nuclear environmental analysis (radioanalytical methods for the investigation of contamination by nuclear facilities). (N.T.) 1 fig.; 7 tabs

Phase separator safety valve blow-off.

CERN Multimedia

G. Perinic

2006-01-01

The fast discharge of the CMS solenoid leads to a pressure rise in the phase separator. On August 28th, a fast discharge was triggered at a current level of 19.1 kA. The pressure in the phase separator increased up to the set pressure of the safety valve and some helium was discharged. In consequence of this and prevoious similar observations the liquid helium level in the phase separator has been reduced from 60% to 50% and later to 45% in order to reduce the helium inventory in the magnet.

Radiochemical aging of an epoxy network; Vieillissement radiochimique d'un reseau epoxyde

Energy Technology Data Exchange (ETDEWEB)

Devanne, Th

2003-05-01

This thesis is to give a better understanding of the radiochemical aging of a thermoset resin under gamma irradiation. The conditions of aging are gamma irradiation under air with a dose rate of 2 kGy/h at 120 C. The requested lifetime is four years, it means a dose of 70 MGy. The first step of this work was the choice of a resistive epoxy resin. This choice was made thanks to the literature data. The high glass transition temperature and the high amount of aromatic groups were the main criteria of the final choice. After this choice, thermal and mechanical properties were followed under thermal and radiochemical aging: i) under thermal aging, after 600 hours at 220 C, the glass transition temperature remained unchanged. But, from a mechanical point of view, properties at break dramatically decreased. This embrittlement was assigned to a critical oxidized layer. The thickness of this layer was estimated about 30 {mu}m. ii) the same kind of embrittlement was observed under radiochemical aging. Moreover, it appeared a decrease of the glass transition temperature when increasing the dose of irradiation. This indicates that the main degradation mechanism is chain scission under anaerobic atmosphere. We, then, proposed a mechanistic model associated with a kinetic model to predict the evolution of the glass transition temperature depending on the irradiation conditions. Parameters of the kinetic model were determined by solid NMR and ESR experiments. Comparison between experimental and calculated values at 120 C is satisfactory, a global good agreement was found. (author)

On the radiochemical purity of elementary 35S with high specific activity

International Nuclear Information System (INIS)

Todorovsky, D.S.; Kostadinov, K.N.; Efremova, Yu.N.

1979-01-01

Radiochemical composition and chemical changes with increasing storage time of benzene solutions and of solid species of elementary 35 S with high specific activity are studied. The dependence of the stability on the specific activity and the radioactive concentration is shown and some tentative limits are given for permissible storage periods. (author)

Use of fast reactors for actinide transmutation

International Nuclear Information System (INIS)

1993-03-01

The management of radioactive waste is one of the key issues in today's discussions on nuclear energy, especially the long term disposal of high level radioactive wastes. The recycling of plutonium in liquid metal fast breeder reactors (LMFBRs) would allow 'burning' of the associated extremely long life transuranic waste, particularly actinides, thus reducing the required isolation time for high level waste from tens of thousands of years to hundreds of years for fission products only. The International Working Group on Fast Reactors (IWGFR) decided to include the topic of actinide transmutation in liquid metal fast breeder reactors in its programme. The IAEA organized the Specialists Meeting on Use of Fast Breeder Reactors for Actinide Transmutation in Obninsk, Russian Federation, from 22 to 24 September 1992. The specialists agree that future progress in solving transmutation problems could be achieved by improvements in: Radiochemical partitioning and extraction of the actinides from the spent fuel (at least 98% for Np and Cm and 99.9% for Pu and Am isotopes); technological research and development on the design, fabrication and irradiation of the minor actinides (MAs) containing fuels; nuclear constants measurement and evaluation (selective cross-sections, fission fragments yields, delayed neutron parameters) especially for MA burners; demonstration of the feasibility of the safe and economic MA burner cores; knowledge of the impact of maximum tolerable amount of rare earths in americium containing fuels. Refs, figs and tabs

Standard method of test for atom percent fission in uranium fuel - radiochemical method

International Nuclear Information System (INIS)

Anon.

The determination of the U at. % fission that has occurred in U fuel from an analysis of the 137 Cs ratio to U ratio after irradiation is described. The method is applicable to high-density, clad U fuels (metal, alloys, or ceramic compounds) in which no separation of U and Cs has occurred. The fuels are best aged for several months after irradiation in order to reduce the 13-day 136 Cs activity. The fuel is dissolved and diluted to produce a solution containing a final concentration of U of 100 to 1000 mg U/l. The 137 Cs concentration is determined by ASTM method E 320, for Radiochemical Determination of Cesium-137 in Nuclear Fuel Solutions, and the U concentration is determined by ASTM method E 267, for Determination of Uranium and Plutonium Concentrations and Isotopic Abundances, ASTM method E 318, for Colorimetric Determination of Uranium by Controlled-Potential Coulometry. Calculations are given for correcting the 137 Cs concentration for decay during and after irradiation. The accuracy of this method is limited, not only by the experimental errors with which the fission yield and the half-life of 137 Cs are known

Radiochemical trace analysis methods: Development and application of a fast and very sensitive procedure to determine long-living neutron activation products

Energy Technology Data Exchange (ETDEWEB)

Schupfner, R [Environmental Radioactivity Lab., Regensburg Univ. (Germany); Koenig, W [Environmental Radioactivity Lab., Regensburg Univ. (Germany); Scheuerer, C [Environmental Radioactivity Lab., Regensburg Univ. (Germany); Schuettelkopf, H [Environmental Radioactivity Lab., Regensburg Univ. (Germany)

1997-03-01

The first purification step is a preconcentration of Fe-55 or Ni-63/59 respectively using the chelaing resin column CHELEX 100. This chelating resin is composed of a styrene-divinyl-benzene polymer as a carrier of the iminoacetic groups. In the past CHELEX 100 has been used for reconcentrating heavy metal ions in sea water or spring water. At low pH values this chelating resin is able to preconcentrate Fe-55 or Ni-63/59 respectively. Undesireable ions from the sample material e.g. Na{sup +}, K{sup +}, Mg{sup 2+}, Ca{sup 2+}, SiO{sub 4}{sup 2-}, SO{sub 4}{sup 2-}, PO{sub 4}{sup 3-} are completely removed. Because of its not jet sufficient selectivity various highly selective and fast purification steps including anion exchange to separate Co-60 and liquid-liquid extraction with diisopropylether for Fe-55 and chloroform for Ni-63/59 are applied to obtain a diluted sulfuric acided solution which can be mixed with a suitable scintillation cocktail and measured by means of liquid scintillation counting (LSC). (orig./DG)

Self-decomposition of radiochemicals. Principles, control, observations and effects

International Nuclear Information System (INIS)

Evans, E.A.

1976-01-01

The aim of the booklet is to remind the established user of radiochemicals of the problems of self-decomposition and to inform those investigators who are new to the applications of radiotracers. The section headings are: introduction; radionuclides; mechanisms of decomposition; effects of temperature; control of decomposition; observations of self-decomposition (sections for compounds labelled with (a) carbon-14, (b) tritium, (c) phosphorus-32, (d) sulphur-35, (e) gamma- or X-ray emitting radionuclides, decomposition of labelled macromolecules); effects of impurities in radiotracer investigations; stability of labelled compounds during radiotracer studies. (U.K.)

Guiding Principles for Sustainable Existing Buildings: Radiochemical Processing Laboratory

Energy Technology Data Exchange (ETDEWEB)

Pope, Jason E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2013-11-11

In 2006, the United States (U.S.) Department of Energy (DOE) signed the Federal Leadership in High Performance and Sustainable Buildings Memorandum of Understanding (MOU), along with 21 other agencies. Pacific Northwest National Laboratory (PNNL) is exceeding this requirement and, currently, about 25 percent of its buildings are High Performance and Sustainable Buildings. The pages that follow document the Guiding Principles conformance effort for the Radiochemical Processing Laboratory (RPL) at PNNL. The RPL effort is part of continued progress toward a building inventory that is 100 percent compliant with the Guiding Principles.

Radiochemical separation and ICP-AES determination of some common metallic elements in ThO2 matrix

International Nuclear Information System (INIS)

Adya, V.C.; Hon, N.S.; Bangia, T.R.; Sastry, M.D.; Iyer, R.H.

1997-01-01

Radioactive tracer and also ICP-AES studies have been carried out to determine Al, Cd, Ca, Cr, Co, Cu, Mn, Mo and Pd in ThO 2 matrix after chemical separation. Di-2-ethyl-hexyl phosphoric acid/xylene/HNO 3 extraction system was used for quantitative separation of thorium. The recovery of elements as determined by tracers and ICP-AES was found to be quantitative within experimental error. (author). 3 refs., 1 tab

Leakage evaluation in the PCV (Primary Containment Vessel) using chemical and radiochemical data

International Nuclear Information System (INIS)

Maeda, Katsuji; Nagasawa, Katsumi

1998-01-01

Keeping the reliability of nuclear power plant operation, the primary coolant leakage in the PCV is strictly restricted by the Technical Specifications. It is very important to detect an indication of leakage and estimate the source of leakage to provide countermeasures. Usually the indication of leakage will be detected by increase of drain flow in the PCV sump. There are some possibilities of leakage sources in the PCV, such as reactor water, main steam, condensate, feedwater and closed cooling water. The leakage source contain different chemical and radiochemical species. This means that the leakage source can be presumed and detected by using chemical information from the PCV atmosphere and sump water. To detect the leakage indication and the source quickly and exactly, the PCV Leakage Detection Expert System has been developed. This paper describes how to evaluate the leakage indication and source in the PCV by using chemical and radiochemical data. (author)

Computer aided piping layout design in radiochemical plants- an improved software package

International Nuclear Information System (INIS)

Raju, R.P.; Siddiqui, H.R.

1995-01-01

A software package was developed and it was successfully implemented for the piping layout design of the four process cells of the Kalpakkam Reprocessing Project. This paper discusses in detail all the improvements and modifications that are being carried out in the package so that it becomes more meaningful and useful for implementation for the forthcoming radiochemical plants

Radiochemical study of 45Sc(n,p)45Ca and 89Y(n,p)89Sr reactions in the neutron energy range of 13.9 to 14.7 MeV

International Nuclear Information System (INIS)

Molla, N.I.; Basunia, S.; Miah, M.R.; Hossain, S.M.; Rahman, M.M.; Spellerberg, S.; Qaim, S.M.

1998-01-01

Cross sections for 45 Sc(n,p) 45 Ca and 89 Y(n,p) 89 Sr reactions were measured using the activation technique. Monoenergetic neutrons in the energy range of 13.9 to 14.7 MeV were produced using a D-T neutron generator. The purely β - emitting products 45 Ca and 89 Sr were separated radiochemically; their radioactivity was assayed via low-level β - counting. The measured data complement the available published experimental information, and agree with the results of statistical model calculations. (orig.)

Facility Effluent Monitoring Plan for the 325 Radiochemical Processing Laboratory

International Nuclear Information System (INIS)

Shields, K.D.; Ballinger, M.Y.

1999-03-01

This Facility Effluent Monitoring Plan (FEMP) has been prepared for the 325 Building Radiochemical Processing Laboratory (RPL) at the Pacific Northwest National Laboratory (PNNL) to meet the requirements in DOE Order 5400.1, ''General Environmental Protection Programs.'' This FEMP has been prepared for the RPL primarily because it has a ''major'' (potential to emit >0.1 mrem/yr) emission point for radionuclide air emissions according to the annual National Emission Standards for Hazardous Air Pollutants (NESHAP) assessment performed. This section summarizes the airborne and liquid effluents and the inventory based NESHAP assessment for the facility. The complete monitoring plan includes characterization of effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements. The RPL at PNNL houses radiochemistry research, radioanalytical service, radiochemical process development, and hazardous and radioactive mixed waste treatment activities. The laboratories and specialized facilities enable work ranging from that with nonradioactive materials to work with picogram to kilogram quantities of fissionable materials and up to megacurie quantities of other radionuclides. The special facilities within the building include two shielded hot-cell areas that provide for process development or analytical chemistry work with highly radioactive materials and a waste treatment facility for processing hazardous, mixed radioactive, low-level radioactive, and transuranic wastes generated by PNNL activities

Facility Effluent Monitoring Plan for the 325 Radiochemical Processing Laboratory

Energy Technology Data Exchange (ETDEWEB)

Shields, K.D.; Ballinger, M.Y.

1999-04-02

This Facility Effluent Monitoring Plan (FEMP) has been prepared for the 325 Building Radiochemical Processing Laboratory (RPL) at the Pacific Northwest National Laboratory (PNNL) to meet the requirements in DOE Order 5400.1, ''General Environmental Protection Programs.'' This FEMP has been prepared for the RPL primarily because it has a ''major'' (potential to emit >0.1 mrem/yr) emission point for radionuclide air emissions according to the annual National Emission Standards for Hazardous Air Pollutants (NESHAP) assessment performed. This section summarizes the airborne and liquid effluents and the inventory based NESHAP assessment for the facility. The complete monitoring plan includes characterization of effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements. The RPL at PNNL houses radiochemistry research, radioanalytical service, radiochemical process development, and hazardous and radioactive mixed waste treatment activities. The laboratories and specialized facilities enable work ranging from that with nonradioactive materials to work with picogram to kilogram quantities of fissionable materials and up to megacurie quantities of other radionuclides. The special facilities within the building include two shielded hot-cell areas that provide for process development or analytical chemistry work with highly radioactive materials and a waste treatment facility for processing hazardous, mixed radioactive, low-level radioactive, and transuranic wastes generated by PNNL activities.

Lanthanide fission product separation from the transuranics in the integral fast reactor fuel cycle demonstration

International Nuclear Information System (INIS)

Goff, K.M.; Mariani, R.D.; Benedict, R.W.; Ackerman, J.P.

1993-01-01

The Integral Fast Reactor (IFR) is an innovative reactor concept being developed by Argonne National Laboratory. This reactor uses liquid-metal cooling and metallic fuel. Its spent fuel will be reprocessed using a pyrochemical method employing molten salts and liquid metals in an electrofining operation. The lanthanide fission products are a concern during reprocessing because of heating and fuel performance issues, so they must be removed periodically from the system to lessen their impact. The actinides must first be removed form the system before the lanthanides are removed as a waste stream. This operation requires a relatively good lanthanide-actinide separation to minimize both the amount of transuranic material lost in the waste stream and the amount of lanthanides collected when the actinides are first removed. A computer code, PYRO, that models these operations using thermodynamic and empirical data was developed at Argonne and has been used to model the removal of the lanthanides from the electrorefiner after a normal operating campaign. Data from this model are presented. The results demonstrate that greater that 75% of the lanthanides can be separated from the actinides at the end of the first fuel reprocessing campaign using only the electrorefiner vessel

Testing the radiochemical purity of a radiopharmaceutical: study of 99mTc-Tetrofosmin (Myoview)

International Nuclear Information System (INIS)

Moati, F.; Quartarone, C.; Jourdain, J.R.; Rizzo, N.; Dumont, A.; De Beco, V.; Ait Ben Ali, S.; Lours, S.; Piketty, M.L.; Izembart, M.; Goudou, C.; Lemercier, V.; Schlageter, M.H.; Moretti, J.L.; Progent, A.

1997-01-01

The goal of this study is to optimize the testing method of radiochemical purity (RCP) of 99m Tc-Tetrofosmin proposed by the Amersham Company: thin-layer chromatography (TLC); ITLC-SG support, migration on 15 Cm; acetone-dichloromethane mobile phase, (35/65, v/v), This technique allows separating the reduced-Tc (Rf = 0), the TcO 4 - (Rf = 1), and in intermediary position (0.2 99m Tc-Tetrofosmin. The results of RCP depend on working conditions, particularly, on the volume of deposit (10 to 20 μl, expected). If the deposited is too small, the 99m Tc-Tetrofosmin does not migrate. With a volume of 20 μl, the separation is weak and the peak width is un-resolvable. The results obtained correspond to the following operational conditions: migration on 8 cm; deposit of 8 to 10 μl; no drying. In these conditions the peak of 99m Tc-Tetrofosmin is well singled out: migration Rf of 0.375 to 0.625. These results have been obtained by the analysis of radio-chromatographic peak. Every strip has been cut cm by cm and the activity was measured by a gamma counter. Repeatability of the method on a series of 8 tests is good: average RCP 93.22%, mean value = 93.24%. The reproducibility was realized by measuring directly by the activity-meter the activity corresponding to 3 identifiable peaks: Reduced Tc (Rf 4 - (Rf 99m Tc-Tetrofosmin (0.25 < Rf < 0.75). On the 21 effectuated tests the inter-test RCP reproducibility was good: average value = 95.24%, CV = 2.07%, mean value 95.3%). In conclusion, the miniaturization improves the separation by Myoview (0.25 < Rf < 0.75), diminishes the migration time by a factor 4 and lowers the reactive cost of testing by 50%

Safety decommissioning regulations of radiochemical objects - the problem, requires urgent decision

International Nuclear Information System (INIS)

Rovnyj, S.I.; Arsent'eva, N.V.; Emel'yanov, N.M.; Kolesnikov, V.N.

2001-01-01

The necessity of planning and pursuance of the measures on decommissioning of radiochemical industry is discussed. Technological processes were stopped more than in 30 buildings and constructions of the PO Mayak. The characteristics of the technological buildings to be decommissioned were treated in the context of building peculiarities, function, character and level of contamination. An acceptable variant for reactor decommissioning invites development of the standard-legal aspects [ru

Novel Protic Ionic Liquid Composite Membranes with Fast and Selective Gas Transport Nanochannels for Ethylene/Ethane Separation.

Science.gov (United States)

Dou, Haozhen; Jiang, Bin; Xiao, Xiaoming; Xu, Mi; Tantai, Xiaowei; Wang, Baoyu; Sun, Yongli; Zhang, Luhong

2018-04-25

Protic ionic liquids (PILs) were utilized for the fabrication of composite membranes containing silver salt as the C 2 H 4 transport carrier to perform C 2 H 4 /C 2 H 6 separation for the first time. The intrinsic nanostructures of PILs were adopted to construct fast and selective C 2 H 4 transport nanochannels. The investigation of structure-performance relationships of composite membranes suggested that transport nanochannels (polar domains of PILs) could be tuned by the sizes of cations, which greatly manipulated activity of the carrier and determined the separation performances of membranes. The role of different carriers in the facilitated transport was studied, which revealed that the PILs were good solvents for dissolution and activation of the carrier due to their hydrogen bond networks and waterlike properties. The operating conditions of separation process were investigated systemically and optimized, confirming C 2 H 4 /C 2 H 6 selectivity was enhanced with the increase of silver salt concentration, the flow rate of sweep gas, and the feed ratio of C 2 H 4 to C 2 H 6 , as well as the decrease of the transmembrane pressure and operating temperature. Furthermore, the composite membranes exhibited long-term stability and obtained very competitive separation performances compared with other results. In summary, PIL composite membranes, which possess good long-term stability, high C 2 H 4 /C 2 H 6 selectivity, and excellent C 2 H 4 permeability, may have a good perspective in industrial C 2 H 4 /C 2 H 6 separation.

Requirement of radiochemical recovery determination for gross alpha and gross beta estimation in drinking water

International Nuclear Information System (INIS)

Raveendran, Nanda; Rao, D.D.; Hegde, A.G.

2010-01-01

Presence of radionuclides in drinking water which emits Alpha and Beta particles are the potential sources of internal exposure in drinking water. Gross alpha and gross beta determination in drinking water and packaged drinking water (PDW) as per BIS (Bureau of Indian standards) standards is discussed here. The methods have been tested to account for losses in the radiochemical procedures using radionuclides such as 137 Cs, 90 Sr, 226 Ra, 239 Pu, 243 Am, 232 U. The methods have also been validated in an IAEA proficiency test conducted during 2009. Monitoring of gross alpha and gross beta activity observed in drinking water/packaged drinking water from various states of India were within the limits set by BIS. Average radiochemical recoveries of 84% and 63% were obtained for gross α and gross β respectively. (author)

New radiochemistry techniques monograph: open-quotes Ultrafast chemical separationsclose quotes

International Nuclear Information System (INIS)

Ypsilanti, M.I.; Meyer, R.A.; Rengan, K.

1992-01-01

Study of decay characteristics of short-lived nuclides has fascinated nuclear chemists ever since the discovery of radioactivity. In the last two decades nuclides with half-lives in the range of several seconds to several tens of seconds have been explored. In addition to manual procedures, several automatic batch (autobatch) as well as continuous separation procedures have been developed for the study of these nuclides. The first part of the radiochemical techniques monograph entitled open-quotes Ultrafast Chemical Separationsclose quotes reviews the techniques used in fast separations. A collection of known fast procedures, arranged according to the name of the element, is presented in the second part. A total of 316 procedures for 75 elements are included

Standard test methods for chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of nuclear-grade uranyl nitrate solutions

CERN Document Server

American Society for Testing and Materials. Philadelphia

1999-01-01

1.1 These test methods cover procedures for the chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of nuclear-grade uranyl nitrate solution to determine compliance with specifications. 1.2 The analytical procedures appear in the following order: Sections Determination of Uranium 7 Specific Gravity by Pycnometry 15-20 Free Acid by Oxalate Complexation 21-27 Determination of Thorium 28 Determination of Chromium 29 Determination of Molybdenum 30 Halogens Separation by Steam Distillation 31-35 Fluoride by Specific Ion Electrode 36-42 Halogen Distillate Analysis: Chloride, Bromide, and Iodide by Amperometric Microtitrimetry 43 Determination of Chloride and Bromide 44 Determination of Sulfur by X-Ray Fluorescence 45 Sulfate Sulfur by (Photometric) Turbidimetry 46 Phosphorus by the Molybdenum Blue (Photometric) Method 54-61 Silicon by the Molybdenum Blue (Photometric) Method 62-69 Carbon by Persulfate Oxidation-Acid Titrimetry 70 Conversion to U3O8 71-74 Boron by ...

Production and radiochemical separation of 203Pb radioisotope for nuclear medicine

International Nuclear Information System (INIS)

Szuecs, Z.; Takacs, S.; Andrasi, D.; Kovacs, B.

2012-01-01

Complete text of publication follows. The heavy metal pollution due to their industrial production, waste repository or accident as the cyanide spill in river Tisza in 2002, increase the scientific interest for using an ideal trace isotope for monitoring these type of events. The lead is one of the most toxic and commonly used heavy metal, its poisoning is often deadly because very difficult to recognize and identify. The neuro-scientific study of biodegradation effect of lead could be an impressive scientific field of application of 203 Pb radioisotope. However the targeted radionuclide therapy especially the α-emitting radioisotope therapy is also strongly interested to find an ideal tracer for the 213 Bi and 212 Pb therapy. Therefore the 203 Pb is a potential radioisotope for this role due to its radiation behaviour and as heavy metal element. The 203 Tl(p,n) 203 Pb nuclear reaction was chosen for the production. The irradiation was done at the compact cyclotron of Atomki with proton beam 14.5 MeV energy and beam current of 7 μAs. The thickness of the target material was 840 μm, the irradiation time was 3 hours and the produced activity was 40 MBq at EOB. It corresponds to 1.87 MBq/μAh physical yield of the reaction which correlating with the cross section curve. A new technique was developed for target preparation. The metal Tl was pressed into a copper backing and covered with a HAWAR foil with thickness of 11 μm. The covering foil saved the surface of the Tl from the oxidation and also transferred the dissipating heat to the cooling He gas. The back side of the target was cooled with pressured cold water. The irradiated Tl target was pressed out from the copper backing, which had only the thickness of 0.2 mm. Then the Thallium was dissolved in nitric acid. The excess acid was evaporated slowly. The nitrate form was transferred to chloride form by 8 mol/dm 3 HCl and the Thallium was kept in 3+ oxidation stage by hydrogen peroxide. The separation was

Separation and determination of radiostrontium in calcium carbonate matrices of biological origin

International Nuclear Information System (INIS)

Clark, S.B.

1994-01-01

Radiostrontium is concentrated in the shells of mollusks and other animals due to the isomorphic substitution of strontium for calcium in the calcium carbonate shell matrix. Radiochemical separation of strontium from such matrices is difficult because of the chemical similarity between strontium and calcium. This paper describes a technique using a commercially-available, solid-phase extractant to separate Sr-89 and Sr-90 from high concentrations of Ca 2+ . The extractant removes Sr(NO 3 ) 2 from acidic nitrate media, and strontium activities are determined via conventional β-counting techniques. This method has been used to process mollusk shells collected from contaminated reactor cooling ponds at the Savannah River Site and Chernobyl Nuclear Power Plant. (author). 13 refs., 2 figs., 2 tabs

Fast response system for vacuum volume emergency separation

International Nuclear Information System (INIS)

Gubrienko, K.I.; Lastochkin, Yu.A.

1982-01-01

A system which allows to separate vacuum systems of the magnetic-optic beam channels connected with the accelerator has been worked out for case of emergency environment break through the extraction ''window''. The system, consisting of two valve - gate devices and a control unit, allows one in the emergency case to separate more than 20 m long volume from the accelerator without any pressure changes in the latter one

Facile Synthesis of Flexible Methylsilsesquioxane Aerogels with Surface Modifications for Sound- Absorbance, Fast Dye Adsorption and Oil/Water Separation

Directory of Open Access Journals (Sweden)

Xingzhong Guo

2018-04-01

Full Text Available New flexible methylsilsesquioxane (MSQ aerogels have been facilely prepared by a sol–gel process with methyltrimethoxysilane (MTMS and dimethyldimethoxysilane (DMDMS as co-precursors, followed by surface modification and ambient pressure drying. The microstructure, mechanical properties and hydrophobicity of these MSQ aerogels after surface modifications of hexamethyldisiloxane (HMDSO and/or hexamethyldisilazane (HMDS were investigated in detail, and the applications of surface-modified MSQ aerogels in sound-absorbance, fast dye adsorption and oil/water separation were evaluated, respectively. The MSQ aerogels surface-modified by HMDS possess flexibility, elasticity and superhydrophobicity, and demonstrate good performance in the mentioned applications. The resultant MSQ aerogel used in sound-absorbance has high frequency (about 6 kHz acoustic absorptivity of up to 80%, benefiting from its macroporous structure and porosity of 94%, and it also possesses intermediate frequency acoustic absorptivity (about 1 kHz up to 80% owing to its elasticity. This MSQ aerogel can selectively separate oil from oil/water mixtures with high efficiency due to its superhydrophobicity and superlipophilicity, resulting from a lot of methyl groups, density as low as 0.12 cm3·g−1 and a water contact angle as high as 157°. This MSQ aerogel can be assembled to be a monolithic column applied for fast dye adsorption, and shows selective adsorption for anionic dyes and removal efficiency of methyl orange of up to 95%.

The use of radiochemical analysis for detecting biotracers of food radioactive contamination in Cherkasy Region

International Nuclear Information System (INIS)

Matvyijenko, D.G.

2003-01-01

Stable biotracers of radioactive contamination according to the findings of analytical control of the foodstuffs was determined. The use of radiochemical analysis for determining the activity of the foodstuffs and water (Sr-90, Cs-137) was evaluated

Statistical analysis of radiochemical measurements of TRU radionuclides in REDC waste

International Nuclear Information System (INIS)

Beauchamp, J.; Downing, D.; Chapman, J.; Fedorov, V.; Nguyen, L.; Parks, C.; Schultz, F.; Yong, L.

1996-10-01

This report summarizes results of the study on the isotopic ratios of transuranium elements in waste from the Radiochemical Engineering Development Center actinide-processing streams. The knowledge of the isotopic ratios when combined with results of nondestructive assays, in particular with results of Active-Passive Neutron Examination Assay and Gamma Active Segmented Passive Assay, may lead to significant increase in precision of the determination of TRU elements contained in ORNL generated waste streams

Quick analytical separation of glucose and fructose with impregnated woven glass fiber

International Nuclear Information System (INIS)

Jones, S.C.

1978-01-01

(1) A wide separation of glucose and fructose was obtained in 30 min with simple, inexpensive equipment using polysilicic impregnated woven glass fiber and the solvent acetone-n-butanol-1 M H 3 BO 3 (50:40:10). (2) A calibration of a radiochromatogram scanner was performed for 11 C. (3) Three Rsub(F) values could be compared to provide positive chemical identification of [ 11 C]glucose and [ 11 C]fructose. (4) Radiochemical composition and approximate specific activity were determined from a small aliquot (1-4 μl). (Auth.)

Separation of Actinium 227 from the uranium minerals

International Nuclear Information System (INIS)

Martinez-Tarango, S.

1991-01-01

The purpose of this work was to separate Actinium 227, whose content is 18%, from the mineral carnotite found in Gomez Chihuahua mountain range in Mexico. The mineral before processing is is pre-concentrated and passed, first through anionic exchange resins, later the eluate obtained is passed through cationic resins. The resins were 20-50 MESH QOWEX and 100-200 MESH 50 X 8-20 in some cased 200-400 MESH AG 50W-X8, 1X8 in other cases. The eluates from the ionic exchange were electrodeposited on stainless steel polished disc cathode and platinum electrode as anode; under a current ODF 10mA for 2.5 to 5 hours and of 100mA for .5 of an hour. it was possible to identify the Actinium 227 by means of its descendents, TH-227 and RA-223, through alpha spectroscopy. Due to the radiochemical purity which the electro deposits were obtained the Actinium 227 was low and was not quantitatively determined. A large majority of the members of the natural radioactive series 3 were identified and even alpha energies reported in the literature with very low percentages of non-identified emissions were observed. We conclude that a more precise study is needed concerning ionic exchange and electrodeposit to obtain an Actinium 227 of radiochemical purity. (Author)

A direct reading on-line flowrate meter for use in radiochemical plant

International Nuclear Information System (INIS)

Shah, B.V.; Kaimal, C.K.R.; Siddiqui, I.A.; Kumar, S.V.

1987-01-01

A device for measurement and remote direct reading display of the flowrates of streams in a radiochemical plant is described. The device is interposed in the measured stream and consists of a syphon pot with a specially developed attachment on the discharge line. Differential pressure switches are used to trigger a timer device at set levels in the pot and the time required for filling the pot during each cycle is measured and is used to compute and display the flowrate. The device is accurate and reliable and is simple to fabricate and install. It is maintenance-free since it has no moving parts. It is also suggested that a manometer with conductive contacts could be used in place of the d.p. switches. The background and various stages of development of the device are described. The operating data is tabulated and parameters required for plant applications are indicated in detail. A simple method to detect and correct for errors due to drift in d.p. switch setting is also outlined. Sketches of typical syphon pot, the schematic of the apparatus and suggested layout for application in radiochemical plant are also included. (author). 11 figures, 6 tables

Separation of 90Sr from Purex high level waste and development of a 90Sr-90Y generator

International Nuclear Information System (INIS)

Ramanujam, A.; Dhami, P.S.; Chitnis, R.R.; Achuthan, P.V.; Kannan, R.; Gopalakrishnan, V.; Balu, K.

2000-04-01

90 Y (T 1/2 =64.2 h) finds several applications in nuclear medicine. It is formed from the decay of 90 Sr which has a long half-life of 28.8 years. 90 Sr can be used as a long-lasting source for the production of carrier-free 90 Y. 90 Sr itself is abundantly available in high level waste (HLW) of PUREX origin. The present studies deal with the separation of pure 90 Sr from HLW and the subsequent separation of 90 Y from 90 Sr. Actinides and some of the fission products like lanthanides, zirconium, molybdenum and cesium were first removed from the HLW using methods based on solvent extraction and ion-exchange studied earlier in our laboratory. The resulting waste solution was used as a feed for the present process. The separation of 90 Sr from HLW was based on radiochemical method which involved a repeated scavenging with ferric hydroxide followed by strontium carbonate precipitation. The separation of 90 Y from 90 Sr was achieved by membrane separation technique. A compact generator is developed for this separation using a commercially available polytetrafluoroethylene (PTFE) membrane, impregnated with indigenously synthesised 2-ethylhexyl 2-ethylhexyl phosphonic acid (KSM-17). Generator system overcomes the drawbacks associated with conventional solvent extraction and ion-exchange based generators. The product is in chloride form and is suitable for complexation studies. After gaining an operating experience of ∼3 years in generating carrier-free 90 Y at 2 mCi level for initial studies in radiotherapeutic applications, the process was scaled up for the production of about 12 mCi of 90 Y to be used for animal studies before its application to patients. Radiochemical and chemical purity of the product was critically assayed by radiometry, ICP-AES, etc. The process is amenable for further scaling up. (author)

Investigation of equilibrium core by recycling MA and LLFP in fast reactor cycle. 2. Investigation of LLFP confined in Equilibrium Core with element separation

International Nuclear Information System (INIS)

Mizutani, Akihiko; Shono, Akira; Ishikawa, Makoto

2000-02-01

A feasibility study has been performed on a self-consistent fuel cycle system in the nuclear fuel recycle system with fast reactors. In this system, the self-generated MAs (Minor Actinides) and LLFPs (Long-Lived Fission Products) are confined and incinerated in the fast reactor, which is called the 'Equilibrium Core' concept. However, as the isotope separations for selected LLFPs have been assumed in this cycle system, it seems that this assumption is far from realistic one from the viewpoint of economy with respect to the fuel cycle system. In this study, the possibility for realization of the 'Equilibrium Core' concept is evaluated for three fuel types such as oxide, nitride and metallic fuels, provided that the isotopic separation of LLFPs is changed to the element one. This study provides, that is to say, how many LLFP elements can be confined in the 'Equilibrium Core' with element separation. This report examines the nuclear properties of the Equilibrium Core' for various combinations of LLFP incineration schemes from the viewpoints of the risk of geological disposal and the limit in confinable quantity of LLFPs. From the viewpoint of the risk of geological disposal estimated by the retardation factor, it is possible to confine with element separation for Tc, I and Se even in the oxide fueled core. From the standpoint of the limit of confinable amounts of LLFPs, on the other hand, Tc, I, Se, Sn and Cs can be confined with element separate only in case that the nitride fuel is chosen. (author)

Determination of radiochemical purity of 125I-TOC and 125I-F-PGA

International Nuclear Information System (INIS)

Yang Keya; Fan Wo; Zhang Youjiu; Xu Yujie; Zhu Ran; Hu Mingjiang

2006-01-01

To explore whether there is accordance among three determination methods of the radiochemical purity of [Tyr 3 ] octreotide (TOC) and folate-penicillin G amidase conjugate (F-PGA), which are both labeled with 125 I by Iodogen method, the RCP of the labelings are determined by high performance liquid chromatography (HPLC), paper chromatography and trichloroacetic acid (TCA) precipitation, in which four different concentrations of proteins are used to investigate the effect of them on the determination of RCP. It is shown that both HPLC and paper chromatography can separate the labelings from free iodine efficiently, though HPLC is the most precise and reliable method to determinate RCP of such labelings. In TCA precipitation, the RCP measured with 0.2%BSA is the lowest, but those with three other concentrations of the BSA are similar (P>0.05). When RCP 0.05), whereas higher than that with HPLC (P 10%, the RCP of 125 I-TOC obtained by TCA precipitation is a bit lower than those by two other methods (P 0.05), and there are no significant differences to determinate the RCP of 125 I-F-PGA (P>0.05). The three methods are correlated each other (r=0.0996-0.999, P<0.001). (authors)

Cleanout and decontamination of radiochemical hot cells

International Nuclear Information System (INIS)

Surma, J.E.; Holton, L.K. Jr.; Katayama, Y.B.; Gose, J.E.; Haun, F.E.; Dierks, R.D.

1990-01-01

The Pacific Northwest Laboratory is developing and employing advanced remote and contact technologies in cleaning out and decontaminating six radiochemical hot cells at Hanford under the Department of Energy's Surplus Facilities Management Program. The program is using a series of remote and contact decontamination techniques to reduce costs and to significantly lower radiation doses to workers. Refurbishment of the cover blocks above the air lock trench reduced radiation exposure in the air lock and cleanout and decontamination of an analytical cell achieved a reduction in radioactive contamination. Nuclear Regulatory Commission-approved Type B burial boxes are also being used to reduce waste disposal costs and radiation doses. PNL is currently decommissioning its pilot-scale radioactive liquid-fed ceramic melter. Special tools have been developed and are being used to accomplish the world's first such effort. 4 refs., 5 figs

International intercalibration as a method for control of radiochemical analyses

International Nuclear Information System (INIS)

Angelova, A.; Totseva, R.; Karaivanova, R.; Dandulova, Z.; Botsova, L.

1994-01-01

The participation of the Radioecology Section at the National Centre for Radiology and Radiation Protection (NCRRP) in the International Interlaboratory Comparison of radiochemical analyses organized by WHO is reported. The method of evaluating accuracy of the results from inter calibrations concerning radionuclide determination of environmental samples is outlined. The data from analysis of cesium 137, strontium 90 and radium 226 in milk, sediments, soil and seaweed made by 21 laboratories are presented. They show a good accuracy values of the results from NCRRP. 1 tab. 2 figs., 6 refs

Preparation of proton rich radionuclides in support of radiochemical analysis

International Nuclear Information System (INIS)

Jerome, Simon; Larijani, Cyrus; Parker, David

2012-01-01

The production of proton rich radionuclides supports a wide range of radiochemical analyses via radioactive yield tracers ( 95m Tc and 236 Pu). In recent years, NPL and the University of Birmingham cyclotron have collaborated to produce these, and other, radionuclides. - Highlights: ► In this paper we options for the production of Tc and Pu tracers. ► The irradiation and measurement of targets producing Tc-95 m and Pu-236 are described. ► Options for production are discussed. ► The results of this study and future work needed are described.

Determination of mercury in biologycal samples by radiochemical neutron activation analysis

International Nuclear Information System (INIS)

Suc, N.V.

1989-01-01

The radiochemical neutron activation analysis was applied to determine contents of mercury in biological samples. Samples were digested in mixing of H 2 SO 4 and HNO 3 acid. After extraction of mercury by Ni-Ditiodietylphosphoric acid in carbontetrachloride, mercury was back extracted by 5% KI solution. Contents of mercury from five samples of fish was determined by this method. The accuracy of the method was checked by comparing it with NBS standard samples and results are good agreement

Radiochemical analyses of several spent fuel Approved Testing Materials

International Nuclear Information System (INIS)

Guenther, R.J.; Blahnik, D.E.; Wildung, N.J.

1994-09-01

Radiochemical characterization data are described for UO 2 and UO 2 plus 3 wt% Gd 2 O 3 commercial spent nuclear fuel taken from a series of Approved Testing Materials (ATMs). These full-length nuclear fuel rods include MLA091 of ATM-103, MKP070 of ATM-104, NBD095 and NBD131 of ATM-106, and ADN0206 of ATM-108. ATMs 103, 104, and 106 were all irradiated in the Calvert Cliffs Nuclear Power Plant (Reactor No.1), a pressurized-water reactor that used fuel fabricated by Combustion Engineering. ATM-108 was part of the same fuel bundle designed as ATM-105 and came from boiling-water reactor fuel fabricated by General Electric and irradiated in the Cooper Nuclear Power Plant. Rod average burnups and expected fission gas releases ranged from 2,400 to 3,700 GJ/kgM. (25 to 40 Mwd/kgM) and from less than 1% to greater than 10%, respectively, depending on the specific ATM. The radiochemical analyses included uranium and plutonium isotopes in the fuel, selected fission products in the fuel, fuel burnup, cesium and iodine on the inner surfaces of the cladding, 14 C in the fuel and cladding, and analyses of the gases released to the rod plenum. Supporting examinations such as fuel rod design and material descriptions, power histories, and gamma scans used for sectioning diagrams are also included. These ATMs were examined as part of the Materials Characterization Center Program conducted at Pacific Northwest Laboratory provide a source of well-characterized spent fuel for testing in support of the US Department of Energy Office of Civilian Radioactive Waste Management Program

Radiochemical purity of Mo and Tc solution obtained after irradiation and dissolution of Mo-100-enriched and ultra-high-purity natural Mo disks

Energy Technology Data Exchange (ETDEWEB)

Tkac, Peter [Argonne National Lab. (ANL), Argonne, IL (United States); Gromov, Roman [Argonne National Lab. (ANL), Argonne, IL (United States); Chemerisov, Sergey D. [Argonne National Lab. (ANL), Argonne, IL (United States); Rotsch, David A. [Argonne National Lab. (ANL), Argonne, IL (United States); Vandegrift, George F. [Argonne National Lab. (ANL), Argonne, IL (United States)

2016-09-01

Four irradiations of ultra-high-purity natural Mo targets and one irradiation using 97.4% Mo-100-enriched material were performed. The purpose of these irradiations was to determine whether the presence of Sn stabilizer in the H₂O₂ used for the dissolution of sintered Mo disks can affect the radiochemical purity of the final K₂MoO₄ in 5M KOH solution. Results from radiochemical purity tests performed using thin-layer paper chromatography show that even 2– 3× excess of Sn-stabilized H₂O₂ typically used for dissolution of sintered Mo disks did not affect the radiochemical purity of the final product.

Protein binding studies with radiolabeled compounds containing radiochemical impurities. Equilibrium dialysis versus dialysis rate determination

DEFF Research Database (Denmark)

Honoré, B

1987-01-01

The influence of radiochemical impurities in dialysis experiments with high-affinity ligands is investigated. Albumin binding of labeled decanoate (97% pure) is studied by two dialysis techniques. It is shown that equilibrium dialysis is very sensitive to the presence of impurities resulting...

Radiometric determination of 90Sr in the dissolver solution of the spent PHWR fuel after its separation with solvent extraction and extraction chromatography

International Nuclear Information System (INIS)

Kulkarni, P.G.; Gupta, K.K.; Pant, D.K.; Bhalerao, B.A.; Gurba, P.B.; Janardan, P.; Changrani, R.D.; Dey, P.K.; Pathak, P.N.; Mohapatra, P.K.; Manchanda, V.K.

2010-01-01

A simple radiometric method for 90 Sr determination in the dissolver solution of the PHWR spent fuel has been developed.The method involves the quantitative separation of Sr from the associated actinides and other fission products by solvent extraction with 30% trialkylphosphine oxide (TRPO) -n-dodecane followed by extraction chromatography with XAD-7-Di-butylcyclohexano-18-crown-6 resin. The separation scheme yields quantitative recovery of 90 Sr and the separated 90 Sr was found to be radiochemically pure. 90 Sr was estimated by β-radiometry and the precision of the method at 5 mCi/mL level was 2% (RSD). (author)

Future directions for separation science in nuclear and radiochemistry

International Nuclear Information System (INIS)

Pruett, D.J.

1986-01-01

Solvent extraction and ion exchange have been the most widely used separation techniques in nuclear and radiochemistry since their development in the 1940s. Many successful separations processes based on these techniques have been used for decades in research laboratories, analytical laboratories, and industrial plants. Thus, it is easy to conclude that most of the fundamental and applied research that is needed in these areas has been done, and that further work in these ''mature'' fields is unlikely to be fruitful. A more careful review, however, reveals that significant problems remain to be solved, and that there is a demand for the development of new reagents, methods, and systems to solve the increasingly complex separations problems in the nuclear field. Specifically, new separation techniques based on developments in membrane technology and biotechnology that have occurred over the last 20 years should find extensive applications in radiochemical separations. Considerable research is needed in such areas as interfacial chemistry, the design and control of highly selective separation agents, critically evaluated data bases and mathematical models, and the fundamental chemistry of dilute solutions if these problems are to be solved and new techniques developed in a systematic way. Nonaqueous separation methods, such as pyrochemical and fluoride volatility processes, have traditionally played a more limited role in nuclear and radiochemistry, but recent developments in the chemistry and engineering of these processes promises to open up new areas of research and application in the future

Multi trace element analysis of dry biological materials by neutron activation analysis including a chemical group separation

International Nuclear Information System (INIS)

Weers, C.A.

1980-07-01

Multi-element analysis of dry biological material by neutron activation analysis has to include radiochemical separation. The evaporation process is described in terms of the half-volume. The pretreatment of the samples and the development of the destruction-evaporation apparatus are described. The successive adsorption steps with active charcoal, Al 2 O 3 and coprecipitation with Fe(OH) 3 are described. Results obtained for standard reference materials are summarized. (G.T.H.)

Evaluation of different detection systems to determine the radiochemical purity of the technetium eluate and the radiopharmaceutical sestamibi

Energy Technology Data Exchange (ETDEWEB)

Santos, Poliane Angelo de L.; Andrade, Wellington G., E-mail: polianeangelo@gmail.com, E-mail: wandrade@cnen.gov.br [Universidade Federal de Pernambuco (UFPE), Recife, PE (Brazil). Dept. de Energia Nuclear; Santos, Luiz Antonio P.; Lima, Fabiana Farias de, E-mail: luanps@uol.com.br, E-mail: fflima@cnen.gov.br [Centro Regional de Ciencias Nucleares do Nordeste (CRCN/CNEN-PE), Recife, PE (Brazil)

2013-07-01

Since 2008 the Brazilian Health Surveillance Agency (ANVISA) has imposed some rules requiring that Nuclear Medicine Services (NMS) perform a minimum of tests with the radiopharmaceuticals before they are administered to their patients according to the Resolution n. 38 (RDC 38). Among the tests, the radiochemical purity is very important because the effectiveness for the use in vivo, and the fact radiochemical impurities may increase the radiation dose beyond to cause some damage in the diagnostic images. Radiochemical Purity is determined by ascendant chromatography technique and when it is used by NMS, the strips are analyzed in dose calibrator. Furthermore, the low activity on the strips can produce errors due to the low detection of this equipment type. Therefore, the aim of this paper is to compare different methods for determining the radiochemical purity of {sup 99m}Tc eluate and {sup 99m}Tc-MIBI radiopharmaceutical; gamma camera, and dose calibrator. The study was developed in three clinics in Recife-PE, and 15 analyses were performed to determine radiochemical purity of technetium eluate and {sup 99m}Tc-MIBI. For evaluating technetium eluate it was used Whatman® 3MM paper in 1cmx8cm strips. On the other hand, for analyzing MIBI radiopharmaceutical it was used 3 Whatman® 3MM paper strips and 3 with silica gel in 1cmx6.5cm format. According to the manufactures, an 1cm point from the base of the strip was labeled. It was dropped 50μ1 of sodium pertechnetate and {sup 99m}Tc-MIBI and, then, the strips were put in the glass tank, with solvent, according to the pharmacopoeia and inserts of the drug manufacturers. After the solvent front reached the end point, the strips were removed and allowed to dry. Firstly, the radioactivity count was made with a gamma camera. After that, the strips were cut in half (eluate) and in 2.5 cm from the base (MIBI) and measured with a dose calibrator. The results of the average radiochemical purity of the eluate in clinics A, B

Radiochemical studies of the separation of some chloro-complexes of tin, antimony, cadmium and indium

International Nuclear Information System (INIS)

Ramamoorthy, N.; Mani, R.S.

1976-01-01

Radioisotopes of tin, antimony, cadmium and indium such as tin-113, antimony-124, antimony-125, cadmium-109, cadmium-115, indium-113m and indium-111 find extensive applications as tracers in various fields. These isotopes are produced by irradiation of targets in a reactor or a cyclotron. It is usually observed that in addition to the nuclear reactions giving rise to the desired isotopes, side reactions also take place giving rise to radionuclidic contaminants. Thus, antimony-125, indium-114m and indium-114 will be present in the cyclotron produced indium-111. The authors have studied column chromatography over hydrous zirconia for the separation of antimony from tin and indium, and cadmium from indium. These studies have thrown light on the role and behaviour of antimony-125 present as an impurity in tin-113 during the preparation of tin-113-indium-113m generators and have indicated methods for the preparation of 115 Cd-sup(115m)In generators and for separation of 111 In from proton irradiated cadmium targets. (Authors)

Fast beam radiofrequency spectroscopy

International Nuclear Information System (INIS)

Pipkin, F.M.

1983-01-01

The combination of a fast atom or ion beam derived from a small accelerator with radiofrequency spectroscopy methods provides a powerful method for measuring the fine structure of atomic and molecular systems. The fast beam makes possible measurements in which two separated oscillatory fields are used to obtain resonance lines whose widths are less than the natural line width due to the lifetimes of the states. The separated oscillatory field lines have, in addition, a number of features which make possible measurements with greater precision and less sensitivity to systematic errors. The fast beam also makes accessible multiple photon radiofrequency transitions whose line width is intrinsically narrower than that of the single photon transitions and which offer great potential for high precision measurements. This report focuses on the techniques and their promise. Recent measurements of the fine structure of H and He + are used as illustrations

Radiochemical separation from111In from Cd and Cu by Ion exchange chromatography

International Nuclear Information System (INIS)

Yavari, R.; Khanchi, A. R.; Rafii, H.; Maragheh, M. G.; Farajzadeh, M. A.

2005-01-01

In this work, during the nuclear reaction of nat Cd (p, xn) 111 In, the irradiated cadmium target was dissolved in 3 M nitric acid. It was passed through a cation exchange column, containing 4 g. of AG 5OW-X8, and then was separated from cadmium and copper impurities by using a simple two stage procedure. At the first stage, cadmium was eluted with acetone-water-hydrobromic acid solution. At the second stage, indium was eluted with acetone-water-hydrochloric acid solution. The effluent was evaporated to dry and the residue was dissolved in 0.01M hydrochloric acid. The overall yield of the procedure was 95 ± 1 percent and the amount of cadmium and copper contamination were 0.3 and 0.1 ppm, respectively

Study of the short-lived fission products. Separation of iodine and xenon fission radionuclides

International Nuclear Information System (INIS)

Barrachina, M.; Villar, M. A.

1965-01-01

The separation by distillation in a sulfuric acid or phosphoric acid-hydrogen peroxide medium of the iodine isotopes (8 day iodine-131, 2,3 hour iodine-132 21 hour iodine-133, 53 minute iodine-134 and 6,7 hour iodine-135) present in a uranium sample after different irradiation and cooling times is here described. It is also reported the use of active charcoal columns for the retention of xenon isotopes (5,27 days xenon-133 and 9,2 hours xenon-135) either released during the dissolution of the uranium irradiated samples or generated along the fission isobaric chains in the solutions of distillated iodine. In both cases the radiochemical purity of the separated products is established by gamma spectrometry. (Author) 15 refs

Fast synthesis of 11C-Raclopride and its initial PET study on animal model

International Nuclear Information System (INIS)

Zhang Jinming; Tian Jiahe; Yao Shulin; Ding Weimin; Yin Dayi; Liu Boli

2008-01-01

Objective: 11 C-Raclopride is a type-2 dopamine receptor (D 2 R) binding agent used in the study of Parkinson's disease. This study introduced a fast and convenient method for preparation of 11 C- Raclopride and reported on the preclinical trial of this receptor tracer on animal studies. Methods: 11 C- Raclopride was synthesized via reaction of 11 C-CH 3 -Triflate with Nor-Raclopride. The mixture of primary product was water-diluted and loaded on Sep-Pak C18 column for separation. The final product, 11 C-Raclopride, was purified by column chromatography and then eluted from the C18 column with ethanol. The bio-distribution was studied in SD rats and the in vivo imaging pattern was studied in hem ipark insonjan mon- keys. Results: Within 16 min from beginning of processing with 11 CO 2 , the synthetic yield of 11 C-Raclopride was 60%, radiochemical purity (RCP) > 95% and specific activity 8 GBq/mmol. The uptake ratios of striatum to cerebellum and cerebral cortex were 4.67 and 6.20, respectively, at 30 min after 11 C-Raclopride administration. The striatal uptake in normal rat brain could be blocked by N-methylspiperone (NMSP) and raclopride, but not by Nor-raclopride. PET imaging showed higher striatal D 2 R uptake on the D 2 receptor up-regulated side of the experimental monkeys relative to the contralateral side. Conclusions: Column chromatography for purification of 11 C-Raclopride was fast, convenient and with a RCP similar to that of high performance liquid chromatography purification. Preliminary PET findings using animal model suggested that 11 C-Raclopride by column chromatogram purification might be considered for clinical use. (authors)

A LabVIEW®-based software for the control of the AUTORAD platform. A fully automated multisequential flow injection analysis Lab-on-Valve (MSFIA-LOV) system for radiochemical analysis

International Nuclear Information System (INIS)

Barbesi, Donato; Vilas, Victor Vicente; Millet, Sylvain; Sandow, Miguel; Colle, Jean-Yves; Heras, Laura Aldave de las

2017-01-01

A LabVIEW®-based software for the control of the fully automated multi-sequential flow injection analysis Lab-on-Valve (MSFIA-LOV) platform AutoRAD performing radiochemical analysis is described. The analytical platform interfaces an Arduino®-based device triggering multiple detectors providing a flexible and fit for purpose choice of detection systems. The different analytical devices are interfaced to the PC running LabVIEW®VI software using USB and RS232 interfaces, both for sending commands and receiving confirmation or error responses. The AUTORAD platform has been successfully applied for the chemical separation and determination of Sr, an important fission product pertinent to nuclear waste. (author)

A LabVIEW®-based software for the control of the AUTORAD platform: a fully automated multisequential flow injection analysis Lab-on-Valve (MSFIA-LOV) system for radiochemical analysis.

Science.gov (United States)

Barbesi, Donato; Vicente Vilas, Víctor; Millet, Sylvain; Sandow, Miguel; Colle, Jean-Yves; Aldave de Las Heras, Laura

2017-01-01

A LabVIEW ® -based software for the control of the fully automated multi-sequential flow injection analysis Lab-on-Valve (MSFIA-LOV) platform AutoRAD performing radiochemical analysis is described. The analytical platform interfaces an Arduino ® -based device triggering multiple detectors providing a flexible and fit for purpose choice of detection systems. The different analytical devices are interfaced to the PC running LabVIEW ® VI software using USB and RS232 interfaces, both for sending commands and receiving confirmation or error responses. The AUTORAD platform has been successfully applied for the chemical separation and determination of Sr, an important fission product pertinent to nuclear waste.

Group separation of rare earth elements by liquid-liquid extraction for the neutron activation analysis of silicate rocks

International Nuclear Information System (INIS)

Wyttenbach, A.; Bajo, S.; Tobler, L.

1983-01-01

Rare earth elements are isolated as a group from neutron activated rock samples by a new radiochemical procedure based on extraction with thenoyltrifluoracetone/phenanthroline in CHCl 3 . The procedure consists of three extraction steps, obviates the use of inactive carriers and gives practically quantitative chemical yields, thereby avoiding fractionation of the individual rare earths. Details of the dissolution, chemical separations. and counting procedure are given together with an analysis of BCR-1. (author)

HPLC-ICP-MS compared with radiochemical detection for metabolite profiling of H-3-bromohexine in rat urine and faeces

DEFF Research Database (Denmark)

Jensen, B.P.; Gammelgaard, B.; Hansen, S.H.

2005-01-01

H-3-Bromohexine was dosed to rats as a model compound to allow comparison of HPLC-ICP-MS detection on bromine to radiochemical detection in an in vivo drug metabolism study. Metabolite profiles were obtained in urine and faeces extracts. No influence of the methanol gradient on the bromine response...... was observed in the range of 18 - 75% methanol. The sensitivity obtained by HPLC- ICP-MS was almost two orders of magnitude better than on-line H-3 radiochemical detection. For ICP- MS, the limit of detection was calculated to be 69 nM Br ( injection volume 100 mu l), corresponding to an absolute limit...

Radiochemical separations of target-like reaction products from Au-, Pt-, and Th-targets after irradiation with GeV protons

International Nuclear Information System (INIS)

Szweryn, B.; Bruechle, W.; Schausten, B.; Schaedel, M.

1988-08-01

Chemical separation procedures for separations of reaction products after spallation reactions with 2.6 GeV protons and heavy element targets are presented. To determine independent cross sections of individual isotopes the elements Au, Pt, Ir, Os, Re, W, Ta, Hf, (Lu, Yb, Tm, Er), (Gd, Eu, Sm), were separated from gold targets, Pt, Ir, Os, W, Ta, Hf, (Lu, Yb, Tm, Er), (Gd, Eu, Sm) from a platinum target and Au, Tl from a thorium target. (orig.)

Radiochemical guidelines and process specifications for reactor shutdown: the EDF strategy

International Nuclear Information System (INIS)

Mole, D.; Wintergerst, M.; Meylogan, Th.; Rocher, A.; Sagot, M.J.; Bonelli, V.; Bonnefon, J.; Dupont, B.

2012-09-01

Changes to French nuclear regulations made in June 2006 [1.] have made it necessary for EDF to modify its ruling principles. These modifications required the restructuring of radiochemical guidelines to better reflect their impact on nuclear safety, the environment and radioprotection. In accordance with these aims, a new authoritative document has been produced. This ruling document identifies all parameters with a potential impact on nuclear safety, radiological releases to the environment and personnel dose rates. These diagnostic and control parameters have been identified for a reactor in production and for a reactor during shutdown. For parameters related to a reactor in production, some indicators are used to evaluate impacts on availability, radioprotection and the environment during shutdown and on outage and to anticipate mitigation ways. On the other side, several parameters related to the stages of shutdown were also directly evaluated in order to minimize the impacts. This paper describes the EDF methodology used to establish operational documents: radiochemical guidelines and process specifications, and includes the following: - description of monitored parameters and their associated areas of risk; - justification of target values, frequencies of inspection and the required actions for the monitored parameters. The sizing methodology is based on theoretical studies and on EDF operational experience analysis. By implementing in the operational and technical specifications requirements linked to nuclear safety, radioprotection and environment respect, EDF will benefit from an improved compromise between these areas as well as an increased focus. (authors)

Chemical methods for the use of niobium from pressure vessel cladding as a fast neutron dosimeter

International Nuclear Information System (INIS)

Karnani, Hari

1986-08-01

the steel samples from the cladding of a pressure vessel of an operating nuclear power reactor were obtained by scraping. The cladding material of the pressure vessel contained about 0.5 % niobium. It was desired to use the niobium as a dosimeter for estimating fast fluences at the pressure vessel. The weak radiation from the reaction product 93m Nb cannot be measured in the presence of other elements and interfering activities. A method was developed to separate niobium from other metals present; the concentration and yield of niobium were determined spectrophotometrically. The irradiated niobium was electrodeposited from aqueous solutions on copper discs. The amount of the deposited niobium was determined by a radiochemical method which makes use of its own radioactivity - measured with a liquid scintillation counter - and the known starting mass of niobium. It was possible to determine the deposited niobium masses (5 to 200 microgram) with a desired degree of accuracy. The absolute emission rate of X-rays could then be measured without any self-absorption or interference from other activities. The mass of niobium on each preparate and its X-ray emission rate, later on, were used as basic experimental data for the estimation of last neutron doses at the pressure vessel

Ion exchange separation of carrier-free 140Ba and 140La from their equilibrium mixture using nitrilotriacetic acid and ascorbic acid as eluents

International Nuclear Information System (INIS)

Das, N.R.; Bhattacharyya, S.N.

1982-01-01

A simple cation exchange procedure for separation of 140 Ba- 140 La using Dowex 50W-X8 and nitrilotriacetic acid or ascorbic acid as the eluent has been described. The optimal separation of the daughter from the parent has been achieved using a 4% Na-nitrilotriacetate or Na-ascorbate solution at pH 7. The parent, 140 Ba, left in the column can be eluted with dilute hydrochloric acid or it can be retained in the column for milking off the daughter, 140 La, when needed. The radiochemical purity of the separated isotopes, 140 Ba and 140 La, were verified by γ-ray spectrometry. (author)

Instant thin layer chromatography (ITLC) - the most true and convenient method for the determination of radiochemical purity of Tc-99m Labeled radiopharmaceuticals

International Nuclear Information System (INIS)

Anwar-Ul-Azim, M.; Ansari, M.I.H.

2007-01-01

Full text: Determination of radiochemical purity usually involves paper chromatography method or some column chromatography such as ion exchange or gel filtration technique. In this study, a modified chromatography method with thin-layer support called instant thin Layer chromatography (ITLC) was used for the measurement of radiochemical purity. The aim of the study was to present instant thin layer chromatography-Silica-Gel (ITLC-SG) technique as a fairly rapid , convenient and inexpensive system for the screening of radiochemical impurities of 99mTc-labeled radiopharmaceuticals resulting from physical , chemical and/or radiation decomposition. Materials and Methods: The experiment was carried out at the Institute of Nuclear Medicine and Ultrasound, Dhaka for a period of 10 months from August '05 to May '06. Radiochemical purity of seven types of 99mTc-labeled radiopharmaceuticals, namely 99mTc-DTPA,99mTc- MI I, 99m Tc - HDP, 99m Tc - DMSA, 99m Tc - Tetofosmin, 99mTc-Fyton and 99mTc-ECD were measured by the use of two solvent dual-instant thin layer chromatography systems. Commercially available instant thin layer chromatography plate ( 20cm x20cm) impregnated with silica gel (ITLC-SG: Merck, Germany) was used as a stationary phase for the measurement of radiochemical impurities.Acetone, Ethyl methyl ketone, chloroform and methanol were used to measure the amount of free pertechnetate in the labelled radiopharmaceuticals and 0.9% saline was used in all cases as solvent (Mobile phase) to measure the amount of the hydrolyzed-reduced technetium colloid. Results: The results showed that the measured radiochemical purity of 99mTc-DTPA, 99mTc-MIBI, 99mTc-HDP, 99mTc-DMSA, 99mTc-Tetofosmin, 99mTc-Fyton and 99mTc-ECD were acceptable for all the studied samples except two samples of 99mTc-MIBI, one sample of 99mTc-Fyton and two samples of 99mTc-ECD, where the measured radiochemical purity were not within the acceptable RCP limits of commonly used radiopharmaceuticals (RCP

Separated Representations and Fast Algorithms for Materials Science

National Research Council Canada - National Science Library

Beylkin, Gregory; Monzon, Lucas; Perez, Fernando

2007-01-01

...) and to develop and test algorithms for computing multiparticle wave functions both based on representing operators and functions of many variables as short sums of separable functions the so-called...

Radiolabeling of anti-CD20 with Re-188 for treatment of non-Hodgkin's lymphoma: radiochemical control

International Nuclear Information System (INIS)

Dias, Carla R.; Osso Junior, Joao A.

2009-01-01

The development of tumor-selective radiopharmaceuticals is clinically desirable as a means of detecting or confirming the presence and location of primary and metastatic lesions and monitoring tumor response to (chemo)therapy. In addition, the application of targeted radiotherapeutics provides a unique and effective modality for direct tumor treatment. In this manner the radioimmunotherapy (RIT) uses the targeting features of monoclonal antibody to deliver radiation from an attached radionuclide. Antibody therapy directed against the CD20 antigen on the surface of B-cells is considered one of the first successful target-specific therapies in oncology. The radionuclide rhenium-188 ( 188 Re) is currently produced from the father nuclide tungsten-188 ( 188 W) through a transportable generator system. Because of its easy availability and suitable nuclear properties (EβMAX = 2.1 MeV, t 1/2 = 16.9 h, Eγ = 155 keV), this radionuclide is considered an attractive candidate for application as therapeutic agent and could be conveniently utilized for imaging and dosimetric purposes. The purpose of this work is to show the radiochemical control of the optimized formulation (solution) and lyophilized formulation (kit) of labeled rituximab (anti-CD20) with 188 Re. Rituximab was reduced by incubation with 2-mercaptoethanol at room temperature. The number of resulting free sulfhydryl groups was assayed with Ellman's reagent. Radiochemical purity of 188 Re-rituximab was evaluated using instant thin layer chromatography-silica gel (ITLC-SG). Quality control methods for evaluation of radiochemical purity showed good labeling yield of the antibody. (author)

Benchmark Evaluation of Dounreay Prototype Fast Reactor Minor Actinide Depletion Measurements

Energy Technology Data Exchange (ETDEWEB)

Hess, J. D.; Gauld, I. C.; Gulliford, J.; Hill, I.; Okajima, S.

2017-01-01

Historic measurements of actinide samples in the Dounreay Prototype Fast Reactor (PFR) are of interest for modern nuclear data and simulation validation. Samples of various higher-actinide isotopes were irradiated for 492 effective full-power days and radiochemically assayed at Oak Ridge National Laboratory (ORNL) and Japan Atomic Energy Research Institute (JAERI). Limited data were available regarding the PFR irradiation; a six-group neutron spectra was available with some power history data to support a burnup depletion analysis validation study. Under the guidance of the Organisation for Economic Co-Operation and Development Nuclear Energy Agency (OECD NEA), the International Reactor Physics Experiment Evaluation Project (IRPhEP) and Spent Fuel Isotopic Composition (SFCOMPO) Project are collaborating to recover all measurement data pertaining to these measurements, including collaboration with the United Kingdom to obtain pertinent reactor physics design and operational history data. These activities will produce internationally peer-reviewed benchmark data to support validation of minor actinide cross section data and modern neutronic simulation of fast reactors with accompanying fuel cycle activities such as transportation, recycling, storage, and criticality safety.

Placement of the radiochemical processing plant at Oak Ridge National Laboratory into a safe standby condition

International Nuclear Information System (INIS)

Holladay, D.W.; Bopp, C.D.; Farmer, A.J.; Johnson, J.K.; Miller, C.H.; Powers, B.A.; Collins, E.D.

1986-01-01

Extensive upgrade, cleanup, and decontamination efforts are being conducted for appropriate areas in the Radiochemical Processing Plant (RPP) with the goal of achieving safe standby condition by the end of FY 1989. The ventilation system must maintain containment thus, it is being upgraded via demolition and replacement of marginally adequate ductwork, fans, and control systems. Areas that are being decontaminated and stripped of various services (e.g., piping, ductwork, and process tanks) include hot cells, makeup rooms, and pipe tunnels. Operating equipment that is being decontaminated includes glove boxes and hoods. Replacement of the ventilation system and removal of equipment from pipe tunnels, cells, and makeup rooms are accomplished by contact labor by workers using proper attire, safety rules, and shielding, Removal of contaminated ductwork and piping is conducted with containment enclosures that are strategically located at breakpoints, and methods of separation are chosen to conform with health physics requirements. The methods of cutting contaminated piping and ductwork include portable reciprocating saws, pipe cutters, burning, and plasma torch. Specially designed containment enclosures will be used to prevent the spread of radioactive contamination while maintaining adequate ventilation

Placement of the radiochemical processing plant at Oak Ridge National Laboratory into a safe standby condition

International Nuclear Information System (INIS)

Holladay, D.W.; Bopp, C.D.; Farmer, A.J.; Johnson, J.K.; Miller, C.H.; Powers, B.A.; Collins, E.D.

1986-01-01

Extensive upgrade, cleanup, and decontamination efforts are being conducted for appropriate areas in the Radiochemical Processing Plant (RPP) with the goal of achieving ''safe standby'' condition by the end of FY 1989. The ventilation system must maintain containment; thus, it is being upgraded via demolition and replacement of marginally adequate ductwork, fans, and control systems. Areas that are being decontaminated and stripped of various services (e.g., piping, ductwork, and process tanks) include hot cells, makeup rooms, and pipe tunnels. Operating equipment that is being decontaminated includes glove boxes and hoods. Replacement of the ventilation system and removal of equipment from pipe tunnels, cells, and makeup rooms are accomplished by contact labor by workers using proper attire, safety rules, and shielding. Removal of contaminated ductwork and piping is conducted with containment enclosures that are strategically located at breakpoints, and methods of separation are chosen to conform with health physics requirements. The methods of cutting contaminated piping and ductwork include portable reciprocating saws, pipe cutters, burning, and plasma torch. Specially designed containment enclosures will be used to prevent the spread of radioactive contamination while maintaining adequate ventilation. 6 figs

Optimized procedures for manganese-52: Production, separation and radiolabeling

DEFF Research Database (Denmark)

Fonslet, Jesper; Tietze, Sabrina; Jensen, Andreas Tue Ingemann

2017-01-01

±0.4×105. An additional AG 1-X8 column was used to remove copper, iron, cobalt and zinc impurities from the prepared 52Mn in 8M HCl. The macrocyclic chelator DOTA was rapidly radiolabeled with 52Mn in aq. ammonium acetate (pH 7.5R.T.) with a radiochemical yield >99% within 1min and was stable for >2 days in bovine serum......Pressed chromium-powder cyclotron targets were irradiated with 16MeV protons, producing 52Mn with average yields of 6.2±0.8MBq/µAh. Separation by solid-phase anion exchange from ethanol-HCl mixtures recovered 94.3±1.7% of 52Mn and reduced the chromium content by a factor of 2.2...

Labeling of thymidine analog with an organometallic complex of technetium-99m for diagnostic of cancer: radiochemical and biological evaluation

International Nuclear Information System (INIS)

Santos, Rodrigo Luis Silva Ribeiro

2007-01-01

Thymidine analogs have been labeled with different radioisotopes due to their potential in monitoring the uncontrollable cell proliferation. Considering that the radioisotopes technetium-99m still keep a privileged position as a marker due to its chemical and nuclear properties, this dissertation was constituted by the developed of a new technique of labeling of thymidine analog with 99m Tc, by means of the organometallic complex. The aims of this research were: synthesis of the organometallic complex technetium-99m-carbonyl, thymidine labeling with this precursor, evaluation of stability, and radiochemical e biological evaluation with healthy and tumor-bearing animals. The preparation of the organometallic precursor, using the CO gas, was easily achieved, as well as the labeling of thymidine with this precursor, resulting itself a radiochemical pureness of ≥ 97% and ≥ 94%, respectively. Chromatography systems with good levels of trustworthiness were used, ensuring the qualification and quantification of the radiochemical samples. The result of in vitro testing of lipophilicity disclosed that the radiolabeled complex is hydrophilic, with a partition coefficient (log P) of -1.48. The precursor complex and the radiolabeled have good radiochemical stability up to 6 h in room temperature. The cysteine and histidine challenge indicated losses between 8 and 1 1 % for concentrations until 300 mM. The biodistribution assay in healthy mice revealed rapid blood clearance and low uptake by general organs with renal and hepatobiliary excretion. The tumor concentration was low with values of 0.28 and 0.18 %ID/g for lung and breast cancer, respectively. The results imply more studies in other tumor models or the modification of the structure of the organic molecule that act like ligand. (author)

Mixed matrix membranes with fast and selective transport pathways for efficient CO2 separation

Science.gov (United States)

Hou, Jinpeng; Li, Xueqin; Guo, Ruili; Zhang, Jianshu; Wang, Zhongming

2018-03-01

To improve CO2 separation performance, porous carbon nanosheets (PCNs) were used as a filler into a Pebax MH 1657 (Pebax) matrix, fabricating mixed matrix membranes (MMMs). The PCNs exhibited a preferential horizontal orientation within the Pebax matrix because of the extremely large 2D plane and nanoscale thickness of the matrix. Therefore, the micropores of the PCNs provided fast CO2 transport pathways, which led to increased CO2 permeability. The reduced pore size of the PCNs was a consequence of the overlapping of PCNs and the polymer chains penetrating into the pores of the PCNs. The reduction in the pore size of the PCNs improved the CO2/gas selectivity. As a result, the CO2 permeability and CO2/CH4 selectivity of the Pebax membrane with 10 wt% PCNs-loading (Pebax-PCNs-10) were 520 barrer and 51, respectively, for CO2/CH4 mixed-gas. The CO2 permeability and CO2/N2 selectivity of the Pebax-PCNs-10 membrane were 614 barrer and 61, respectively, for CO2/N2 mixed-gas.

A novel approach to Ca-Sr separation in the determination of 90Sr using inorganic exchangers

International Nuclear Information System (INIS)

Stella, R.; Pavia Univ.; Valentini, M.T.G.; Maggi, L.

1992-01-01

A procedure for 90 Sr determination in calcium rich samples is presented. It is based on the precipitation of calcium oxalate in homogeneous solution and under controlled conditions to minimize the comprecipitation of strontium. The latter is subsequently separated as carbonate and radiochemical purification is completed by ion exchange chromatography on two inorganic exchangers: PRTD (partially reduced tin dioxide) and CUCR (copper chromate). The procedure was applied to environmental samples such as ashed sediment, fish and vegetable and results are reported. (author) 15 refs.; 2 tabs

An experimental investigation of accumulation and transmutation behavior of americium in the MOX fuel irradiated in a fast reactor

International Nuclear Information System (INIS)

Osaka, Masahiko; Koyama, Shin-ichi; Maeda, Shigetaka; Mitsugashira, Toshiaki

2005-01-01

Americium isotopes generated in the MOX fuel irradiated in the experimental fast reactor JOYO were analyzed by applying a sophisticated radiochemical technique. Americium was isolated from the irradiated MOX fuel by a combined method of anion-exchange chromatography and oxidation of Am. The isotopic ratios of americium and its content were determined by thermal ionization mass spectroscopy and α-spectrometry, respectively. The americium isotopic ratio was similar for all the specimens, but was significantly different from that of PWR-MOX. On the basis of present analytical results, the accumulation and transmutation behavior of americium nuclides in a fast reactor is discussed from the viewpoints of neutron spectrum dependence and the isomeric ratio of the 241 Am capture reaction. The estimated isomeric ratio is about 87%, which is close to the latest evaluated value. A rapid estimation method of Am content by using the 240 Pu to 239 Pu ratio was adopted and proved to be valid for the spent fuel irradiated in the fast reactor

Liquid--liquid extraction of gold with nickel bis(diethyldithiocarbamate) and its application to activation analysis

Energy Technology Data Exchange (ETDEWEB)

Bajo, S.; Wyttenbach, A.

1977-10-01

The extraction of Au/sup 3 +/ with nickel bis(diethyldithiocarbamate), Ni((C/sub 2/H/sub 5/)/sub 2/NCS/sub 2/)/sub 2/, is investigated. It is shown that this extraction offers a simple, fast, and selective isolation of Au from a variety of matrices. Applications of this separation scheme to the neutron activation analysis of Sn, Fe/sub 2/O/sub 3/, standard rocks, and biological materials are given. The recovery of Au is quantitative, and there is therefore no need to determine the chemical yield of the separation. The recovered Au is of high radiochemical purity.

Frontiers in nuclear chemistry

International Nuclear Information System (INIS)

Sood, D.D.; Reddy, A.V.R.; Pujari, P.K.

1996-01-01

This book contains articles on the landmarks in nuclear and radiochemistry which takes through scientific history spanning over five decades from the times of Roentgen to the middle of this century. Articles on nuclear fission and back end of the nuclear fuel cycle give an insight into the current status of this subject. Reviews on frontier areas like lanthanides, actinides, muonium chemistry, accelerator based nuclear chemistry, fast radiochemical separations and nuclear medicine bring out the multidisciplinary nature of nuclear sciences. This book also includes an article on environmental radiochemistry and safety. Chapters relevant to INIS are indexed separately

In vivo radiochemical properties of Tb-149: A new radiolanthanide for targeted cancer therapy

International Nuclear Information System (INIS)

Allen, B.J.; Beyer, G.J.; Morel, C.H.; Aleksandrova, Y.; Jahn, S.

1996-01-01

Full text: 149 Tb (4.15 h) decays by the emission of both 3.9 MeV alpha particles (17% branching) and positrons (4% branch), and uniquely combines both therapeutic and PET diagnostic properties. In this paper we report the production route, systemic studies of radio-lanthanides with ethylenediaminetetra methylene phosphonate (EDTMP) ligand, and the first 149 Tb phantom studies using PET. The radio-lanthanides used in this study were produced at the ISOLDE (isotope separator on-line) facility at CERN. They are produced carrier free, isotopically and chemically separated (isobaric separation using cation exchange chromatography) in a form suitable for protein labelling. Batches up to 20 mCi of 1 4 9T b are available. We have established relationships between biokinetics, EDTMP concentration, and the ionic radius of the radiolanthanide used. The tumour to liver ratio in mice reaches a maximum value at 1 mM 10 mM and decreases from 10 by almost two decades according to the ionic radius of the lanthanide. For Tb, a tumour to liver ratio of 5 can be obtained, similar to Gd. No significant differences in the uptake in bone for all lanthanides in the EDTMP system were observed. A fast blood clearance allows clear bone images to be obtained via PET at 60-90 min post-injection, as shown with rabbits using 142 Sm-EDTMP. The first phantom PET studies with 149 Tb are also reported. We conclude that the fast biokinetics and the alpha decay mode open up new possibilities for a more efficient endo-radionuclide therapy using EDTMP. The high purity of the 149T b (isotopically separated and carrier free) produced in this way makes it very suitable for the labelling of octretides

Chromatographic hydrogen isotope separation

International Nuclear Information System (INIS)

Aldridge, F.T.

1983-01-01

Intermetallic compounds with the CaCu5 type of crystal structure, particularly LaNiCo and CaNi5, exhibit high separation factors and fast equilibrium times and therefore are useful for packing a chromatographic hydrogen isotope separation column. The addition of an inert metal to dilute the hydride improves performance of the column. A large scale multi-stage chromatographic separation process run as a secondary process off a hydrogen feedstream from an industrial plant which uses large volumes of hydrogen can produce large quantities of heavy water at an effective cost for use in heavy water reactors

Chromatographic hydrogen isotope separation

International Nuclear Information System (INIS)

Aldridge, F.T.

1981-01-01

Intermetallic compounds with the CaCu5 type of crystal structure , particularly LaNiCo and CaNi5, exhibit high separation factors and fast equilibrium times and therefore are useful for packing a chromatographic hydrogen isotope separation colum. The addition of an inert metal to dilute the hydride improves performance of the column. A large scale mutli-stage chromatographic separation process run as a secondary process off a hydrogen feedstream from an industrial plant which uses large volumes of hydrogen can produce large quantities of heavy water at an effective cost for use in heavy water reactors

Fast blood plasma separation device for point-of-care applications

Czech Academy of Sciences Publication Activity Database

Ďurč, P.; Foret, František; Kubáň, Petr

2018-01-01

Roč. 183, JUN (2018), s. 55-60 ISSN 0039-9140 Institutional support: RVO:68081715 Keywords : blood plasma separation * capillary electrophoresis * point of care analysis * methanol * metabolites Subject RIV: CB - Analytical Chemistry, Separation OBOR OECD: Analytical chemistry Impact factor: 4.162, year: 2016

Radiochemical and thermal studies of the copper(II)-exchanged form of synthetic zeolite linde sieve A

International Nuclear Information System (INIS)

Banerjee, S.P.

1978-01-01

Synthetic zeolite Linde Sieve A displays a double ion-sieve action. Only small cations can penetrate the single 6-rings into the beta cages. The radiochemical and thermal studies of copper(II)-exchanges form of 4A shows evidence of hydrated copper(II) ions in the zeolite structure. (author)

Fast separation and quantification of three anti-glaucoma drugs by high-performance liquid chromatography UV detection

Directory of Open Access Journals (Sweden)

Mohamed Walash

2016-04-01

Full Text Available In this study, a simple and accurate high-performance liquid chromatography method was developed and validated for fast separation of three anti-glaucoma drugs: timolol maleate (TM, brimonidine tartrate (BM, and latanoprost (LP. Separation of the three drugs was achieved in < 6 minutes using a BDS Hypersil phenyl column and a mobile phase consisting of acetonitrile: 25mM phosphate buffer, pH 4.0 (50: 50, v/v at 1.2 mL/min with UV detection at 210 nm. The method was linear over the concentration ranges of 5.0–200.0 μg/mL, 2.0–80.0 μg/mL and 1.0–25.0 μg/mL with lower detection limits of 0.21 μg/mL, 0.10 μg/mL and 0.11 μg/mL for TM, BM and LP, respectively. The method was applied for the determination of two fixed-dose combination eye drops for the treatment of glaucoma, containing TM together with either BM or LP. Commercial samples of single-ingredient ophthalmic solutions containing the studied drugs were also successfully analyzed. The results obtained by the proposed method were favorably compared with those obtained by the comparison methods using Student's t test and the variance ratio F test.

Integral method of treatment of experimental data from radiochemical solar neutrino detectors

International Nuclear Information System (INIS)

Gavrin, V.N.; Kopylov, A.V.; Streltsov, A.V.

1985-01-01

An analysis is made of the statistical errors in solar neutrino detection by radiochemical detectors at different times of exposure. It is shown that short exposures (tau/sub e/ = one-half to one half-life) give minimal one-year error. The possibility is considered of the detection of the solar neutrino flux variation due to annual changes of the Earth-Sun distance. The integral method of treatment of the experimental data is described. Results are given of the statistical treatment of computer simulated data

Aspects of 6-[18F]fluoro-L-DOPA preparation: precursor synthesis, preparative HPLC purification and determination of radiochemical purity

International Nuclear Information System (INIS)

Fuechtner, F.; Angelberger, P.; Kvaternik, H.; Hammerschmidt, F.; Simovc, B. Peric; Steinbach, J.

2002-01-01

A modified method for the synthesis of the intermediate product N-Boc-3,4-di(Boc-O)-6-iodo-L-phenylalanine ethyl ester of the [ 18 F]FDOPA precursor preparation was developed. With the application of bis-(trifluoroacetoxy)-iodobenzene for the iodination step with elemental iodine the yield of the intermediate can be increased from 12% to 50-60%. By replacing silica-gel-based RP HPLC column by a polymer-based column for semi-preparative purification of [ 18 F]FDOPA from the reaction mixture the radiochemical purity of the final product can be increased up to >99%. For the determination of the radiochemical impurity [ 18 F]fluoride a HPLC method using a column with polymer-based RP material was introduced

The role of electromagnetic separators in the production of radiotracers for bio-medical research and nuclear medical application

CERN Document Server

Beyer, Gerd-Jürgen

2003-01-01

With the growing complexity of positron emission tomography/single photon emission computed tomography imaging and the new developments in systemic radionuclide therapy there is a growing need for radioisotope preparations with higher radiochemical and radionuclidic purity that has not been achievable before. Especially important for the new applications is the specific activity of the radiotracer. Conventional methods in medical isotope production have reached their technical limitations. The role of isotope separators is discussed with examples of typical production and characterization experiments conducted at the ISOLDE and TRIUMF facilities. These preliminary experiments indicate that isotope separators have a definite role to play in the future for the production of radioisotopes for biomedical research and medical application.

Development of a portable, automated system for the separation of radionuclides by column chromatography

International Nuclear Information System (INIS)

Schumacher, C.; Burow, M.; Flucht, R.; Hill, P.; Zoriy, M.V.

2012-01-01

The determination of the chemical recovery is one of the most important challenges in the radiochemical analysis. Small changes at the pH-value and temperature changes lead to uncontrollable conditions in process. To improve the reproducibility of the chemical determination a separate separating column system (TSM) was developed at the analytic laboratory at JUeLICH. Using the TSM it is possible to separate nuclides by applying variable eluents and ion exchangers also in samples with a very high salt content like urine. Up to now the methods are developed for the elements U, Am and Pu. The automation provides a bigger number of analysed samples per working day and a remarkable economy of time. Due to the increasing of the sample volume it is possible to improve the detection limit of overall analytical procedure (time needed for separation increases). Experimental parameters like rate of flow and chemical recovery were tested. In this progress it was tried to develop a dense portable system which is easy to use. This new TSM allows a realisation of various separating processes by the easy handling via laptop. (orig.)

High radiochemical yield synthesis of [18F]FLT from 3'-O-nosylated thymidine and its 3-N-BOC-protected analogue

International Nuclear Information System (INIS)

Yoon, M. K.; Oh, S. J.; Ryu, J. S.; Moon, D. H.

2002-01-01

We synthesized 3'-O-nosylate and its 3-N-BOC-protected thymidine derivatives as two precursors for high radiochemical yield synthesis of [ 18 F]FLT and optimized [ 18 F]fluorination conditions. (5'-O-DMTr-2'-deoxy-3'-O-nosyl-β-D-threo-pentofuranosyl)thymidine and its s 3-N-BOD-protected analogue were prepared with 54% and 28% yield, respectively. After drying of [ 18 F]F-, 3'-O-nosylate(10-30 mg) or its 3-N-BOC-protected(11-34 mg) precursor was added to 500 μl of CH3CN, respectively. The mixtures were heated at 100-130 .deg. C for 5-30 min. For hydrolysis, 250-500 μl 1N HCl at 50 .deg. C for 5 min condition was used and 1.5ml of 2M sodium acetate was used for neutralization. Reaction mixture was purified by HPLC. The optimal [ 18 F]fluorination yield of 3'-O-nosylate precursor was 85±5.4% with 34 mg of precursor and a reaction time of 5 min at 130 .deg. C. For 3-N-BOC-protected analogue, [ 18 F]fluorination yield was 82±5.4% with 34 mg of precursor and a reaction time of 5 min at 110. deg. C. After HPLC purification, overall radiochemical yield using each precursors were 40±5.2% and 42±5.4% and radiochemical purity were 98±0.5% and 97±2.1% for two precursors, respectively. Preparation time was 60±10.5 min including HPLC purification for two precursors. From these two precursors, [ 18 F]FLT can be easily prepared with high radiochemical yield. 3-N-BOC-protected precursor required milder [ 18 F]fluorination conditions than 3'-O-nosylate precursor

High performance separation of lanthanides and actinides

International Nuclear Information System (INIS)

Sivaraman, N.; Vasudeva Rao, P.R.

2011-01-01

The major advantage of High Performance Liquid Chromatography (HPLC) is its ability to provide rapid and high performance separations. It is evident from Van Deemter curve for particle size versus resolution that packing materials with particle sizes less than 2 μm provide better resolution for high speed separations and resolving complex mixtures compared to 5 μm based supports. In the recent past, chromatographic support material using monolith has been studied extensively at our laboratory. Monolith column consists of single piece of porous, rigid material containing mesopores and micropores, which provide fast analyte mass transfer. Monolith support provides significantly higher separation efficiency than particle-packed columns. A clear advantage of monolith is that it could be operated at higher flow rates but with lower back pressure. Higher operating flow rate results in higher column permeability, which drastically reduces analysis time and provides high separation efficiency. The above developed fast separation methods were applied to assay the lanthanides and actinides from the dissolver solutions of nuclear reactor fuels

Comparison study among methodologies of planar chromatography for radiochemical control of technetium-99m

International Nuclear Information System (INIS)

Monteiro, Elisiane de Godoy

2012-01-01

Radiopharmaceuticals are substances that have radioisotopes in their composition. About 95% of the procedures performed in nuclear medicine use radiopharmaceuticals with diagnostic purposes, and the Lyophilized Reagents (LR) labeled with Technetium-99m ( 99 mTc), obtained from 99 Mo/ 99 mTc generator, are the most one used. Quality Control represents the set of assays to be performed to assure that the product is adequate to its purpose. An important feature to be evaluated in 99m Tc radiopharmaceuticals is the radiochemical purity (% RqP) to quantify free pertechnetate ( 99 mTcO 4 - ) and technetium colloidal (99mTcO 2 ) mainly by paper chromatography (PC), thin layer (TLC) and High Performance Liquid Chromatography (HPLC). The objective of this work was to perform the comparison among the radiochemical control methodologies of LR labeled with 99m Tc, described in the United States Pharmacopoeia (USP) and European Pharmacopoeia (EP) and those used by IPEN. 99m TcO 4 - eluate and DISIDA, DMSA, DTPA, EC, ECD, GHA, MIBI, MDP, PIRO, SAH and Sn Coloidal LR were provided by IPEN-CNEN/SP. TLC-cellulose, TLC-SG.TLC-SG reverse phase, HPTLC-cellulose, HPTLC-SG (Merck) and ITLC-SG (Pall Corporation), W1MM, W3MM, W17M e W31ET (Whatman) chromatographic plates were used. The measurement of the radioactivity was done in a Perkin Elmer Cobra D-5002 gamma counter. LR were labeled to obtain 55,0 MBq mL 1 (1,5 mCi mL 1 ) of final radioactive concentration. The % 99m TcO 4 - , % 99m TcO 2 and % RqP were determined up to 4 hour labeling. From 11 LR, only EC and GHA have no radiochemical control methods in USP and EP. In USP and/or EP, DTPA, MDP, PIRO, SAH and Sn Coloidal methods use ITLC-SG; IPEN uses this chromatography plate in DISIDA, EC, ECD, GHA, PIRO, MIBI and SAH. As ITLC-SG had been out of production (recommended in 40, 70 and 41% of the USP, EP and IPEN methodologies, respectively), it was necessary to search alternatives to replace ITLC-SG plate in the radiochemical control

Evaluation of radiochemical neutron activation analysis methods for determination of arsenic in biological materials.

Science.gov (United States)

Paul, Rick L

2011-01-01

Radiochemical neutron activation analysis (RNAA) with retention on hydrated manganese dioxide (HMD) has played a key role in the certification of As in biological materials at NIST. Although this method provides very high and reproducible yields and detection limits at low microgram/kilogram levels, counting geometry uncertainties may arise from unequal distribution of As in the HMD, and arsenic detection limits may not be optimal due to significant retention of other elements. An alternate RNAA procedure with separation of arsenic by solvent extraction has been investigated. After digestion of samples in nitric and perchloric acids, As(III) is extracted from 2 M sulfuric acid solution into a solution of zinc diethyldithiocarbamate in chloroform. Counting of (76)As allows quantitation of arsenic. Addition of an (77)As tracer solution prior to dissolution allows correction for chemical yield and counting geometries, further improving reproducibility. The HMD and solvent extraction procedures for arsenic were compared through analysis of SRMs 1577c (bovine liver), 1547 (peach leaves), and 1575a (pine needles). Both methods gave As results in agreement with certified values with comparable reproducibility. However, the solvent extraction method yields a factor of 3 improvement in detection limits and is less time-consuming than the HMD method. The new method shows great promise for use in As certification in reference materials.

Radiochemical analysis in the nuclear research establishment (KFA) Juelich, FRG

International Nuclear Information System (INIS)

Anon.

1975-01-01

KFA Juelich is one of the two great nuclear research centres of the Federal Republic of Germany. About 3700 employees including about 700 scientists are engaged in a great number of programs and projects belonging to six main fields of research and development: high temperature reactor and energy techniques; nuclear fusion; properties of materials; materials research; life and environment; methods. In the article the radiochemical analysis work of the former Central Institute of Analytical Chemistry and its two successors is described: activation analysis, application of tracer techniques, fission product analysis. Further on the irradiation facilities are described, a short survey is given on the instrumentation, and the future work is outlined. (T.G.)

Radiochemical methods for studying lipase-catalyzed interesterification of lipids

International Nuclear Information System (INIS)

Schuch, R.; Mukherjee, K.D.

1987-01-01

Reactions involving lipase-catalyzed interesterification of lipids, which are of commendable interest in biotechnology, have been monitored and assayed by radiochemical methods using 14 C-labeled substrates. Medium chain (C 12 plus C 14 ) triacylglycerols were reacted in the presence of an immobilized lipase from Mucor miehei and hexane at 45 0 C with methyl [1- 14 C]oleate, [1- 14 C]oleic acid, [carboxyl- 14 C]trioleoylglycerol, [1- 14 C]octadecenyl alcohol, and [U- 14 C]glycerol, each of known specific activity. The reactions were monitored and the rate of interesterification determined by radio thin layer chromatography from the incorporation of radioactivity into acyl moieties of triacylglycerols (from methyl oleate, oleic acid, and trioleoylglycerol), alkyl moieties of wax esters (from octadecenyl alcohol), and into glycerol backbone of monoacylglycerols and diacylglycerols (from glycerol). (orig.)

Radiochemical plasma salicylamide assay using ring-labeled tritiated salicylamide

Energy Technology Data Exchange (ETDEWEB)

Stella, V J; Varia, S A; Riedy, M

1979-05-01

A rat plasma salicylamide assay was developed using ring-labeled tritiated salicylamide, synthesized by reacting salicylamide with tritium oxide in the presence of heptafluorobutyric acid. The reaction yielded /sup 3/H-salicylamide of specific activity up to 8.41 mCi/mmole, 60% yield. Plasma containing /sup 3/H-salicylamide and its metabolites was extracted with a toluene-based scintillation fluid, which was subsequently counted. Specificity for free salicylamide was demonstrated by radiochemical and standard fluorescence plasma salicylamide level-time curves. Specificity resulted from nonextraction of the salicylamide sulfate and glucuronide metabolites. Sulfatase and beta-glucuronidase treatment allowed the analysis of plasma sulfate and glucuronide conjugates as free salicylamide. This procedure should be effective for the analysis of salicylamide and its metabolites in the presence of similar phenolic compounds.

Magnetic separations in biotechnology.

Science.gov (United States)

Borlido, L; Azevedo, A M; Roque, A C A; Aires-Barros, M R

2013-12-01

Magnetic separations are probably one of the most versatile separation processes in biotechnology as they are able to purify cells, viruses, proteins and nucleic acids directly from crude samples. The fast and gentle process in combination with its easy scale-up and automation provide unique advantages over other separation techniques. In the midst of this process are the magnetic adsorbents tailored for the envisioned target and whose complex synthesis spans over multiple fields of science. In this context, this article reviews both the synthesis and tailoring of magnetic adsorbents for bioseparations as well as their ultimate application. Copyright © 2013 Elsevier Inc. All rights reserved.

Radiochemical determination of strontium-90 and cesium-137 in waters of the Pacific Ocean and its neighboring seas

International Nuclear Information System (INIS)

Borisenko, G.S.; Kandinskii, P.A.; Gedeonov, L.I.; Ivanova, L.M.; Petrov, A.A.

1987-01-01

Depending on the salinity of the water, two versions of strontium-90 and cesium-137 concentration from water samples are presented. Cesium-137 was concentrated by precipitating sparingly soluble mixed hexacyanoferrates (II), and strontium-90 by precipitating carbonates together with calcium. A scheme has been given for radiochemical analysis of the concentrates. Strontium-90 and cesium-137 contents in the waters of the Pacific Ocean and its neighboring seas have been determined by the radiochemical method described. The levels of radionuclide content in the water and atmospheric precipitations have been shown to be inter-related. Strontium-90 and cesium-137 contents in the surface water of the northwestern Pacific were found to be much lower in 1980 than in the early seventies. The area of technogenic radioactive pollution was found to persist in the region of the Columbia mouth into the Pacific Ocean

The material control and accounting system model development in the Radiochemical plant of Siberian Chemical Combine (SChC)

International Nuclear Information System (INIS)

Kozyrev, A.S.; Purygin, V.Ya.; Skuratov, V.A.; Lapotkov, A.A.

1999-01-01

The nuclear material (NM) control and accounting computerized system is designed to automatically account NM reception, movement and storage at the Radiochemical Plant. The objective of this system development is to provide a constant surveillance over the process material movement, to improve their accountability and administrative work, to upgrade the plant protection against possible NM thefts, stealing and diversion, to rule out any casual errors of operators, to improve the timeliness and significance (reliability) of information about nuclear materials. The NM control and accounting system at the Radiochemical Plant should be based on the computerized network. It must keep track of all the material movements in each Material Balance Areas: material receipt from other plant; material local movement within the plant; material shipment to other plants; generation of required documents about NM movements and its accounting [ru

Volatile and non-volatile elements in grain-size separated samples of Apollo 17 lunar soils

International Nuclear Information System (INIS)

Giovanoli, R.; Gunten, H.R. von; Kraehenbuehl, U.; Meyer, G.; Wegmueller, F.; Gruetter, A.; Wyttenbach, A.

1977-01-01

Three samples of Apollo 17 lunar soils (75081, 72501 and 72461) were separated into 9 grain-size fractions between 540 and 1 μm mean diameter. In order to detect mineral fractionations caused during the separation procedures major elements were determined by instrumental neutron activation analyses performed on small aliquots of the separated samples. Twenty elements were measured in each size fraction using instrumental and radiochemical neutron activation techniques. The concentration of the main elements in sample 75081 does not change with the grain-size. Exceptions are Fe and Ti which decrease slightly and Al which increases slightly with the decrease in the grain-size. These changes in the composition in main elements suggest a decrease in Ilmenite and an increase in Anorthite with decreasing grain-size. However, it can be concluded that the mineral composition of the fractions changes less than a factor of 2. Samples 72501 and 72461 are not yet analyzed for the main elements. (Auth.)

A radiochemical separation of spallogenic 88Zr in the carrier-free state for radioisotopic photoneutron sources

International Nuclear Information System (INIS)

Whipple, R.E.; Grant, P.M.; Daniels, R.J.; Daniels, W.R.; O'Brien, H.A.Jr.

1976-01-01

As the precursor of its 88 Y daughter, 88 Zr could be advantageously included in the active component of the 88 Y-Be photoneutron source for several reasons. The spallation of Mo targets with medium-energy protons at LAMPF procedure has been developed to separate radiozirconium from the target material and various spallogenic impurities. 88 Zr can consequently be obtained carrier-free and in quantitative yield. (author)

Radiochemical surveillance of KNK primary sodium

International Nuclear Information System (INIS)

Stamm, H.-H.; Stade, K.Ch.

1987-05-01

Radiochemical surveillance of the KNK primary sodium has been performed now for 15 years with 953 effective full-power days. The overflow method used for sodium sampling proved to be reliable. Different crucible materials have been used for different analytical tasks. The amount of radionuclides in the primary system has not given restrictions to plant operation at any time. On-line gamma spectroscopy on pipings and components of the primary circuits was accomplished in reactor downtimes. Activity depositions on the walls were dominated by Ta-182 after KNK I operation. Main deposited activities at KNK II were Mn-54 (fresh core) and after operation with failed fuel Cs-137, in cover gas areas together with Zn-65. Efficient experimental radionuclide traps for the removal of Mn-54, Zn-65 and Cs-137 from the primary coolant were tested successfully. The dose rates on primary pipes and components of KNK I and KNK II were lower by an order of magnitude compared to water-cooled reactors. This is in good agreement with experiences from LMFBR's in other countries. The resulting average yearly accumulated personal dose rate was 0.21 man-Sv at KNK, compared to 3.9 man-Sv at German light-water-cooled power reactors

Radiochemical studies on amorphous zirconium phosphate

Energy Technology Data Exchange (ETDEWEB)

Dyer, A; Moores, G E [Salford Univ. (UK). Dept. of Chemistry and Applied Chemistry

1981-01-01

Amorphous zirconium phosphate (ZrP) is used in some hemodialysis machines for the regeneration of dialysate. Its function is to adsorb ammonium ions formed by the pretreatment of urea by urease. It also adsorbs Ca, Mg and K ions but leaches phosphate ions which are then removed (along with F/sup -/ ions) by a bed of hydrous zirconium oxide. The sodium form of ZrP is used although other forms have been suggested for use. The work reported here describes some preliminary radiochemical studies on the mechanism of release of phosphate ions and its possible relationship to sodium ion-exchange. /sup 32/P labelled material (HHZrP) was used for elution experiments with deionized water and buffer solutions having the pH's 4.2, 7.0 and 9.2. Buffer solutions used were as supplied by BDH. Elution was at four different temperatures in the range 293 to 363/sup 0/C. In the second series of experiments HHZrP was suspended in a NaCl solution labelled with /sup 22/Na. From this, /sup 22/Na labelled ZrP (NaHZrP) was prepared and eluted in the same way as the HHZrP. Results are given and discussed.

Determination of chromium, cobalt and nickel in tissue samples by radiochemical activation analysis

International Nuclear Information System (INIS)

Reisell, A.; Lakomaa, E.L.

1983-03-01

A radiochemical neutron activation analysis method for the determination of chromium, cobalt and nickel in tissue samples. A radiochemical neutron activation analysis method for the determination of chromium, cobalt and nickel has been developed. The destruction device used consisted of a combined wet-ashing-distillation and ion-exchange system. Six samples could be treated at the same time. The samples were wet-ashed with H*L2SO*L4-H*L2O*L2 mixture. Volatile elements were distilled as bromide compounds with HBr*H-. The distillation residue in 8M HCl was passed through hydrated antimony pentoxide (HAP) in order to remove disturbing *H2*H4Na-activity and through a Dowex 2 x 8 column so as to retain *H6*H0Co (formed from *H5*H8Ni). Chromium was elutriated from the column and precipitated as Cr(OH)*L3 for the removal of disturbing *H3*H2P-activity. The standards and samples were treated in a similar manner each so that the yield determination is not necessarily needed. The yields by tracer experiments were (43 +- 5) % for Cr, (93 +- 4) % for Co and (88 +- 14) % for Ni. The precision and accuracy of the method were studied by using reference materials of the National Bureau of Standards (NBS) and the International Atomic Energy Agency (IAEA)

The design of a new radiochemical laboratory complex

International Nuclear Information System (INIS)

Lewis, A.G.

1984-01-01

A brief account is given of the history and scope of Amersham International plc in the manufacture of radiopharmaceuticals and other labelled organic compounds, and radioactive sources. Extra facilities were needed and a new site was found, and contracts placed for new radiochemical laboratories. The two new laboratories, which are described in some detail, are intended as follows: (a) a Medical Products building for the production of a range of diagnostic kits for use in the treatment of thyroid and other disorders, the main isotope used being iodine-125; and (b) the Chemical Products building, for the development and manufacture of a wide range of organic compounds, which are labelled with either tritium or carbon-14. Particular emphasis is given to the description of the air conditioning and ventilation systems, the open work benches, and the special ventilated enclosures, and the drainage system. Planning for maximum flexibility is also stressed. (U.K.)

Fast synthesis and separation of the arsenoglutathione complexes

Czech Academy of Sciences Publication Activity Database

Petry-Podgorska, Inga; Balcarová, B.; Matoušek, Tomáš

2016-01-01

Roč. 14, č. 5 (2016), s. 192-192 ISSN 2336-7202. [Sjezd chemických společností /68./. 04.09.2016-07.09.2016, Praha] R&D Projects: GA MŠk(CZ) LH15174 Institutional support: RVO:68081715 Keywords : ICP-MS * HPLC * arsenoglutathione complexes Subject RIV: CB - Analytical Chemistry, Separation

Radiochemical studies in chemical separation and spectrographic determination of rare earths in thorium oxide matrix (Preprint No. RA.06)

International Nuclear Information System (INIS)

Adya, V.C.; Dhawale, B.A.; Rajeshwari, B.; Bangia, T.R.; Sastry, M.D.

1989-01-01

A chemical separation procedure was standardised for the separation of traces of rare earths from ThO 2 matrix using HDEHP (Di 2-ethyl hexyl phosphoric acid). The studies were carried out using both nitric acid and hydrochloric acid medium in different concentrations. The extraction studies were also carried out using radioactive isotopes of rare earths viz. 141 Ce, 152-154 Eu, 153 Gd, 170 Tm etc. The extraction was effective in both media. In 0.1 M HDEHP/xylene and 3 M HNO 3 , Ce was partially extracted into organic phase. So HCl/xylene medium was chosen for extraction purposes. The recovery was confirmed by both gamma counting and emission spectropgraphic method. It was found to be quantitative within experimental error. The separation procedure development here was used for determination of rare earths in thorium oxide matrix by emission spectrographic method. (author)

Radiochemical Procedures Used at Iaea-Ilmr Monaco for Measuring Artificial Radionuclides Resulting from the Chernobyl Accident

Science.gov (United States)

Ballestra, S.; Gastaud, J.; Lopez, J. J.

The Chernobyl accident which occurred on 26 April 1986 resulted in relatively high levels of radioactive fallout over the major part of Europe. Air filter and precipitation samples enabled us to follow the contamination from the accident. In addition contamination was also monitored in selected environmental samples such as seaweeds, sea water, sediment, soil, suspended matter and biological material from the Mediterranean. All samples were counted on Ge(Li) or Ge(HP) detectors to determine the type and quantity of gamma emitting radionuclides and plutonium, americium and curium isotopes were separated and measured using radiochemical techniques and alpha counting. Increased atmospheric radioactivity from the Chernobyl accident was first detected by observing increased activity levels on air filters taken on April 30, 1986, with maximum activities occurring during 1-3 May. Most of the radionuclides initially measured were short-lived fission products. Cs-137 was one of the predominant isotope in the fallout debris and its deposition at Monaco due to Chernobyl was estimated to be around 1400 Bq m-2, which represents 25-40% of the integrated fallout at this latitude. The deposition of Pu-239+240 was much smaller and was estimated to be around 10 mBq m-2 or only 0.1% of the total deposition from nuclear weapon testing.

Separation of plutonium on the anion exchanger BIO-RAD 1-X2 and its application to radiochemical analysis

International Nuclear Information System (INIS)

Bajo, S.; Gann, C.; Eikenberg, J.; Wyer, L.; Beer, H.; Ruethi, M.; Jaeggi, M.; Zumsteg, I.

2007-12-01

The element Pu (Z = 94) is a member of the actinide series of the elements (Z = 89 -103). The actinides have similar chemical properties and are also similar to the lanthanides (Z = 57 -71). Sixteen isotopes of Pu have been synthesized, all of which are radioactive. The Pu present in the environment originates from the atmospheric nuclear tests from 1950 to 1963, which produced the so-called 'global fallout'. As a result, 6.5 · 10 15 Bq 239 Pu (2.8 tons), 4.4 · 10 15 Bq 240 Pu (0.52 tons), and 3.7 · 10 4 Bq 241 Pu (0.04 tons) were dispersed over the world. A contribution also to the global fallout was the ignition of the satellite SWAP 9A in the atmosphere in 1964, equipped with a battery powered by 6.3 · 10 14 Bq (1 kg) of 238 Pu. In addition to these sources, nuclear reactors, reprocessing plants and radioactive waste facilities may contribute with their emissions to increase locally the Pu concentration in their environment. In the PSI laboratory, we are confronted with the determination of traces of 238 Pu, 239 Pu and 240 Pu in environmental and biological materials. Because of the low quantity of Pu in the analyzed samples, which is usually below 100 mBq, it is mandatory to separate the Pu from all other accompanying elements. The separated Pu is then measured by alpha spectrometry. In this work, the anion exchanger BIO-RAD AG 1 is extensively used for the separation of Pu from different matrices. This exchanger is superior when only Pu is determined in the sample. In addition, it is also very suitable when other actinides, such as Am and Cm, are also determined. No preconcentration step is necessary for the Pu separation. The resins introduced by the company Eichrom Industries in the 90's, which allow the separation of the actinides from the major environmental elements and from each other, requires relatively small volumes of sample solution. This report describes the extensive utilization of the classical anion exchanger BIO-RAD 1-X2 in 8 molar nitric

Study of performance characteristics of a radiochemical method to determine uranium in biological samples

International Nuclear Information System (INIS)

Puga, Maria J.; Cerchietti, Maria L.R.; Prudenzo, J.E.; Arguelles, Maria G.

2005-01-01

In this paper is described a methodology to calculate detection limit (Ld), quantification level (Lq) and minimum detectable activity (MDA) in a radiochemical method for determination of uranium in urine samples. The concentration is measured by fluorimetry and alpha gross activity using liquid scintillation counting (LSC). The calculation of total propagated uncertainty on a spike sample is presented. Furthermore, the major sources of uncertainty and percentage contribution in both measurements are assessed. (author)

Radio-chemical applications of columns of precipitated insoluble sulphates - contribution to the study of fission product solutions (1962); Applications en radiochimie de colonnes de precipites de sulfates insolubles - contribution a l'etude des solutions vieillies de produits de fission (1962)

Energy Technology Data Exchange (ETDEWEB)

Sauvagnac, R [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires; Barrachina, M [Junta de la Energia Nuclear, Madrid (Spain)

1962-07-01

After describing the preparation of SrSO{sub 4} and BaS0{sub 4} columns, the authors study the following variables affecting fixation of Sr{sup 90}: - influence of pH, of the SO{sub 4}{sup --} concentration in the solution studied, of the column density, of the flow rate, of the use of the EDTA complex. A mechanism is proposed for the exchange and fixation. Once the column characteristics had been chosen, the fixation of rare-earths in the absence or presence of EDTA was studied. - it was observed that for nitrate or chloride concentrations of over 2 mg/ml, or in the presence of stronger than 1 N HNO{sub 3} or HCl, barium was fixed selectively. - these results were applied to radiochemical separations in fission product solutions: Ba{sup 140} and Sr{sup 90} separation, and that of the ceric earth group and the yttric earth group. - In order to establish a complete scheme for the radio-chemical separation in fission product solution, after at least one year ageing, the techniques of column separation and of solvent extraction using thenoyltrifluoroacetone and bis di-ethylhexylphosphoric acid are combined. (authors) [French] Apres avoir decrit la preparation des colonnes de SrS0{sub 4} et BaS0{sub 4}, on etudie les variables suivantes pour la fixation de {sup 90}Sr: - influence du pH, de la concentration en SO{sub 4}{sup --} dans la solution etudiee, de la densite de la colonne, de la vitesse de passage, de l'emploi du complexant EDTA. On propose une explication du mode d'echange et de fixation. Les caracteristiques de la colonne etant choisies, on a etudie la fixation des terres rares en presence ou non de EDTA. - on a d'autre part constate qu'en milieu chlorure ou nitrate, de concentration superieure a 2 mg/ml, ou en presence de HNO{sub 3} ou HCl superieur a 1 N, on fixait selectivement le baryum. - on a applique ces resultats a des separations radiochimiques dans des solutions de produits de fission: separation de {sup 140}Ba, {sup 90}Sr, separation du groupe des

Use of 236Pu and 242Pu as a radiochemical tracer for estimation of Pu in bioassay samples by fission track analysis

International Nuclear Information System (INIS)

Sawant, Pramilla D.; Prabhu, Supreetha P.; Kalsi, P.C.

2008-01-01

236 Pu and 242 Pu are routinely used as radiochemical yield monitors in India for bioassay monitoring of occupational workers by alpha spectrometry. Fission Track Analysis (FTA) is also being standardized for trace level determination of Pu in bioassay samples. The present study, reports the utility of 236 Pu and 242 Pu as radiochemical tracers in estimation of Pu in bioassay samples by FTA technique. The advantages of using 236 Pu tracer in FTA over 242 Pu as well as the interference caused due to presence of 241 Pu in the bioassay samples of occupational workers handling power reactor grade Pu is discussed. (author)

Separation of 99Mo from 132Te using thiourea as complexing agent. Application to the separation of 99Mo from the fission products

International Nuclear Information System (INIS)

Mestnik, S.A.C.

1987-01-01

A radiochemical method to isolate 99 Mo from 132 Te both produced in the fission of 235 U has been developed. The method is based on the formation of a cationic complex of tellurium with thiourea in acid medium wich is retained (98.7+-0.5) % on a cation exchange resin (Dowex 50W-X8, 100-200 mesh) wile (99.8+-0.05)% 99 Mo passes through it, due to the non formation of such complex in the same experimental conditions. The radiochemical purity of the separated 99 Mo verified by using gamma spectrometry was found to be suitable for the preparation of 99 Mo- 99m Tc generators. The retention of 99 Mo on an alumina column as function of pH was investigated. The best pH range for this purpose was found to be between 4.0-4.5. Yellow crystals with melting point of 115 0 C were formed when non-irradiated tellurium reacted with thiourea. Elemental analysis, ultra-violet and infra-red absorption spectrophotometry as well as thermogravimetry were used to characterize the complex formed. In the studies made in order to characterize the compound it has been observed: 1. the most probable chemical composition of the complex studied is [Te(SCN 2 H 4 ) 4 ] (SO 4 ) 2 ; 2. the coordination takes place between tellurium and sulphur atoms; 3. the maximum absorption in the ultra-violet region occurs near 310nm. The thermogravimetric curves obtained allowed to propose the concerned thermodecomposition mechanism. (author) [pt

Hydrologic conditions and distribution of selected radiochemical and chemical constituents in water, Snake River Plain aquifer, Idaho National Engineering Laboratory, Idaho, 1992 through 1995

International Nuclear Information System (INIS)

Bartholomay, R.C.; Tucker, B.J.; Ackerman, D.J.; Liszewski, M.J.

1997-04-01

Radiochemical and chemical wastewater discharged since 1952 to infiltration ponds and disposal wells at the Idaho National Engineering Laboratory (INEL) has affected water quality in the Snake River Plain aquifer. The US Geological Survey, in cooperation with the US Department of Energy, maintains a monitoring network at the INEL to determine hydrologic trends and to delineate the movement of radiochemical and chemical wastes in the aquifer. This report presents an analysis of water-level and water-quality data collected from the Snake River Plain aquifer during 1992--95

Radiochemical applications of insoluble sulfate columns. Analytical possibilities in the field of the fission product solutions; Aplicaciones radioquimica de las columnas de precipitados de sulfatos insolubles. Contribucion al estudio de las soluciones envejecidas de productos de fision

Energy Technology Data Exchange (ETDEWEB)

Barrachina, M; Sauvagnac, R

1962-07-01

In this paper we go on with our study of the heterogeneous ion-isotopic exchange in column. At present, we apply it to determine the radiochemical composition of the raw solutions used in the industrial recuperation of the long-lived fission products. The separation of the radioelements contained in these solutions is carried out mainly by making use of small columns, 1-3 cm height, of BaSO{sub 4} or SrSO{sub 4}, under selected experimental conditions. These columns behave like a special type of inorganic exchangers, working by absorption or by ion-isotopic exchange depending on the cases,a nd they provide the means for the selective separation of several important fission products employing very small volumes of fixing and eluting solutions. (Author) 11 refs.

Application of fast Fourier transforms to the direct solution of a class of two-dimensional separable elliptic equations on the sphere

Science.gov (United States)

Moorthi, Shrinivas; Higgins, R. W.

1993-01-01

An efficient, direct, second-order solver for the discrete solution of a class of two-dimensional separable elliptic equations on the sphere (which generally arise in implicit and semi-implicit atmospheric models) is presented. The method involves a Fourier transformation in longitude and a direct solution of the resulting coupled second-order finite-difference equations in latitude. The solver is made efficient by vectorizing over longitudinal wave-number and by using a vectorized fast Fourier transform routine. It is evaluated using a prescribed solution method and compared with a multigrid solver and the standard direct solver from FISHPAK.

A new radiochemical assay for fructose-1,6-diphosphatase in human leucocytes

International Nuclear Information System (INIS)

Janssen, A.J.M.; Trijbels, F.J.M.

1982-01-01

Fructose-1,6-diphosphatase (D-fructose-1,6-diphosphate 1-phosphohydrolase, EC 3.1.3.11, FDPase) is one of the key enzymes of the gluconeogenic pathway. Measuring the activity both in the presence and in the absence of AMP yields the true FDPase activity, corrected for non-specific phosphatase activity. In this paper the authors introduce a new radiochemical assay for FDPase, based on the decarboxylating activity of 6-phosphogluconate dehydrogenase. One molecule [U- 14 C]fructose-1,6-diphosphate yields one molecule 14 CO 2 which can be captured in strongly basic solutions and counted in a liquid scintillation counter. (Auth.)

Separation of plutonium on the anion exchanger BIO-RAD 1-X2 and its application to radiochemical analysis

Energy Technology Data Exchange (ETDEWEB)

Bajo, S.; Gann, C.; Eikenberg, J.; Wyer, L.; Beer, H.; Ruethi, M.; Jaeggi, M.; Zumsteg, I

2007-12-15

The element Pu (Z = 94) is a member of the actinide series of the elements (Z = 89 -103). The actinides have similar chemical properties and are also similar to the lanthanides (Z = 57 -71). Sixteen isotopes of Pu have been synthesized, all of which are radioactive. The Pu present in the environment originates from the atmospheric nuclear tests from 1950 to 1963, which produced the so-called 'global fallout'. As a result, 6.5 {center_dot} 10{sup 15} Bq {sup 239}Pu (2.8 tons), 4.4 {center_dot} 10{sup 15} Bq {sup 240}Pu (0.52 tons), and 3.7 {center_dot} 10{sup 4} Bq {sup 241}Pu (0.04 tons) were dispersed over the world. A contribution also to the global fallout was the ignition of the satellite SWAP 9A in the atmosphere in 1964, equipped with a battery powered by 6.3 {center_dot} 10{sup 14} Bq (1 kg) of {sup 238}Pu. In addition to these sources, nuclear reactors, reprocessing plants and radioactive waste facilities may contribute with their emissions to increase locally the Pu concentration in their environment. In the PSI laboratory, we are confronted with the determination of traces of {sup 238}Pu, {sup 239}Pu and {sup 240}Pu in environmental and biological materials. Because of the low quantity of Pu in the analyzed samples, which is usually below 100 mBq, it is mandatory to separate the Pu from all other accompanying elements. The separated Pu is then measured by alpha spectrometry. In this work, the anion exchanger BIO-RAD AG 1 is extensively used for the separation of Pu from different matrices. This exchanger is superior when only Pu is determined in the sample. In addition, it is also very suitable when other actinides, such as Am and Cm, are also determined. No preconcentration step is necessary for the Pu separation. The resins introduced by the company Eichrom Industries in the 90's, which allow the separation of the actinides from the major environmental elements and from each other, requires relatively small volumes of sample solution

Fractionation of Cardiolite for clinical use: comparative evaluation of radiochemical purity by thin-layer and paper chromatography of 99mTc-hexakis-2-methoxy-isobutyl-isonitrile complex

International Nuclear Information System (INIS)

Albernaz, M.S.; Pantoja, M.R.; Martinho, M.J.R.; Fonseca, M.L.B.; Bernardo-Filho, Mario

1996-01-01

Twenty-five vials of the previous divided Cardiolite (technetium-99m-hexakis-2-metoxi-isobutyl-isonitrile) were evaluated immediately after labeling with technetium-99m and in 15 them the specific activity assurance was checked at hourly intervals up to 3 hours. Quality control assessment comprised instant thin-layer chromatography, as suggested by the manufacturer, compared to paper chromatography which is widely available and less expensive than the former. Among the 25 bottles, 21 had a radiochemical purity higher than 89%. The redistribution of the Cardiolite in small doses vacuum containers was a practical and reliable technique. The technetium-99m-isonitrile was a stable radiochemical compound thought the three hours period of observation and proved adequate for clinical use. When thin-layer and paper chromatography were compared there was no significant difference regarding radiochemical purity. (author)

Radiochemical Study on the Separation of Chromium-51 from the Irradiated Target by Using Commercial and/or Synthesized Ion Exchanger

International Nuclear Information System (INIS)

Aydia, M.I.M.M.

2012-01-01

This work involves the following steps:1- Preparation of Triton X-100 Cerium(IV) Phosphate (TX-100CeP) as a surface active ion exchanger or organometallic molecules. 2- Characterization of the TX-100CeP by different methods (i.e. IR, TGA/DTA X-ray diffraction, X-ray fluorescence and elemental analysis). 3- Development a method for separation and quantification of Cr(III) and Cr(VI) by using high pressure liquid chromatography (HPLC). 4- Separation of 51 Cr(III) from Cr(VI) in the target of K 2 CrO 4 on TX-100CeP and Permutit as a commercial ion exchanger. 5- Quality control on the separated 51 Cr(III).

Validation of the FDG (18F) radiochemical purity assay by thin layer chromatography

International Nuclear Information System (INIS)

Leao, R.L.C.; Oliveira, M.L.; Nascimento, J.E.; Nascimento, N.C.E.S.

2013-01-01

All methodologies utilized in radiopharmaceutical industry should be validated in order to prove that they meet the requirements of analytical applications, ensuring the reliability of the results. At a radiopharmaceutical industry there is one challenge aspect: sometimes it is not possible use a stable standard to perform the validation analysis. In order to overcome this difficulty, the objective of this study was to suggest a validation protocol for these methodologies, based on the recommendations of RE n° 899/Agencia Nacional de Vigilancia Sanitaria (ANVISA), and prove its efficiency, performing the radiochemical purity validation test of FDG (18F), by TLC. To obtain the calibration curve, we suggested that the theoretical activity values should be determined using a dose calibrator, simultaneously of each analysis performed by TLC, for 5 hours. The method was linear (R 2 of 0.996), precise (CV% <5%) and accurate (96.85% < accuracy < 102.56%). In relation to the robustness test, our experiments evaluated the influence of the distance travelled by mobile phase, variations at mobile phase concentration and type of chromatographic plate (silica gel on glass or aluminium plates). The detection and quantification limits were determined (321.9 and 1065.6 kBq, respectively). As expected, this methodology was nonspecific, showing a slight spot corresponding to the FDM. The proposed protocol was efficient and the methodology tested was effective to determine the radiochemical purity of FDG (18F), in accordance to the limits recommended by ANVISA. (author)

Simultaneous radiochemical determination of plutonium, strontium, uranium, and iron nuclides and application to atmospheric deposition and aerosol samples

International Nuclear Information System (INIS)

Rosner, G.; Hoetzl, H.; Winkler, R.

1990-01-01

A procedure for the sequential radiochemical determination of plutonium, strontium, uranium and iron nuclides is described. The separation is carried out on a single anion exchange column. Pu(IV), U(VI) and Fe(III) are fixed on Bio Rad AG 1-X4 from 9 mol/l HCl, while the sample effluent is used for the determination of radiostrontium. Fe and U are eluted separately with 7 mol/l HNO 3 , and Pu(III) is eluted with 1.2 mol/l HCl containing hydrogen peroxide. Subsequently, Pu and U are electrolysed and counted by alpha spectrometry. Radiostrontium is purified by the nitrate method and counted in a low level beta proportional counter. Fe is purified by extraction and cation exchange and 55 Fe is counted by X-ray spectrometry with a Si(Li) detector. The sample preparation and the application of the procedure to large samples, namely aerosols from 10 5 m 3 of air, and monthly deposition samples from 0.6 m 2 sampling area (10-100 l) are described. Chemical yields are for Pu 70 ± 20, for Sr 80 ± 15, for U 80-90, and for Fe 75 ± 10%. As an example, the maximum airborne radionuclide concentrations determined with that procedure in fortnightly collected samples at Neuherberg after the Chernobyl accident were: 239+240 Pu, 2.58; 238 Pu, 1.40; 238 U, 0.65; 234 U, 0.67; 90 Sr, 7600; and 55 Fe, 990 μBqm -3 . With appropriate changes in sample preparation, the procedure is applicable to other kinds of samples. (orig.)

Microsystems for anion exchange separation of radionuclides in nitric acid media

Energy Technology Data Exchange (ETDEWEB)

Losno, M.; Brennetot, R.; Mariet, C. [DEN/Service d' Etudes Analytiques et de Reactivite des Surfaces - SEARS, CEA, Centre de Saclay, Universite Paris-Saclay, F-91191, Gif sur Yvette (France); Ferrante, I.; Descroix, S. [MMBM Group, Institut Curie Research Center, CNRS UMR 168, Paris (France)

2016-07-01

An efficient and reproducible photo-polymerized poly(ethylene glycol methacrylate methacrylate-co- allyl methacrylate) monolith was synthesized and a photo-grafting process based on the ene-thiol click-chemistry has been performed to give anion exchange properties to the monolith. Since their introduction in the early 1990's polymethacrylate monoliths have emerged as a powerful alternative for microscale separations or sample treatment. Their relatively simple implementation in columns with small internal diameters makes them particularly attractive for the new chromatographic challenges of complex matrices analysis and on-chip separations. Despite their relatively poor ion-exchange capacity due to their highly porous structure, their use as anion exchangers is of large interest for nuclear analysis as numerous separations are based on this process. This paper presents a systematic study of the synthesis of the polymeric porous monolith and the versatile and robust functionalization method developed for the specific strong acidic media used in radiochemical procedures. The robustness of the stationary phase was tested in concentrated nitric acid. It appears that the C-S bond formed via thiol-ene chemistry is strong enough to be used to graft function of interest for separation in strong nitric acid medium. The photo-grafted anion exchanger, a quaternary ammonium, presents sufficient resistance to be used for radionuclide separation in [HNO{sub 3}]=5 mol.L{sup -1}so the next step is its integration in the cyclo olefin copolymer (COC) micro-system.

An automated system for selective fission product separations; decays of 113-115Pd

International Nuclear Information System (INIS)

Meikrantz, D.H.; Gehrke, R.J.; McIsaac, L.D.; Baker, J.D.; Greenwood, R.C.

1981-01-01

A microcomputer controlled radiochemical separation system has been developed for the isolation and study of fission products with half-lives of approx. >= 10 s. The system is based upon solvent extraction with three centrifugal contactors coupled in series, which provides both rapid and highly efficient separations with large decontamination factors. This automated system was utilized to study the radioactive decays of 113-115 Pd via solvent extraction of the Pd-dimethylglyoxime complex from 252 Cf fission products. As a result of this effort, γ-rays associated with the decay of approx. equal to 90-s sup(113,113m)Pd, 149-s 114 Pd and 47-s 115 Pd have been identified. The isotopic assignments to each of these Pd radioactivities have been confirmed from observation of the growth and decay curves of their respective Ag daughters. In addition, previously unreported Ag γ-rays have been assigned; one to the decay of 69-s 113 Ag, and two to the decay of 19-s 115 Ag. (orig.)

Paleomagnetism and radiochemical age estimates for Late Brunhes polarity episodes

International Nuclear Information System (INIS)

Denham, C.R.; Anderson, R.F.; Bacon, M.P.

1977-01-01

Several reversed polarity magnetozones occur within deep-sea sediment core CH57-8 from the Greater Antilles Outer Ridge, within sediment of latest Pleistocene/Late Brunhes age. The uppermost reversed interval spanning 31 data points coincides with the X faunal zone of the Last Interglacial Period. Radiochemical dating of cores CH57-8 and KN25-4 has shown that all the reversed polarity magnetozones are significantly younger than the Brunhes/Matuyama boundary at 0.7 m.y.B.P. A variation of the excess 230 Th method was used, in which 210 Po and 238 U were the actual radionuclides measured. In a third core from the Mid-Atlantic Ridge, the 210 Po results were similar to those which others obtained earlier by direct 230 Th measurements. (Auth.)

Research reactor FR2 - 20 years chemical and radiochemical measurements

International Nuclear Information System (INIS)

Feuerstein, H.; Graebner, H.; Oschinski, J.; Hoffmann, W.; Beyer, J.

1986-09-01

The FR2 has been a D 2 O cooled and moderated research reactor with a thermal output of 44 MW. It was in operation from 1961 to 1981. Because of the operating conditions of the reactor, only a small number of routine measurements were performed. For these however special techniques had to be developed. During the 20 years of operation a number of special events occured or have been observed, sometimes with very amazing results, e.g. the 'aceton effect'. This report describes the chemical and radiochemical conditions of the reactor systems, as well as the results of the surveilance work. Not described are measurements for the many experiments. The last chapter gives in a short form a description of the most unusual events and observations. (orig.) [de

Study of the isotopic exchange associated with ionic exchange for the radiochemical separation of 233-Th

International Nuclear Information System (INIS)

Sepulveda Munita, C.J.A.

1983-01-01

The isotopic ion exchange procedure is applied in order to establish an analytical method for the determination of thorium by means of the 233 Th activity, when the presence of interfering elements does not allow a direct non-destructive activation analysis. The separation is based on the retention of 233 Th by a thorium saturated resin, due to the isotopic exchange effect, and subsequent elution of the interfering radioisotopes with a solution of thorium in diluted hydrochloric acid. The interfering elements were those which either present a great affinity for the resin or emit gamma rays with energies close to that of 233 Th (86.6 KeV), when a NaI(Tl) detector is used to obtain the gama-ray spectra of the irradiated samples. The equilibrium time for the thorium isotopic ion exchange and the distribution coefficients for the interfering elements were determined by using Bio-Rad AG 50W resins (100-200 mesh), with 4% to 8% of divinylbenzene. The best separation conditions were established in terms of the thorium and hydrochloric acid concentrations in the solution, the resin cross-linking degree, and the solution flow through the resin. The analytical method was applied to the determination of thorium in samples of ammonium diuranate as well in standard rock samples from the United States Geological Survey. The sensitivity, precision and accuracy of the method are also discussed. (Author) [pt

Gradient method for blind chaotic signal separation based on proliferation exponent

International Nuclear Information System (INIS)

Lü Shan-Xiang; Wang Zhao-Shan; Hu Zhi-Hui; Feng Jiu-Chao

2014-01-01

A new method to perform blind separation of chaotic signals is articulated in this paper, which takes advantage of the underlying features in the phase space for identifying various chaotic sources. Without incorporating any prior information about the source equations, the proposed algorithm can not only separate the mixed signals in just a few iterations, but also outperforms the fast independent component analysis (FastICA) method when noise contamination is considerable. (general)

Report on the radiochemical and environmental isotope character for monitoring well UE-1-q: Groundwater Characterization Program

International Nuclear Information System (INIS)

Davisson, M.L.; Hudson, G.B.; Kenneally, J.; Nimz, G.J.; Rego, J.H.

1993-06-01

Well UE-1-q is located in the northeastern portion of area 1 of the Nevada Test Site in southwestern Nevada, 1244.1 meters above sea level. The well was originally an exploratory hole drilled to a depth of 743 meters below the surface (mbs) by LANL in November of 1980. In May 1992, the Groundwater Characterization Program (GCP) extended the total depth to approximately 792.5 mbs. UE-1-q is cased to a total depth of 749.5 mbs, with the remaining uncased depth exposed exclusively to Paleozoicaged carbonate rock, the principle zone of groundwater sampling. Geologic logging indicates approximately 390 meters of tuffaceous and calcareous alluvium overlies 320 meters of Tertiary-aged volcanic ash-flow and bedded tuffs. Paleozoic carbonate lithology extends from 716 mbs to the total well depth and is separated from the overlying Tertiary volcanic deposits by 6 meters of paleocolluvium. This report outlines the results and interpretations of radiochemical and environmental isotopic analyses of groundwater sampled from UE-1-q on July 10, 1992 during the well pump test following well development. In addition, results of the field tritium monitoring performed during the well drilling are reported in Appendix 1. Sampling, analytical techniques, and analytical uncertainties for the groundwater analyses are presented in Appendix 2

Syntheses of therapeutically active labelled molecules for metabolic and pharmacokinetic studies. Synthesis, preservation and radiochemical purity problems

International Nuclear Information System (INIS)

Pichat, L.

1977-01-01

Molecules labelled with radioactive isotopes are without question an essential tool for metabolic and pharmacokinetic studies. Carbon 14 is often preferred to tritium since it allows better observation of the fate of carbonated structures. The fact that 14 CO 2 alone is used as basic material is the distinguishing feature of syntheses with isotopic carbon. In many cases the synthesis schemes of labelled drugs diverge considerably or entirely from those normally adopted for the unlabelled product. It is usually necessary to work on micro-quantities in order to maintain high specific activities, which implies the use of special synthesis techniques and of chromatographic separation and purification methods. Radiochemical purity tests are carried out by thin layer, column and gas phase chromatography, purity and identity checks by mass spectrometry and by 13 C and proton RMN. Labelled products are radiolysed by interaction of excited species with the molecules of the compound, a phenomenon much faster with tritiated than with 14 C-labelled molecules. The radiolysis rates may be reduced by molecule dilution. For ethical reasons it is not convenient to use 14 C molecules in human experiments, but molecular labelled with stable isotopes ( 13 C, 15 N, D) can serve instead [fr

NMR-based approach to the analysis of radiopharmaceuticals: radiochemical purity, specific activity, and radioactive concentration values by proton and tritium NMR spectroscopy.

Science.gov (United States)

Schenk, David J; Dormer, Peter G; Hesk, David; Pollack, Scott R; Lavey, Carolee Flader

2015-06-15

Compounds containing tritium are widely used across the drug discovery and development landscape. These materials are widely utilized because they can be efficiently synthesized and produced at high specific activity. Results from internally calibrated (3)H and (1)H nuclear magnetic resonance (NMR) spectroscopy suggests that at least in some cases, this calibrated approach could supplement or potentially replace radio-high-performance liquid chromatography for radiochemical purity, dilution and scintillation counting for the measurement of radioactivity per volume, and liquid chromatography/mass spectrometry analysis for the determination of specific activity. In summary, the NMR-derived values agreed with those from the standard approaches to within 1% to 9% for solution count and specific activity. Additionally, the NMR-derived values for radiochemical purity deviated by less than 5%. A benefit of this method is that these values may be calculated at the same time that (3)H NMR analysis provides the location and distribution of tritium atoms within the molecule. Presented and discussed here is the application of this method, advantages and disadvantages of the approach, and a rationale for utilizing internally calibrated (1)H and (3)H NMR spectroscopy for specific activity, radioactive concentration, and radiochemical purity whenever acquiring (3)H NMR for tritium location. Copyright © 2015 John Wiley & Sons, Ltd.

Comparison of the radiochemical separation procedures od plutonium applied for its determination in the environmental samples using alpha spectrometry

International Nuclear Information System (INIS)

Komosa, A.; Michalik, S.

2006-01-01

Alpha spectrometry of the plutonium isotopes can be performed only after the perfect plutonium separation from other components of the matrix. So, till now numerous procedures have been elaborated and tested. The communication presents comparison of the plutonium content determination in soil, bones, eggshells and in the reference materials obtained by alpha spectrometry combined with two different separation procedures. The samples were mineralized in the concentrated HCl or HF prior to plutonium electrodeposition or coprecipitation with NdF 3 . Some other details were also tested in various variants. Quality of the spectra is discussed in terms of all these pre-treatment methods

Radiochemical analysis of concrete samples for decommission of nuclear reactors

Energy Technology Data Exchange (ETDEWEB)

Zapata-Garcia, Daniel; Wershofen, Herbert [Physikalisch-Technische Bundesanstalt (PTB), Bundesallee 100 38116, Braunschweig (Germany); Larijani, Cyrus; Sobrino-Petrirena, Maitane; Garcia-Miranda, Maria; Jerome, Simon M. [National Physical Laboratory (NPL), Hampton Road, Teddington, Middlesex, TW11 0LW (United Kingdom)

2014-07-01

Decommissioning of the oldest nuclear power reactors are some of the most challenging technological legacy issues many countries will face in forthcoming years, as many power reactors reach the end of their design lives. Decommissioning of nuclear reactors generates large amounts of waste that need to be classified according to their radioactive content. Approximately 10 % of the contaminated material ends up in different repositories (depending on their level of contamination) while the rest is decontaminated, measured and released into the environment or sent for recycling. Such classification needs to be done accurately in order to ensure that both the personnel involved in decommissioning and the population at large are not needlessly exposed to radiation or radioactive material and to minimise the environmental impact of such work. However, too conservative classification strategies should not be applied, in order to make proper use of radioactive waste repositories since space is limited and the full process must be cost-effective. Implicit in decommissioning and classification of waste is the need to analyse large amounts of material which usually combine a complex matrix with a non-homogeneous distribution of the radionuclides. Because the costs involved are large, it is possible to make great savings by the adoption of best available practices, such as the use of validated methods for on-site measurements and simultaneous determination of more than one radionuclide whenever possible. The work we present deals with the development and the validation of a procedure for the simultaneous determination of {sup 241}Am, plutonium isotopes, uranium isotopes and {sup 90}Sr in concrete samples. Samples are firstly ground and fused with LiBO{sub 2} and Li{sub 2}B{sub 4}O{sub 7}. After dissolution of the fused sample, silicate and alkaline elements are removed followed by radiochemical separation of the target radionuclides using extraction chromatography. Measurement

Surface-Enhanced Separation of Water from Hydrocarbons: Potential Dewatering Membranes for the Catalytic Fast Pyrolysis of Pine Biomass

Energy Technology Data Exchange (ETDEWEB)

Engtrakul, Chaiwat; Hu, Michael Z.; Bischoff, Brian L.; Jang, Gyoung G.

2016-10-20

The impact of surface-selective coatings on water permeation through a membrane when exposed to catalytic fast pyrolysis (CFP) vapor products was studied by tailoring the surface properties of the membrane coating from superhydrophilic to superhydrophobic. Our approach used high-performance architectured surface-selective (HiPAS) membranes that were inserted after a CFP reactor. At this insertion point, the inner wall surface of a tubular membrane was exposed to a mixture of water and upgraded product vapors, including light gases and deoxygenated hydrocarbons. Under proper membrane operating conditions, a high selectivity for water over one-ring upgraded biomass pyrolysis hydrocarbons was observed as a result of a surface-enhanced capillary condensation process. Owing to this surface-enhanced effect, HiPAS membranes have the potential to enable high flux separations, suggesting that water can be selectively removed from the CFP product vapors.

Stationary and through-flow radiochemical detectors in cooperation with high performance liquid chromatography: Application in biochemistry

International Nuclear Information System (INIS)

Kehr, J.

1986-01-01

A review article is presented containing some original experimental data and discussing the usability of radiochemical detection of labelled compounds using high performance liquid chromatography. The stationary and through-flow types of detection are compared with respect to efficiency, chromatographic zone resolution, usability in biochemical research, and also to the current trends of development of liquid chromatography. (author). 3 figs., 1 tab., 19 refs

Determination of As, Cd, Cr, Cu, Hg, Sb and Se concentrations by radiochemical neutron activation analysis in different Brazilian regional diets

International Nuclear Information System (INIS)

Favaro, D.I.T.; Maihara, V.A.; Armelin, M.J.A.; Vasconcellos, M.B.A.; Cozzolino, S.M.

1994-01-01

Radiochemical separation procedures developed for the determination of seven elements: As, Cd, Cr, Cu, Hg, Sb and Se in different Brazilian regional diets are described. In the case of the elements As, Hg, Sb and Se, the procedure was based on retention in inorganic exchanger TFO (tin dioxide) and determination of Hg by extraction with Ni(DDC) 2 . For determination of Cd, Cr, Cu and Se the procedure chosen was based on retention in inorganic exchanger HMD (hydrated manganese dioxide) and extraction of Cu and Cd as diethyldithiocarbamate compounds. The accuracy and precision of the methods studied were tested by means of analyses of different reference materials-Due to the lack of data on trace element levels in Brazilian foodstuffs and diets, these methods were applied to determination of these elements in different Brazilian regional diets. These s were supplied by the Food and Experimental Nutrition Department of the Faculty of Pharmaceutical Science, University of Sao Paulo. The daily intake values for these diets are presented for As, Cd, Cr, Cu, Hg, Sb and Se. (author) 21 refs.; 6 tabs

Radiochemical techniques for determining some naturally occurring radionuclides in marine environmental materials

Energy Technology Data Exchange (ETDEWEB)

Baker, C W [Ministry of Agriculture, Fisheries and Food, Lowestoft (UK). Fisheries Lab.

1984-06-15

The determination of some of the naturally-occurring, alpha-emitting radionuclides in marine environmental materials, is of interest for several reasons. Radium and radon nuclides are potentially useful as oceanographic tracers. Lead and thorium nuclides may be used to study sedimentation rates, mixing processes and bioturbation in sediments. Radium and polonium nuclides are incorporated into food chains and the data may provide a perspective against which to assess the significance, for marine organisms, of exposure to radiation in a marine radioactive waste disposal situation. This paper discusses the manner in which samples are taken, and the radiochemical methods which have been employed to measure the nuclides, together with some data produced.

Computer aided design of piping for a radiochemical plant

Energy Technology Data Exchange (ETDEWEB)

Selvaraj, P G; Chandrasekhar, A; Chandrasekar, A V [Reprocessing Group, Indira Gandhi Centre for Atomic Research, Kalpakkam (India); Raju, R P; Mahudeeswaran, K V; Kumar, S V [Reprocessing Group, Bhabha Atomic Research Centre, Mumbai (India)

1994-06-01

In a radiochemical plant such as reprocessing plants, process equipment, storage tanks, liquid transfer systems and the associated pipe lines etc. are housed in series of concrete cells. Availability of limited cell space/volume, provision of various modes of liquid transfers with associated redundancies and instrumentation lines with standby alternatives increase the overall piping density. Designing such high density piping layout without interference is quite complex and needs lot of human efforts. This paper briefly describes development of computer codes for the entire scheme of design, drafting and fabrication of piping for nuclear fuel reprocessing plant. The general organisation of various programs, their functions, the complete sequence of the scheme and the flow of data are presented. High degree of reliability of each routine, considerable error checking facilities, marking legends on the drawings, provision for scaling in drafting and accuracy to the extent of one mm in layout design are some of the important features of this scheme. (author). 1 fig.

Handling of Ammonium Nitrate Mother-Liquid Radiochemical Production - 13089

International Nuclear Information System (INIS)

Zherebtsov, Alexander; Dvoeglazov, Konstantine; Volk, Vladimir; Zagumenov, Vladimir; Zverev, Dmitriy; Tinin, Vasiliy; Kozyrev, Anatoly; Shamin, Dladimir; Tvilenev, Konstantin

2013-01-01

The aim of the work is to develop a basic technology of decomposition of ammonium nitrate stock solutions produced in radiochemical enterprises engaged in the reprocessing of irradiated nuclear fuel and fabrication of fresh fuel. It was necessary to work out how to conduct a one-step thermal decomposition of ammonium nitrate, select and test the catalysts for this process and to prepare proposals for recycling condensation. Necessary accessories were added to a laboratory equipment installation decomposition of ammonium nitrate. It is tested several types of reducing agents and two types of catalyst to neutralize the nitrogen oxides. It is conducted testing of modes of the process to produce condensation, suitable for use in the conversion of a new technological scheme of production. It is studied the structure of the catalysts before and after their use in a laboratory setting. It is tested the selected catalyst in the optimal range for 48 hours of continuous operation. (authors)

Use of thin layer chromatography for the determination of radiochemical purity of radiopharmaceuticals in nuclear medicine services of Paraiba and Rio Grande do Norte, Brazil; Utilizacao da cromatografia em camada delgada para determinacao da pureza radioquimica de radiofarmacos em servicos de medicina nuclear da Paraiba e Rio Grande do Norte, Brasil

Energy Technology Data Exchange (ETDEWEB)

Andrade, W.G.; Santos, P.A.L.; Lima, F.R.A. [Universidade Federal de Pernambuco (UFPE), Recife, PE (Brazil). Programa de Pos-Graduacao em Tecnologia Energetica; Lima, F.F., E-mail: wellington.gandrade@gmail.com [Centro Regional de Ciencias Nucleares do Nordeste (CRCN-NE/CNEN-PE), Recife, PE (Brazil)

2012-07-01

The paper chromatography and the thin layer chromatography are separation techniques in which the radioactive components migrate because of their affinity with the eluent (mobile phase) or stationary phase, respectively. In radiopharmaceuticals labeled with {sup 99m}Tc, besides its own radiopharmaceutical, {sup 99m}TcO{sup 4-} free and TcO{sub 2} can be identified and quantified. The evaluation of radiochemical purity of radiopharmaceuticals is essential to produce images free of artifacts as well as avoid unnecessary absorbed dose to the patient. Once they are managed in humans it is important and necessary that they undergo to strict quality control. Because of this, ANVISA in its 'Resolucao da Diretoria Colegiada (RDC) 38 of June 4th, 2008 states the obligation of performing a minimum of tests in nuclear medicine services routine prior to human administration. This work evaluated, by the method of thin layer chromatography (TLC), radiochemical purity, determined the pH of the radiopharmaceutical DEXTRAN- 500, DMSA, DTPA, PHYTATE, MDP, MIBI and Sn-Col used in nuclear medicine services in the states of Paraiba and Rio Grande do Norte - Brazil. The results show that the use of thin layer chromatography (TLC) as a standard method in routine of nuclear medicine services is possible, because it provides important data for the evaluation of radiochemical purity, allowing the exclusion of a radiopharmaceutical poorly marked. (author)

Project Title: Radiochemical Analysis by High Sensitivity Dual-Optic Micro X-ray Fluorescence

International Nuclear Information System (INIS)

Havrilla, George J.; Gao, Ning

2002-01-01

A novel dual-optic micro X-ray fluorescence instrument will be developed to do radiochemical analysis of high-level radioactive wastes at DOE sites such as Savannah River Site and Hanford. This concept incorporates new X-ray optical elements such as monolithic polycapillaries and double bent crystals, which focus X-rays. The polycapillary optic can be used to focus X-rays emitted by the X-ray tube thereby increasing the X-ray flux on the sample over 1000 times. Polycapillaries will also be used to collect the X-rays from the excitation site and screen the radiation background from the radioactive species in the specimen. This dual-optic approach significantly reduces the background and increases the analyte signal thereby increasing the sensitivity of the analysis. A doubly bent crystal used as the focusing optic produces focused monochromatic X-ray excitation, which eliminates the bremsstrahlung background from the X-ray source. The coupling of the doubly bent crystal for monochromatic excitation with a polycapillary for signal collection can effectively eliminate the noise background and radiation background from the specimen. The integration of these X-ray optics increases the signal-to-noise and thereby increases the sensitivity of the analysis for low-level analytes. This work will address a key need for radiochemical analysis of high-level waste using a non-destructive, multi-element, and rapid method in a radiation environment. There is significant potential that this instrumentation could be capable of on-line analysis for process waste stream characterization at DOE sites

The radiochemical purity of technetium-99m-tin-diethylene-triamino-pentaacetic acid (DTPA) complex

International Nuclear Information System (INIS)

Besnard, M.; Costerousse, O.; Merlin, L.; Coehn, Y.

1975-01-01

The effect on radiochemical purity was studied as a function of the storage period of tin-DTPA solution and of the technetium-complex solution. The quantity of the pertechnetate ions present in the solution is determined by ascending paper chromatography, and an attempt was made to clarify the bond type of technetium by a spectrophotometric method. The tin-DTPA solutions for complexing of the reduced technetium are stable over a period of 8 weeks. The yield of the radiopharmaceutical product is better than 95%. (G.Gy.)

AUTOMATED PROCESS MONITORING: APPLYING PROVEN AUTOMATION TECHNIQUES TO INTERNATIONAL SAFEGUARDS NEEDS

International Nuclear Information System (INIS)

O'Hara, Matthew J.; Durst, Philip C.; Grate, Jay W.; Devol, Timothy A.; Egorov, Oleg; Clements, John P.

2008-01-01

Identification and quantification of specific alpha- and beta-emitting radionuclides in complex liquid matrices is highly challenging, and is typically accomplished through laborious wet chemical sample preparation and separations followed by analysis using a variety of detection methodologies (e.g., liquid scintillation, gas proportional counting, alpha energy analysis, mass spectrometry). Analytical results may take days or weeks to report. Chains of custody and sample security measures may also complicate or slow the analytical process. When an industrial process-scale plant requires the monitoring of specific radionuclides as an indication of the composition of its feed stream or of plant performance, radiochemical measurements must be fast, accurate, and reliable. Scientists at Pacific Northwest National Laboratory have assembled a fully automated prototype Process Monitor instrument capable of a variety of tasks: automated sampling directly from a feed stream, sample digestion/analyte redox adjustment, chemical separations, radiochemical detection and data analysis/reporting. The system is compact, its components are fluidically inter-linked, and analytical results could be immediately transmitted to on- or off-site locations. The development of a rapid radiochemical Process Monitor for 99Tc in Hanford tank waste processing streams, capable of performing several measurements per hour, will be discussed in detail. More recently, the automated platform was modified to perform measurements of 90Sr in Hanford tank waste stimulant. The system exemplifies how automation could be integrated into reprocessing facilities to support international nuclear safeguards needs

Radiochemical neutron activation analysis for trace elements evaluation of human milk

International Nuclear Information System (INIS)

Gill, K.P.; Zaidi, J.H.; Ahmad, S.

2003-01-01

The principal objective pursued in this study is to establish the base-line data on the status of elemental composition in human milk from Pakistani subjects of Rawalpindi/Islamabad area. Radiochemical neutron activation analysis (RNAA) methodology was developed and successfully employed to determine the concentration of 18 minor and trace elements (essential, toxic and nonessential) in human milk. This methodology has significantly improved the detection limits of most of these elements due to suppression of Compton background. The data provide the base-line values of these elements in human milk of low- and medium-income group subjects of the region. The results obtained show good compatibility with the data reported by the WHO on elemental composition of human milk from different geological regions. (orig.)

Development of robotic plasma radiochemical assays for positron emission tomography

International Nuclear Information System (INIS)

Alexoff, D.L.; Shea, C.; Fowler, J.S.; Gatley, S.J.; Schlyer, D.J.

1995-01-01

A commercial laboratory robot system (Zymate PyTechnology II Laboratory Automation System; Zymark Corporation, Hopkinton, MA) was interfaced to standard and custom laboratory equipment and programmed to perform rapid radiochemical analyses for quantitative PET studies. A Zymark XP robot arm was used to carry out the determination of unchanged (parent) radiotracer in plasma using only solid phase extraction methods. Robotic throughput for the assay of parent radiotracer in plasma is 4--6 samples/hour depending on the radiotracer. Robotic assays of parent compound in plasma were validated for the radiotracers [ 11 C]Benztropine, [ 11 C]cocaine, [ 11 C]clorgyline, [ 11 C]deprenyl, [ 11 C]methadone, [ 11 C]methylphenidate, [ 11 C]raclorpride, and [ 11 C]SR46349B. A simple robot-assisted methods development strategy has been implemented to facilitate the automation of plasma assays of new radiotracers

Rapid and accurate determination of radiochemical purity of sup(99m)Tc compounds

International Nuclear Information System (INIS)

Tamat, S.R.

1977-01-01

The wide spread use of sup(99m)Tc-labelled radiopharmaceuticals and limitation of the short half-life of the isotope, is associated with an urgent need for a rapid, simple but accurate method for determining the radiochemical purity of the compound. A short paper chromatographic (KK) or thin layer chromatographic (KLT) method using 95% methanol or 0.9% saline solution as solvents, has solved the problem. With these methods, the amount of free sup(99m)Tc pertechnetate in a compound, can be determined in only a few minutes. These methods compare satisfactorily with lengtheir procedures. (author)

Production of carrier-free 28Mg and 24Na by 50-180 MeV protons on Si, P, S, Cl, Ar and K. Excitation functions and chemical separation

International Nuclear Information System (INIS)

Lundqvist, H.; Malmborg, P.

1976-01-01

This work investigates the possible use of high energy proton bomardment of silicon, phosphorous, sulphur, chlorine, argon or potassium for production of carrier-free 28 Mg. A chemical separation is essential in this preparation in order to get rid of the bulk of target material and contaminating radionuclides. A simple and efficient method to get carrier-free 28 Mg with neglectible amounts of radio-chemical impurities has been established. (Auth.)

Development of radiochemical methods for the determination of radionuclides in water samples

International Nuclear Information System (INIS)

Vajda, N.; Molnar, Zs.; Bodizs, D.

2004-01-01

Depending on the composition of minerals, ores, soils and the properties of water various amounts of radionuclides of natural origin are released into different types of water i.e. surface and ground water, mineral and well water. Furthermore, man-made radionuclides can contaminate the surface waters in the form of fallout from nuclear incidents followed by migration of the deposited isotopes into water. Measurement of radionuclides in water helps prevent the consumption of radioactive water causing high radiation doses and also enables the early discovery of contamination sources. For the latter reason monitoring radioactivity in ground water in the vicinity of nuclear installations is of great importance. High sensitivity radiochemical methods have been developed/adopted for the simultaneous determination of 90 Sr-Pu nuclides, 137 Cs- 90 Sr-Pu nuclides in 50-100 L of water. Typically, procedures contain a pre-concentration step most likely by means of co-precipitation followed by a selective separation procedure preferably by means of extraction chromatography. In most cases Sr and Pu are extracted with a crown ether and an organic phosphonate compound, respectively, while Cs is concentrated using AMP. In the presence of extremely high salt content e.g. in case of 100 L of sea water the standard extraction chromatographic procedure has to be replaced by the conventional technique of Sr-Ca separation based on the different solubilities of the nitrate precipitates. Selection criteria as well as description of the procedures will be given in detail. A high sensitivity procedure has been developed for the analysis of 129 I in 100 L of ground water based on pre-concentration with AgCI and separation by extraction with CCl 4 . The following nuclear measuring techniques were applied: LSC, alpha spectrorhetry, gamma spectrometry, neutron activation (including gamma spectrometry) for 90 Sr, 239,240 Pu, 137 Cs, and 129 I, respectively. Sensitivities of the given methods

Simultaneous radiochemical determination of plutonium, strontium, uranium, and iron nuclides and application to atmospheric deposition and aerosol samples

Energy Technology Data Exchange (ETDEWEB)

Rosner, G.; Hoetzl, H.; Winkler, R. (Gesellschaft fuer Strahlen- und Umweltforschung mbH Muenchen, Neuherberg (Germany, F.R.). Inst. fuer Strahlenschutz)

1990-11-01

A procedure for the sequential radiochemical determination of plutonium, strontium, uranium and iron nuclides is described. The separation is carried out on a single anion exchange column. Pu(IV), U(VI) and Fe(III) are fixed on Bio Rad AG 1-X4 from 9 mol/l HCl, while the sample effluent is used for the determination of radiostrontium. Fe and U are eluted separately with 7 mol/l HNO{sub 3}, and Pu(III) is eluted with 1.2 mol/l HCl containing hydrogen peroxide. Subsequently, Pu and U are electrolysed and counted by alpha spectrometry. Radiostrontium is purified by the nitrate method and counted in a low level beta proportional counter. Fe is purified by extraction and cation exchange and {sup 55}Fe is counted by X-ray spectrometry with a Si(Li) detector. The sample preparation and the application of the procedure to large samples, namely aerosols from 10{sup 5} m{sup 3} of air, and monthly deposition samples from 0.6 m{sup 2} sampling area (10-100 l) are described. Chemical yields are for Pu 70 {plus minus} 20, for Sr 80 {plus minus} 15, for U 80-90, and for Fe 75 {plus minus} 10%. As an example, the maximum airborne radionuclide concentrations determined with that procedure in fortnightly collected samples at Neuherberg after the Chernobyl accident were: {sup 239+240}Pu, 2.58; {sup 238}Pu, 1.40; {sup 238}U, 0.65; {sup 234}U, 0.67; {sup 90}Sr, 7600; and {sup 55}Fe, 990 {mu}Bqm{sup -3}. With appropriate changes in sample preparation, the procedure is applicable to other kinds of samples. (orig.).

Monte Carlo analysis of thermochromatography as a fast separation method for nuclear forensics

International Nuclear Information System (INIS)

Garrison, J.R.; Hanson, D.E.; Hall, H.L.

2012-01-01

Nuclear forensic science has become increasingly important for global nuclear security, and enhancing the timeliness of forensic analysis has been established as an important objective in the field. New, faster techniques must be developed to meet this objective. Current approaches for the analysis of minor actinides, fission products, and fuel-specific materials require time-consuming chemical separation coupled with measurement through either nuclear counting or mass spectrometry. These very sensitive measurement techniques can be hindered by impurities or incomplete separation in even the most painstaking chemical separations. High-temperature gas-phase separation or thermochromatography has been used in the past for the rapid separations in the study of newly created elements and as a basis for chemical classification of that element. This work examines the potential for rapid separation of gaseous species to be applied in nuclear forensic investigations. Monte Carlo modeling has been used to evaluate the potential utility of the thermochromatographic separation method, albeit this assessment is necessarily limited due to the lack of available experimental data for validation. (author)

Monte Carlo analysis of thermochromatography as a fast separation method for nuclear forensics

International Nuclear Information System (INIS)

Hall, Howard L.

2012-01-01

Nuclear forensic science has become increasingly important for global nuclear security, and enhancing the timeliness of forensic analysis has been established as an important objective in the field. New, faster techniques must be developed to meet this objective. Current approaches for the analysis of minor actinides, fission products, and fuel-specific materials require time-consuming chemical separation coupled with measurement through either nuclear counting or mass spectrometry. These very sensitive measurement techniques can be hindered by impurities or incomplete separation in even the most painstaking chemical separations. High-temperature gas-phase separation or thermochromatography has been used in the past for the rapid separations in the study of newly created elements and as a basis for chemical classification of that element. This work examines the potential for rapid separation of gaseous species to be applied in nuclear forensic investigations. Monte Carlo modeling has been used to evaluate the potential utility of the thermochromatographic separation method, albeit this assessment is necessarily limited due to the lack of available experimental data for validation.

Ultra-purification of radiostrontium samples by ion chromatography

International Nuclear Information System (INIS)

Stadlbauer, E.A.; Trieu, C.; Hingmann, H.; Rohatzsch, H.; Maushart, R.

1988-01-01

Environmental radiostrontium analysis demands fast and effective radiochemical separation methods due to the lack of suitable gamma radiation. The procedure described consists in the preconcentration of radiostrontium by precipitation as SrCO 3 together with other alkaline earth metals. Next, strontium is separated from other constituents on a surface-sulfonated cation exchange resin HPIC-CS2. The chemical yields of strontium carrier as well as of radiostrontium were 80%. γ-spectrometry of the strontium eluate leveals less than 0.35 Bq Ra-226 as the remaining ultra trace contamination with a 3 σ error of about 80%. The method reported permits quantitative on-line detection of radiostrontium down to 5 Bq/l or 5 Bq/kg. (orig.)

Gas separation techniques in nuclear facilities

International Nuclear Information System (INIS)

Hioki, Hideaki; Morisue, Tetsuo; Ohno, Masayoshi

1983-01-01

The literatures concerning the gas separation techniques which are applied to the waste gases generated from nuclear power plants and nuclear fuel reprocessing plants, uranium enrichment and the instrumentation of nuclear facilities are reviewed. The gas permeability and gas separation performance of membranes are discussed in terms of rare gas separation. The investigation into the change of the gas permeability and mechanical properties of membranes with exposure to radiation is reported. The theoretical investigation of the separating cells used for the separation of rare gas and the development of various separating cells are described, and the theoretical and experimental investigations concerning rare gas separation using cascades are described. The application of membrane method to nuclear facilities is explained showing the examples of uranium enrichment, the treatment of waste gases from nuclear reactor buildings and nuclear fuel reprocessing plants, the monitoring of low level β-emitters in stacks, the detection of failed fuels and the detection of water leak in fast breeder reactors. (Yoshitake, I.)

Design of the Laboratory-Scale Plutonium Oxide Processing Unit in the Radiochemical Processing Laboratory

Energy Technology Data Exchange (ETDEWEB)

Lumetta, Gregg J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Meier, David E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Tingey, Joel M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Casella, Amanda J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Delegard, Calvin H. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Edwards, Matthew K. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Orton, Robert D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Rapko, Brian M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Smart, John E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2015-05-01

This report describes a design for a laboratory-scale capability to produce plutonium oxide (PuO₂) for use in identifying and validating nuclear forensics signatures associated with plutonium production, as well as for use as exercise and reference materials. This capability will be located in the Radiochemical Processing Laboratory at the Pacific Northwest National Laboratory. The key unit operations are described, including PuO₂ dissolution, purification of the Pu by ion exchange, precipitation, and re-conversion to PuO₂ by calcination.

Fast harmonic field mapper

International Nuclear Information System (INIS)

Au, R.; Fowler, M.; Hanawa, H.; Riedel, J.; Qua, Z.G.

1984-01-01

In early 1983 it was decided to mount coils on arms separated by 120 degrees and buck them out so that the third harmonic dphi/dt component would be cancelled and thus the first and second field harmonics could be very accurately measured. The original intention was to do as others had done, namely, use fast ADC's to read the voltages, and computer process the result to get the Fourier components. However, because of the 100 to 1 dynamic range of the fast ADC's and the likelihood that noise would be a problem, the authors decided to do things differently. Using a fast Fourier transform analyzer was considered, but this instrument is very expensive, so they decided to use a completely electronic analog approach: The authors decided to use active bandpass filters to render the harmonic components

Fast Timing for Collider Detectors

CERN Multimedia

CERN. Geneva

2017-01-01

Advancements in fast timing particle detectors have opened up new possibilities to design collider detectors that fully reconstruct and separate event vertices and individual particles in the time domain. The applications of these techniques are considered for the physics at HL-LHC.

The reliability of radiochemical and chemical trace analyses in environmental materials

International Nuclear Information System (INIS)

Heinonen, Jorma.

1977-12-01

After theoretically exploring the factors which influence the quality of analytical data as well as the means by which a sufficient quality can be assured and controlled, schemes of different kinds have been developed and applied in order to demonstrate the analytical quality assurance and control in practice. Methods have been developed for the determination of cesium, bromine and arsenic by neutron activation analysis at the natural ''background'' concentration level in environmental materials. The calibration of methods is described. The methods were also applied on practical routine analysis, the results of which are briefly reviewed. In the case of Ce the precision of a comprehensive calibration was found to vary between 5.2-9.2% as a relative standard deviation, which agrees well with the calculated statistical random error 5.7-8.7%. In the case of Br the method showed a reasonable precision, about 11% on the average, and accuracy. In employing the method to analyze died samples containing Br from 3 to 12 ppm a continuous control of precison was performed. The analysis of As demonstrates the many problems and difficulties associated with environmental analysis. In developing the final method four former intercomparison materials of IAEA were utilized in the calibration. The tests performed revealed a systematic error. In this case a scheme was developed for the continuous control of both precision and accuracy. The results of radiochemical analyses in environmental materials show a reliability somewhat better than that occuring in the determination of stable trace elements. According to a rough classification, 15% of the results of radiochemical analysis show excellent reliability, whereas 60% show a reliability adequate for certain purposes. The remaining 15% are excellent, 60% adequate for some purposes and 30% good-for-nothing. The reasons for often insufficient reliability of results are both organizational and technical. With reasonable effort and

Remote sampling of process fluids in radiochemical plants

International Nuclear Information System (INIS)

Sengar, P.B.; Bhattacharya, R.; Ozarde, P. D.; Rana, D.S.

1990-01-01

Sampling of process fluids, continuous or periodic, is an essential requirement in any chemical process plant, so as to keep a control on process variables. In a radiochemical plant the task of taking and conveying the samples is a very tricky affair. This is due to the fact that neither the vessels/equipment containing radioactive effluents can be approached for manual sampling nor sampled fluids can be handled directly. The problems become more accute with higher levels of radioactivity. As such, inovative systems have to be devised to obtain and handle the raioactive samples employing remote operations. The remote sampling system developed in this Division has some of the unique features such as taking only requisite amount of samples in microlitre range, practically maintenance free design, avoidence of excess radioactive fluids coming out of process systems, etc. The paper describes in detail the design of remote sampling system and compares the same with existing systems. The design efforts are towards simplicity in operation, obtaining homogenised representative samples and highly economical on man-rem expenditure. The performance of a prototype system has also been evaluated. (author). 3 refs

A rapid, simple method for obtaining radiochemically pure hepatic heme

International Nuclear Information System (INIS)

Bonkowski, H.L.; Bement, W.J.; Erny, R.

1978-01-01

Radioactively-labelled heme has usually been isolated from liver to which unlabelled carrier has been added by long, laborious techniques involving organic solvent extraction followed by crystallization. A simpler, rapid method is devised for obtaining radiochemically-pure heme synthesized in vivo in rat liver from delta-amino[4- 14 C]levulinate. This method, in which the heme is extracted into ethyl acetate/glacial acetic acid and in which porphyrins are removed from the heme-containing organic phase with HCl washes, does not require addition of carrier heme. The new method gives better heme recoveries than and heme specific activities identical to, those obtained using the crystallization method. In this new method heme must be synthesized from delta-amino[4- 14 C]levulinate; it is not satisfactory to use [2- 14 C]glycine substrate because non-heme counts are isolated in the heme fraction. (Auth.)

Radiochemical investigations on the solubility of molybdatophosphate in phosphate determination

International Nuclear Information System (INIS)

Noack, S.

1975-01-01

The solubility of various molybdatophosphates was determined under the conditions of a gravimetric phosphate determination by radiochemical means by labelling PO 4 3- with P-32. Starting with various conditions for phosphate determination via the molybdatophosphate of quinoline, 8-hydroxyquinoline, dimorpholino ethane, N,N,N',N'-tetrakis-β-hydroxypropyl ethylene diamine and N,N,N',N'-tetrakis-β-hydroxybutyl ethylene diamine, a general working rule was developed to determine the solubility. Taking the example of quinoline molybdatophosphates, a series of influencing factors - work, concentration and measuring parameters - were investigated in order to be able to limit the reliability region of the gravimetric phosphate determination. Depending on the conditions, the measured solubilities were between 10 -10 and 10 -6 Mol/l, the corresponding degrees of precipitation between 99.0 and 99.9999%. Apparent solubility products were calculated for the different molybdatophosphates using computer programmes especially developed for this purpose. (orig./RB) [de

Characterization of filter cartridges from the IEA-R1 reactor by radiochemical method

International Nuclear Information System (INIS)

Geraldo, Bianca; Vicente, Roberto; Ferreira, Robson J.; Goes, Marcos M.; Marumo, Julio T.

2015-01-01

The filter cartridges used in water purification system of research nuclear reactor IEA-R1 are considered radioactive wastes after their useful life. The characterization of these wastes is one of the stages of management, which aims to identify and quantify the radionuclides present, including those known as 'difficult to measure' (DTM) radionuclides. Establish a radiochemical analysis methodology for this type of waste is a difficult job, not only by the application of these techniques, but also by the amount of radionuclides that should be analyzed. In the waste produced in a nuclear reactor, the most important radionuclides are fission products, activation products and transuranic elements. Since these radionuclides emit gamma radiation not measurable in its decay process and consequently are difficult to measure, their concentrations can be estimated by indirect methods such as scale factors. This method is used to evaluate the DTM concentration, which is represented by alpha and beta nuclides using the correlation between them and the radionuclide key, a gamma emitter. The objective of this work is to describe a radiochemical analysis methodology for gamma emitter nuclides, present in the filter cartridges, evaluating the activity and concentrations by destructive assays. At the same time, two studies have been performed by non-destructive assays, the first one based on dose rates and the point kernel method to correlate the results and the second one based on calibration efficiency with Monte Carlo method. These studies belong to the radioactive waste characterization program that has been conducted at the Waste Management Laboratory of Nuclear and Energy Research Institute, IPEN-CNEN/SP. (author)

Characterization of filter cartridges from the IEA-R1 reactor by radiochemical method

Energy Technology Data Exchange (ETDEWEB)

Geraldo, Bianca; Vicente, Roberto; Ferreira, Robson J.; Goes, Marcos M.; Marumo, Julio T., E-mail: bgeraldo@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2015-07-01

The filter cartridges used in water purification system of research nuclear reactor IEA-R1 are considered radioactive wastes after their useful life. The characterization of these wastes is one of the stages of management, which aims to identify and quantify the radionuclides present, including those known as 'difficult to measure' (DTM) radionuclides. Establish a radiochemical analysis methodology for this type of waste is a difficult job, not only by the application of these techniques, but also by the amount of radionuclides that should be analyzed. In the waste produced in a nuclear reactor, the most important radionuclides are fission products, activation products and transuranic elements. Since these radionuclides emit gamma radiation not measurable in its decay process and consequently are difficult to measure, their concentrations can be estimated by indirect methods such as scale factors. This method is used to evaluate the DTM concentration, which is represented by alpha and beta nuclides using the correlation between them and the radionuclide key, a gamma emitter. The objective of this work is to describe a radiochemical analysis methodology for gamma emitter nuclides, present in the filter cartridges, evaluating the activity and concentrations by destructive assays. At the same time, two studies have been performed by non-destructive assays, the first one based on dose rates and the point kernel method to correlate the results and the second one based on calibration efficiency with Monte Carlo method. These studies belong to the radioactive waste characterization program that has been conducted at the Waste Management Laboratory of Nuclear and Energy Research Institute, IPEN-CNEN/SP. (author)

Cherenkov and scintillation light separation on the CheSS experiment

Science.gov (United States)

Caravaca, Javier; Land, Benjamin; Descamps, Freija; Orebi Gann, Gabriel D.

2016-09-01

Separation of the scintillation and Cherenkov light produced in liquid scintillators enables outstanding capabilities for future particle detectors, the most relevant being: particle directionality information in a low energy threshold detector and improved particle identification. The CheSS experiment uses an array of small, fast photomultipliers (PMTs) and state-of-the-art electronics to demonstrate the reconstruction of a Cherenkov ring in liquid scintillator using two techniques: based on the photon density and using the photon hit time information. A charged particle ionizing a scintillation medium produces a prompt Cherenkov cone and late isotropic scintillation light, typically delayed by several ns. The fast response of our PMTs and DAQ provides a precision well below the ns level, making possible the time separation. Furthermore, the usage of the new developed water-based liquid scintillators (WbLS) enhances the separation since it allows tuning of the Cherenkov/Scintillation ratio. Latest results on the separation for pure liquid scintillators and WbLS will be presented.

Feasibility test for production and separation of 103Pd

International Nuclear Information System (INIS)

Szuecs, Z.; Takacs, S.; Hunyadi, M.; Gacsi, Z.; Zeevaart, J.R.

2011-01-01

Complete text of publication follows. 103 Pd as a well-known Auger-emitter is commonly employed in brachytherapy, but the ultra-short range stopping of Auger-electrons can be more potentially exploited in applications of targeted radionuclide therapy in the future. The no-carrier-added production of 103 Pd is practically possible through charged particle induced reactions. However, separation techniques of 103 Pd from the target material (typically Rh), as well as its recovery by wet chemistry are expensive, and yields high amounts of radioactive waste. An alternative and more efficient procedure, called drydistillation method (DDM), is based on differences between the isothermal vapor pressures of the radionuclide element and the target element. In an appropriately selected temperature region the diffusion and out-gassing rates of radionuclides from the solid matrix of the target material are enhanced. Optimal irradiation parameters were determined in previous experiments at ATOMKI. Separation of 103 Pd was demonstrated at the Isotope Separator Laboratory with an evaporating-condensing system (Fig. 1). Figure 1. Evaporation-condensation system at the Isotope Separator Laboratory of ATOMKI. The irradiated Rh foil was kept above 1800?C in vacuum for several hours. The evaluation of γ-spectra of the Rh foil and the 103 Pd condensed on a low-temperature substrate (Fig. 2). The analysis resulted in a radiochemical yield of about 99.5% for 103 Pd and a radionuclidic purity of better than 99% with respect to the level of 101 Rh in the end product. Acknowledgement. The work was partly supported by the Hungarian TeT Bilateral Cooperation (OMFB- 00138/2009) and by the South African NRF (UID 68768).

A fast pointwise strategy for anisotropic wave-mode separation in TI media

KAUST Repository

Liu, Qiancheng

2017-08-17

The multi-component wavefield contains both compressional and shear waves. Separating wave-modes has many applications in seismic workflows. Conventionally, anisotropic wave-mode separation is implemented by either directly filtering in the wavenumber domain or nonstationary filtering in the space domain, which are computationally expensive. These methods could be categorized into the pseudo-derivative family and only work well within Finite Difference (FD) methods. In this paper, we establish a relationship between group-velocity direction and polarity direction and propose a method, which could go beyond modeling by FD. In particular, we are interested in performing wave-mode separation in a Spectral Element Method (SEM), which is widely used for seismic wave propagation on various scales. The separation is implemented pointwise, independent of its neighbor points, suitable for running in parallel. Moreover, no correction for amplitude and phase changes caused by the derivative operator is required. We have verified our scheme using numerical examples.

A fast pointwise strategy for anisotropic wave-mode separation in TI media

KAUST Repository

Liu, Qiancheng; Peter, Daniel; Lu, Yongming

2017-01-01

The multi-component wavefield contains both compressional and shear waves. Separating wave-modes has many applications in seismic workflows. Conventionally, anisotropic wave-mode separation is implemented by either directly filtering in the wavenumber domain or nonstationary filtering in the space domain, which are computationally expensive. These methods could be categorized into the pseudo-derivative family and only work well within Finite Difference (FD) methods. In this paper, we establish a relationship between group-velocity direction and polarity direction and propose a method, which could go beyond modeling by FD. In particular, we are interested in performing wave-mode separation in a Spectral Element Method (SEM), which is widely used for seismic wave propagation on various scales. The separation is implemented pointwise, independent of its neighbor points, suitable for running in parallel. Moreover, no correction for amplitude and phase changes caused by the derivative operator is required. We have verified our scheme using numerical examples.

Preparation, radiochemical analysis and biodistribution of 99mTc-dihydrobis(1-pyrazolyl)borate

International Nuclear Information System (INIS)

Owunwanne, A.; Abdel-Dayem, H.; Yacoub, T.

1987-01-01

Optimum preparation of 99m Tc-dihydrobis(1-pyrazolyl)borate ( 99m Tc-HBPz 2 ) was done by mixing 1.4 mg/ml HBPz 2 and 1.0 mg/ml of stanous PYP. Radiochemical analysis of the preparation using paper chromatography (PC), thin layer chromatography (TLC) and high performance liquid chromatography (HPLC) indicated a stable product with one major component. The labelling efficiency was approximately 90%. Animal biodistribution studies performed in mice showed that most of the injected radioactivity was confined to the liver, kidney, lungs, intestine and heart. The heart to blood ratio was small but persisted up to 3 hrs. after the injection. (orig.) [de

Separation of macro-quantities of actinide elements at Savannah River by high-pressure cation exchange

International Nuclear Information System (INIS)

Burney, G.A.

1980-01-01

Large-scale separation of actinides from fission products and from each other by pressurized cation exchange chromatography at Savannah River is reviewed. Several kilograms of 244 Cm have been separated, with each run containing as much as 150 g of 244 Cm. Dowex 50W-X8 (Dow Chemical Co.) cation resin, graded to 30-70 micron size range, is used, and separation is made by eluting with 0.05M diethylenetriamine pentaacetic acid (DTPA) at a pH of 3. The effluent from the column is continuously monitored by a BF 3 detector, a NaI detector, and a lithium-drifted germanium detector and gamma spectrometer to guide collection of product fractions. Operating the columns at 300 to 1000 psi pressure eliminates resin bed disruption caused by radiolytically produced gases, and operating at increased flow rates decreases the radiolytic degradation of the resin per unit of product processed. A portion of the hot canyon of a production radiochemical separation plant was converted from a remote crane-operated facility to a master-slave manipulator-operated facility for separation and purification of actinide elements by pressurized cation exchange. It also contains an evaporator, furnaces, a calorimeter, and several precipitators and associated tanks. Actinide processing from target dissolution to packaging of purified product is planned in this facility

Separation techniques for low-level determination of actinides in soil samples

Energy Technology Data Exchange (ETDEWEB)

Eikenberg, J. [Paul Scherrer Institute, Department Logistics for Radiation Safety and Security, CH-5232 Villigen (Switzerland)], E-mail: jost.eikenberg@psi.ch; Jaeggi, M.; Beer, H.; Ruethi, M.; Zumsteg, I. [Paul Scherrer Institute, Department Logistics for Radiation Safety and Security, CH-5232 Villigen (Switzerland)

2009-05-15

The separation methods for soil samples applied at PSI are based on extraction chromatography and ion exchange. After sample leaching, the actinides are pre-concentrated via precipitation using oxalic acid. Besides the classical separation methods applying the extraction chromatographic resins U/TEVA{sup TM} (for U, Th), TRU{sup TM} (Pu, Am), new methods were recently implemented to increase the radiochemical recovery of particularly trivalent Am and Cm. These methods do not require initial reduction of Pu(IV) to Pu(III) but stabilize Pu on the tetravalent oxidation state using a mixture of NaNO{sub 2}/H{sub 2}O{sub 2} in strong acidic medium. The Pu-fraction is then fixed along with Th onto Dowex AG 1-X2 anion exchanger resin. Th is eluted via complexation with 10 M HCl, Pu via reduction with HI. The fractions of Am+Cm and U are loaded onto DGA{sup TM} resin. This resin shows extraordinary high distribution coefficients (k'-values) exceeding 10{sup 4} (for Am) in strong nitric acid medium. The separation between U and Am is obtained quantitatively by decreasing the HNO{sub 3} concentration from 3 to 0.25 M (stripping of the U-fraction) while Am can be easily eluted thereafter using 0.25 M HCl as complexation compound.

Radiochemical and thermal studies of the cation-exchanged forms of synthetic zeolite Linde sieve A

Energy Technology Data Exchange (ETDEWEB)

Banerjee, S P [Saugar Univ. (India). Dept. of Chemistry

1976-02-01

The compositions of the cobalt and silver-exchanged forms of synthetic zeolite Sieve A have been determined by radiochemical and TGA studies and correspond to Co/sub 6/A.19.8H/sub 2/O and Ag/sub 12/..cap alpha... 20H/sub 2/O respectively (A=Al/sub 12/Si/sub 12/O/sub 48//sup 12/-). Heating of these zeolites inhibits their capacity for cation exchange and water absorption. No evidence of occluded NaAlO/sub 2/ has been found.

Development of a radiochemical sensor. Part I: Feasibility study

Energy Technology Data Exchange (ETDEWEB)

Tarancon, A. [Departament de Quimica Analitica, Facultat de Quimica, Universitat de Barcelona, C/ Marti Franques 1, 08028 Barcelona (Spain); Garcia, J.F. [Departament de Pintura, Facultat de Belles Arts, Universitat de Barcelona, C/ Pau Gargallo 4, 08028 Barcelona (Spain)]. E-mail: jfgarcia@apolo.qui.ub.es; Rauret, G. [Departament de Quimica Analitica, Facultat de Quimica, Universitat de Barcelona, C/ Marti Franques 1, 08028 Barcelona (Spain)

2005-05-04

The evolution of nuclear activities and criteria for radiation protection have led to a continuous increase in measures to monitor and control the environment and therefore in the number of determinations required for such purposes. Classical analytical procedures are time-consuming, labor-intense and generate a large amount of waste. The alternative use of sensors for such determinations has seen very limited development. The present study focuses on the evaluation of the behavior of a prototype radiochemical sensor for liquid effluents. The sensor is based on a receptor made of a plastic scintillator and is capable of continuous, on-time and accurate remote quantification of the activity of alpha, beta and beta-gamma emitters. Low-level active solutions of {sup 90}Sr/{sup 90}Y, {sup 238}Pu, {sup 134}Cs and {sup 60}Co in matrices of groundwater, seawater and drinking water were quantified with prediction errors lower than 10% in most cases. The study also yields information about light generation and transmission and transductor configuration that will be useful in the design of future versions of this sensor.

A general approach to the construction of 'very accurate' or 'definitive' methods by radiochemical NAA and the role of these methods in QA

International Nuclear Information System (INIS)

Dybczynski, R.

1998-01-01

Constant progress in instrumentation and methodology of inorganic trace analysis is not always paralleled by improvement in reliability of analytical results. Our approach to construction of 'very accurate' methods for the determination of selected trace elements in biological materials by RNAA is based on an assumption that: (i) The radionuclide in question should be selectively and quantitatively isolated from the irradiated sample by a suitable radiochemical scheme, optimized with respect to this particular radionuclide, yielding finally the analyte in the state of high radiochemical purity what assures interference-free measurement by gamma-ray spectrometry. (ii) The radiochemical scheme should be based on ion exchange and/or extraction column chromatography resulting in an easy automatic repetition of an elementary act of distribution of the analyte and accompanying radionuclides between stationary and mobile phases. (iii) The method should have some intrinsic mechanisms incorporated into the procedure preventing any possibility of making gross errors. Based on these general assumptions, several more specific rules for devising of 'very accurate' methods were formulated and applied when elaborating our methods for the determination of copper, cobalt, nickel, cadmium, molybdenum and uranium in biological materials. The significance of such methods for Quality Assurance is pointed out and illustrated by their use in the certification campaign of the new Polish biological CRMs based on tobacco

Which fast track elements predict early recovery after colon cancer surgery?

NARCIS (Netherlands)

Vlug, M. S.; Bartels, S. A. L.; Wind, J.; Ubbink, D. T.; Hollmann, M. W.; Bemelman, W. A.; Sprangers, Mirjam; Preckel, Benedikt; Bossuyt, Patrick; Gouma, Dirk; van Berge Henegouwen, Mark; Fuhring, Jan; Lenthe, Ineke Picard-van; Bakker, Chris; King-Kalimanis, Bellinda; Hofland, Jan; Dejong, Cornelis; van Dam, Ronald; Cuesta, Miguel; van der Peet, Donald; van Zalingen, Edith; Noordhuis, Astrid; de Jong, Dick; Engel, Alexander; Goei, T. Hauwy; de Stoppelaar, Erica; van den Dongen, Marjon; van Wagensveld, Bart; van Tets, Willem; van den Elsen, Maarten; Swart, Annemiek; Gerhards, Michael; de Wit, Laurens; Siepel, Muriel; Molly, Glaresa; Gasthuis, Onze Lieve Vrouwe; van Geloven, Anna; Juttmann, Jan; Clevers, Wilfred; Bieleman, Andrea; van der Zaag, Edwin; Coenen, Ludo; Bonekamp, Elly; Cense, Huib; van Abeelen, Jacobus; van Iterson-de Jong, Diana; Krombeen, Margriet

2012-01-01

Aim It is questioned whether all separate fast track elements are essential for enhanced postoperative recovery. We aimed to determine which baseline characteristics and which fast track elements are independent predictors of faster postoperative recovery in patients undergoing resection for colon

Optimization, validation and standardization of a method of measuring the radiochemical purity of 99mTc-HMDP in Necker hospital

International Nuclear Information System (INIS)

Dumont, A.; Izembart, M.; Barritault, L.

1997-01-01

By the end of 1996, the tests of the radiochemical purity (RCP) of preparation of HMDP- 99m Tc at Necker hospital were effected by means of 'Tech-Kit' technique which allowed making evident only one radiochemical impurity, the free TcO 4 - . So, the aim of this work has been the search for another technique able to detect also the reduced hydrolyzed 99m Tc, and then, to optimize, validate and standardize this new technique. Several methods have been tested and compared on different points (the chemical species identified, practical difficulties, duration, reproducibility) in order to chose 'the best' one, consisting in associating two TLC (migration time, 3 minutes): - TLC no.1, ITLC-SG/Methyl-ethyl-ketone; - TLC no.2, ITLC-SG/1M Sodium acetate. This method has been subsequently: - optimized, concerning the quantity of deposed sampling, way of deposit drying, migration range, reading protocol by radio-chromatograph; - validated, by verifying the migration of radiochemical impurities by means of controls and by evaluating its sensitivity; - standardized, by defining the interest zones for interpreting the radio-chromatograms, by evaluating the reproducibility and by calculating the 'normal values' of RCP percentages. This method has been adopted as routine and with current recoil (40 preparations) and our conditions of realizations, the extreme values of the percentages obtained for the impurity zones of interests, have been the following: - TcO 4 - zone, [0.39%-1.07%]; - hydrolyzed reduced Tc zone, [0.96%-5.09%]. By taking into account their distribution we calculated a minimum RCP value of 94% to accept the preparation (the RCP being defined as equal to 100% - % TcO 4 - % hydrolyzed reduced Tc)

Radiolabeling of thioguanine with 125I for diagnosis and therapy: in vitro and in vivo evaluation

International Nuclear Information System (INIS)

Amin, A.M.; Killa, H.M.; El-Aziz, H.A.

2010-01-01

Labeling was carried out by direct iodination of thioguanine (100 μg) with radioiodine in a fast single step at 60 deg C, to produce iodo-6-thioguanine ( 125 I-S6G). Chloramine-T (200 μg) was used as oxidizing agent to oxidize the iodide ion to the iodonium ion, at pH 7 and the reaction time was 30 min. A high radiochemical yield of 96.4% was obtained. The labeled compound was quantitatively separated and purified by means of high pressure liquid chromatography (HPLC) with a radiochemical purity greater than 98%, which facilitates its clinical use for human application. The biodistribution of 125 I-6-thioguanine was studied by injection of the tracer in both normal and tumor bearing mice. The uptake in ascetic fluid was 35.4 and 23.9% at 1 and 24 h post intravenous injection (h.p.i.), respectively, indicating the suitability of this labeled compound for use as a radiopharmaceutical agent. (author)

Trace element evaluation of different varieties of chewing gum by radiochemical neutron activation analysis

International Nuclear Information System (INIS)

Zaidi, J.H.; Arif, M.; Fatima, I.; Ahmad, S.; Qureshi, I.H.

2000-01-01

Extensive use of chewing gums, by children in particular, entails the evaluation of trace element contents in them. Radiochemical neutron activation analysis (RNAA) was successfully employed to determine the concentration of 35 trace elements (essential, toxic and nonessential) in eight different brands of chewing gum generally consumed in Rawalpindi/Islamabad area. Comparison of trace element data of our work with literature has been presented. None of the elements detected in the brands of chewing gum examined was found to be present at a level representing a substantial contribution to the total dietary intake of the element. (author)

Radiochemical method for evaluating the effect of antibiotics on Escherichia coli biofilms

International Nuclear Information System (INIS)

Dix, B.A.; Cohen, P.S.; Laux, D.C.; Cleeland, R.

1988-01-01

A simple radiochemical method for evaluating the action of antibiotics on Escherichia coli cells in biofilms is reported. After growth, biofilms of E. coli ATCC 25922 on disks of urinary catheter material were suspended in fresh medium containing or lacking an antibiotic, incubated for 4 h at 37 degrees C, and pulse-labeled with [ 3 H]leucine for 5 min. Radioactivity in trichloracetic acid-precipitable material in the biofilm and in the surrounding medium (planktonic E. coli) was then measured. Antibiotic-induced inhibition of incorporation of [ 3 H]leucine into the cells in the biofilm was far less pronounced than incorporation into planktonic cells and, furthermore, correlated well with loss in viable counts. The method is simple, inexpensive, and extremely timesaving

Application of radiochemical methods to investigate mercury in water-ecosystems

International Nuclear Information System (INIS)

Kraemer, H.J.

1975-01-01

Two topics have been picked out of the vast scope of possible questions on mercury ecology in this work: 1) Development for a method of enrichment of mercury from surface water and neutron activation analytical determination of the influence of dissolved Hg compounds on the water/fish part-process taking course in the water-ecosystem with the help of radiochemical tracer methods. The developed enrichment method, adsorbents on aniline sulphur resin basis, was applied to the activation analytical Hg determination in model solutions with a specified content as well as in water of the Rhine, where a Hg content of 1.1 +- 0.2 x 10 -3 ppm was determined. 2) The uptake (and yield) of Hg (NO 3 ) 2 and CH 3 HgCl from fish was traced using radioactive tracers Hg 197 and Hg 203. The measured accumulation and yield kinetics and observed influence due to additions enable the development of model to interpret the interaction between fish and dissolved Hg compounds. (RB) [de

SCAN- a maintenance-free flowrate meter with direct digital read-out for computerised control applications in radiochemical plants

Energy Technology Data Exchange (ETDEWEB)

Shah, B V; Siddiqui, I A; Theyyunni, T K [Process Engineering and Systems Division, Bhabha Atomic Research Centre, Mumbai (India)

1994-06-01

In radiochemical plants, the choice of flowrate sensor is subject to stringent requirements of fail-safe design and freedom from maintenance. The SCAN remote digital direct indicating flowrate meter described in this paper was developed to meet the requirements of flowrate and transmitting it to the control room, and to a computerised control system. SCAN is designed on the principle that flowrate through an orifice is a function of the head of liquid acting upon it. SCAN consists of a small chamber which receives the flow, and discharges it through an orifice located in bottom. The level of liquid in the pot represents the flowrate of the input stream. SCAN has been developed into an accurate, rugged and practical device by refinements in the design of internals, and by introducing a special end-section which makes the calibration insensitive to location. An important feature of SCAN is that it is passive, maintenance free, fail-safe device and contains no moving parts. There is no liquid hold up in the SCAN when idle, which is a desirable feature for the radiochemical plant environment. (author). 3 figs., 2 tabs.

Radiochemical studies, pre-clinical investigation and preliminary clinical evaluation of "1"7"0Tm-EDTMP prepared using in-house freeze-dried EDTMP kit

International Nuclear Information System (INIS)

Das, Tapas; Shinto, Ajit; Kamaleshwaran, Koramadai K.; Sarma, Haladhar D.; Mohammed, Sahiralam Khan; Mitra, Arpit; Lad, Sangita; Rajan, M.G.R.; Banerjee, Sharmila

2017-01-01

The objective of the present work is to formulate "1"7"0Tm-EDTMP using an in-house freeze-dried EDTMP kit and evaluate its potential as a bone pain palliation agent. Patient dose of "1"7"0Tm-EDTMP was prepared with high radiochemical purity using the lyophilized kit at room temperature within 15 min. Pre-clinical evaluation in normal Wistar rats revealed selective skeletal accumulation with extended retention. Preliminary clinical investigation in 8 patients with disseminated skeletal metastases exhibited selective uptake in the bone and retention therein for a long duration. - Highlights: • Formulation of patient dose of "1"7"0Tm-EDTMP using freeze-dried EDTMP kit. • Radiochemical studies and pre-clinical evaluation of the agent in animal model. • Clinical evaluation in eight cancer patients with disseminated skeletal metastases.

Radiochemical purity and in vitro stability of Tc-99m radiopharmaceuticals

International Nuclear Information System (INIS)

Vucina, J.

2001-01-01

The increased contents of long lived 99 Tc, oxygen and cupric ions could affect the labeling yield of eight radiopharmaceuticals. Oxygen and in leaser extend copper were found to affect the radiochemical purity of the preparations. In vitro stability of radiopharmaceuticals, examined on 99m Tc(Sn)-pyrosphoshate solutions, was extended when ascorbic acid was added as the chemical stabilizer. The quantity of 5x10 -7 mol/dm 3 of ascorbic acid was found to be sufficient to keep the content of 99m Tc-pertechnetate below 1 % six hours after labeling even in the cases when 99m Tc was present in high radioactive concentrations (740-814 GBq/dm 3 ). The results led to the development of the kits in which ascorbic or gentisic acid are the standards component in the kit composition (author)

Literature search, review, and compilation of data for chemical and radiochemical sensors: Task 1 report

International Nuclear Information System (INIS)

1993-01-01

During the next several decades, the US Department of Energy is expected to spend tens of billions of dollars in the characterization, cleanup, and monitoring of DOE's current and former installations that have various degrees of soil and groundwater contamination made up of both hazardous and mixed wastes. Each of these phases will require site surveys to determine type and quantity of hazardous and mixed wastes. It is generally recognized that these required survey and monitoring efforts cannot be performed using traditional chemistry methods based on laboratory evaluation of samples from the field. For that reason, a tremendous push during the past decade or so has been made on research and development of sensors. This report contains the results of an extensive literature search on sensors that are used or have applicability in environmental and waste management. While restricting the search to a relatively small part of the total chemistry spectrum, a sizable body of reference material is included. Results are presented in tabular form for general references obtained from data base searches, as narrative reviews of relevant chapters from proceedings, as book reviews, and as reviews of journal articles with particular relevance to the review. Four broad sensor types are covered: electrochemical processes, piezoelectric devices, fiber optics, and radiochemical processes. The topics of surface chemistry processes and biosensors are not treated separately because they often are an adjunct to one of the four sensors listed. About 1,000 tabular entries are listed, including selected journal articles, reviews of conference/meeting proceedings, and books. Literature to about mid-1992 is covered

Literature search, review, and compilation of data for chemical and radiochemical sensors: Task 1 report

Energy Technology Data Exchange (ETDEWEB)

NONE

1993-01-01

During the next several decades, the US Department of Energy is expected to spend tens of billions of dollars in the characterization, cleanup, and monitoring of DOE`s current and former installations that have various degrees of soil and groundwater contamination made up of both hazardous and mixed wastes. Each of these phases will require site surveys to determine type and quantity of hazardous and mixed wastes. It is generally recognized that these required survey and monitoring efforts cannot be performed using traditional chemistry methods based on laboratory evaluation of samples from the field. For that reason, a tremendous push during the past decade or so has been made on research and development of sensors. This report contains the results of an extensive literature search on sensors that are used or have applicability in environmental and waste management. While restricting the search to a relatively small part of the total chemistry spectrum, a sizable body of reference material is included. Results are presented in tabular form for general references obtained from data base searches, as narrative reviews of relevant chapters from proceedings, as book reviews, and as reviews of journal articles with particular relevance to the review. Four broad sensor types are covered: electrochemical processes, piezoelectric devices, fiber optics, and radiochemical processes. The topics of surface chemistry processes and biosensors are not treated separately because they often are an adjunct to one of the four sensors listed. About 1,000 tabular entries are listed, including selected journal articles, reviews of conference/meeting proceedings, and books. Literature to about mid-1992 is covered.

Conceptual Design for the Pilot-Scale Plutonium Oxide Processing Unit in the Radiochemical Processing Laboratory

Energy Technology Data Exchange (ETDEWEB)

Lumetta, Gregg J.; Meier, David E.; Tingey, Joel M.; Casella, Amanda J.; Delegard, Calvin H.; Edwards, Matthew K.; Jones, Susan A.; Rapko, Brian M.

2014-08-05

This report describes a conceptual design for a pilot-scale capability to produce plutonium oxide for use as exercise and reference materials, and for use in identifying and validating nuclear forensics signatures associated with plutonium production. This capability is referred to as the Pilot-scale Plutonium oxide Processing Unit (P3U), and it will be located in the Radiochemical Processing Laboratory at the Pacific Northwest National Laboratory. The key unit operations are described, including plutonium dioxide (PuO2) dissolution, purification of the Pu by ion exchange, precipitation, and conversion to oxide by calcination.

Application of a Fast Separation Method for Anti-diabetics in Pharmaceuticals Using Monolithic Column: Comparative Study With Silica Based C-18 Particle Packed Column.

Science.gov (United States)

Hemdan, A; Abdel-Aziz, Omar

2018-04-01

Run time is a predominant factor in HPLC for quality control laboratories especially if there is large number of samples have to be analyzed. Working at high flow rates cannot be attained with silica based particle packed column due to elevated backpressure issues. The use of monolithic column as an alternative to traditional C-18 column was tested for fast separation of pharmaceuticals, where the results were very competitive. The performance comparison of both columns was tested for separation of anti-diabetic combination containing Metformin, Pioglitazone and Glimepiride using Gliclazide as an internal standard. Working at high flow rates with less significant backpressure was obtained with the monolithic column where the run time was reduced from 6 min in traditional column to only 1 min in monolithic column with accepted resolution. The structure of the monolith contains many pores which can adapt the high flow rate of the mobile phase. Moreover, peak symmetry and equilibration time were more efficient with monolithic column.

Fast reactors and nonproliferation

International Nuclear Information System (INIS)

Orlov, V.V.

1997-01-01

1.Three aspects of nonproliferation relevant to nuclear power are: Pu buildup in NPP spent fuel cooling ponds (∼ 104 t in case of consumption of ∼ 107 t cheap uranium). Danger of illegal radiochemical extraction of Pu for weapons production; Pu extraction from NPP fuel at the plants available in nuclear countries, its burning along with weapon-grade Pu in NPP reactors or in special-purpose burners; increased hazard of nuclear weapons sprawl with breeders and closed fuel cycle technology spreading all over the world. 2.The latter is one of major obstacles to creation of large-scale nuclear power. 3.Nuclear power of the first stage using 235 U will be able to meet the demands of certain fuel-deficient countries and regions, replacing ∼ 5-10% of conventional fuels in the global consumption for a number of decades. 4.Fast reactors of the first generation and the currently employed fuel technology are far from exhausting their potential for solving economic problems and meeting the challenges of safety, radioactive waste and nonproliferation. Development of large-scale nuclear power will become an option accepted by society for solving energy problems in the following century, provided a breeder technology is elaborated and demonstrated in the next 15-20 years, which would comply with the totality of the following requirement: full internal Pu breeding deterministic elimination of severe accidents involving fuel damage and high radioactivity releases: fast runaway, loss of coolant, fires, steam and hydrogen explosions, etc.; reaching a balance between radioactive wastes disposed of and uranium mined in terms of radiation hazard; technology of closed fuel cycle preventing its use for Pu extraction and permitting physical protection from fuel thefts;economic competitiveness of nuclear power for most of countries and regions, i.e. primarily the cost of NPPs with fat reactors is to be below the cost of modern LWR plants, etc

Waste treatment at the Radiochemical Engineering Development Center

International Nuclear Information System (INIS)

Brunson, R.R.; Bond, W.D.; Chattin, F.R.; Collins, R.T.; Sullivan, G.R.; Wiles, R.H.

1997-01-01

At the Radiochemical Engineering Development Center (REDC) irradiated targets are processed for the recovery of valuable radioisotopes, principally transuranium nuclides. A system was recently installed for treating the various liquid alkaline waste streams for removal of excess radioactive contaminants at the REDC. Radionuclides that are removed will be stored as solids and thus the future discharge of radionuclides to liquid low level waste tank storage will be greatly reduced. The treatment system is of modular design and is installed in a hot cell (Cubicle 7) in Building 7920 at the REDC where preliminary testing is in progress. The module incorporates the following: (1) a resorcinol-formaldehyde resin column for Cs removal, (2) a cross flow filtration unit for removal of rare earths and actinides as hydroxide, and (3) a waste solidification unit. Process flowsheets for operation of the module, key features of the module design, and its computer-assisted control system are presented. Good operability of the cross flow filter system is mandatory to the successful treatment of REDC wastes. Results of tests to date on the operation of the filter in its slurry collection mode and its slurry washing mode are presented. These tests include the effects of entrained organic solvent in the waste stream feed to the filter

Direct Fast-Neutron Detection

International Nuclear Information System (INIS)

DC Stromswold; AJ Peurrung; RR Hansen; PL Reeder

2000-01-01

Direct fast-neutron detection is the detection of fast neutrons before they are moderated to thermal energy. We have investigated two approaches for using proton-recoil in plastic scintillators to detect fast neutrons and distinguish them from gamma-ray interactions. Both approaches use the difference in travel speed between neutrons and gamma rays as the basis for separating the types of events. In the first method, we examined the pulses generated during scattering in a plastic scintillator to see if they provide a means for distinguishing fast-neutron events from gamma-ray events. The slower speed of neutrons compared to gamma rays results in the production of broader pulses when neutrons scatter several times within a plastic scintillator. In contrast, gamma-ray interactions should produce narrow pulses, even if multiple scattering takes place, because the time between successive scattering is small. Experiments using a fast scintillator confirmed the presence of broader pulses from neutrons than from gamma rays. However, the difference in pulse widths between neutrons and gamma rays using the best commercially available scintillators was not sufficiently large to provide a practical means for distinguishing fast neutrons and gamma rays on a pulse-by-pulse basis. A faster scintillator is needed, and that scintillator might become available in the literature. Results of the pulse-width studies were presented in a previous report (peurrung et al. 1998), and they are only summarized here

Determination of 90Sr in environmental samples with resonance ionization spectroscopy in collinear geometry

International Nuclear Information System (INIS)

Zimmer, K.; Stenner, J.; Kluge, H.J.; Lantzsch, J.; Monz, L.; Otten, E.W.; Passler, G.; Schwalbach, R.; Schwarz, M.; Stevens, H.; Wendt, K.; Herrmann, G.; Niess, S.; Trautmann, N.; Walter, K.; Bushaw, B.A.

1994-01-01

A new, fast technique for trace analysis of the radioactive isotopes 89 Sr and 90 Sr in environmental samples has been developed. Conventional mass separation is combined with resonance ionization spectroscopy in collinear geometry, which provides high selectivity and sensitivity. In addition, a chemical separation procedure for sample preparation has been developed. The described technique was used to determine the 90 Sr content in ∼ 870 m 3 air samples collected near Munich during and shortly after the Chernobyl reactor accident in April 1986. The content of 90 Sr was measured to be 1.4 mBq per m 3 , corresponding to 1.6 x 10 9 atoms of 90 Sr per sample. This value is in good agreement with the results of radiochemical measurements. (orig.)

Actinide Separation Demonstration Facility, Tarapur

International Nuclear Information System (INIS)

Vishwaraj, I.

2017-01-01

Partitioning of minor actinide from high level waste could have a substantial impact in lowering the radio toxicity associated with high level waste as well as it will reduce the burden on geological repository. In Indian context, the partitioned minor actinide could be routed into the fast breeder reactor systems scheduled for commissioning in the near period. The technological breakthrough in solvent development has catalyzed the partitioning programme in India, leading to the setting up and hot commissioning of the Actinide Separation Demonstration Facility (ASDF) at BARC, Tarapur. The engineering scale Actinide Separation Demonstration Facility (ASDF) has been retrofitted in an available radiological hot cell situated adjacent to the Advanced Vitrification Facility (AVS). This location advantage ensures an uninterrupted supply of high-level waste and facilitates the vitrification of the high-level waste after separation of minor actinides

On the presence of fictitious solar neutrino flux variations in radiochemical experiments

International Nuclear Information System (INIS)

Vladimirskii, B.M.; Bruns, A.V.

2004-01-01

The currently available data on solar neutrino flux variation in radiochemical experiments and Cherenkov measurements have so far defied a simple interpretation. Some of the results concerning these variations are indicative of their relationship to processes on the solar surface. It may well be that a poorly understood, uncontrollable factor correlating with solar activity indices affects the neutrino flux measurements. This factor is assumed to modulate the detection efficiency on different detectors in different ways. To test this assumption, we have analyzed all available radiochemical measurements obtained with the Brookhaven (1970-1994, 108 runs), GALLEX (1991-1997, 65 runs), and SAGE (1989-2000, 80 runs) detectors for possible instability of the detection efficiency. We consider the heliophysical situation at the final stage of the run, the last 7-27 days, when the products of the neutrino reaction with the target material had already been accumulated. All of the main results obtained previously by other authors were found to be reproduced for chlorine-argon measurements. The neutrino flux anticorrelates with the sunspot numbers only for an odd solar cycle. A similar behavior is observed for the critical frequencies of the E-ionosphere. The neutrino flux probably correlates with the A p magnetic activity index only for an even solar cycle. The predominance of a certain sign of the radial interplanetary magnetic field (IMF) in the last 14 (or 7) days of the run has the strongest effect on the recorded neutrino flux. The effect changes sign when the polarity of the general solar magnetic field is reversed and is most pronounced for the shortest runs (less than 50 days). The dependence of the flux on IMF polarity completely disappears if the corresponding index is taken for the first rather than the last days of the run. The IMF effect on the recorded neutrino flux was also found for short runs in the gallium-germanium experiment, but this effect for a given

First- and second-chance proton emission in the interactions of fast neutrons with 92Mo

International Nuclear Information System (INIS)

Qaim, S.M.; Wolfle, R.; Strohmaier, B.

1989-01-01

Cross sections were measured radiochemically for the 92 Mo(n,p) 92 Nb m and 92 Mo(n,n'p +pn+d) 91 Nb m reactions over the neutron energy range of 9.0--10.6 MeV, and for the latter reaction also between 12.6 and 14.4 MeV. Use was made of high-resolution γ-ray and x-ray spectroscopy. Statistical-model calculations taking into account precompound effects were performed for fast neutron induced reactions on 92 Mo. The calculational results agree well with the experimental data on emitted proton spectra as well as on the excitation functions of various reaction channels. The second-chance proton emission is significant for incident neutron energies above 11 MeV; between 13 and 14 MeV it is comparable to the first-chance proton emission

Ionic Liquid-salt based aqueous biphasic system for quick separation of no-carrier-added 203Pb from proton irradiated natTl2CO3 target

International Nuclear Information System (INIS)

Choudhury, Dibyasree; Ghosh, Kaustab; Lahiri, Susanta; Sarkar, Kangkana; Naskar, Nabanita

2016-01-01

In the present study, no-carrier-added (NCA) 203 Pb was radiochemically separated from bulk Tl target applying the ABS composing of 4 M K 2 HPO 4 and 0.1 mL of different strengths of IL (bmim)Cl ranging from 40% to 80% (w/v). Bulk Tl was spiked with 200Tl (T 1/2 = 26.1 h). A separation condition was achieved with 70% IL concentration and with 10 min shaking and 10 min settling time, where ∼84% of NCA 203 Pb was extracted into the IL rich phase with ∼10% contamination from bulk Tl. Therefore, further studies, i.e. variation in shaking and settling time were carried out keeping the concentration of IL fixed at 70%

Multiparametric fat-water separation method for fast chemical-shift imaging guidance of thermal therapies.

Science.gov (United States)

Lin, Jonathan S; Hwang, Ken-Pin; Jackson, Edward F; Hazle, John D; Stafford, R Jason; Taylor, Brian A

2013-10-01

A k-means-based classification algorithm is investigated to assess suitability for rapidly separating and classifying fat/water spectral peaks from a fast chemical shift imaging technique for magnetic resonance temperature imaging. Algorithm testing is performed in simulated mathematical phantoms and agar gel phantoms containing mixed fat/water regions. Proton resonance frequencies (PRFs), apparent spin-spin relaxation (T2*) times, and T1-weighted (T1-W) amplitude values were calculated for each voxel using a single-peak autoregressive moving average (ARMA) signal model. These parameters were then used as criteria for k-means sorting, with the results used to determine PRF ranges of each chemical species cluster for further classification. To detect the presence of secondary chemical species, spectral parameters were recalculated when needed using a two-peak ARMA signal model during the subsequent classification steps. Mathematical phantom simulations involved the modulation of signal-to-noise ratios (SNR), maximum PRF shift (MPS) values, analysis window sizes, and frequency expansion factor sizes in order to characterize the algorithm performance across a variety of conditions. In agar, images were collected on a 1.5T clinical MR scanner using acquisition parameters close to simulation, and algorithm performance was assessed by comparing classification results to manually segmented maps of the fat/water regions. Performance was characterized quantitatively using the Dice Similarity Coefficient (DSC), sensitivity, and specificity. The simulated mathematical phantom experiments demonstrated good fat/water separation depending on conditions, specifically high SNR, moderate MPS value, small analysis window size, and low but nonzero frequency expansion factor size. Physical phantom results demonstrated good identification for both water (0.997 ± 0.001, 0.999 ± 0.001, and 0.986 ± 0.001 for DSC, sensitivity, and specificity, respectively) and fat (0.763 ± 0.006, 0

Status of national programmes on fast breeder reactors

International Nuclear Information System (INIS)

1989-07-01

The twenty-second Annual Meeting of the International Working Group on Fast Reactors took place in Vienna, 18-21 April 1989. Nineteen representatives from twelve Member States and International Organizations attended the Meeting. This publication is a collection of presentations in which the participants reported the status of their national programmes on fast breeder reactors. A separate abstract was prepared for each of the twelve papers from this collections. Refs, figs, tabs and 1 graph

Zirconium-titanium-phosphate nanoparticles. Triton X-100 based size modification, characterization and application in radiochemical separation

Energy Technology Data Exchange (ETDEWEB)

Chakraborty, R.; Sen, B.; Chattopadhyay, P. [Burdwan Univ. (India). Dept. of Chemistry

2014-07-01

Zirconium-titanium-phosphate nanoparticles (ZTP) of different sizes were synthesized using tritron X-100 (polyethylene glycol-p-isooctylphenyl ether) surfactant. The materials were characterized by FTIR and powdered X-ray diffraction (XRD). The structural and morphological details of the material were obtained by scanning electron microscopy (SEM) and transmission electron microscopy (TEM). The SEM study was followed by energy dispersive spectroscopic analysis (EDS) for elemental analysis of the sample. The important peaks of the XRD spectra were analyzed to determine the probable composition of the material. The particle sizes were determined by dynamic light scattering (DLS) method. Ion exchange capacity was measured for different metal ions with sizes of the ZTP nanoparticles and size-dependent ion exchange property of the material was investigated thoroughly. The nanomaterial of the smallest size of around 5 nm was employed to separate carrier-free {sup 137m}Ba from {sup 137}Cs in column chromatographic technique using 1.0 M HNO{sub 3} as eluting agent at pH = 5. (orig.)

Development of an advanced code system for fast-reactor transient analysis

International Nuclear Information System (INIS)

Konstantin Mikityuk; Sandro Pelloni; Paul Coddington

2005-01-01

FAST (Fast-spectrum Advanced Systems for power production and resource management) is a recently approved PSI activity in the area of fast spectrum core and safety analysis with emphasis on generic developments and Generation IV systems. In frames of the FAST project we will study both statics and transients core physics, reactor system behaviour and safety; related international experiments. The main current goal of the project is to develop unique analytical and code capability for core and safety analysis of critical (and sub-critical) fast spectrum systems with an initial emphasis on a gas cooled fast reactors. A structure of the code system is shown on Fig. 1. The main components of the FAST code system are 1) ERANOS code for preparation of basic x-sections and their partial derivatives; 2) PARCS transient nodal-method multi-group neutron diffusion code for simulation of spatial (3D) neutron kinetics in hexagonal and square geometries; 3) TRAC/AAA code for system thermal hydraulics; 4) FRED transient model for fuel thermal-mechanical behaviour; 5) PVM system as an interface between separate parts of the code system. The paper presents a structure of the code system (Fig. 1), organization of interfaces and data exchanges between main parts of the code system, examples of verification and application of separate codes and the system as a whole. (authors)

Labeling of vasoactive intestinal peptide (VIP) and VIP 10-28 fragment with radioiodine by direct method. Comparative study of the kinetics biodistribution and affinity for neuroendocrine tumor cells

International Nuclear Information System (INIS)

Colturato, Maria Tereza

2005-01-01

In the progress of the Nuclear Medicine, many protein based radiopharmaceuticals have been developed in the last years using antibodies and, more recently, biologically active natural peptides or similar synthetic peptides. In the search for agents with specificity for the target tissue in tumors detection, it was verified that small sequences of amino acids may interact with selective sites, with homogenous distribution, fast accumulation in tissues and fast blood clearance when compared to the antibodies. Among the peptides used in the diagnosis of tumors, Vasoactive Intestinal Peptide (VIP) has been studied. VIP labeled with iodine-123 is applied in the images of intestinal adenocarcinoma and endocrine tumors. The molecule of VIP contains two tyrosine residues, in the positions 10 and 22 that are, theoretically, equally susceptible to radioiodination for direct method. The objective of this work was to produce VIP labeled with radioiodine (iodine-123), in order to introduce to the brazilian medical class this radiopharmaceutical of interest for the diagnosis and recurrence of tumors that express specific receptors. In an unpublished way, the work studied the labeling and the kinetic distribution of the VIP fragment (VIP 10-28) and verified its potential as radiopharmaceutical applied in the identification of tumors that express VIP receptors. After the choice of the appropriated technique for labeling VIP and VIP 10-28 with radioiodine, using Ceremonial T as oxidant agent and sodium metabisulfite as reducing agent, the quality control procedures were accomplished (electrophoresis and high performance liquid chromatography, HPLC) for radiochemical purity determination as well as the separation of the radiochemical species obtained. Labeling and quality control procedures applied were efficient and accurate. [ 131 I]VIP and [ 131 l]VIP 10-28 were obtained with high radiochemical purity (> 95%). The purification studies to remove free radioiodine in the labeling

Methods for nuclear material control used in the basic production of a typical radiochemical plant

International Nuclear Information System (INIS)

Kositsyn, V.F.; Mukhortov, N.F.; Korovin, Yu.I.; Rudenko, V.S.; Petrov, A.M.

1999-01-01

Techniques for destructive and non-destructive assay of the component and isotopic composition of nuclear materials are described, namely gravimetric, titrimetric, coulometric, mass spectrometry, as well as those based on registration of neutron and γ radiations. Their metrologic characteristics are described. The techniques described are suggested to be used for nuclear material (NM) control and accounting purposes at the model radiochemical plant for processing irradiated fuel subassemblies from power reactors. The measurement control program is also described. This program is intended for the measurement quality assurance in the framework of NM control and accountancy system [ru

Current research work carried out at the 250 kW TRIGA Mark II reactor

International Nuclear Information System (INIS)

Dimic, V.; Kristof, E.; Rant, J.

1972-01-01

The main physics experiments accomplished during the last two years of the reactor operation include the cold neutron, fast neutron and n-gamma spectrometry, neutron radiography and in the radiochemical laboratory quite extensive program on neutron activation analysis is carried on the seed irradiation facilities in connection with the research contract with the IAEA were constructed. In additional, the connection of the reactor to the on-line computer CDC 1700 is finished. The task of this work is the monitoring and control of the reactor power level and other operating conditions. This paper deals briefly only with the cold neutron, fast neutron and n-gamma spectrometry. The other fields of activity at our reactor will be described more in detail in the separate papers presented in this section

1.9 μm superficially porous packing material with radially oriented pores and tailored pore size for ultra-fast separation of small molecules and biomolecules.

Science.gov (United States)

Min, Yi; Jiang, Bo; Wu, Ci; Xia, Simin; Zhang, Xiaodan; Liang, Zhen; Zhang, Lihua; Zhang, Yukui

2014-08-22

In this work, 1.9 μm reversed-phase packing materials with superficially porous structure were prepared to achieve the rapid and high efficient separation of peptides and proteins. The silica particles were synthesized via three steps, nonporous silica particle preparation by a modified seeded growth method, mesoporous shell formation by a one pot templated dissolution and redeposition strategy, and pore size expansion via acid-refluxing. By such a method, 1.9 μm superficially porous materials with 0.18 μm shell thickness and tailored pore diameter (10 nm, 15 nm) were obtained. After pore enlargement, the formerly dense arrays of mesoporous structure changed, the radially oriented pores dominated the superficially porous structure. The chromatographic performance of such particles was investigated after C18 derivatization. For packing materials with 1.9 μm diameter and 10 nm pore size, the column efficiency could reach 211,300 plates per m for naphthalene. To achieve the high resolution separation of peptides and proteins, particles with pore diameter of 15 nm were tailored, by which the baseline separation of 5 peptides and 5 intact proteins could be respectively achieved within 1 min, demonstrating the superiority in the high efficiency and high throughput analysis of biomolecules. Furthermore, BSA digests were well separated with peak capacity of 120 in 30 min on a 15 cm-long column. Finally, we compared our columns with a 1.7 μm Kinetex C18 column under the same conditions, our particles with 10nm pore size demonstrated similar performance for separation of the large intact proteins. Moreover, the particles with 15 nm pore size showed more symmetrical peaks for the separation of large proteins (BSA, OVA and IgG) and provided rapid separation of protein extracts from Escherichia coli in 5 min. All these results indicated that the synthesized 1.9 μm superficially porous silica packing materials would be promising in the ultra-fast and high

Extraction chromatographic separation of Sr, Pu and Am in environmental samples

Energy Technology Data Exchange (ETDEWEB)

Sidhu, Rajdeep

2004-04-01

An accurate determination of radionuclides from various sources in the environment is essential for assessment of the potential hazards and suitable countermeasures both in case of an authorised release, accidents and routine surveillance. Due to the short range of alpha and beta radiation, the accurate determination of pure alpha and beta emitters must always include radiochemical separations to separate the analytes from the matrix and from other interfering stable and radioactive nuclides. Hence, the procedures used for their determination are usually tedious and involve several preconcentration and separation steps. This work deals with the determination of {sup 90}Sr, {sup 241}Am, {sup 238}Pu, {sup 239,240}Pu and {sup 244}Cm, whic some of the most important artificial radionuclides. Due to either absence or low yield of gamma radiation, a secure determination of low concentrations of all these nuclides requires a dedicated chemistry. Selective extraction chromatographic resins (TRU- and Sr-Resin) have been utilised to develop new procedures for the analyses of Pu, Am and Cm isotopes in seawater and both these and {sup 90}Sr in soil, sediment, urine and low-level liquid radioactive effluents. The proposed method for the analyses of Pu and Am in seawater offers a quick and secure mode for the determination of these radionuclides in marine waters. Combined pre-concentration of actinides and strontium (oxalate or phosphate precipitation) followed by dual column separation on TRU- and Sr-Resin significantly reduces the through put time and costs compared to traditional ion exchange and precipitation methods. The greatest gain in productivity and environmental friendliness is achieved in Sr separations using Sr-Resin instead of precipitations involving fuming nitric acid and oxalate, hydroxide, chromate and carbonate precipitations. (author)

On different experimental behaviour of fast secondary particles produced in 12C interactions at relativistic energies as studied with radiochemistry and in a propane chamber

International Nuclear Information System (INIS)

Kulakov, B.A.; Karachuk, J.; Gelovani, L.K.; Gridnev, T.G.; Sosnin, A.N.; Brandt, R.

1998-01-01

Energetic secondary fragments produced in the interaction of (41-44) GeV 12 C ions with copper exhibit experimentally a broader angular distribution as compared to energetic secondary fragments produced in the interactions at a lower 12 C-energy (15-25) GeV when studied with radiochemical techniques. Such a different experimental behaviour of secondary fragments produced by 12 C ions of the same two energy groups is not observed, when these secondary fragments are investigated with a propane bubble chamber. Separation of secondary particles is described

Determination of radiochemical yields of 186Re-labelled complexes using thin layer chromatography

International Nuclear Information System (INIS)

Konirova, R.; Kohlickova, M.; Jedinakova-Krizova, V.

1999-01-01

The reaction conditions for synthesis of three rhenium complexes 186 Re-methylendiphosphonate (MDP), 186 Re-hydroxyethylidendiphosphonate (HEDP) and 186 Re-citrate have been investigated. Radiochemical yield of complexation has been determined by thin layer chromatography and paper chromatography. The rhenium complexation with corresponding ligand is dependent on pH values of reaction mixture, concentration of studied ligand (MDP, HEDP and sodium citrate) and concentration of reducing agent. Stannous chloride with ascorbic acid (as antioxidant) was used for reduction of perrhenate. The labeling yield of 186 Re-MDP was about 90 %, of 186 Re-HEDP more than 80 % and more than 75 % for 186 Re-citrate under optimum conditions. Besides, the possibility of application of porphyrins as organic ligands for complexation with rhenium isotopes is examined. (authors)

Radiochemical determination of Inertial Confinement Fusion capsule compression at the National Ignition Facility

Energy Technology Data Exchange (ETDEWEB)

Shaughnessy, D. A., E-mail: shaughnessy2@llnl.gov; Moody, K. J.; Gharibyan, N.; Grant, P. M.; Gostic, J. M.; Torretto, P. C.; Wooddy, P. T.; Bandong, B. B.; Cerjan, C. J.; Hagmann, C. A.; Caggiano, J. A.; Yeamans, C. B.; Bernstein, L. A.; Schneider, D. H. G.; Henry, E. A.; Fortner, R. J. [Lawrence Livermore National Laboratory, 7000 East Avenue, Livermore, California 94551 (United States); Despotopulos, J. D. [Lawrence Livermore National Laboratory, 7000 East Avenue, Livermore, California 94551 (United States); Radiochemistry Program, University of Nevada Las Vegas, Las Vegas, Nevada 89154 (United States)

2014-06-15

We describe a radiochemical measurement of the ratio of isotope concentrations produced in a gold hohlraum surrounding an Inertial Confinement Fusion capsule at the National Ignition Facility (NIF). We relate the ratio of the concentrations of (n,γ) and (n,2n) products in the gold hohlraum matrix to the down-scatter of neutrons in the compressed fuel and, consequently, to the fuel's areal density. The observed ratio of the concentrations of {sup 198m+g}Au and {sup 196g}Au is a performance signature of ablator areal density and the fuel assembly confinement time. We identify the measurement of nuclear cross sections of astrophysical importance as a potential application of the neutrons generated at the NIF.

Limits of the radiochemical and geochemical method for the test of nucleon stability

Energy Technology Data Exchange (ETDEWEB)

Bergamasco, L [CNR, Laboratorio di Cosmo-Geofisica, Turin, Italy; Texas A and M University, College Station, Tex.); Cini, G [CNR, Laboratorio di Cosmo-Geofisica; Torino, Universita, Turin, Italy)

1978-07-01

An estimate is obtained for the limiting nucleon lifetime that can be determined by the radiochemical method of Steinberg and Evans (1977), which counts the Ar-37 production from reactions due to nucleon decay in a large sample of KC2H3O2. To estimate the background rate, processes due to the atmospheric muon component are considered. It is found that the asymptotic limit on the maximum value of the nucleon lifetime is 2 x 10/sup 30/years. This value cannot be increased by going to larger depths or by using a larger sample, but is inherent in the method itself. To improve the limit one would have to resort to methods based on multiparticle decay modes.

Determination of trace elements in bottled water in Greece by instrumental and radiochemical neutron activation analyses

International Nuclear Information System (INIS)

Soupioni, M.J.; Symeopoulos, B.D.; Papaefthymiou, H.V.

2006-01-01

Four different bottled water brands sold in Greece in the winter of 2001-2002 were analyzed for a wide range of chemical elements, using neutron activation analysis (NAA). The elements Na and Br were determined instrumentally (INAA), whereas the other metals and trace elements radiochemically (RNAA). The results indicated that the mean level of all the elements determined in the samples were well within the European Union (EU) directive on drinking water and accomplish the drinking water standards of the World Health Organisation (WHO) as well as of the Food and Drug Administration (FDA). (author)

The effect of lunar soil, metal oxides on thermal and radio-chemical stability of amino acids

International Nuclear Information System (INIS)

Khenokh, M.A.; Lapinskaya, E.M.

1983-01-01

Data on study of the effect of lunar soil and some metal oxides characteristic both for land and sea basaltS of lunar sojls on thermal and radio-chemical stability of amino acids are presented. The data obtained permit to suppose that extremely small quantity of amino acids discovered in lunar soil is conditioned by their decomposition under combined effect of different types of radiation, solar wind and sharp change of temperature. Probably, the effect of soil on photochemical activity of UV-radiation of the Sun and solid-phase radiolysis is not practically observed

Determination of 63Ni and 55Fe in nuclear waste samples using radiochemical separation and liquid scintillation counting

DEFF Research Database (Denmark)

Hou, Xiaolin; Frøsig Østergaard, L.; Nielsen, S.P.

2005-01-01

An analytical method for the determination of Ni-63 and Fe-55 in nuclear waste samples such as graphite, heavy concrete, aluminium and lead was developed. Different decomposition methods (i.e. ashing, acid digestion and alkali fusion) were investigated for the decomposition of the samples...... by extraction chromatography. The purified Ni-63 and Fe-55 was then measured by liquid scintillation counting. The chemical yields of the separation procedures for Fe-55 and Ni-63 are above 90% and the decontamination factors for all interfering radionuclides are more than 10(5). The detection limits...

Centrifugal separation for miscible solutions: Fundamentals and applications to separation of molten salt nuclear material

International Nuclear Information System (INIS)

Li Ning; Camassa, Roberto; Ecke, Robert E.; Venneri, Francesco

1995-01-01

We report on the physical separation of dilute solutions using centrifugal techniques. We use numerical simulations of the diffusion and sedimentation dynamics of centrifugation to model the approach to an equilibrium concentration profile. We verify experimentally the equilibrium profiles for aqueous solutions of different salts under rotation at 25000 rpm corresponding to centrifugal accelerations of about 57,000 g and 75,000 g in two different commercial centrifuges. These measurements provide ratios of sedimentation and diffusion coefficients. We show experimental results for the dynamics of separation that confirm the predictions of the theoretical model. We also measure the mass diffusion coefficient for several solutions. Although the relaxation to equilibrium is long, we have determined a method for efficiently extracting enriched components from a ternary mixture based on fast dynamics at early times. These dynamics are modeled in numerical simulations with realistic fluid parameters. Based on these studies we show that a multistage centrifugal separation process could provide efficient physical separation of actinides and fission products from a molten-salt solution in proposed transmutation/energy-production systems. We consider technical issues in the design of such a separation system

Centrifugal separation for miscible solutions: Fundamentals and applications to separation of molten salt nuclear material

International Nuclear Information System (INIS)

Ning Li; Camassa, R.; Ecke, R.E.

1995-01-01

The authors report on the physical separation of dilute solutions using centrifugal techniques. They use numerical simulations of the diffusion and sedimentation dynamics of centrifugation to model the approach to an equilibrium concentration profile. They verify experimentally the equilibrium profiles for aqueous solutions of different salts under rotation at 25000 rpm corresponding to centrifugal accelerations of about 57,000 g and 75,000 g in two different commercial centrifuges. These measurements provide ratios of sedimentation and diffusion coefficients. The authors show experimental results for the dynamics of separation that confirm the predictions of the theoretical model. They also measure the mass diffusion coefficient for several solutions. Although the relaxation to equilibrium is long, they have determined a method for efficiently extracting enriched components from a ternary mixture based on fast dynamics at early times. These dynamics are modeled in numerical simulations with realistic fluid parameters. Based on these studies the authors show that a multistage centrifugal separation process could provide efficient physical separation of actinides and fission products from a molten-salt solution in proposed transmutation/energy-production systems. The authors consider technical issues in the design of such a separation system

Centrifugal separation for miscible solutions: Fundamentals and applications to separation of molten salt nuclear material

Energy Technology Data Exchange (ETDEWEB)

Ning Li; Camassa, R.; Ecke, R.E. [Los Alamos National Laboratory, NM (United States)] [and others

1995-10-01

The authors report on the physical separation of dilute solutions using centrifugal techniques. They use numerical simulations of the diffusion and sedimentation dynamics of centrifugation to model the approach to an equilibrium concentration profile. They verify experimentally the equilibrium profiles for aqueous solutions of different salts under rotation at 25000 rpm corresponding to centrifugal accelerations of about 57,000 g and 75,000 g in two different commercial centrifuges. These measurements provide ratios of sedimentation and diffusion coefficients. The authors show experimental results for the dynamics of separation that confirm the predictions of the theoretical model. They also measure the mass diffusion coefficient for several solutions. Although the relaxation to equilibrium is long, they have determined a method for efficiently extracting enriched components from a ternary mixture based on fast dynamics at early times. These dynamics are modeled in numerical simulations with realistic fluid parameters. Based on these studies the authors show that a multistage centrifugal separation process could provide efficient physical separation of actinides and fission products from a molten-salt solution in proposed transmutation/energy-production systems. The authors consider technical issues in the design of such a separation system.

Metrological aspects of radiochemical methods for determining activity of gamma-emitting nuclides

International Nuclear Information System (INIS)

Shcherbakov, B.Y.

1986-01-01

The author considers the problem of metrological compatibility of the two stages in the radiochemical method of determining the activity of a gamma-emitting nuclide: chemical isolation of the nuclide and radiometric measurement of its activity. The authors show that preparation of the specimen in liquid form provides for important advantages compared with the traditional application of the solid residue onto a flat substate. The work here is of interest for analytical chemists who are involved with determination of the activity of gamma emitting nuclides such as Ru 103, Rh 106, Sn 113, Cs 134, Cs 137, La 140, Ce 141, Ce 144, Hg 203, Na 24, Mn 54, Fe 59, Co 60, Zn 65, Zr 95, and Nb 95, for example, in waste water or in emissions to the atmosphere, with the goal of protecting the environment

The Risk of Growing Fast: Does fast growth have a negative impact on the survival rates of firms?

NARCIS (Netherlands)

Zhou, Haibo; van der Zwan, Peter; de Kok, Jan; Hartog, Chantal

2012-01-01

Fast-growing firms are considered as the central drivers of job creation in the economy. There is an abundance of literature on the separate subjects of firm growth and firm survival. However, the relationship between survival and growth is neglected. Using the Dutch Longitudinal Enterprise Database

Highly accurate and fast optical penetration-based silkworm gender separation system

Science.gov (United States)

Kamtongdee, Chakkrit; Sumriddetchkajorn, Sarun; Chanhorm, Sataporn

2015-07-01

Based on our research work in the last five years, this paper highlights our innovative optical sensing system that can identify and separate silkworm gender highly suitable for sericulture industry. The key idea relies on our proposed optical penetration concepts and once combined with simple image processing operations leads to high accuracy in identifying of silkworm gender. Inside the system, there are electronic and mechanical parts that assist in controlling the overall system operation, processing the optical signal, and separating the female from male silkworm pupae. With current system performance, we achieve a very highly accurate more than 95% in identifying gender of silkworm pupae with an average system operational speed of 30 silkworm pupae/minute. Three of our systems are already in operation at Thailand's Queen Sirikit Sericulture Centers.

The dissolver paradox as a coupled fast-thermal reactor

International Nuclear Information System (INIS)

Lutz, H.F.; Webb, P.S.

1993-05-01

The dissolver paradox is treated as coupled fast-thermal reactors. Each reactor is sub-critical but the coupling is sufficient to form a critical system. The practical importance of the system occurs when the fast system by itself is mass limited and the thermal system by itself is volume limited. Numerous 1D calculations have been made to calculate the neutron multiplication parameters of the separate fast and thermal systems that occur in the dissolver paradox. A model has been developed to describe the coupling between the systems. Monte Carlo calculations using the MCNP code have tested the model

Elementary computation of radiation doses and shieldings for radiochemical laboratories; Calculo Elemental de dosis y blindajes para laboratorios radioquimicos

Energy Technology Data Exchange (ETDEWEB)

Jimeno de Osso, F

1971-07-01

Simple procedures for the calculation of radiation exposition, half thickness, shield thickness, etc. are described and equations and graphs are included for those gamma-emitting radionuclides, that are more often used in radiochemical laboratories. Application is made of these procedures to three radionuclides, bromine-82, sodium-24 and cobalt-60 which cover a rather wl.de energy range; theoretical results are compared with those obtained from experimental measurements. (Author) 23 refs.

FAST - A multiprocessed environment for visualization of computational fluid dynamics

International Nuclear Information System (INIS)

Bancroft, G.V.; Merritt, F.J.; Plessel, T.C.; Kelaita, P.G.; Mccabe, R.K.

1991-01-01

The paper presents the Flow Analysis Software Toolset (FAST) to be used for fluid-mechanics analysis. The design criteria for FAST including the minimization of the data path in the computational fluid-dynamics (CFD) process, consistent user interface, extensible software architecture, modularization, and the isolation of three-dimensional tasks from the application programmer are outlined. Each separate process communicates through the FAST Hub, while other modules such as FAST Central, NAS file input, CFD calculator, surface extractor and renderer, titler, tracer, and isolev might work together to generate the scene. An interprocess communication package making it possible for FAST to operate as a modular environment where resources could be shared among different machines as well as a single host is discussed. 20 refs

Radiochemical and chemical constituents in water from selected wells and springs from the southern boundary of the Idaho National Laboratory to the Hagerman Area, Idaho, 2003

Science.gov (United States)

Rattray, Gordon W.; Wehnke, Amy J.; Hall, L. Flint; Campbell, Linford J.

2005-01-01

The U.S. Geological Survey and the Idaho Department of Water Resources, in cooperation with the U.S. Department of Energy, sampled water from 14 sites as part of an ongoing study to monitor the water quality of the eastern Snake River Plain aquifer between the southern boundary of the Idaho National Laboratory (INL) and the Burley-Twin Falls-Hagerman area. The State of Idaho, Department of Environmental Quality, Division of INL Oversight and Radiation Control cosampled with the U.S. Geological Survey and the Idaho Department of Water Resources and their analytical results are included in this report. The samples were collected from four domestic wells, two dairy wells, two springs, four irrigation wells, one observation well, and one stock well and analyzed for selected radiochemical and chemical constituents. Two quality-assurance samples, sequential replicates, also were collected and analyzed. None of the concentrations of radiochemical or organic-chemical constituents exceeded the maximum contaminant levels for drinking water established by the U.S. Environmental Protection Agency. However, the concentration of one inorganic-chemical constituent, nitrate (as nitrogen), in water from site MV-43 was 20 milligrams per liter which exceeded the maximum contaminant level for that constituent. Of the radiochemical and chemical concentrations analyzed for in the replicate-sample pairs, 267 of the 270 pairs (with 95 percent confidence) were statistically equivalent.

A study of some neutron-rich isotopes of lanthanum, cerium and praseodymium by means of fast chemical on-line separation technique SISAK

International Nuclear Information System (INIS)

Skarnemark, G.

1977-01-01

The fast on-line chemical separation technique SISAK has been utilized to study the decay properties of neutron-rich isotopes of La, Ce and Pr. The results include partial decay schemes and γ-ray intensity data for 14 min 143 La, 42 s 144 La, 25 s 145 La, 9 s 146 La, 3 min 145 Ce, 14 min 146 Ce, 56 s 147 Ce, 50 s 148 Ce, 12 min 147 Pr, 2 min 148 Pr, 3 min 149 Pr and 6 s 150 Pr. Half-lives and γ-ray energies are reported for the previously unknown nuclides 147 La (Tsub(1/2) = 2.2 s), 148 La (Tsub(1/2) approximately 1 s), 149 Ce (Tsub(1/2) = 5.7 s) and 150 Ce (Tsub(1/2) = 4.1 s). The nuclides were formed in thermal neutron-induced fission of 235 U. The fission products were transferred to the SISAK system via a gas jet recoil transportation (GJRT) system. The combination of the GJRT system with SISAK is discussed, as well as the chemical separation systems used for the isolation of La, Ce and Pr. The appendices I - IX contain previously published material which is included in the thesis. (Auth.)

The analysis of thallium in geological materials by radiochemical neutron activation and x-ray fluorescence spectrometry: a comparison

Energy Technology Data Exchange (ETDEWEB)

McGoldrick, P J; Robinson, P [Tasmania Univ., Sandy Bay, TAS (Australia)

1994-12-31

Carrier-based radiochemical neutron activation (RNAA) is a precise and accurate technique for the analysis of Tl in geological materials. For about a decade, until the mid-80s, a procedure modified from Keays et al. (1974) was used at the University of Melbourne to analyse for Tl in a wide variety of geological materials. Samples of powdered rock weighing several hundred milligrams each were irradiated in HIFAR for between 12 hours and 1 week, and subsequently fused with a sodium hydroxide - sodium peroxide mixture and several milligrams of inactive Tl carrier. Following acid digestion of the fusion mixture anion exchange resin was used to separate Tl from the major radioactive rock constituents. The Tl was then stripped from the resin and purified as thallium iodide and a yield measured gravimetrically. Activity from {sup 204}Tl (a {beta}-emitter with a 3 8 year half-life) was measured and Tl determined by reference to pure chemical standards irradiated and processed along with the unkowns. Detection limits for the longer irradiations were about one part per billion. Precision was monitored by repeat analyses of `internal standard` rocks and was estimated to be about five to ten percent (one standard deviation). On the other hand, X-ray fluorescence spectrometry (XRF) was seen as an excellent cost-effective alternative for thallium analysis in geological samples, down to 1 ppm. 6 refs. 1 tab., 1 fig.

The analysis of thallium in geological materials by radiochemical neutron activation and x-ray fluorescence spectrometry: a comparison

Energy Technology Data Exchange (ETDEWEB)

McGoldrick, P.J.; Robinson, P. [Tasmania Univ., Sandy Bay, TAS (Australia)

1993-12-31

Carrier-based radiochemical neutron activation (RNAA) is a precise and accurate technique for the analysis of Tl in geological materials. For about a decade, until the mid-80s, a procedure modified from Keays et al. (1974) was used at the University of Melbourne to analyse for Tl in a wide variety of geological materials. Samples of powdered rock weighing several hundred milligrams each were irradiated in HIFAR for between 12 hours and 1 week, and subsequently fused with a sodium hydroxide - sodium peroxide mixture and several milligrams of inactive Tl carrier. Following acid digestion of the fusion mixture anion exchange resin was used to separate Tl from the major radioactive rock constituents. The Tl was then stripped from the resin and purified as thallium iodide and a yield measured gravimetrically. Activity from {sup 204}Tl (a {beta}-emitter with a 3 8 year half-life) was measured and Tl determined by reference to pure chemical standards irradiated and processed along with the unkowns. Detection limits for the longer irradiations were about one part per billion. Precision was monitored by repeat analyses of `internal standard` rocks and was estimated to be about five to ten percent (one standard deviation). On the other hand, X-ray fluorescence spectrometry (XRF) was seen as an excellent cost-effective alternative for thallium analysis in geological samples, down to 1 ppm. 6 refs. 1 tab., 1 fig.

Design and construction of a prototype for the obtention of 32P

International Nuclear Information System (INIS)

Duarte A, C.

2003-01-01

The 32 P are a pure emitting radioisotope of maximum energy of 1.71 MeV with half life of 14.28 days that he has applications in the industry, in agriculture, in medicine, in biology and in ecology (6,11,12,13,17,21,22,23,24,25,26,27,28,29,30,31,32 33).The 32 P can be used in the industry like radiotracer in the investigation of some operations and processes and as element of measurement of some industrial meters. In agriculture is used as radiotracer (29) in the investigation of diverse biological processes that have to do with the production of diverse nutritious products. In medicine has uses but very therapeutic mainly in the treatment of some become cancerous (28, 31, 25, 27) in the diagnosis of blood disorders (24) and like part of materials of production of aortic prosthesis (6). The 32 P are also used in the molecular investigation in biology and in genetics (33), and in studies of ecosystems (32) and of DNA (22). One can obtain the 32 P by means of diverse nuclear reactions depending on the material used as matter it prevails, since it doesn't exist in the nature. But anyone in the ways of obtaining it it should imply a process of radiochemical separation that involves so many steps like they are required, depending on the material used as matter prevails, of the purity with which he wants himself to obtain and of the resources that it has available. The objective of this work was design, to build and to prove a prototype to obtain the 32 P to leave of the irradiation of S α with fast neutrons at experimental level, which implies also to design a process that contemplates diverse stages and procedures for each one of them. The process was outlined in five stages: matter purification prevails, preparation of irradiation capsules, irradiation of irradiation capsules, transport and opening capsules of irradiation and radiochemical separation. In the last stage it was where uses the prototype of radiochemical separation in basis to the outlined process and

Design and construction of a prototype for the obtention of {sup 32}P; Diseno y construccion de un prototipo para la obtencion de {sup 32}P

Energy Technology Data Exchange (ETDEWEB)

Duarte A, C

2003-07-01

The {sup 32} P are a pure emitting radioisotope of maximum energy of 1.71 MeV with half life of 14.28 days that he has applications in the industry, in agriculture, in medicine, in biology and in ecology (6,11,12,13,17,21,22,23,24,25,26,27,28,29,30,31,32 33).The {sup 32} P can be used in the industry like radiotracer in the investigation of some operations and processes and as element of measurement of some industrial meters. In agriculture is used as radiotracer (29) in the investigation of diverse biological processes that have to do with the production of diverse nutritious products. In medicine has uses but very therapeutic mainly in the treatment of some become cancerous (28, 31, 25, 27) in the diagnosis of blood disorders (24) and like part of materials of production of aortic prosthesis (6). The {sup 32} P are also used in the molecular investigation in biology and in genetics (33), and in studies of ecosystems (32) and of DNA (22). One can obtain the {sup 32} P by means of diverse nuclear reactions depending on the material used as matter it prevails, since it doesn't exist in the nature. But anyone in the ways of obtaining it it should imply a process of radiochemical separation that involves so many steps like they are required, depending on the material used as matter prevails, of the purity with which he wants himself to obtain and of the resources that it has available. The objective of this work was design, to build and to prove a prototype to obtain the {sup 32} P to leave of the irradiation of S {alpha} with fast neutrons at experimental level, which implies also to design a process that contemplates diverse stages and procedures for each one of them. The process was outlined in five stages: matter purification prevails, preparation of irradiation capsules, irradiation of irradiation capsules, transport and opening capsules of irradiation and radiochemical separation. In the last stage it was where uses the prototype of radiochemical separation

Determination of [sup 90]Sr in environmental samples with resonance ionization spectroscopy in collinear geometry

Energy Technology Data Exchange (ETDEWEB)

Zimmer, K. (Inst. fuer Physik, Univ. Mainz (Germany)); Stenner, J. (Inst. fuer Physik, Univ. Mainz (Germany)); Kluge, H.J. (Inst. fuer Physik, Univ. Mainz (Germany)); Lantzsch, J. (Inst. fuer Physik, Univ. Mainz (Germany)); Monz, L. (Inst. fuer Physik, Univ. Mainz (Germany)); Otten, E.W. (Inst. fuer Physik, Univ. Mainz (Germany)); Passler, G. (Inst. fuer Physik, Univ. Mainz (Germany)); Schwalbach, R. (Inst. fuer Physik, Univ. Mainz (Germany)); Schwarz, M. (Inst. fuer Physik, Univ. Mainz (Germany)); Stevens, H. (Inst. fuer Physik, Univ. Mainz (Germany)); Wendt, K. (Inst. fuer Physik, Univ. Mainz (Germany)); Herrmann, G. (Inst. fuer Kernchemie, Univ. Mainz (Germany)); Niess, S. (Inst. fuer Kernchemie, Univ. Mainz (Germany)); Trautmann, N. (Inst. fuer Kernchemie, Univ. Mainz (Germany)); Walter, K. (Inst. fuer Kernchemie, Univ. Mainz (Germany)); Bushaw, B.A. (Pacific Northwest Lab., Richland, WA (United States))

1994-08-01

A new, fast technique for trace analysis of the radioactive isotopes [sup 89]Sr and [sup 90]Sr in environmental samples has been developed. Conventional mass separation is combined with resonance ionization spectroscopy in collinear geometry, which provides high selectivity and sensitivity. In addition, a chemical separation procedure for sample preparation has been developed. The described technique was used to determine the [sup 90]Sr content in [approx] 870 m[sup 3] air samples collected near Munich during and shortly after the Chernobyl reactor accident in April 1986. The content of [sup 90]Sr was measured to be 1.4 mBq per m[sup 3], corresponding to 1.6 x 10[sup 9] atoms of [sup 90]Sr per sample. This value is in good agreement with the results of radiochemical measurements. (orig.)

Radiochemical studies on Bikini ashes

Energy Technology Data Exchange (ETDEWEB)

Shiokawa, T

1954-01-01

Decay characteristics of the ashes which were brought back by the crew of the Fukuryu Maru No. 5 were: untreated ash I = ct/sup -1/ /sup 81/, water soluble part t/sup -2/ /sup 71/, insoluble part t/sup -1/ /sup 68/. Radioactive species separated by chemical method with carrier or collector were: nuclide, activity of nuclide (counts/min)/activity of original sample (counts/min), and the date of separation, /sup 89/Sr 6000/80 X 10/sup 4/, April 24; /sup 95/Zr, 280/80 x 10/sup 4/, -; /sup 111/Ag, 200/200 x 10/sup 4/, April 14; /sup 103/Ru, 2.300/25 x 10/sup 4/, etc.

Separation and recovery of Cm from Cm-Pu mixed oxide samples containing Am impurity

International Nuclear Information System (INIS)

Hirokazu Hayashi; Hiromichi Hagiya; Mitsuo Akabori; Yasuji Morita; Kazuo Minato

2013-01-01

Curium was separated and recovered as an oxalate from a Cm-Pu mixed oxide which had been a 244 Cm oxide sample prepared more than 40 years ago and the ratio of 244 Cm to 240 Pu was estimated to 0.2:0.8. Radiochemical analyses of the solution prepared by dissolving the Cm-Pu mixed oxide in nitric acid revealed that the oxide contained about 1 at% of 243 Am impurity. To obtain high purity curium solution, plutonium and americium were removed from the solution by an anion exchange method and by chromatographic separation using tertiary pyridine resin embedded in silica beads with nitric acid/methanol mixed solution, respectively. Curium oxalate, a precursor compound of curium oxide, was prepared from the purified curium solution. 11.9 mg of Cm oxalate having some amounts of impurities, which are 243 Am (5.4 at%) and 240 Pu (0.3 at%) was obtained without Am removal procedure. Meanwhile, 12.0 mg of Cm oxalate (99.8 at% over actinides) was obtained with the procedure including Am removals. Both of the obtained Cm oxalate sample were supplied for the syntheses and measurements of the thermochemical properties of curium compounds. (author)

Comparing monolithic and fused core HPLC columns for fast chromatographic analysis of fat-soluble vitamins.

Science.gov (United States)

Kurdi, Said El; Muaileq, Dina Abu; Alhazmi, Hassan A; Bratty, Mohammed Al; Deeb, Sami El

2017-06-27

HPLC stationary phases of monolithic and fused core type can be used to achieve fast chromatographic separation as an alternative to UPLC. In this study, monolithic and fused core stationary phases are compared for fast separation of four fat-soluble vitamins. Three new methods on the first and second generation monolithic silica RP-18e columns and a fused core pentafluoro-phenyl propyl column were developed. Application of three fused core columns offered comparable separations of retinyl palmitate, DL-α-tocopheryl acetate, cholecalciferol and menadione in terms of elution speed and separation efficiency. Separation was achieved in approx. 5 min with good resolution (Rs > 5) and precision (RSD ≤ 0.6 %). Monolithic columns showed, however, a higher number of theoretical plates, better precision and lower column backpressure than the fused core column. The three developed methods were successfully applied to separate and quantitate fat-soluble vitamins in commercial products.

Single patient doses of {sup 99m}Tc-HDP: Assessment of radiochemical purity, sterility and extractables from a polypropylene syringe over six hours

Energy Technology Data Exchange (ETDEWEB)

Parkes, S.L.; Varelis, P. [St George Hospital, Kogarah, NSW (Australia). Department of Nuclear Medicine

1997-12-01

Full text: The purpose of this investigation was to determine the radiochemical purity (RCP), sterility and extractables for {sup 99m}Tc oxidronate ({sup 99m}Tc-HDP) stored in polypropylene syringes over < six-hour period. The radiochemical purity was determined using a two-strip ITLC procedure, performed at time 0, 1, 2, 4, 6 hours. The sterility and endotoxin levels were tested by a NATA accredited laboratory, after allowing the radiopharmaceutical to stand at room temperature for six hours in the syringes. Plasticisers and other likely compounds that could be extracted from the syringes into the aqueous solution were determined by high pressure liquid chromatography (HPLC) diode array detection. This analysis involved shaking normal saline in a syringe over night and then injecting an aliquot of this solution onto a C18 analytical column and monitoring the effluent at 200 and 253 nm. The radiochemical purity of {sup 99m}Tc-HDP did not significantly change over the course of the study and remained above the recommended RCP for this radiopharmaceutical. Furthermore, at six hours the RCP of {sup 99m}Tc-HDP stored in both the manufacturer`s vial and a syringe were identical. Sterility testing of {sup 99m}Tc-HDP stored in syringes showed no microbial growth and less than 10 endotoxin units/mL (pass). The HPLC analysis did not show the presence of any extraneous compounds in the aqueous solution. Single patient doses of {sup 99m}Tc-HDP stored in polypropylene syringes over a six-hour period fulfill all the quality control requirements for administration to humans.

Determination of radiochemical yield of 99mTc radiopharmaceutical preparations using gamma counter and linear radiochromatography scanner

International Nuclear Information System (INIS)

Martins, Patricia de A.; Moura, Rebeca G.; Shiki, Andressa M.; Fukumori, Neuza T.O.; Matsuda, Margareth M.N.

2013-01-01

The radiochemical purity (RCP) evaluation is a prerequisite for radiopharmaceuticals before the administration in patients. RCP is defined as the proportion of the total radioactivity in the product that is present in the specified chemical form. The most widely used techniques for RCP determination in radiopharmaceutical preparations are thin layer chromatography (TLC-Al), instant thin layer chromatography (ITLC-SG) and paper chromatography (PC). These techniques combined with radioactivity detection are one of the most important tools in the RCP of the radiopharmaceutical compounds. Several methods are used for the determination of the spatial distribution of radioactivity on the strips. The aim of this study was to compare two methods for radioactivity measurement in the determination of RCP in 99m Tc radiopharmaceuticals using gamma counter and linear radiochromatography scanner. Lyophilized radiopharmaceuticals were labeled with 99m Tc. The analysis was carried out using TLC-Al and high performance thin layer chromatography (HPTLC-Cellulose) sheets, ITLC-SG and 3MM Whatman PC. The radioactivity distribution was determined by counting each strip during 1 minute in a radiochromatography TLC scanner. For comparison, the strips were cut into small pieces and each one was separately measured in a gamma-counter during 0.20 minutes in 70-210 KeV 99m Tc window. USP 36 and FDA specify that not less than 90% of the total radioactivity must be in the spot corresponding to 99m Tc labeled compound. In conclusion, the procedure for RCP determination of ALBUMINA-TEC, DEX500-TEC, ECD-TEC, MACRO-TEC and MIBI-TEC can be faster using radiochromatography. (author)

Radiochemical determination of the neutron capture cross sections of {sup 241}Am irradiated in the JMTR reactor

Energy Technology Data Exchange (ETDEWEB)

Shinohara, N.; Hatsukawa, Y.; Hata, K.; Kohno, N. [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

1997-03-01

The thermal neutron capture cross section {sigma}{sub 0} and Resonance integral I{sub 0} of {sup 241}Am leading to the production of {sup 242m}Am and {sup 242g}Am were measured by radiochemical method. The cross sections obtained in this study are {sigma}{sub 0}=60.9 {+-} 2.6 barn, I{sub 0}=213 {+-} 13 barn for {sup 241}Am(n,{gamma}){sup 242m}Am and {sigma}{sub 0}=736 {+-} 31 barn, I{sub 0}=1684 {+-} 92 barn for {sup 241}Am(n,{gamma}){sup 242g}Am. (author)

Pollution of agricultural crops with lanthanides, thorium and uranium studied by instrumental and radiochemical neutron activation analysis

International Nuclear Information System (INIS)

Kucera, J.; Mizera, J.; Randa, Z.; Vavrova, M.

2007-01-01

The lanthanide elements, Th and U were measured in soils and agricultural crops collected in an area polluted by emissions from a phosphate fertilizer plant. Concentrations of the above elements in the soil and crop samples were determined by instrumental neutron activation analysis (INAA). Selected crop samples were also analyzed using radiochemical neutron activation analysis (RNAA) based on alkaline-oxidative fusion of the irradiated samples followed by precipitation of REE oxalates. Elevated levels of lanthanides, Th and U were found in some samples, especially in wheat chaff and parsley. (author)

Radiochemical synthesis of 3-(4-[18F] Fluorophenyl)-8-hydroxy-1, 2, 3, 4-tetrahydrochromeno [3, 4-c] pyridin-5-one: A putative dopamine D$4 receptor PET imaging agent

International Nuclear Information System (INIS)

Li, G.C.; Yin, D.Z.; Wang, M.W.; Cheng, D.F.; Wang, Y.X.

2005-01-01

Introduction: The dopamine D 4 receptor has lately received increasing interest since it has been hypothesized to be involved in the pathology and pharmacotherapy of schizophrenia. While this receptor is expressed in lower density in various extrastriatal brain regions and its distribution is still unclear due to the lack of suitable imaging agent and its level change in schizophrenia is controversial. Herein, based on the structure-activity analysis of chromeno[3, 4-c]pyridine- 5-ones as potential dopamine D 4 receptor ligands, a putative D 4 subtype positron emission tomography (PET) radioligand, 3-(4-[ 18 F]fluorophenyl)-8-hydroxy-1, 2, 3, 4-tetrahydrochromeno [3, 4-c]pyridin-5-one ([ 18 F]FHTP), was designed and synthesized. Methods: The radiochemical synthesis route was shown in Figure 1. [ 18 F]Fluoride was produced with a Cyclone-30 (IBA, Belgium) by 18 O(p, n) 18 F reaction using enriched 18 O-H 2 O and eluted from a Dowex 1-X8 anion-exchange column with aqueous potassium carbonate (20 mg/mL). 4-[ 18 F]Fluorobenzaldehyde was prepared according to the method reported by Alan A. Wilson and et al.. Then, 8-hydroxy-1, 2, 3, 4-tetrahydrochromeno [3, 4-c]pyridin-5-one, sodium cyanoborohydride, methanol and acetic acid were added to the dry residue, The mixture was then sealed and heated at 120 degree C for 12 min. At the end of the reaction, the mixture was cooled, diluted with ethyl acetate and washed with water. The extracted organic layer was passed through a small anhydrous magnesium sulfate column. After removal of the solvents in the mixture at 50 degree C under a stream of nitrogen, the obtained residue was redissolved in methanol and purified with a semi-preparative HPLC system, then the desired product was collected. Results: The radiochemical synthesis of [ 18 F]FHTP took around 110 min at EOS with an overall radiochemical yield 19% (decay-corrected) and its radiochemical purity was higher than 95%. Conclusion: A presumed dopamine D 4 receptor PET

Final technical report on the development of the Cenenkov[sic] triggered radiochemical solar neutrino detector and the potential for single atom extraction and classification

CERN Document Server

Lande, K

2001-01-01

The most direct way to search for flavor changing of neutrinos after their generation in the solar core is to compare the solar neutrino detection rate of a purely electron neutrino detector with that of a detector that can detect all neutrino flavors. The ''all flavor'' flux measurement involves nu-e elastic scattering, while the nu sub e flux measurement involves an inverse beta decay detection, such as sup 3 sup 7 Cl(nu sub e , e sup -) sup 3 sup 7 Ar. The interactions due to sup 7 Be neutrinos must be separated FR-om those due to sup 8 B neutrinos. A Cherenkov signal-triggered radiochemical detector is proposed that will allow a very precise determination of both the sup 8 B and sup 7 Be electron neutrino fluxes FR-om the Sun. The basic concept is to identify each sup 8 B electron neutrino interaction in the detector and then sweep out the sup 3 sup 7 Ar atom produced by this sup 8 B neutrino as soon as it is made. A set of photomultipler tubes can be used to detect the Ar atom production and immediately ...

Development of production of {sup 99}Mo from LEU target

Energy Technology Data Exchange (ETDEWEB)

Adang, H G; Mutalib, A; Lubis, H [Radioisotope Production Centre, National Atomic Energy Agency, Kawasan Puspiptek, Serpong (Indonesia); and others

1998-10-01

{sup 99}TC, the most popular radioisotope in nuclear medicine, is daughter of {sup 99}Mo. {sup 99}Mo is produced in research reactor by irradiating of high enriched uranium (HEU). However, in recent year, strict regulation that has been implemented by USA DOE and NPT has led to the difficulty in getting HEU. Therefore, BATAN has tried to develop the production of {sup 99}Mo by using low enriched uranium (LEU). The research involves the use of LEU in the production of {sup 99}Mo. This research was started in 1994 by joint-research between BATAN and Argonne National Laboratory USA. This program is divided into three research groups. The first group emphasizes its research on fabrication of LEU foil that is going to be irradiated. The second group studies the irradiation`s aspects and physical characteristic of irradiated LEU foils. The third group studies the radiochemical separation process of fission product {sup 99}Mo from solution of irradiated LEU foils. There are five steps that are carried out in studying of radiochemical separation of {sup 99}Mo from irradiated LEU. First is designing a dissolver that is going to be used in dissolving of LEU foil and testing its reliability. Second is dissolving LEU in the new design dissolver. Third is evaluation the modified of Cintichem`s radiochemical separation process of {sup 99}Mo from LEU. Forth is modifying the Cintichem`s radiochemical separation process of {sup 99}Mo from the solution of irradiated LEU. And fifth is using the modified of Cintichem`s radiochemical separation process for separation {sup 99}Mo from solution of irradiated LEU. The first through the forth steps of experiments were already carried out and will be reported in this workshop, whereas the fifth step of experiment is going to be conducted in February 1998. (author)

Application of 241Am EDXRF in detecting and controlling of rare earth separation process by solvent extraction

International Nuclear Information System (INIS)

Yan Chunhua; Jia Jiangtao; Liao Chunsheng; Wang Mingwen; Li Biaoguo; Xu Guangxian

1996-01-01

The article investigated a fast EDXRF analysis method by radioisotope excited ( 241 Am) employing a high-purity germanium detector in rare earth separation process by solvent extraction. Applying the method, hydrochloride aqueous samples of SeEuGd/Tb/Dy separation processes were off-line analyzed. Comparative results measured by ICP were also given out. The results show that the method can be used for a wide rare earth concentration range with low error. Being fast, effective, precise and non-destructive, it can be used for on-line analysis to detect and control rare earth separation process by solvent extraction