De Novo Sequencing and Assembly Analysis of Transcriptome in Pinus bungeana Zucc. ex Endl.

Directory of Open Access Journals (Sweden)

Qifei Cai

2018-03-01

Full Text Available To enrich the molecular data of Pinus bungeana Zucc. ex Endl. and study the regulating factors of different morphology controled by apical dominance. In this study, de novo assembly of transcriptome annotation was performed for two varieties of Pinus bungeana Zucc. ex Endl. that are obviously different in morphology. More than 147 million reads were produced, which were assembled into 88,092 unigenes. Based on a similarity search, 11,692 unigenes showed significant similarity to proteins from Picea sitchensis (Bong. Carr. From this collection of unigenes, a large number of molecular markers were identified, including 2829 simple sequence repeats (SSRs. A total of 158 unigenes expressed differently between two varieties, including 98 up-regulated and 60 down-regulated unigenes. Furthermore, among the differently expressed genes (DEGs, five genes which may impact the plant morphology were further validated by reverse transcription quantitative polymerase chain reaction (RT-qPCR. The five genes related to cytokinin oxidase/dehydrogenase (CKX, two-component response regulator ARR-A family (ARR-A, plant hormone signal transduction (AHP, and MADS-box transcription factors have a close relationship with apical dominance. This new dataset will be a useful resource for future genetic and genomic studies in Pinus bungeana Zucc. ex Endl.

Study of the sensitivity of integral parameters related to 232 Thorium cross sections

International Nuclear Information System (INIS)

Guimaraes, L.N.F.; Menezes, A.

1986-01-01

The THOR critical assembly is used to test 232 Th basic nuclear data from ENDL-78, ENDF/B-IV, INDL-83, JENDL-1 and JENDL-2. The FORSS and UNISENS systems are used to calculate integral parameters and sensitivity profiles. The results show that 232 Th from JENDL-2 is superior to the others, with ENDL-78 showing the worst performance. The discrepancies can be credited to the different evaluations for the 232 Thorium scattering cross section. (Author) [pt

Two new species of Callerya Endl. (Leguminosae: Papilionoideae) from Thailand

DEFF Research Database (Denmark)

Sirichamon, Yotsawate; Balslev, Henrik; Mathapa, Sawai

2016-01-01

Two new species of the genus Callerya (Endl.); C. chlorantha and C. tennaserimensis are illustrated and described. They are commonly found in dry deciduous or bamboo forest in Kanchanaburi and Ratchaburi province, South-western Thailand. It was also found that C. chlorantha might be associated...... with limestone habitat. Callerya chlorantha is characterized by its greenish flowers, which is relatively uncommon among species of this genus. Callerya tennaserimensis is characterized by its glabrous leaves and stems and rather small, purplish or maroonish flowers with golden-brown hairs on calyx and abaxial...

Differential cross sections for gamma-ray production by 14 MeV neutrons with several elements in structural materials

International Nuclear Information System (INIS)

Murata, Isao; Yamamoto, Junji; Takahashi, Akito

1988-01-01

Energy differential cross sections for the gamma-rays produced from the (n,xγ) reactions by 14 MeV neutrons were measured in the gamma-ray energy range from 700 keV to 10 MeV using an NaI spectrometer. Results were obtained for the 8 natural elements; C, Al, Si, Cr, Fe, Ni, Cu and Mo. For prominent discrete gamma-rays in the differential cross sections, the production cross sections were determined by measuring angular distributions with a Ge detector. The gamma-ray energy covered the range between 500 and 3000 keV. The energy distributions have been compared with the differential cross sections evaluated in the nuclear data files of JENDL-3T, ENDL and ENDF/B-IV. The evaluations in JENDL-3T agreed fairly well with the measurements concerning the continuum energy spectra for secondary photons. Discrepancies appeared, however, for Si, Cr and Ni at the energies where the discrete gamma-rays were dominant. The ENDL evaluations were largely deviated from the experimental data. The production cross sections for the discrete gamma-rays in ENDL and ENDF/B-IV were available for the comparison with some of the measured cross sections. Results are presented for C, Al and Si. (author)

Prebiotic effects of yacon (Smallanthus sonchifolius Poepp. & Endl), a source of fructooligosaccharides and phenolic compounds with antioxidant activity

NARCIS (Netherlands)

Campos, D.; Betalleluz-Pallardel, I.; Chirinos, R.; Aguilar-Glalvez, A.; Noratto, G.; Pedreschi, R.

2012-01-01

Thirty-five different yacon (Smallanthus sonchifolius Poepp. & Endl) accessions were evaluated as potential alternative sources of fructooligosaccharides (FOS) and phenolic type natural antioxidants. FOS, total phenolics (TPC) and antioxidant capacity (AC) contents in the ranges of 6.4–65 g/100

Revising and Updating the Inventory of Cross-Cultural Sensitivity

Science.gov (United States)

Mahon, Jennifer A.; Cushner, Kenneth

2014-01-01

The following article outlines research conducted to examine cross-cultural sensitivity in a sample of 949 incoming university students in the USA. The study was conducted during the process of updating an existing measure of cross-cultural sensitivity known as the Inventory of Cross-Cultural Sensitivity (ICCS), and to examine the various levels…

Thermal neutron cross section measurements for technetium-99

International Nuclear Information System (INIS)

Yates, M.A.; Schroeder, N.C.; Fowler, M.M.

1993-01-01

Technetium, because of its long half-like (213,000 years) and ability to migrate in the environment, is a primary contributor to the long-term radioactivity related risk associated with geologic nuclear waste disposal. One proposal for converting technetium to an environmentally benign element investigating transmutation with an accelerator-based system, (i.e., Accelerator Transmutation of Waste, ATW). Planning for efficient processing of technetium through the transmuter will require knowledge of the thermal neutron cross section for the 99 Tc (n,γ) 100 Tc reaction. The authors have recently remeasured this cross section. Weighed aliquots (19-205 μg) of a NIST traceable 99 Tc standard were irradiated for 30-150 sec using the pneumatic open-quotes rabbitclose quotes system of LANL's Omega West Reactor. The two gamma rays from the 15.7-sec half-life product were measured immediately after irradiation on a high-resolution Ge detector. Thermal fluxes were measured using gold foils and Cd wrapped gold foils. The observation cross section is 19 ± 1 b. This agrees well with the 1977 value but has half the uncertainty

Updated Higgs cross section at approximate N3LO

International Nuclear Information System (INIS)

Bonvini, Marco; Ball, Richard D; Forte, Stefano; Marzani, Simone; Ridolfi, Giovanni

2014-01-01

We update our estimate of the cross section for Higgs production in gluon fusion at next-to-next-to-next-to-leading order in α s in view of the recent full computation of the result in the soft limit for infinite top mass, which determines a previously unknown constant. We briefly discuss the phenomenological implications. Results are available through the updated version of the ggHiggs code. (paper)

Updated Higgs cross section at approximate N3LO

International Nuclear Information System (INIS)

Bonvini, Marco; Ball, Richard D.; Marzani, Simone

2014-04-01

We update our estimate of the cross section for Higgs production in gluon fusion at next-to-next-to-next-to-leading order (N 3 LO) in α s in view of the recent full computation of the result in the soft limit for infinite top mass, which determines a previously unknown constant. We briefly discuss the phenomenological implications. Results are available through the updated version of the ggHiggs code.

Fuzzy cross-model cross-mode method and its application to update the finite element model of structures

International Nuclear Information System (INIS)

Liu Yang; Xu Dejian; Li Yan; Duan Zhongdong

2011-01-01

As a novel updating technique, cross-model cross-mode (CMCM) method possesses a high efficiency and capability of flexible selecting updating parameters. However, the success of this method depends on the accuracy of measured modal shapes. Usually, the measured modal shapes are inaccurate since many kinds of measured noises are inevitable. Furthermore, the complete testing modal shapes are required by CMCM method so that the calculating errors may be introduced into the measured modal shapes by conducting the modal expansion or model reduction technique. Therefore, this algorithm is faced with the challenge of updating the finite element (FE) model of practical complex structures. In this study, the fuzzy CMCM method is proposed in order to weaken the effect of errors of the measured modal shapes on the updated results. Then two simulated examples are applied to compare the performance of the fuzzy CMCM method with the CMCM method. The test results show that proposed method is more promising to update the FE model of practical structures than CMCM method.

Updated Higgs cross section at approximate N{sup 3}LO

Energy Technology Data Exchange (ETDEWEB)

Bonvini, Marco [Deutsches Elektronen-Synchrotron (DESY), Hamburg (Germany); Ball, Richard D. [Edinburgh Univ. (United Kingdom). Tait Inst.; Forte, Stefano [Milano Univ. (Italy). Dipt. di Fisica; INFN, Milano (Italy); Marzani, Simone [Durham Univ. (United Kingdom). Inst. for Particle Physics Phenomenology; Ridolfi, Giovanni [Genova Univ. (Italy). Dipt. di Fisica; INFN, Genova (Italy)

2014-04-15

We update our estimate of the cross section for Higgs production in gluon fusion at next-to-next-to-next-to-leading order (N{sup 3}LO) in α{sub s} in view of the recent full computation of the result in the soft limit for infinite top mass, which determines a previously unknown constant. We briefly discuss the phenomenological implications. Results are available through the updated version of the ggHiggs code.

Cross-sections for formation of 99mTc through natRu(n,x) 99mTc reaction induced by neutrons at 13.5 and 14.8 MeV

International Nuclear Information System (INIS)

Luo Junhua; Han Jiuning; Tuo Fei; Kong Xiangzhong; Liu Rong; Jiang Li

2012-01-01

The cross-sections for formation of metastable state of 99 Tc ( 99m Tc, 140.511 keV, 6.01 h) through nat Ru(n,x) 99m Tc reaction induced by 13.5 MeV and 14.8 MeV neutrons were measured. Fast neutrons were produced via the 3 H(d,n) 4 He reaction on the K-400 neutron generator. Induced gamma activities were measured by a high-resolution gamma-ray spectrometer with a high-purity germanium (HpGe) detector. Measurements were corrected for gamma-ray attenuations, dead time and fluctuation of neutron flux. Data for nat Ru(n,x) 99m Tc reaction cross sections are reported to be 9.6±1.5 and 9.2±1.1 mb at 13.5±0.2 and 14.8±0.2 MeV incident neutron energies, respectively. Results were compared with the data by other authors. - Highlights: ► D–T neutron source was used to measure cross sections using activation method. ► 27 Al(n,α) 24 Na was used as the monitor for the measurement. ► Cross-sections for formation of 99m Tc through nat Ru(n,x) 99m Tc were measured. ► Data for nat Ru(n,x) 99m Tc reaction cross sections are reported. ► The results were discussed and compared with experimental data in the literature.

Comparative analysis of the neutron cross-sections of iron from various evaluated data libraries

International Nuclear Information System (INIS)

Bychkov, V.M.; Vozyakov, V.V.; Manokhin, V.N.; Smoll, F.; Resner, P.; Seeliger, D.; Hermsdorf, D.

1983-09-01

The comparative analysis of neutron cross-sections of iron from evaluated nuclear data libraries SOKRATOR, KEDAK, ENDL is done in energy interval from 0.025 eV to 20 MeV. Some of iron cross-sections from SOKRATOR library are revised and new data, which are obtained by using new experimental data and more comprehensive theoretical methods, are recommended. As a result the new version of the iron neutron cross-section file (BNF-2012) is produced for SOKRATOR library. (author)

ENDL-84. The Evaluated Nuclear Data Library of the Lawrence Livermore National Laboratory in the ENDF-5 format

International Nuclear Information System (INIS)

Cullen, D.E.; McLaughlin, P.K.; Lemmel, H.D.

1990-09-01

This document summarizes the contents of the evaluated nuclear data library (ENDL) by the Lawrence Livermore National Laboratory, USA, converted to ENDF-5 format. The library contains evaluated data for all significant neutron reactions in the energy range from 10 -4 eV to 20 MeV for 94 elements or isotopes. The entire library or selective retrievals from it can be obtained on magnetic tape, free of charge, from the IAEA Nuclear Data Section. (author)

PCS a code system for generating production cross section libraries

International Nuclear Information System (INIS)

Cox, L.J.

1997-01-01

This document outlines the use of the PCS Code System. It summarizes the execution process for generating FORMAT2000 production cross section files from FORMAT2000 reaction cross section files. It also describes the process of assembling the ASCII versions of the high energy production files made from ENDL and Mark Chadwick's calculations. Descriptions of the function of each code along with its input and output and use are given. This document is under construction. Please submit entries, suggestions, questions, and corrections to (ljc at sign llnl.gov) 3 tabs

Benchmark experiment for the cross section of the 100Mo(p,2n)99mTc and 100Mo(p,pn)99Mo reactions

Science.gov (United States)

Takács, S.; Ditrói, F.; Aikawa, M.; Haba, H.; Otuka, N.

2016-05-01

As nuclear medicine community has shown an increasing interest in accelerator produced 99mTc radionuclide, the possible alternative direct production routes for producing 99mTc were investigated intensively. One of these accelerator production routes is based on the 100Mo(p,2n)99mTc reaction. The cross section of this nuclear reaction was studied by several laboratories earlier but the available data-sets are not in good agreement. For large scale accelerator production of 99mTc based on the 100Mo(p,2n)99mTc reaction, a well-defined excitation function is required to optimise the production process effectively. One of our recent publications pointed out that most of the available experimental excitation functions for the 100Mo(p,2n)99mTc reaction have the same general shape while their amplitudes are different. To confirm the proper amplitude of the excitation function, results of three independent experiments were presented (Takács et al., 2015). In this work we present results of a thick target count rate measurement of the Eγ = 140.5 keV gamma-line from molybdenum irradiated by Ep = 17.9 MeV proton beam, as an integral benchmark experiment, to prove the cross section data reported for the 100Mo(p,2n)99mTc and 100Mo(p,pn)99Mo reactions in Takács et al. (2015).

Update to the R33 cross section file format

International Nuclear Information System (INIS)

Vickridge, I.C.

2003-01-01

In September 1991, in response to the workshop on cross sections for Ion Beam Analysis (IBA) held in Namur (July 1991, Nuclear Instruments and Methods B66(1992)), a simple ascii format was proposed to facilitate transfer and collation of nuclear reaction cross section data for Ion Beam Analysis (IBA) and especially for Nuclear Reaction Analysis (NRA). Although intended only as a discussion document, the ascii format - referred to as the R33 (Report 33) format - has become a de facto standard. In the decade since this first proposal there have been spectacular advances in computing power and in software usability, however the cross-platform compatibility of the ascii character set has ensured that the need for an ascii format remains. Nuclear reaction cross section data for Nuclear Reaction analysis has been collected and archived on internet web sites over the last decade. This data has largely been entered in the R33 format, although there is a series of elastic cross sections that are expressed as the ratio to the corresponding Rutherford cross sections that have been entered in a format referred to as RTR (ratio to Rutherford). During this time the R33 format has been modified and added to - firstly to take into account angular distributions, which were not catered for in the first proposal, and more recently to cater for elastic cross sections expressed as the ratio-to- Rutherford, which it is useful to have for some elastic scattering programs. It is thus timely to formally update the R33 format. There also exists the large nuclear cross section data collections of the Nuclear Data Network - of which the core centres are the OECD NEA Nuclear Data Bank, the IAEA Nuclear Data Section, the Brookhaven National Laboratory National Nuclear Data Centre and CJD IPPE Obninsk, Russia. The R33 format is now proposed to become a legal computational format for the NDN. It is thus also necessary to provide an updated formal definition of the R33 format in order to provide

CFRMF spectrum update and application to dosimeter cross-section data testing

International Nuclear Information System (INIS)

Anderl, R.A.; Harker, Y.D.; Millsap, D.A.; Rogers, J.W.; Ryskamp, J.M.

1982-01-01

The Coupled Fast Reactivity Measurements Facility (CFRMF) at the Idaho National Engineering Laboratory (INEL) is a Cross Section Evaluation Working Group (CSEWG) benchmark for data testing of dosimetry, fission-product and actinide cross sections important to fast-reactor technology. In this paper we present the results of our work in updating the CFRMF spectrum characterization and in applying CFRMF integral data to testing ENDF/B-V dosimeter cross sections. Updated characterization of the central neutron spectrum includes the results of neutronics calculations with ENDF/B-V nuclear data, the generation of a fine-group spectrum representation for integral data-testing applications, and a sensitivity and uncertainty analysis which provides a flux-spectrum covariance matrix related to uncertainties and correlations in the nuclear data used in a neutronics calculation. Our application of CFRMF integral data to cross section testing has included both conventional integral testing analyses and least-squares-adjustment analyses with the FERRET code. The conventional integral data-testing analysis, based on C/E ratios, indicates discrepancies outside the estimated integral test uncertainty for the 6 Li(n,He), 10 B(n,He), 47 Ti(n,p), 58 Fe(n,γ), 197 Au(n,γ) and 232 Th(n,γ) cross sections. The integral test uncertainty included contributions from the measured integral data and from the spectrum and cross sections used to obtain the calculated integral data. Within the uncertainty and correlation specifications for the input spectrum and dosimeter cross sections, the least-squares-adjustment analysis indicated a high degree of consistency between the measured integral data and the ENDF/B-V dosimeter cross sections for all reactions except 10 B

JENDL dosimetry file 99 (JENDL/D-99)

International Nuclear Information System (INIS)

Kobayashi, Katsuhei; Iwasaki, Shin

2002-01-01

The JENDL Dosimetry File 99 (JENDL/D-99), which is a revised version of the JENDL Dosimetry File 91 (JENDL/D-91), has been compiled and released for the determination of neutron flux and energy spectra. This work was undertaken to remove the inconsistency between the cross sections and their covariances in JENDL/D-91 since the covariances were mainly taken from IRDF-85 although the cross sections were based on JENDL-3. Dosimetry cross sections have been evaluated for 67 reactions on 47 nuclides together with covariances. The cross sections for 34 major reactions and their covariances were simultaneously generated, and the remaining 33 reaction data were mainly taken from JENDL/D-91. Latest measurements were taken into account in the evaluation. The resultant evaluated data are given in the neutron energy region below 20 MeV in both of point-wise and group-wise files in the ENDF-6 format. In order to confirm the reliability of the evaluated data, several integral tests have been carried out: comparisons with average cross sections measured in fission neutron fields, fast/thermal reactor spectra, DT neutron fields and Li(d,n) neutron fields. It was found from the comparisons that the cross sections calculated from JENDL/D-99 are generally in good agreement with the measured data. The contents of JENDL/D-99 and the results of the integral tests are described in this report. All of the dosimetry cross sections are shown in a graphical form in the Appendix. (author)

Experimental cross section evaluation for innovative 99Mo production via the (α,n) reaction on 96Zr target

International Nuclear Information System (INIS)

Pupillo, Gaia; Gambaccini, M.; Esposito, J.; Haddad, F.; Michel, N.

2014-01-01

The recent crisis of 99 Mo production by nuclear reactors caused an unexpected worldwide 99m Tc shortening, forcing the international scientific community to find alternative production routes for these vital nuclides. One of the possibilities is to replace the current reactor-based method with the accelerator-based one. The aim of this work is the experimental evaluation of the 96 Zr(α,n) 99 Mo reaction, using the well known stacked foil technique with natural Zr targets, in the energy range 33-8 MeV. The results were compared with the published experimental values, finding good agreement in the trend of the cross section but at higher peak value. The results refer to 100% enriched 96 Zr target. The cross section values measured in the different irradiations show excellent agreement and indicate that the ideal energy range for 99 Mo production is 13-25 MeV. In comparison with the literature, there is good agreement in the trend of the cross section but at higher peak value. The 96 Zr(α,n) 99 Mo reaction is an interesting alternative production route of 99 Mo aimed at the realization of 99 Mo/ 99 mTc generators. Using enriched 96 Zr as target, 99 Mo is the only radioactive Mo-isotope produced, while using natural Zr as target, the resulting 99 Mo still has an high radioisotopic purity (only the radioactive 93 Mo is co-produced), but a lower specific activity. In both cases no Tc-nuclides are directly produced in target and the high purity 99m Tc results only from the decay of 99 Mo

Methods of experimental settlement of contradicting data in evaluated nuclear data libraries

Directory of Open Access Journals (Sweden)

V. A. Libman

2016-12-01

Full Text Available The latest versions of the evaluated nuclear data libraries (ENDLs have contradictions concerning data about neutron cross sections. To resolve this contradiction we propose the method of experimental verification. This method is based on using of the filtered neutron beams and following measurement of appropriate samples. The basic idea of the method is to modify the suited filtered neutron beam so that the differences between the neutron cross sections in accordance with different ENDLs become measurable. Demonstration of the method is given by the example of cerium, which according to the latest versions of four ENDLs has significantly different total neutron cross section.

ORGANOLEPTIC QUALITY OF FRUIT SORBETS CONTAINING YACON (SMALLANTHUS SONCHIFOLIUS Poepp. and Endl.

Directory of Open Access Journals (Sweden)

Kinga Topolska

2015-02-01

Full Text Available Due to the growing consumer interest in functional food, sorbets containing yacon root powder as a source of many valuable compounds, especially fructans, may be a desirable alternative to traditional ice cream desserts. The aim of this work was to evaluate organoleptic quality (taste, color, aroma as well as consistency and structure of fruit sorbets containing Smallanthus sonchifolius (Poepp. and Endl. root powder in dependence on kind of fruit (orange, cherry, strawberry, and its share in sorbet’s recipe, using a 9-point hedonic scale (1 point =„I do not like it at all“, 9 = „I like it very much“. The results showed that organoleptic quality was depended on the kind and the share of fruit used to the sorbet production. Strawberry sorbets gained over 80% of maximal scores. One can conclude that yacon root powder can be used as the ingredient of fruit sorbet, with increased consumer liking.

49 CFR 99.735-1 - Cross-reference to ethical conduct standards and financial disclosure regulations.

Science.gov (United States)

2010-10-01

... 49 Transportation 1 2010-10-01 2010-10-01 false Cross-reference to ethical conduct standards and... Transportation EMPLOYEE RESPONSIBILITIES AND CONDUCT General § 99.735-1 Cross-reference to ethical conduct... the executive branch-wide Standards of Ethical Conduct at 5 CFR part 2635, the Department of...

Integrated system for production of neutronics and photonics calculational constants. Volume XVI. Tabular and graphical presentation of 175 neutron group constants derived from the LLL evaluated neutron data library (ENDL)

International Nuclear Information System (INIS)

Plechaty, E.F.; Cullen, D.E.; Howerton, R.J.; Kimlinger, J.R.

1975-01-01

As of February 3, 1975, 175 neutron group constants had been derived from the Evaluated Nuclear Data Library (ENDL) at LLL. In this volume, tables and graphs of the constants are presented along with the conventions used in their preparation. (U.S.)

Chromatographic purification of neutron capture molybdenum-99 from cross-contaminant radionuclides

International Nuclear Information System (INIS)

Mostafa, M.A.M.

2011-01-01

Technetium-99m is called the work horse, for many reasons, in nuclear medicine diagnostic purposes. It is produced as the β - decay of 99 Mo radionuclide. Molybdenum-99 gel type generators are considered as a suitable alternative of the conventional chromatographic alumina columns loaded with fission molybdenum-99. 99 Mo neutron-capture is cross-contaminated with radionuclides originated from activation of chemical impurities in the Mo target such 60 C0, 65 Zn, 95 Zr, 175 Hf, 181 Hf, 86 Rb, 134 Cs, 141 Ce, 152 Eu, 140 La, 51 Cr, 124 Sb, 46 Sc, 54 Mn, 59 Fe and / or fast neutrons interactions with the stable isotopes of molybdenum such as 92m Nb, 95 Nb and 95 Zr. To prevent contamination of the eluted 99m Tc, successive purification methods were made. After complete dissolution of the irradiated target wrapped with thin Al foil in 5 M NaOH solution, hydrogen peroxide was added to start precipitation of Fe(OH) 3 . The formed Fe (III) minerals allow complete elimination of some radio contaminants from the molybdate solute such as 152 Eu, 140 La, 141 Ce, 45 Mn and 92m Nb in addition to partial elimination of 46 Sc, 60 Co and 59 Fe radionuclides. The remaining supernatant was acidified by concentrated nitric acid to ph 9.5 for precipitation of Al(OH) 3 with complete elimination of radio contaminants such as 95 Zr 175 Hf, 181 Hf, 65 Zn, 124 Sb, 51 Cr, 46 Sc, 60 Co and 59 Fe. 134 Cs and 86 Rb radionuclides were not affected by precipitation of Fe(OH) 3 or Al(OH) 3 . Chromatographic column of potassium nickel hexacyanoferrate (II) (KNHCF) has high affinity towards elimination of 134 Cs and 86 Rb radionuclides. Highly pure molybdate- 99 Mo solution was processed for preparation of zirconium molybdate gel generator with 99m Tc eluate of high radionuclidic, radiochemical and chemical purity suitable for use in medical purposes.

Cancer incidence in the Swedish leather tanning industry: updated findings 1958-99.

Science.gov (United States)

Mikoczy, Z; Hagmar, L

2005-07-01

To assess how a 10 year extension of the follow up period affected cancer incidence in the Swedish leather tanning cohort. A cohort of 2027 tannery workers (of which 482 were women) who had been employed for at least one year between 1900 and 1989 at one of three Swedish leather tanneries, was established. The start of observation varied between 1958 and 1966 for the three plants. Through linkage with the Swedish Cancer Registry, incident cancer cases were recorded up to 1999. Cause specific expected cancer incidence was calculated for 1958-99 based on calendar year, sex, and five year age group specific incidence rates for the counties where the plants had been located. Altogether 56,022 person-years at risk were generated. A total of 351 incident cancer cases were observed compared to 302 expected, which resulted in an increased standardised incidence ratio (SIR) of 1.16 (95% CI 1.04 to 1.29). An enhanced risk for prostate cancer was observed (SIR 1.44, 95% CI 1.10 to 1.86), mainly attributable to the later part of the observation period (1990-99). In this updated analysis the previously observed risk excess for soft tissue sarcomas was no longer significant (SIR 2.62, 95% CI 0.96 to 5.70). For multiple myelomas and sinonasal cancer the slight non-significant excesses remained, still based on very few cases. The increased risk for prostate cancer in the present study might be a chance finding, but is noteworthy, since it is in acccordance with the finding of increased SIR for prostate cancer among leather workers in another recent Swedish study. Moreover, excess risks for prostate cancer among farmers have been reported, indicating pesticides as possible causative agents. Leather tanners have also been exposed to pesticides.

Errata and update to ;Experimental cross sections for L-shell X-ray production and ionization by protons;

Science.gov (United States)

Miranda, J.; Lapicki, G.

2018-01-01

A compilation of experimental L-shell X-ray production and ionization cross sections induced by proton impact was published recently (Miranda and Lapicki, 2014), collecting 15 439 experimental cross sections. The database covers an energy range from 10 keV to 1 GeV, and targets from 10Ne to 95Am. A correction to several tabulated values that were in error, as well as an update including new data published after 2012 and older references not found previously are given in the present work. The updated data base increased the total number of experimental cross sections by 3.1% to 15 921. A new analysis of the total number of experimental points per year shows that the possible saturation in the cumulative total number of data is increased to 15 950 ± 110 points.

Phylogeny and photosynthetic pathway distribution in Anticharis Endl. (Scrophulariaceae).

Science.gov (United States)

Khoshravesh, Roxana; Hossein, Akhani; Sage, Tammy L; Nordenstam, Bertil; Sage, Rowan F

2012-09-01

C(4) photosynthesis independently evolved >62 times, with the majority of origins within 16 dicot families. One origin occurs in the poorly studied genus Anticharis Endl. (Scrophulariaceae), which consists of ~10 species from arid regions of Africa and southwest Asia. Here, the photosynthetic pathway of 10 Anticharis species and one species from each of the sister genera Aptosimum and Peliostomum was identified using carbon isotope ratios (δ(13)C). The photosynthetic pathway was then mapped onto an internal transcribed spacer (ITS) phylogeny of Anticharis and its sister genera. Leaf anatomy was examined for nine Anticharis species and plants from Aptosimum and Peliostomum. Leaf ultrastructure, gas exchange, and enzyme distributions were assessed in Anticharis glandulosa collected in SE Iran. The results demonstrate that C(3) photosynthesis is the ancestral condition, with C(4) photosynthesis occurring in one clade containing four species. C(4) Anticharis species exhibit the atriplicoid type of C(4) leaf anatomy and the NAD-malic enzyme biochemical subtype. Six Anticharis species had C(3) or C(3)-C(4) δ(13)C values and branched at phylogenetic nodes that were sister to the C(4) clade. The rest of Anticharis species had enlarged bundle sheath cells, close vein spacing, and clusters of chloroplasts along the centripetal (inner) bundle sheath walls. These traits indicate that basal-branching Anticharis species are evolutionary intermediates between the C(3) and C(4) conditions. Anticharis appears to be an important new group in which to study the dynamics of C(4) evolution.

EXTRACCIÓN, CRISTALIZACIÓN Y CARACTERIZACIÓN DE INULINA A PARTIR DE YACÓN (Smallanthus sonchifolius (Poepp. & Endl.) PARA SU UTILIZACIÓN EN LA INDUSTRIA ALIMENTARIA Y FARMACÉUTICA EXTRACTION, CRYSTALIZATION AND CHARACTERIZATION OF INULIN FROM YACON (Smallanthus sonchifolius (Poepp. & Endl.) FOR TO BE USED IN FOOD AND FARMACEUTIC INDUSTRY

OpenAIRE

OSCAR ARANGO BEDOYA; GINNA PAOLA CUARÁN; JUAN CAMILO FAJARDO

2008-01-01

La tendencia hacia la adopción de una alimentación sana y balanceada que incluya elementos naturales y benéficos es creciente. Se plantea el aprovechamiento del yacón (Smallanthus sonchifolius (Poepp. & Endl.)), planta silvestre de la región andina de Nariño, por su alto contenido de inulina, fructooligosacárido utilizado en la industria alimentaria y farmacéutica para la elaboración de edulcorantes para diabéticos y como fibra en alimentos refinados. Este estudio reporta la optimización del ...

Update of the BIPM.RI(II)-K1.Tc-99m comparison of activity measurements for the radionuclide {sup 99m}Tc to include new results for the LNE-LNHB and the NPL

Energy Technology Data Exchange (ETDEWEB)

Michotte, C.; Courte, S.; Ratel, G. [Bureau International des Poids et Mesures (BIPM), 92 - Sevres (France); Moune, M. [LNE-LNHB, Laboratoire national de metrologie et d' essais-Laboratoire National Henri Becquerel, Gif sur Yvette (France); Johansson, L.; Keightley, J. [National Physical Laboratory (NPL), Middlesex (United Kingdom)

2010-12-15

In 2007 and 2008 respectively, the Laboratoire national de metrologie et d'essais -Laboratoire national Henri Becquerel (LNE-LNHB), France and the National Physical Laboratory (NPL), UK, submitted ampoules with between 10 MBq and 130 MBq activity of {sup 99m}Tc to the International Reference System (SIR), to update their results in the BIPM.RI(II)-K1.Tc-99m comparison. Together with the four other national metrology institutes (NMI) that are participants, thirteen samples have been submitted since 1983. The key comparison reference value (KCRV) has been recalculated to include the latest primary results of the PTB and the LNE-LNB as this makes the evaluation more robust. The degrees of equivalence between each equivalent activity measured in the SIR are given in the form of a matrix for all six NMIs. A graphical presentation is also given. (authors)

Proteomic profiling of proteins associated with the rejuvenation of Sequoia sempervirens (D. Don Endl

Directory of Open Access Journals (Sweden)

Chen Yu-Ting

2010-12-01

Full Text Available Abstract Background Restoration of rooting competence is important for rejuvenation in Sequoia sempervirens (D. Don Endl and is achieved by repeatedly grafting Sequoia shoots after 16 and 30 years of cultivation in vitro. Results Mass spectrometry-based proteomic analysis revealed three proteins that differentially accumulated in different rejuvenation stages, including oxygen-evolving enhancer protein 2 (OEE2, glycine-rich RNA-binding protein (RNP, and a thaumatin-like protein. OEE2 was found to be phosphorylated and a phosphopeptide (YEDNFDGNSNVSVMVpTPpTDK was identified. Specifically, the protein levels of OEE2 increased as a result of grafting and displayed a higher abundance in plants during the juvenile and rejuvenated stages. Additionally, SsOEE2 displayed the highest expression levels in Sequoia shoots during the juvenile stage and less expression during the adult stage. The expression levels also steadily increased during grafting. Conclusion Our results indicate a positive correlation between the gene and protein expression patterns of SsOEE2 and the rejuvenation process, suggesting that this gene is involved in the rejuvenation of Sequoia sempervirens.

Cancer incidence in the Swedish leather tanning industry: updated findings 1958–99

Science.gov (United States)

Mikoczy, Z; Hagmar, L

2005-01-01

Aims: To assess how a 10 year extension of the follow up period affected cancer incidence in the Swedish leather tanning cohort. Methods: A cohort of 2027 tannery workers (of which 482 were women) who had been employed for at least one year between 1900 and 1989 at one of three Swedish leather tanneries, was established. The start of observation varied between 1958 and 1966 for the three plants. Through linkage with the Swedish Cancer Registry, incident cancer cases were recorded up to 1999. Cause specific expected cancer incidence was calculated for 1958–99 based on calendar year, sex, and five year age group specific incidence rates for the counties where the plants had been located. Altogether 56 022 person-years at risk were generated. Results: A total of 351 incident cancer cases were observed compared to 302 expected, which resulted in an increased standardised incidence ratio (SIR) of 1.16 (95% CI 1.04 to 1.29). An enhanced risk for prostate cancer was observed (SIR 1.44, 95% CI 1.10 to 1.86), mainly attributable to the later part of the observation period (1990–99). In this updated analysis the previously observed risk excess for soft tissue sarcomas was no longer significant (SIR 2.62, 95% CI 0.96 to 5.70). For multiple myelomas and sinonasal cancer the slight non-significant excesses remained, still based on very few cases. Conclusions: The increased risk for prostate cancer in the present study might be a chance finding, but is noteworthy, since it is in acccordance with the finding of increased SIR for prostate cancer among leather workers in another recent Swedish study. Moreover, excess risks for prostate cancer among farmers have been reported, indicating pesticides as possible causative agents. Leather tanners have also been exposed to pesticides. PMID:15961622

Encapsulado de Embriones Somáticos y Embriones Cigóticos para Obtención de Semillas Artificiales de Raulí (Nothofagus alpina (Poepp. & Endl.) Oerst.)

OpenAIRE

Cartes R, Priscila; Castellanos B, Hermes; Ríos L, Darcy; Sáez C, Katia; Spierccolli H, Scarlette; Sánchez O, Manuel

2009-01-01

Somatic and zygotic embryos from mature seeds of rauli-beech, Nothofagus alpina (Poepp. & Endl.) Oerst., were encapsulated in different artificial endosperms in order to generate a cover that fulfills the function of nourishment and protection of the embryos, facilitating their later germination. The content of sodium alginate varied by 4%, 3%, and 2%, as did the immersion time in calcium chloride (CaCl2), which acts as complexing agent. The artificial endosperm components of the Murashige an...

Radioanalytical prediction of radiative capture in 99Mo production via transmutation adiabatic resonance crossing by cyclotron

CERN Document Server

Khorshidi, Abdollah; Pazirandeh, Ali; Tenreiro, Claudio; Kadi, Yacine

2014-01-01

In this study, the transmutation adiabatic resonance crossing (TARC) concept was estimated in Mo-99 radioisotope production via radiative capture reaction in two designs. The TARC method was composed of moderating neutrons in lead or a composition of lead and water. Additionally, the target was surrounded by a moderator assembly and a graphite reflector district. Produced neutrons were investigated by (p,xn) interactions with 30 MeV and 300 mu A proton beam on tungsten, beryllium, and tantalum targets. The Mo-99 production yield was related to the moderator property, cross section, and sample positioning inside the distinct region of neutron storage as must be proper to achieve gains. Gathered thermal flux of neutrons can contribute to molybdenum isotope production. Moreover, the sample positioning to gain higher production yield was dependent on a greater flux in the length of thermal neutrons and region materials inside the moderator or reflector. When the sample radial distance from Be was 38 cm inside the...

Antimalarial, Anticancer, Antimicrobial Activities and Chemical Constituents of Essential Oil from the Aerial Parts of Cyperus kyllingia Endl.

Directory of Open Access Journals (Sweden)

Sorachai Khamsan

2011-01-01

Full Text Available The chemical constituents of the essential oil from Cyperus kyllingia Endl. were analyzed by a GC, GC-MS. Twenty-three compounds were identified, accounting for 93.75% of the total oil that consisted mainly of oxygenated sesquiterpenes (53.52%, particularly sesquiterpene hydrocarbons (38.97%, and carboxylic acid (1.26%. The most representative compounds were a -cadinol (19.32 %, caryophyllene oxide (12.17%, a -muurolol (11.58 %, a -humulene (9.85%, and a -atlantone (6.07%. The oil showed significant activities against Plasmodium falcipalum (K1, multi drug resistant strain and NCI-H187 (Small Cell Lung Cancer with the IC 50 values of 7.52 and 7.72 µg/mL, respectively. The oilexhibited highly active against Staphylococcus aureus ATCC25923 and moderately active against Escherichia coli ATCC25922, Pseudomonas aeruginosa ATCC27553, Aspergillus flavus and Candida albicans.

The Supply of Medical Radioisotopes. 2016 Medical Isotope Supply Review: 99Mo/99mTc Market Demand and Production Capacity Projection 2016-2021

International Nuclear Information System (INIS)

Charlton, Kevin; )

2016-03-01

Medical diagnostic imaging techniques using technetium-99m ( 99 mTc) account for approximately 80% of all nuclear medicine procedures, representing 30-40 million examinations Worldwide every year. Disruptions in the supply chain of these medical isotopes - which have half-lives of 66 hours for molybdenum-99 ( 99 Mo) and only 6 hours for 99m Tc, and thus must be produced continuously - can lead to cancellations or delays in important medical testing services. Supply reliability has been challenged over the past decade due to unexpected shutdowns and extended refurbishment periods at some of the 99 Mo-producing research reactors and processing facilities. These shutdowns have at times created conditions for extended global supply shortages (e.g. 2009-2010). At the request of its member countries, the Nuclear Energy Agency (NEA) became involved in global efforts to ensure a secure supply of 99 Mo/ 99m Tc. Since June 2009, the NEA and its High-level Group on the Security of Supply of Medical Radioisotopes (HLG-MR) have examined the causes of supply shortages and developed a policy approach, including principles and supporting recommendations to address those causes. The NEA has also reviewed the global 99 Mo supply situation periodically, to highlight periods of potential reduced supply and to underscore the case for implementing the HLG-MR policy approach in a timely and globally consistent manner. In 2012, the NEA released a 99 Mo supply and demand forecast up to 2030, identifying periods of potential low supply relative to demand. That 2012 forecast was updated with a report in 2014 that focused on the much shorter 2015-2020 period. That report was updated in 2015 with a report, '2015 Medical Isotope Supply Review: 99 Mo/ 99m Tc Market Demand and Production Capacity Projection 2015-2020' (NEA, 2015), which focused on the same period. This report updates the 2015 report, and focuses on the important 2016-2021 period. At the end of 2015, the OSIRIS reactor

Updated embrittlement trend curve for reactor pressure vessel steels

International Nuclear Information System (INIS)

Kirk, M.; Santos, C.; Eason, E.; Wright, J.; Odette, G.R.

2003-01-01

The reactor pressure vessels of commercial nuclear power plants are subject to embrittlement due to exposure to high energy neutrons from the core. Irradiation embrittlement of RPV belt-line materials is currently evaluated using US Regulatory Guide 1.99 Revision 2 (RG 1.99 Rev 2), which presents methods for estimating the Charpy transition temperature shift (ΔT30) at 30 ft-lb (41 J) and the drop in Charpy upper shelf energy (ΔUSE). A more recent embrittlement model, based on a broader database and more recent research results, is presented in NUREG/CR-6551. The objective of this paper is to describe the most recent update to the embrittlement model in NUREG/CR-6551, based upon additional data and increased understanding of embrittlement mechanisms. The updated ΔT30 and USE models include fluence, copper, nickel, phosphorous content, and product form; the ΔT30 model also includes coolant temperature, irradiation time (or flux), and a long-time term. The models were developed using multi-variable surface fitting techniques, understanding of the ΔT30 mechanisms, and engineering judgment. The updated ΔT30 model reduces scatter significantly relative to RG 1.99 Rev 2 on the currently available database for plates, forgings, and welds. This updated embrittlement trend curve will form the basis of revision 3 to Regulatory Guide 1.99. (author)

'99Mo/99mTc Generator Based on High Radionuclidic Pure Zirconium Molybdate Gel

International Nuclear Information System (INIS)

Amin, M.; Mostafa, M.; El-Amir, M.A.; El-Absy, M.A.; Mohamed, O.I.; Farag, A.B.

2014-01-01

99 Mo / 99 mTc radioisotope generator was prepared using in-situ precipitated zirconium molybdate chromatographic column. Zirconium molybdate gel matrix was synthesized by precipitation of neutron activation molybdenum-99 from its solution after variety purification processes to prevent contamination of the 99m Tc eluate with cross-contaminants. Greeter than 82.7 ± 0.4 % of the generated 99m Tc was immediately and reproducible eluted by passing 10 ml 0.9 % NaCl solution through the 1 g zirconium molybdate- 99 Mo column matrix at a flow rate of 0.5 ml / min and room temperature with high chemical, radionuclide ( ≥ 99.9 % 99m Tc) and radiochemical purity ( ≥ 97.7 % % as 99 mTcO 4 - ) with ph value suitable for medical uses.

Compensation of Cross-Contamination in Simultaneous 201Tl/99mTc Myocardial Perfusion SPECT Imaging

Directory of Open Access Journals (Sweden)

Faraz Kalantari

2009-12-01

Full Text Available Introduction: It is a common protocol to use 201Tl for the rest and 99mTc for the stress cardiac SPECT imaging. Theoretically, both types of imaging may be performed simultaneously using different energy windows for each radionuclide. However, a potential limitation is the cross-contamination of scattered photons from 99mTc and collimator X-rays into the 201Tl energy window. We used a middle energy window method to correct this cross-contamination. Material and Methods: Using NCAT, a typical software torso phantom was generated. An extremely thin line source of 99mTc activity was placed inside the cardiac region of the phantom and no activity in the other parts.  The SimSET Monte Carlo simulator was used to image the phantom in different energy windows. To find the relationship between projections in different energy windows, deconvolution theory was used. We investigated the ability of the suggested functions in three steps: Monte Carlo simulation, phantom experiment and clinical study. In the last step, SPECT images of eleven patients who had angiographic data were acquired in different energy windows. All of these images were compared by determining the contrast between a defect or left ventricle cavity and the myocardium. Results: We found a new 2D kernel which had an exponential pattern with a much higher center. This function was used for modeling 99mTc down scatter distribution from the middle window image. X-ray distribution in the 201Tl window was also modeled as the 99mTc photopeak image convolved by a Gaussian function. Significant improvements in the contrasts of the simultaneous dual 201Tl images were found in each step before and after reconstruction. In comparison with other similar methods, better results were acquired using our suggested functions. Conclusion: Our results showed contrast improvement in thallium images after correction, however, many other parameters should be evaluated for clinical approaches. There are many

Scatter and cross-talk correction for one-day acquisition of 123I-BMIPP and 99mtc-tetrofosmin myocardial SPECT.

Science.gov (United States)

Kaneta, Tomohiro; Kurihara, Hideyuki; Hakamatsuka, Takashi; Ito, Hiroshi; Maruoka, Shin; Fukuda, Hiroshi; Takahashi, Shoki; Yamada, Shogo

2004-12-01

123I-15-(p-iodophenyl)-3-(R,S)-methylpentadecanoic acid (BMIPP) and 99mTc-tetrofosmin (TET) are widely used for evaluation of myocardial fatty acid metabolism and perfusion, respectively. ECG-gated TET SPECT is also used for evaluation of myocardial wall motion. These tests are often performed on the same day to minimize both the time required and inconvenience to patients and medical staff. However, as 123I and 99mTc have similar emission energies (159 keV and 140 keV, respectively), it is necessary to consider not only scattered photons, but also primary photons of each radionuclide detected in the wrong window (cross-talk). In this study, we developed and evaluated the effectiveness of a new scatter and cross-talk correction imaging protocol. Fourteen patients with ischemic heart disease or heart failure (8 men and 6 women with a mean age of 69.4 yr, ranging from 45 to 94 yr) were enrolled in this study. In the routine one-day acquisition protocol, BMIPP SPECT was performed in the morning, with TET SPECT performed 4 h later. An additional SPECT was performed just before injection of TET with the energy window for 99mTc. These data correspond to the scatter and cross-talk factor of the next TET SPECT. The correction was performed by subtraction of the scatter and cross-talk factor from TET SPECT. Data are presented as means +/- S.E. Statistical analyses were performed using Wilcoxon's matched-pairs signed-ranks test, and p corrected total count was 26.0 +/- 5.3%. EDV and ESV after correction were significantly greater than those before correction (p = 0.019 and 0.016, respectively). After correction, EF was smaller than that before correction, but the difference was not significant. Perfusion scores (17 segments per heart) were significantly lower after as compared with those before correction (p correction revealed significant differences in EDV, ESV, and perfusion scores. These observations indicate that scatter and cross-talk correction is required for one

Decentralized Consistent Updates in SDN

KAUST Repository

Nguyen, Thanh Dang

2017-04-10

We present ez-Segway, a decentralized mechanism to consistently and quickly update the network state while preventing forwarding anomalies (loops and blackholes) and avoiding link congestion. In our design, the centralized SDN controller only pre-computes information needed by the switches during the update execution. This information is distributed to the switches, which use partial knowledge and direct message passing to efficiently realize the update. This separation of concerns has the key benefit of improving update performance as the communication and computation bottlenecks at the controller are removed. Our evaluations via network emulations and large-scale simulations demonstrate the efficiency of ez-Segway, which compared to a centralized approach, improves network update times by up to 45% and 57% at the median and the 99th percentile, respectively. A deployment of a system prototype in a real OpenFlow switch and an implementation in P4 demonstrate the feasibility and low overhead of implementing simple network update functionality within switches.

Antibacterial efficacy of Nisin, Pediocin 34 and Enterocin FH99 against Listeria monocytogenes and cross resistance of its bacteriocin resistant variants to common food preservatives.

Science.gov (United States)

Kaur, G; Singh, T P; Malik, R K

2013-01-01

Antilisterial efficiency of three bacteriocins, viz, Nisin, Pediocin 34 and Enterocin FH99 was tested individually and in combination against Listeria mononcytogenes ATCC 53135. A greater antibacterial effect was observed when the bacteriocins were combined in pairs, indicating that the use of more than one LAB bacteriocin in combination have a higher antibacterial action than when used individually. Variants of Listeria monocytogenes ATCC 53135 resistant to Nisin, Pediocin 34 and Enterocin FH99 were developed. Bacteriocin cross-resistance of wild type and their corresponding resistant variants were assessed and results showed that resistance to a bacteriocin may extend to other bacteriocins within the same class. Resistance to Pediocin 34 conferred cross resistance to Enterocin FH 99 but not to Nisin. Similarly resistance to Enterocin FH99 conferred cross resistance to Pediocin 34 but not to Nisin. Also, the sensitivity of Nisin, Pediocin 34 and Enterocin FH99 resistant variants of Listeria monocytogenes to low pH, salt, sodium nitrite, and potassium sorbate was assayed in broth and compared to the parental wild-type strain. The Nisin, Pediocin 34 and Enterocin FH99 resistant variants did not have intrinsic resistance to low pH, sodium chloride, potassium sorbate, or sodium nitrite. In no case were the bacteriocin resistant Listeria monocytogenes variants examined were more resistant to inhibitors than the parental strains.

Antibacterial efficacy of Nisin, Pediocin 34 and Enterocin FH99 against Listeria monocytogenes and cross resistance of its bacteriocin resistant variants to common food preservatives

Directory of Open Access Journals (Sweden)

G. Kaur

2013-01-01

Full Text Available Antilisterial efficiency of three bacteriocins, viz, Nisin, Pediocin 34 and Enterocin FH99 was tested individually and in combination against Listeria mononcytogenes ATCC 53135. A greater antibacterial effect was observed when the bacteriocins were combined in pairs, indicating that the use of more than one LAB bacteriocin in combination have a higher antibacterial action than when used individually. Variants of Listeria monocytogenes ATCC 53135 resistant to Nisin, Pediocin 34 and Enterocin FH99 were developed. Bacteriocin cross-resistance of wild type and their corresponding resistant variants were assessed and results showed that resistance to a bacteriocin may extend to other bacteriocins within the same class. Resistance to Pediocin 34 conferred cross resistance to Enterocin FH 99 but not to Nisin. Similarly resistance to Enterocin FH99 conferred cross resistance to Pediocin 34 but not to Nisin. Also, the sensitivity of Nisin, Pediocin 34 and Enterocin FH99 resistant variants of Listeria monocytogenes to low pH, salt, sodium nitrite, and potassium sorbate was assayed in broth and compared to the parental wild-type strain. The Nisin, Pediocin 34 and Enterocin FH99 resistant variants did not have intrinsic resistance to low pH, sodium chloride, potassium sorbate, or sodium nitrite. In no case were the bacteriocin resistant Listeria monocytogenes variants examined were more resistant to inhibitors than the parental strains.

V.S.O.P. (99/09) computer code system for reactor physics and fuel cycle simulation. Version 2009

Energy Technology Data Exchange (ETDEWEB)

Ruetten, H.J.; Haas, K.A.; Brockmann, H.; Ohlig, U.; Pohl, C.; Scherer, W.

2010-07-15

V.S.O.P. (99/ 09) represents the further development of V.S.O.P. (99/ 05). Compared to its precursor, the code system has been improved again in many details. The main motivation for this new code version was to update the basic nuclear libraries used by the code system. Thus, all cross section libraries involved in the code have now been based on ENDF/B-VII. V.S.O.P. is a computer code system for the comprehensive numerical simulation of the physics of thermal reactors. It implies the setup of the reactor and of the fuel element, processing of cross sections, neutron spectrum evaluation, neutron diffusion calculation in two or three dimensions, fuel burnup, fuel shuffling, reactor control, thermal hydraulics and fuel cycle costs. The thermal hydraulics part (steady state and time-dependent) is restricted to gas-cooled reactors and to two spatial dimensions. The code can simulate the reactor operation from the initial core towards the equilibrium core. This latest code version was developed and tested under the WINDOWS-XP - operating system. (orig.)

V.S.O.P. (99/09) computer code system for reactor physics and fuel cycle simulation. Version 2009

International Nuclear Information System (INIS)

Ruetten, H.J.; Haas, K.A.; Brockmann, H.; Ohlig, U.; Pohl, C.; Scherer, W.

2010-07-01

V.S.O.P. (99/ 09) represents the further development of V.S.O.P. (99/ 05). Compared to its precursor, the code system has been improved again in many details. The main motivation for this new code version was to update the basic nuclear libraries used by the code system. Thus, all cross section libraries involved in the code have now been based on ENDF/B-VII. V.S.O.P. is a computer code system for the comprehensive numerical simulation of the physics of thermal reactors. It implies the setup of the reactor and of the fuel element, processing of cross sections, neutron spectrum evaluation, neutron diffusion calculation in two or three dimensions, fuel burnup, fuel shuffling, reactor control, thermal hydraulics and fuel cycle costs. The thermal hydraulics part (steady state and time-dependent) is restricted to gas-cooled reactors and to two spatial dimensions. The code can simulate the reactor operation from the initial core towards the equilibrium core. This latest code version was developed and tested under the WINDOWS-XP - operating system. (orig.)

Actions needed to ensure a reliable supply of 99Mo and 99mTc?

International Nuclear Information System (INIS)

Cameron, R.; Peykov, P.

2014-01-01

The NEA established the High-level Group on the Security of Supply of Medical Radioisotopes (HLG-MR) to examine the causes of 99 Mo/ 99 mTc supply shortages in 2009. It undertook an economic analysis and determined that lack of economic sustainability in producing reactors was the major cause of the shortages. From that it developed a policy approach, including principles and supporting recommendations to address those causes. Since then it has looked at the way the supply chain has implemented these policy principles through initiating a self-assessment process, which revealed uneven application and lack of adherence to the key principle of full cost recovery. As part of the analysis, the NEA has also reviewed the global 99 Mo/ 99 mTc supply situation periodically, using the most up-to-date data from supply chain participants, to highlight periods of reduced supply and underscore the case for implementing the HLG-MR policy approach in a timely and globally-consistent manner. This current paper presents the preliminary results from an updated 99 Mo supply and demand forecast, focusing on the potentially critical 2015-2020 period, when two major 99 Mo producers (the NRU reactor in Canada and the OSIRIS reactor in France) are scheduled to cease 99 Mo irradiations. It concludes with a review of the effectiveness of the actions taken to date and indicates where further action is needed. (author)

Measurement of formation cross-section of 99Mo from the 98Mo(n,γ) and 100Mo(n,2n) reactions.

Science.gov (United States)

Badwar, Sylvia; Ghosh, Reetuparna; Lawriniang, Bioletty M; Vansola, Vibha; Sheela, Y S; Naik, Haladhara; Naik, Yeshwant; Suryanarayana, Saraswatula V; Jyrwa, Betylda; Ganesan, Srinivasan

2017-11-01

The formation cross-section of medical isotope 99 Mo from the 98 Mo(n,γ) reaction at the neutron energy of 0.025eV and from the 100 Mo(n,2n) reaction at the neutron energies of 11.9 and 15.75MeV have been determined by using activation and off-line γ-ray spectrometric technique. The thermal neutron energy of 0.025eV was used from the reactor critical facility at BARC, Mumbai, whereas the average neutron energies of 11.9 and 15.75MeV were generated using 7 Li(p,n) reaction in the Pelletron facility at TIFR, Mumbai. The experimentally determined cross-sections were compared with the evaluated nuclear data libraries of ENDF/B-VII.1, CENDL-3.1, JENDL-4.0 and JEFF-3.2 and are found to be in close agreement. The 100 Mo(n,2n) 99 Mo reaction cross-sections were also calculated theoretically by using TALYS-1.8 and EMPIRE-3.2 computer codes and compared with the experimental data. Copyright © 2017 Elsevier Ltd. All rights reserved.

Putting Ug99 on the map: An update on current and future monitoring

DEFF Research Database (Denmark)

Hodson, D P; Nazari, K; Park, R F

2011-01-01

Detection of stem rust race TTKSK (Ug99) from Uganda in 1998/99 highlighted not only the extremely high vulnerability of the global wheat crop to stem rust but also a lack of adequate global systems to monitor such a threat. Progress in the development and expansion of the Global Cereal Rust...... Monitoring System (GCRMS) is described. The current situation regarding the Ug99 lineage of races is outlined and the potential for expansion into important wheat areas is considered. The GCRMS has successfully tracked the spread and changes that are occurring within the Ug99 lineage and is now well...... capacity for race analysis is seen to be critical and integration of the Global Rust Reference Centre into the stem rust monitoring network is seen as a positive development. The current acute situation with severe epidemics of stripe rust in many countries indicates a clear need for more effective global...

Encapsulated Somatic Embryos and Zygotic Embryos for Obtaining Artificial Seeds of Rauli-Beech (Nothofagus alpina (Poepp. & Endl. Oerst. Encapsulado de Embriones Somáticos y Embriones Cigóticos para Obtención de Semillas Artificiales de Raulí (Nothofagus alpina (Poepp. & Endl. Oerst.

Directory of Open Access Journals (Sweden)

Priscila Cartes R

2009-03-01

Full Text Available Somatic and zygotic embryos from mature seeds of rauli-beech, Nothofagus alpina (Poepp. & Endl. Oerst., were encapsulated in different artificial endosperms in order to generate a cover that fulfills the function of nourishment and protection of the embryos, facilitating their later germination. The content of sodium alginate varied by 4%, 3%, and 2%, as did the immersion time in calcium chloride (CaCl2, which acts as complexing agent. The artificial endosperm components of the Murashige and Skoog medium (MS were added, supplemented with 0.5 mg L-1 indolacetic acid (IAA, 0.5 mg L-1 naphthaleneacetic acid (NAA, 2 mg L-1 6-benzylaminopurine (BAP and 30 g L-1 sucrose. The germinative behaviors of encapsulated somatic and zygotic embryos were evaluated after 4 wk. Comparing the percentages of germination reached by encapsulated somatic and zygotic embryos it was observed that they had similar germinative behavior according to the type of encapsulation applied. However, zygotic embryos substantially exceeded the germination levels reached by somatic embryos, 100% vs. 45% respectively.Embriones somáticos y cigóticos provenientes de semillas maduras de raulí, Nothofagus alpina (Poepp. & Endl. Oerst., se encapsularon en diferentes endospermas sintéticos con el fin de generar una cubierta que cumpla la función de nutrir y proteger al embrión para facilitar su posterior germinación. Se varió el contenido de alginato de sodio al 4%, 3% y 2% y el tiempo de inmersión en cloruro de calcio (CaCl2, el que actúa como agente acomplejante. Además, a la matriz artificial se adicionaron componentes del medio Murashige y Skoog (MS suplementado con: 0,5 mg L-1 de indolacetic acid (IAA, 0,5 mg L-1 de ácido naftalenacético (NAA, 2 mg L-1 de 6-bencilaminopurina (BAP y 30 gL-1 de sacarosa. Al cabo de 4 semanas el porcentaje de germinación de los embriones somáticos y cigóticos encapsulados tuvieron similar comportamiento germinativo según el tipo de

NADS - Nuclear and Atomic Data System

International Nuclear Information System (INIS)

McKinley, Michael S.; Beck, Bret; McNabb, Dennis

2005-01-01

We have developed NADS (Nuclear and Atomic Data System), a web-based graphical interface for viewing pointwise and grouped cross sections and distributions. Our implementation is a client / server model. The client is a Java applet that displays the graphical interface, which has interactive 2-D, 3-D, and 4-D plots and tables. The server, which can serve and perform computations of the data, has been implemented in Python using the FUDGE package developed by Bret Beck at LLNL. Computational capabilities include algebraic manipulation of nuclear evaluated data in databases such as LLNL's ENDL-99, ENDF/B-V, and ENDF/B-VI, as well as user data. Processed data used in LLNL's transport codes are accessible as well. NADS is available from http://nuclear.llnl.gov/

Intermediate Energy Activation File (IEAF-99)

International Nuclear Information System (INIS)

Korovin, Yu.; Konobeev, A.; Pereslavtsev, P.; Stankovskij, A.; Fischer, U.; Moellendorff, U. von

1999-01-01

Nuclear data library IEAF-99, elaborated to study processes of interactions of intermediate energy neutrons with materials in accelerator driven systems, is described. The library is intended for activation and transmutation studies for materials irradiated by neutrons. IEAF-99 contains evaluated neutron induced reaction cross sections at the energies 0-150 MeV for 665 stable and unstable nuclei from C to Po. Approximately 50,000 excitation functions are included in the library. The IEAF-99 data are written in the ENDF-6 format combining MF = 3,6 MT = 5 data recording. (author)

Review of Extraskeletal Activity on Tc-99m Methylene Diphosphonate Bone Scintigraphy and Value of Cross-Sectional and SPECT-CT Imaging Correlation.

Science.gov (United States)

Bermo, Mohammed; Behnia, Sanaz; Fair, Joanna; Miyaoka, Robert S; Elojeimy, Saeed

2017-07-31

Recognizing the different mechanisms and imaging appearance of extraskeletal Tc-99m methylene diphosphonate uptake enhances the diagnostic value of bone scan interpretation. In this article, we present a pictorial review of the different mechanisms of extraskeletal Tc-99m methylene diphosphonate uptake on bone scintigraphy including neoplastic, inflammatory, ischemic, traumatic, excretory, and iatrogenic. We also illustrate through case examples the added value of correlation with cross-sectional and single photon emission computed tomography and computed tomography imaging in localizing and characterizing challenging cases of extraskeletal uptake. Copyright © 2017 Elsevier Inc. All rights reserved.

Integral benchmark for the attenuation of 14 MeV neutrons passing through lead layers

International Nuclear Information System (INIS)

Antonov, S.; Vojkov, G.; Ilieva, K.; Jordanova, J.

1987-01-01

The attenuation has been studied of the total 14 MeV neutron flux passing through an iron collimator and directly located behind lead slabs with thicknesses 2.5, 5.0, 7.5, 10.0 and 12.5 cm. A comparison is made between the calculated data and results from a benchmark experiment. The experiment is analysed with an one-dimensional model based on ANISN-code and a tree-dimentional model based on MORSE-code (Monte Carlo method). The energy dependences of the cross-sections and neutron fluxes are represented by a 25-group approximation based on the SUPERTOG program and the files ENDL and ENDF/B-4. The mean deviation of MORSE calculated data from experimental ones is 6.4% for ENDL-data and 8.5% for EDDF-data. ANISN-calculated data show practically full coincidence with experimental ones both for ENDL and ENDF

Decentralized Consistent Network Updates in SDN with ez-Segway

KAUST Repository

Nguyen, Thanh Dang

2017-03-06

We present ez-Segway, a decentralized mechanism to consistently and quickly update the network state while preventing forwarding anomalies (loops and black-holes) and avoiding link congestion. In our design, the centralized SDN controller only pre-computes information needed by the switches during the update execution. This information is distributed to the switches, which use partial knowledge and direct message passing to efficiently realize the update. This separation of concerns has the key benefit of improving update performance as the communication and computation bottlenecks at the controller are removed. Our evaluations via network emulations and large-scale simulations demonstrate the efficiency of ez-Segway, which compared to a centralized approach, improves network update times by up to 45% and 57% at the median and the 99th percentile, respectively. A deployment of a system prototype in a real OpenFlow switch and an implementation in P4 demonstrate the feasibility and low overhead of implementing simple network update functionality within switches.

Water-quality and bottom-material characteristics of Cross Lake, Caddo Parish, Louisiana, 1997-99

Science.gov (United States)

McGee, Benton D.

2004-01-01

liter. Based on nitrogen to phosphorus ratios calculated for Cross Lake, median values for all water-quality sites were within the nitrogen-limited range (less than or equal to 5). Historical Trophic State Indexes for Cross Lake classified the lake as eutrophic. Recent (1998-99) Trophic State Indexes classify Cross Lake as mesotrophic-eutrophic, which might indicate a recution in eutrophication. Sedimentation traps indicate that Cross Lake is filling at an average rate of 0.41 inches per year. Concentrations of fecal-coliform and streptococci bacteria generally were low. Fecal coliform was detected in higher concentrations than fecal streptococci. High bacterial concentrations were measured shortly after rainfall-runoff events, possibly washing bacteria from surrounding areas into the lake.

Description of the ENDF-NJOY system for the generation of cross sections libraries

International Nuclear Information System (INIS)

Alonso V, G.

1991-01-01

The physics of nuclear reactors requires of a great number of data to be able to evaluate the different phenomena that happen in a nuclear reactor; these data are mainly the microscopic neutron cross sections, but it is also required of data of radioactive decay and of nuclear structure for a great number of materials as well as of the cross sections of the photons and the production of these for the neutron interaction. These data group in nuclear databases, being the main ones: ENDF Nuclear Evaluated File, ENDL Dates Nuclear Evaluated Library it Dates (of the Laboratory Lawrence Livermore). JENDL Japanese Nuclear Evaluated Library Dates. Soviet SOKRATOR Nuclear Evaluated KEDAF Nuclear Karlsruhe File Dates. JEF Join Evaluated File (coordinated by NEA Data Bank). The existent codes that execute neutron and photon calculations require libraries of data that are very different some of other and of the databases. Of here that it is required of a series of processing codes that use the database like enter and its generate a secondary library of cross sections, which is read as enter for a code of spectra generation. Generally average cross sections by group are obtained; this library is that it is used in the codes that execute neutron calculations. (Author)

Update of ENDF/B-V Mod 3 iron: neutron-producing reaction cross sections and energy-angle correlations

International Nuclear Information System (INIS)

Fu, C.Y.; Hetrick, D.M.

1986-07-01

An update of the ENDF/B-V Mod-3 evaluation for natural iron is described. The cross sections of (n,n') and (n,2n) reactions are revised. Energy-angle correlations in the secondary (n,n') neutrons are introduced in the ENDF/B-V formats. Anisotropic angular distributions are provided for the secondary neutrons in (n,2n), (n,np), and (n,nα) reactions. Revelant integral results, microscopic data, and nuclear model calculations that influence the revised results are summarized. 54 refs., 9 figs., 2 tabs

Development of Indian cross section data files for Th-232 and U-233 and integral validation studies

International Nuclear Information System (INIS)

Ganesan, S.

1988-01-01

This paper presents an overview of the tasks performed towards the development of Indian cross section data files for Th-232 and U-233. Discrepancies in various neutron induced reaction cross sections in various available evaluated data files have been obtained by processing the basic data into multigroup form and intercomparison of the latter. Interesting results of integral validation studies for capture, fission and (n,2n) cross sections for Th-232 by analyses of selected integral measurements are presented. In the resonance range, energy regions where significant differences in the calculated self-shielding factors for Th-232 occur have been identified by a comparison of self-shielded multigroup cross sections derived from two recent evaluated data files, viz., ENDF/B-V (Rev.2) and JENDL-2, for several dilutions and temperatures. For U-233, the three different basic data files ENDF/B-IV, JENDL-2 and ENDL-84 were intercompared. Interesting observations on the predictional capability of these files for the criticality of the spherical metal U-233 system are given. The current status of Indian data file is presented. (author) 62 ref

Updating systematic reviews: an international survey.

Directory of Open Access Journals (Sweden)

Chantelle Garritty

Full Text Available BACKGROUND: Systematic reviews (SRs should be up to date to maintain their importance in informing healthcare policy and practice. However, little guidance is available about when and how to update SRs. Moreover, the updating policies and practices of organizations that commission or produce SRs are unclear. METHODOLOGY/PRINCIPAL FINDINGS: The objective was to describe the updating practices and policies of agencies that sponsor or conduct SRs. An Internet-based survey was administered to a purposive non-random sample of 195 healthcare organizations within the international SR community. Survey results were analyzed using descriptive statistics. The completed response rate was 58% (n = 114 from across 26 countries with 70% (75/107 of participants identified as producers of SRs. Among responders, 79% (84/107 characterized the importance of updating as high or very-high and 57% (60/106 of organizations reported to have a formal policy for updating. However, only 29% (35/106 of organizations made reference to a written policy document. Several groups (62/105; 59% reported updating practices as irregular, and over half (53/103 of organizational respondents estimated that more than 50% of their respective SRs were likely out of date. Authors of the original SR (42/106; 40% were most often deemed responsible for ensuring SRs were current. Barriers to updating included resource constraints, reviewer motivation, lack of academic credit, and limited publishing formats. Most respondents (70/100; 70% indicated that they supported centralization of updating efforts across institutions or agencies. Furthermore, 84% (83/99 of respondents indicated they favoured the development of a central registry of SRs, analogous to efforts within the clinical trials community. CONCLUSIONS/SIGNIFICANCE: Most organizations that sponsor and/or carry out SRs consider updating important. Despite this recognition, updating practices are not regular, and many organizations lack

Tables and graphs of photon-interaction cross sections from 0.1 keV to 100 MeV derived from the LLL evaluated-nuclear-data library

International Nuclear Information System (INIS)

Plechaty, E.F.; Cullen, D.E.; Howerton, R.J.

1981-01-01

Energy-dependent evaluated photon interaction cross sections and related parameters are presented for elements H through Cf(Z = 1 to 98). Data are given over the energy range from 0.1 keV to 100 MeV. The related parameters include form factors and average energy deposits per collision (with and without fluorescence). Fluorescence information is given for all atomic shells that can emit a photon with a kinetic energy of 0.1 keV or more. In addition, the following macroscopic properties are given: total mean free path and energy deposit per centimeter. This information is derived from the Livermore Evaluated-Nuclear-Data Library (ENDL) as of October 1978

Tables and graphs of photon-interaction cross sections from 0.1 keV to 100 MeV derived from the LLL Evaluated-Nuclear-Data Library

International Nuclear Information System (INIS)

Plechaty, E.F.; Cullen, D.E.; Howerton, R.J.

1978-01-01

Energy-dependent evaluated photon interaction cross sections and related parameters are presented for elements H through Cf (Z = 1 to 98). Data are given over the energy range from 0.1 keV to 100 MeV. The related parameters include form factors and average energy deposits per collision (with and without fluorescence). Fluorescence information is given for all atomic shells that can emit a photon with a kinetic energy of 0.1 keV or more. In addition, the following macroscopic properties are given: total mean free path and energy deposit per centimeter. This information is derived from the Livermore Evaluated-Nuclear-Data Library (ENDL) as of October 1978

Evaluación químico bromatológica de las variedades Yurac Llajum, Gello Llajum y Yurac Checche de Smallanthus Sonchifolius (Poepp & Endl).H. Robinson (Yacón) procedente de Puno

OpenAIRE

Ramos Zapana, Rubén; Arias Arroyo, Gladys

2014-01-01

Las variedades Yurac llajum, Qello llajum y Yurac checche de la especie Smallanthus sonchifolius (Poepp & Endl) (Yacón), procedente de la provincia de Sandia del Departamento de Puno, se desarrollan entre 1500 a 3000 msnm. Conocidas como “yacón”, “yakuma”, “llaqón”, “llacun” o “llacuma” en quechua; en aymara “aricoma” o “aricuma“; en español “Yacón”, “Jacón”, “llacón”, “arboloco”, “Puhe”, “jicama”, “jíquima”, “jikima” o “jiquimilla”. Estas raíces tuberosas de sabor dulce y refrescante, de asp...

Measurement and Estimation of the 99Mo Production Yield by 100Mo(n,2n)99Mo

Science.gov (United States)

Minato, Futoshi; Tsukada, Kazuaki; Sato, Nozomi; Watanabe, Satoshi; Saeki, Hideya; Kawabata, Masako; Hashimoto, Shintaro; Nagai, Yasuki

2017-11-01

We, for the first time, measured the yield of 99Mo, the mother nuclide of 99mTc used in nuclear medicine diagnostic procedures, produced by the 100Mo(n,2n)99Mo reaction with accelerator neutrons. The neutrons with a continuous energy spectrum from the thermal energy up to about 40 MeV were provided by the C(d,n) reaction with 40 MeV deuteron beams. It was proved that the 99Mo yield agrees with that estimated by using the latest data on neutrons from the C(d,n) reaction and the evaluated cross section of the 100Mo(n,2n)99Mo reaction given in the Japanese Evaluated Nuclear Data Library. On the basis of the agreement, a systematic calculation was carried out to search for an optimum condition that enables us to produce as much 99Mo as possible with a good 99Mo/100Mo value from an economical point of view. The calculated 99Mo yield from a 150 g 100MoO3 sample indicated that about 30% of the demand for 99Mo in Japan can be met with a single accelerator capable of 40 MeV, 2 mA deuteron beams. Here, by referring to an existing 18F-fluorodeoxyglucose (FDG) distribution system we assumed that 99mTc radiopharmaceuticals formed after separating 99mTc from 99Mo can be delivered to hospitals from a radiopharmaceutical company within 6 h. The elution of 99mTc from 99Mo twice a day would meet about 50% of the demand for 99Mo.

The Supply of Medical Radioisotopes. 2015 Medical Isotope Supply Review: 99Mo/99mTc Market Demand and Production Capacity Projection 2015-2020

International Nuclear Information System (INIS)

Charlton, Kevin; )

2015-08-01

Medical diagnostic imaging techniques using technetium-99m ( 99m Tc) account for approximately 80% of all nuclear medicine procedures, representing 30-40 million examinations Worldwide every year. Disruptions in the supply chain of these medical isotopes - which have half-lives of 66 hours for molybdenum-99 ( 99 Mo) and only 6 hours for 99m Tc, and thus must be produced continuously - can lead to cancellations or delays in important medical testing services. Unfortunately, supply reliability has been challenged over the past decade due to unexpected shutdowns and extended refurbishment periods at some of the mostly ageing, 99 Mo-producing research reactors and processing facilities. These shutdowns have at times created conditions for extended global supply shortages (e.g. 2009-2010). At the request of its member countries, the Nuclear Energy Agency (NEA) became involved in global efforts to ensure a secure supply of 99 Mo/ 99m Tc. Since June 2009, the NEA and its High-level Group on the Security of Supply of Medical Radioisotopes (HLG-MR) have examined the causes of supply shortages and developed a policy approach, including principles and supporting recommendations to address those causes. The NEA has also reviewed the global 99 Mo supply situation periodically, using the most up-to-date data available from supply chain participants, to highlight periods of potential reduced supply and to underscore the case for implementing the HLG-MR policy approach in a timely and globally consistent manner. In 2012, the NEA released a M o supply and demand forecast up to 2030, identifying periods of potential low supply relative to demand. That 2012 forecast was updated with a report 'Medical Isotope Supply in the Future: Production Capacity and Demand Forecast for the 99 Mo/ 99m Tc Market 2015-2020' (NEA, 2014) in 2014 that focused on the much shorter 2015-2020 period. This report updates the 2014 report, and continues to focus on the potentially critical 2015

Effects of the pollution by petroleum on the tracheids along the stem of Podocarpus lambertii Klotzsch ex Endl., Podocarpaceae

Energy Technology Data Exchange (ETDEWEB)

Maranho, L.T.; Dziedzic, M. [Universidade Positivo (UP), Curitiba, PR (Brazil). Curso de Mestrado em Gestao Ambiental], email: maranho@unicenp.edu.br; Muniz, G.I.B.; Kuniyoshi, Y.S.; Galvao, F. [Universidade Federal do Parana (UFPR), Curitiba, PR (Brazil). Dept. de Ciencias Florestais

2009-07-01

Podocarpus lambertii Klotzsch ex Endl. (Podocarpaceae) is native and a member of the Pinophyta (Gymnosperm) of southern Brazil, locally known as 'pinheiro-bravo'. The present work aims to investigate the effects of petroleum on the tracheids dimensions. Wood samples from twenty individuals were studied along the stem, ten being exposed to pollution and ten used as a control set. The wood samples were collected from incisions at three levels: at the ground level, and one and two metres above the ground level. From these samples, sub-samples were selected at the border of the growth layers in the vascular cambium-medulla direction. The methodology followed that traditionally recommended for plant anatomy studies, with analyses done by light microscopy (Olympus - BX41) assisted by the software Image Pro-plus for measurements. Comparison of the individuals exposed to petroleum with the control set, showed that the length, diameter and cell wall width of the tracheids of the former were smaller, a trend which was statistically significant according to the Student's t-test. These traits were observed mainly on the tracheids of the last growth layer, corresponding to the year in which the individuals were exposed to petroleum. (author)

National Educators' Workshop. Update 1999: Standard Experiments in Engineering, Materials Science and Technology

Science.gov (United States)

Arrington, Ginger L. F. (Compiler); Gardner, James E. (Compiler); Jacobs, James A. (Compiler); Fillion, John E. (Compiler); Mallick, P. K. (Compiler)

2000-01-01

This document contains a collection of experiments presented and demonstrated at the National Educators' Workshop: Update 99, held at DaimlerChrysler, Auburn Hills, Michigan, from October 31 - November 3, 1999.

Simultaneous 99mTc and 123I dual-isotope brain striatal phantom single photon emission computed tomography: validation of 99mTc-TRODAT-1 and 123I-IBZM simultaneous dopamine system brain imaging.

Science.gov (United States)

Kao, Pan-Fu; Wey, Shiaw-Pyng; Yang, An-Shoei

2009-11-01

[2[[2-[[[3-(4-chlorophenyl)-8-methyl-8-azabicyclo[3,2,1]-oct-2-yl]-methyl](2-mercaptoethyl)-amino]ethyl]amino]ethanethiolato(3-)-N2,N2',S2,S2]oxo-[1R-exo-exo)])-[99mTc]-technetium (99mTc-TRODAT-1) and 123I-iodobenzamide (123I-IBZM) are radiotracers for brain dopamine pre- and postsynaptic neuron imaging. The purpose of this study was to evaluate imaging parameters and crossed energy interference using simultaneous single photon emission computed tomography (SPECT) 99mTc and 123I data acquisition. A five-compartment brain striatal phantom was filled with 99mTc and/or 123I radioactive solutions with different striatal-to-background ratios, ranging from 3:1 to 9:1. SPECT data were acquired with energy window settings of 15% for the centered window at 140 keV for 99mTc and a 10% asymmetric window at 159 keV for 123I. The experiments were carried out using either individual (99mTc or 123I only) or both radionuclides. The striatal-to-background ratios and energy crossed interference between 99mTc and 123I were calculated. The phantom SPECT images demonstrated that the energy crossed interferences from 123I to 99mTc, and vice versa, were 22 +/- 12.4% and 0.4 +/- 1.0%, respectively. A net interference of 7.1 +/- 4.0% for the counts in the 15% centered 99mTc window can be expected from 123I and a net interference of 1.6 +/- 3.3% for the counts in the 10% asymmetric 123I window was derived from 99mTc. The correlation of striatal-to-background ratios between single isotope and simultaneous dual-isotope was excellent (R2 = 0.99). The imaging parameters used in this simultaneous dualisotope SPECT imaging could be used in future clinical practice for imaging patients with movement disorders by using 99mTc-TRODAT-1 and 123I-IBZM. The striatal-to-background ratios were not affected by the crossed interference between 99mTc and 123I.

Simultaneous 99mTC and 123I Dual-Isotope Brain Striatal Phantom Single Photon Emission Computed Tomography: Validation of 99mTC-Trodat-1 and 123I-IBZM Simultaneous Dopamine System Brain Imaging

Directory of Open Access Journals (Sweden)

Pan-Fu Kao

2009-11-01

Full Text Available [2[[2-[[[3-(4-chlorophenyl-8-methyl-8-azabicyclo[3,2,1]-oct-2-yl]-methyl](2-mercaptoethylamino]ethyl]amino]ethanethiolato(3--N2,N2′,S2,S2]oxo-[1R-exo-exo]-[99mTc]-technetium (99mTc-TRODAT-1 and 123I-iodobenzamide (123I-IBZM are radiotracers for brain dopamine preand postsynaptic neuron imaging. The purpose of this study was to evaluate imaging parameters and crossed energy interference using simultaneous single photon emission computed tomography (SPECT 99mTc and 123I data acquisition. A five-compartment brain striatal phantom was filled with 99mTc and/or 123I radioactive solutions with different striatal-to-background ratios, ranging from 3:1 to 9:1. SPECT data were acquired with energy window settings of 15% for the centered window at 140 keV for 99mTc and a 10% asymmetric window at 159 keV for 123I. The experiments were carried out using either individual (99mTc or 123I only or both radionuclides. The striatal-to-background ratios and energy crossed interference between 99mTc and 123I were calculated. The phantom SPECT images demonstrated that the energy crossed interferences from 123I to 99mTc, and vice versa, were 22 ± 12.4% and 0.4 ± 1.0%, respectively. A net interference of 7.1 ± 4.0% for the counts in the 15% centered 99mTc window can be expected from 123I and a net interference of 1.6 ± 3.3% for the counts in the 10% asymmetric 123I window was derived from 99mTc. The correlation of striatal-to-background ratios between single isotope and simultaneous dual-isotope was excellent (R2 = 0.99. The imaging parameters used in this simultaneous dual-isotope SPECT imaging could be used in future clinical practice for imaging patients with movement disorders by using 99mTc-TRODAT-1 and 123I-IBZM. The striatal-to-background ratios were not affected by the crossed interference between 99mTc and 123I.

14 CFR 99.19-99.31 - [Reserved

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 2 2010-01-01 2010-01-01 false [Reserved] 99.19-99.31 Section 99.19-99.31 Aeronautics and Space FEDERAL AVIATION ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) AIR TRAFFIC AND GENERAL OPERATING RULES SECURITY CONTROL OF AIR TRAFFIC General §§ 99.19-99.31 [Reserved] ...

Nuclear data newsletter. No. 8

Energy Technology Data Exchange (ETDEWEB)

NONE

1985-03-01

This issue lists nuclear data libraries received by the IAEA Nuclear Data Section: ENDL-84; JENDL-2; IRDF-85; INDL/V; CENDL; and nuclear data handbooks. The libraries are concerned with neutron cross sections, neutron radiative capture, statistical properties of excited atomic nuclei, cross-section data for nuclear reactor analysis, thermal constants of fissile isotopes. A selection of new relevant documents is also listed.

Proton-fission for the accelerator production of Mo-99

International Nuclear Information System (INIS)

Lagunas-Solar, M.C.; Jungerman, J.A.; Castaneda, C.M.

1993-01-01

The production of Mo-99 (66.0 h) via de U-238(p,f) Mo-99 fission reaction is proposed as a non-reactor source of this essential precursor of 6.6-h Tc-99m, an isotope of wide use of diagnostic nuclear medicine applications. Measurements of the total excitation function for the U-238(p,f) reaction indicated a maximum and fairly constant cross section of 1.4 barns at > 30 MeV. Combining the advances of high-current (mA) H-accelerators with dual beam (dual target) operation, and assuming a 5% fission yield, estimates of Mo-99 reaches 5 to 14 Ci/h at 1 mA. The proton fission production of Mo-99 appears to more advantageous than the reactor produced via evaporation neutron-induced fission. An accelerator method could allow securing ample supply of Mo-99 independently of the current scarce reactor operation, while also simplifying the associated waste management problems as well as some of the environmental concerns

Synthesis and formulation of {sup 99m} Tc-ECD radiopharmaceutical; Sintesis y formulacion del radiofarmaco {sup 99m} Tc-ECD

Energy Technology Data Exchange (ETDEWEB)

Ocampo G, B E

1998-06-01

Nuclear medicine is a medical specialty which uses radioactive compounds (radionuclides) for diagnostic and therapeutic purposes. {sup 99m} Tc is the more common radionuclide used in many studies in nuclear medicine because its advantages: it has a photopeak of 140 KeV and a half-life of 6 hours; it can be eluted from a Molybdenum 99 generator, so radiopharmaceuticals can be prepared on site. Ethyl cysteine dimer (ECD) labelled with reduced Technetium 99m has been purposed recently as a promising radiopharmaceutical for brain perfusion imaging {sup 99m} Tc-ECD is a lipophilic neutral complex which cross the brain blood barrier and show high brain uptake. The objective of this work was synthesize and to design a freeze dried formulation for the instant preparation of {sup 99m} Tc-ECD complex useful for brain perfusion imaging. We obtained a freeze dried stable formulation for the preparation of {sup 99m} Tc-ECD kit with a radiochemical purity higher than 90 %, which fulfills with the quality control of radiopharmaceuticals. Furthermore, we developed analytic techniques for the determination of the different chemical compounds into the lyophilized kit. (Author).

EXTRACCIÓN, CRISTALIZACIÓN Y CARACTERIZACIÓN DE INULINA A PARTIR DE YACÓN (Smallanthus sonchifolius (Poepp. & Endl. PARA SU UTILIZACIÓN EN LA INDUSTRIA ALIMENTARIA Y FARMACÉUTICA EXTRACTION, CRYSTALIZATION AND CHARACTERIZATION OF INULIN FROM YACON (Smallanthus sonchifolius (Poepp. & Endl. FOR TO BE USED IN FOOD AND FARMACEUTIC INDUSTRY

Directory of Open Access Journals (Sweden)

OSCAR ARANGO BEDOYA

2008-12-01

Full Text Available La tendencia hacia la adopción de una alimentación sana y balanceada que incluya elementos naturales y benéficos es creciente. Se plantea el aprovechamiento del yacón (Smallanthus sonchifolius (Poepp. & Endl., planta silvestre de la región andina de Nariño, por su alto contenido de inulina, fructooligosacárido utilizado en la industria alimentaria y farmacéutica para la elaboración de edulcorantes para diabéticos y como fibra en alimentos refinados. Este estudio reporta la optimización del proceso de extracción sólido-líquido, con agua caliente, de inulina a partir de raíces de yacón. La cuantificación de inulina presente en el extracto se hizo a través de refractometría. Varias combinaciones de tiempo, temperatura y relación solvente-materia prima fueron analizadas empleando un diseño experimental compuesto 2³ más puntos estrella. Se alcanzó un rendimiento óptimo de 20.7% de inulina bajo unas condiciones de extracción de 23 min a 82.2°C y relación solvente-materia prima de 4.5 l/500 g. La técnica para la separación de los cristales a partir de la solución rica en inulina tuvo un rendimiento del 17.3% con relación al peso en fresco del material experimental. Los cristales fueron caracterizados bajo propiedades físicas, químicas y organolépticasThe tendency toward a healt and balanced feeding, wich include natural and beneficent elements is growing. Was stablished the use of yacon (Smallanthus sonchifolius (Poepp. & Endl., an uncultivated plant of the andina región in Nariño, wich for his high level of inulin, fructoligosaccharide use in the food and farmaceutic industry for the edulcorant manufacture for diabetics and as fiber in refined food. This estudy report the optimization of the solid-liquid extraction process, with hot water, of inulin provided by yacon root. The quantification of inulin in the extract is made through refractometry. Several combinations of time, temperature and solvent-raw material

Benchmarking of the 99-group ANSL-V library

International Nuclear Information System (INIS)

Wright, R.Q.; Ford, W.E. III; Greene, N.M.; Petrie, L.M.; Primm, R.T. III; Westfall, R.M.

1987-01-01

The purpose of this paper is to present thermal benchmark data testing results for the BAPL-1, TRX-1, and SEEP-1 lattices, using selected processed cross-sections from the ANSL-V 99-group library. 7 refs., 1 tab

Determination of 99Mo contamination in 99mTc elute obtained from 99Mo/99mTc- generator

International Nuclear Information System (INIS)

Momennezhad, M.; Zakavi, S. R.; Sadeghi, R.

2010-01-01

99m Tc is a widely used radioisotope in nuclear medicine centers which is obtained by elution from Mo-99/Tc-99m generators. Usually the generators are either supplied by the Iran Atomic Energy Agency or by private companies from foreign countries. In this study we have measured 99 Mo contamination in 99m Tc elute from different generators in a period of one year. Materials and Methods: The radionuclide impurity of the 99m Tc elute were studied in two types of radionuclide generators (A: produced in Iran and B: Imported from other country). In-vitro measurements were performed using dose calibrator. Direct measurements were made, using a standard canister at the time of milking of the generators and also in Subsequent hours after milking. Results: The results showed a mean of 99 Mo impurity in generators A and B to be 0.00932±0.0043 and 0.0170±0.0127 respectively. Although the results showed that the 99 Mo contamination in 99 mTc elute was lesser than the maximum accepted activity limit of 0.015%, the difference in these two types may reflect different methods of productions of generator, as well as the quality control procedures. Conclusion: The mean of 99 Mo contamination in generators produced in Iran Atomic Energy Organization was lesser than generators imported from foreign origin.

Minimizing Molybdenum 99 contamination in Technetium 99m Pertechnetate from the elution of 99Mo/ 99m Tc Generator

International Nuclear Information System (INIS)

Zakaria Ibrahim; Zulkifli Hashim; Bohari Yaacob

2011-01-01

Radioisotope Tc-99m is widely used for variety of nuclear medicine diagnostic procedures. For many commercial applications, it is prepared in a portable type generator. Nuclear Malaysia has been producing a dry type alumina chromatographic column generator utilizing fission Mo-99. This injectable Tc-99m must meet the British Pharmacopeia [1] product specification prior to be apply on patient. This paper provides a method to minimize the up to acceptable level Mo-99 in the final product. Purposely made pertechnetate contaminated with Mo-99 and re-eluate by using old generator. Excellent removal of Mo-99 impurity was achieved and more than 80 % of Tc-99m total activity was recovered. (author)

Spent 99Mo/99mTc generator as an economical source of 99Mo

International Nuclear Information System (INIS)

El-Kolaly, M.T.

1990-01-01

An improved method for utilization and purification of 99 Mo from spent 90 Mo/ 99m Tc generators has been described. After washing the generator with saline to remove the generated 99m Tc, followed by 2 mL 5 M NaOH containing a few drops of H 2 O 2 , the 99 Mo was quantitatively eluted from the generator with 5 mL 5 M NaOH. The alkaline eluate containing 99 Mo was contaminated with partially dissolved alumina. In the present method, an anion-exchange resin Dowex 1 x 8 column was used for purification of 99 Mo from the contaminating alumina. The resultant 99 Mo was of high purity and contained 3+ /mL 99 Mo solution, as estimated by atomic absorption. (author)

Feasibility study on mass production of (n,γ)99Mo

International Nuclear Information System (INIS)

Jun, Byung Jin; Tanimoto, Masataka; Kimura, Akihiro; Hori, Naohiko; Izumo, Hironobu; Tsuchiya, Kunihiko

2011-01-01

The world is currently suffering from a severe shortage of 99 Mo and various efforts have been given for its availability. The (n,γ) method is one of candidates for the alternative supply of 99 Mo. The only but critical shortage of (n,γ) 99 Mo is its extremely low specific activity, which gives inconveniency in the extraction of 99m Tc and is consequently converted to additional cost. Potential technologies which make the (n,γ) 99 Mo competitive by reducing the additional cost are already available. It is expected that verification of such technologies is much easy and cost effective compared to any other options known for the alternative 99 Mo production. Because Japan and Korea import all 99 Mo from long distance, the cost benefit of local (n,γ) 99 Mo production in these countries is especially large. If five high flux reactors in China, Japan and Korea are utilized for the cross backup supply of (n,γ) 99 Mo, stable availability of 99 Mo in the region can be secured. Therefore, it is necessary to evaluate its feasibility on (n,γ) 99 Mo production in the Asia region. In this report, we studied feasibility of the mass (n,γ) 99 Mo production from viewpoints of global and regional status of 99 Mo demand and supply, competitiveness with other production methods, requirements and flow of the 99 Mo, production capability, cost, convenience in usage, and alternative technologies to overcome its shortage. (author)

The relation between crossed cerebellar blood flow and severities of hemiplegia. A technetium-99m hexamethylpropylene amine oxine SPECT study using Patlak plot method

International Nuclear Information System (INIS)

Watanabe, Hiromi; Niwa, Naoki; Kanai, Masanori; Sasaki, Setuo.

1996-01-01

Crossed cerebellar diaschisis (CCD), decrease in crossed cerebellar blood flow (CCBF) (ml/100 g/min), is often observed in the cerebral blood flow imaging of hemiplegic patients. We studied the relations between severities of hemiplegia and degrees of CCD. Severities of hemiplegia were evaluated by Brunnstrom stages (Br. stage) of lower limbs. Degree of CCD was evaluated as CCBF and asymmetry index (ASI) (%) of CCBF, which were calculated from technetium- 99m hexamethylpropylene amine oxine ( 99m Tc HMPAO) SPECT study using Patlak plot method (Matsuda et al. 1992, 1993). We have studied twenty consecutive patients. The CCBF was significantly different between Br. stage II and IV (p=0.0357), III and IV (p<0.001) and III and V (p<0.001). ASI was significantly different between II and IV (p=0.0357), III and IV (p<0.001) and III and VI (p=0.0238). Both of CCBF and ASI of the group of II and III were significantly lower than those of the group of IV, V and VI (p=0.0033 for CCBF and p=0.0087 for ASI). We conclude that this study indicate a close correlation between the severities of hemplegia and the degrees of CCD. (author)

New measurement of excitation functions for (p,x) reactions on Mo-nat with special regard to the formation of Tc-95m, Tc96m+g, Tc-99m and Mo-99

Czech Academy of Sciences Publication Activity Database

Lebeda, Ondřej; Pruszynski, M.

2010-01-01

Roč. 68, č. 12 (2010), s. 2355-2365 ISSN 0969-8043 Institutional research plan: CEZ:AV0Z10480505 Keywords : Cross-sections * Tc-99m * Mo-99 Subject RIV: BG - Nuclear, Atomic and Molecular Physics, Colliders Impact factor: 0.999, year: 2010

40 CFR 86.1729-99-86.1733-99 - [Reserved

Science.gov (United States)

2010-07-01

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40 CFR 86.1736-99-86.1769-99 - [Reserved

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2010-07-01

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2010-07-01

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Successful labeling of 99mTc-MDP using 99mTc separated from 99Mo produced by 100Mo(n,2n)99Mo

International Nuclear Information System (INIS)

Nagai, Yasuki; Hatsukawa, Yuichi; Kin, Tadahiro; Hashimoto, Kazuyuki; Motoishi, Shoji; Konno, Chikara; Ochiai, Kentaro; Takakura, Kosuke; Sato, Yuichi; Sato, Norihito; Ohta, Akio; Yamabayashi, Hisamichi; Tanase, Masakazu; Fujisaki, Saburo; Kawauchi, Yukimasa; Teranaka, Tomoyuki; Takeuchi, Nobuhiro; Igarashi, Takashi

2011-01-01

We have for the first time succeeded in separating 99m Tc from a MoO 3 sample irradiated with accelerator neutrons free from any radioactive impurities and in formulating 99m Tc-methylene diphosphonate ( 99 mTc-MDP). 99 Mo, the mother nuclide of 99m Tc, was produced by the 100 Mo(n,2n) 99 Mo reaction using about 14 MeV neutrons provided by the 3 H(d,n) 4 He reaction at the Fusion Neutronics Source of Japan Atomic Energy Agency. The 99m Tc was separated from 99 Mo by sublimation and its radionuclide purity was confirmed to be higher than 99.99% by γ-spectroscopy. The labeling efficiency of 99m Tc-MDP was shown to be higher than 99% by thin-layer chromatography. These values exceed the United States Pharmacopeia requirements for a fission product, 99 Mo. Consequently, a 99m Tc radiopharmaceutical preparation formed by using the mentioned 99 Mo can be a promising substitute for the fission product 99 Mo, which is currently produced using a highly enriched uranium target in aging research reactors. A longstanding problem to ensure a reliable and constant supply of 99 Mo in Japan can be partially mitigated. (author)

On the effect of updated MCNP photon cross section data on the simulated response of the HPA TLD.

Science.gov (United States)

Eakins, Jonathan

2009-02-01

The relative response of the new Health Protection Agency thermoluminescence dosimeter (TLD) has been calculated for Narrow Series X-ray distribution and (137)Cs photon sources using the Monte Carlo code MCNP5, and the results compared with those obtained during its design stage using the predecessor code, MCNP4c2. The results agreed at intermediate energies (approximately 0.1 MeV to (137)Cs), but differed at low energies (<0.1 MeV) by up to approximately 10%. This disparity has been ascribed to differences in the default photon interaction data used by the two codes, and derives ultimately from the effect on absorbed dose of the recent updates to the photoelectric cross sections. The sources of these data have been reviewed.

Pullback and pushout crossed polymodules

Indian Academy of Sciences (India)

Crossed module; polygroup; crossed polymodule; action; pullback; pushout; fundamental relation. Mathematics Subject Classification. 13D99, 20N20, 18D35. 1. Introduction. Crossed module was defined by Whitehad in [21] and many have worked on this sub- ject. There are many examples of crossed module such as ...

Excitation functions of deuteron induced nuclear reactions on natMo up to 21 MeV. An alternative route for the production of 99mTc and 99Mo

International Nuclear Information System (INIS)

Sonck, M.; Hermanne, A.; Takacs, S.; Szelecsenyi, F.; Tarkanyi, F.

1999-01-01

Cross sections of deuteron induced nuclear reactions on natural molybdenum have been studied in the frame of a systematic investigation of charged particle induced nuclear reactions on metals for different applications. The excitation functions of 92m,95 Nb-, 93,94g,94m,95g,95m,96,99m Tc- and 99 Mo were measured up to 21 MeV deuteron energy by using stacked foil technique and activation method. The goal of this work was to study the production possibility of the medical important 94m,99m Tc- and 99 Mo-nuclides. Production of 99m Tc and 99 Mo is of importance for their use in nuclear medicine, whereas 94m Tc is of interest regarding quantification of kinetics of well-established 99m Tc-radiopharmaceuticals. The production possibilities of 99m Tc and 99 Mo above 20 MeV deuteron energies up to 50 MeV were estimated and was found that beside the proton induced reactions the deuteron induced reactions on enriched molybdenum target are very promising. (author)

Synthesis and formulation of 99m Tc-ECD radiopharmaceutical

International Nuclear Information System (INIS)

Ocampo G, B.E.

1998-01-01

Nuclear medicine is a medical specialty which uses radioactive compounds (radionuclides) for diagnostic and therapeutic purposes. 99m Tc is the more common radionuclide used in many studies in nuclear medicine because its advantages: it has a photopeak of 140 KeV and a half-life of 6 hours; it can be eluted from a Molybdenum 99 generator, so radiopharmaceuticals can be prepared on site. Ethyl cysteine dimer (ECD) labelled with reduced Technetium 99m has been purposed recently as a promising radiopharmaceutical for brain perfusion imaging 99m Tc-ECD is a lipophilic neutral complex which cross the brain blood barrier and show high brain uptake. The objective of this work was synthesize and to design a freeze dried formulation for the instant preparation of 99m Tc-ECD complex useful for brain perfusion imaging. We obtained a freeze dried stable formulation for the preparation of 99m Tc-ECD kit with a radiochemical purity higher than 90 %, which fulfills with the quality control of radiopharmaceuticals. Furthermore, we developed analytic techniques for the determination of the different chemical compounds into the lyophilized kit. (Author)

Evaluation by scintigraphic images of musculoskeletal infection with 99mTc ciprofloxacin

International Nuclear Information System (INIS)

Casacó, C.A.; Hernández, A.; Perera, A.; Prats, A.; Batista, J.F.; Torres, L.A.; Quesada, R.; Sánchez, Y.; Valladares, L.; Sánchez, E.L.; Marrero, L.O.; Mustelier, E.

2016-01-01

Introduction: Infectious diseases present high morbidity and mortality in all countries, especially in the third world. In Cuba between 2005 and 2014, approximately 1.3% of the total deaths were killed. Orthopedic infections are among the most common. The scintigraphic methods currently used are not able to discern between a septic focus and a sterile inflammation. Radiological methods detect a bone infection only when there is significant anatomical damage. Ciprofloxacin as a drug binds and inhibits topoisomerase II or bacterial gyrase DNA. Objective: to evaluate the efficacy of 99m Tc-ciprofloxacin in the detection of osteo-articular bacterial processes. Materials and Methods: An experimental, cross-sectional, cross-sectional study was conducted involving 258 patients with suspected osteoarticular infectious processes. The presence of the lesion and the quantification and intensity of uptake in the foci of infection in images with 99m Tc-MDP (3h post-administration) and 99m Tc-ciprofloxacin (1, 4 and 24h post-administration) were visually determined. Studies of 99m Tc-ciprofloxacin were compared with Culture / Biopsy results. Results: The germ that most frequently appears in infected osteo-articular sites is staphilococcusaureus. No adverse effects were detected in any of the subjects studied. Studies with 99m Tc-MDP allow delineating infected areas but are not specific. 99mTc-ciprofloxacin shows the sites of active osteo-articular bacterial infection and when it is fixed in a septic focus gives intense captures at both 4 and 24 hours. It exhibits a sensitivity similar to 99mTc-MDP, but a significantly higher specificity. Conclusions: Scintigraphic images with 99m Tc-ciprofloxacin show sites of active osteo-articular bacterial infection with a specificity significantly higher than 99m Tc-MDP. The microbiological and scintigraphic results were positive for sepsis in 122 patients out of 219 who were sampled.

Total Cross Sections at High Energies An update

CERN Document Server

Fazal-e-Aleem, M; Alam, Saeed; Qadee-Afzal, M

2002-01-01

Current and Future measurements for the total cross sections at E-811, PP2PP, CSM, FELIX and TOTEM have been analyzed using various models. In the light of this study an attempt has been made to focus on the behavior of total cross section at very high energies.

Effect of milking efficiency on Tc-99 content of Tc-99m derived from Tc-99m generators

International Nuclear Information System (INIS)

Bonnyman, J.

1983-01-01

Tc-99m obtained by separation from its parent Mo-99 always contains Tc-99 produced by decay of Tc-99m and Mo-99. Factors effecting the Tc-99/Tc-99m ratios are discussed. An HPLC method has been developed to measure the 99 TcO 4- content of sodium pertechnetate from generators with a detection limit of 0.9 ng Tc-99 for a 500 μl/ aliquot of TcO 4- -99m. First eluates of 10 chromatograph-ic generators gave Tc-99/Tc-99m ratios ranging from 3.5-46 ng Tc/mCi Tc-99m measured at the time of milking. The measurements indicate that Tc-99/Tc-99m ratios high enough to cause adverse labelling effects could be found in 'instant pertechnetate' and in the first eluate from Tc-99m generators for the activities normally used in radiopharmaceutical production

Production technologies for molybdenum-99 and technetium-99m

International Nuclear Information System (INIS)

1999-02-01

Technetium-99m (6.02 h) is the most widely used radioisotope in nuclear medicine, accounting for more than 80% of all diagnostic nuclear medicine procedures. It is almost exclusively produced from the decay of its parent 99 Mo. The present sources of 99 Mo are research reactors by using the (n,γ) nuclear reaction with natural Mo ( 98 Mo, ∼24%), resulting in inexpensive but low-specific activity 99 Mo, or by neutron-induced fission of 235 U, which results in expensive but high specific activity 99 Mo. This publication covers several aspects related to the production of 99 Mo and 99m Tc. The contributed papers reflect the current status of the technology and discuss potential alternative methodologies for the production of 99 Mo and 99m Tc for medical use. The first four papers address the technologies using nuclear reactors, including the description of a new method using an aqueous homogenous reactor core for production of fission 99 Mo and the latest development efforts to fabricate 235 U low enriched targets (LEU, 235 U). The next five papers discuss the potential of utilizing particle accelerators and assess the current status of the available nuclear data for the production of both, 99 Mo and 99m Tc with proton and deuteron beams. The last paper discusses a new technology based on gel system for the preparation of 99 Mo/ 99m Tc generators using low specific activity 99 Mo produced in research reactors by the neutron activation of natural and inexpensive molybdenum oxide targets. Each individual paper was indexed and abstracted

Update on Kramers-Kronig relation for proton

Energy Technology Data Exchange (ETDEWEB)

Gryniuk, Oleksii [JGU, Mainz (Germany); KNU, Kyiv (Ukraine); Hagelstein, Franziska; Pascalutsa, Vladimir [JGU, Mainz (Germany)

2015-07-01

New evaluation of the Baldin sum rule and forward Compton scattering amplitude, as well as higher order sum rules, was made with updated data for proton total photoabsorption cross-section. Stability of resulting values, comparison to previous evaluations and consequences of results for higher order sum rules are discussed.

ENDF/B-5 fission product cross section evaluations

International Nuclear Information System (INIS)

Schenter, R.E.; England, T.R.

1979-12-01

Cross section evaluations were made for the 196 fission product nuclides on the ENDF/B-5 data files. Most of the evaluations involve updating the capture cross sections of the important absorbers for fast and thermal reactor systems. This included updating thermal values, resonance integrals, resonance parameter sets, and fast capture cross sections. For the fast capture results generalized least-squares calculations were made with the computer code FERRET. Input for these cross section adjustments included nuclear models calculations and both integral and differential experimental data results. The differential cross sections and their uncertainties were obtained from the CSIRS library. Integral measurement results came from CFRMF and STEK Assemblies 500, 1000, 2000, 3000, 4000. Comparisons of these evaluations with recent capture measurements are shown. 15 figures, 10 tables

Report to the DOE Nuclear Data Committee, 1991

International Nuclear Information System (INIS)

Resler, D.A.; White, R.M.

1991-03-01

This document provides a discussion of charged-particle evaluations for applications; advanced modeling of reaction cross sections for light nuclei; thermonuclear data file (TDF) -- a processed file for thermonuclear applications; evaluation of (n,2n) reactions on isotopes of Y and Zr; extension of the LLNL evaluated nuclear database (ENDL) to 30 MeV; and calculated kerma values

ANITA-IEAF activation code package - updating of the decay and cross section data libraries and validation on the experimental data from the Karlsruhe Isochronous Cyclotron

Science.gov (United States)

Frisoni, Manuela

2017-09-01

ANITA-IEAF is an activation package (code and libraries) developed in the past in ENEA-Bologna in order to assess the activation of materials exposed to neutrons with energies greater than 20 MeV. An updated version of the ANITA-IEAF activation code package has been developed. It is suitable to be applied to the study of the irradiation effects on materials in facilities like the International Fusion Materials Irradiation Facility (IFMIF) and the DEMO Oriented Neutron Source (DONES), in which a considerable amount of neutrons with energies above 20 MeV is produced. The present paper summarizes the main characteristics of the updated version of ANITA-IEAF, able to use decay and cross section data based on more recent evaluated nuclear data libraries, i.e. the JEFF-3.1.1 Radioactive Decay Data Library and the EAF-2010 neutron activation cross section library. In this paper the validation effort related to the comparison between the code predictions and the activity measurements obtained from the Karlsruhe Isochronous Cyclotron is presented. In this integral experiment samples of two different steels, SS-316 and F82H, pure vanadium and a vanadium alloy, structural materials of interest in fusion technology, were activated in a neutron spectrum similar to the IFMIF neutron field.

An ORIGEN-2 update for PCs and mainframes

International Nuclear Information System (INIS)

Ludwig, S.B.

1992-01-01

This paper reports that an updated version of the ORIGEN2 code package has been prepared by Oak Ridge National Laboratory. ORIGEN2 is used extensively by the DOE office of Civilian Radioactive Waste Management (OCRWM) and its contractors to determine the characteristics of spent fuel and high-level radioactive waste due to irradiation, decay, and processing. Included in this update are revised ORIGEN2 cross-section libraries for standard- and extended-burnup PWRs and BWRs. This update also includes improvements to the ORIGEN2 computer code (designated as ORIGEN2, Version 2.1 8-1-91 release). This version of ORIGEN2 provides a single source code that may be executed on both mainframes and 80386 or 80486 PCs, effectively smashing the 640 KB barrier that limited previous PC implementations

Tumor affinity of technetium-99m labeled radiopharmaceuticals. II. Sup(99m)Tc-Sn-diphosphonate (sup(99m)Tc-EHDP), sup(99m)Tc-Sn-dimercaptosuccinic acid (sup(99m)Tc-DMSA), sup(99m)Tc-Sn-diethyl stilbestrol diphosphate (sup(99m)Tc-DSDP)

Energy Technology Data Exchange (ETDEWEB)

Itoh, K; Kobayashi, S; Hisada, K; Tonami, N [Kanazawa Univ. (Japan). School of Medicine; Ando, A

1976-10-01

The authors have examined the tumor affinity of various sup(99m)Tc-labelled radiopharmaceuticals to Ehrlich's tumor for the purpose of delineating human malignant neoplasm positively. The biologic distributions of sup(99m)Tc-Sn-diphosphonate (sup(99m)Tc-EHDP), sup(99m)Tc-Sn-dimercaptosuccinic acid (sup(99m)Tc-DMSA) and sup(99m)Tc-Sn-diethyl stilbestrol diphosphate (sup(99m)Tc-DSDP, sup(99m)Tc-Honvan) are included as the second report on the tumor affinity of Ehrlich-bearing mice. Tumor concentration of sup(99m)Tc-EHDP was lowest and the positive delineation of implanted tumor with sup(99m)Tc-EHDP was poorest in sequential images, though active accumulation in some soft tissues malignant neoplasms, breast cancer, and thyroid cancer, has been reported. Tumor concentration and the tumor-to-blood ratio of sup(99m)Tc-DMSA were not so high, contrary to our expectation that /sup 197/Hg-DMSA might show high tumor concentration and high tumor-to-blood ratio the same as /sup 197/Hg chlormerodrin of the renal scanning radiopharmaceuticals. Tumor concentration of sup(99m)Tc-DSDP was highest. The tumor-to-blood concentration ratio was lower than that of the above mentioned radiopharmaceuticals but the tumor-to-liver ratio and/or tumor-to-lung ratio was over 1.0 at the earlier time. Biologic distribution of sup(99m)Tc-DSDP was similar to that of /sup 32/P labeled DSDP. It is presumed that sup(99m)Tc is labeled at the phosphate ester of DSDP which is dephospholytated immediately by phospholylase in vivo following intravenous injection. Although it is not known precisely it may be assumed that the mechanism of accumulating sup(99m)Tc-DSDP in Ehrlich's tumor is related to the phospholylase activity in neoplasms.

Low-activity 124I-PET/low-dose CT versus 99mTc-pertechnetate planar scintigraphy or 99mTc-pertechnetate single-photon emission computed tomography of the thyroid: a pilot comparison.

Science.gov (United States)

Darr, Andreas M; Opfermann, Thomas; Niksch, Tobias; Driesch, Dominik; Marlowe, Robert J; Freesmeyer, Martin

2013-10-01

The standard thyroid functional imaging method, 99mTc-pertechnetate (99mTc-PT) planar scintigraphy, has technical drawbacks decreasing its sensitivity in detecting nodules or anatomical pathology. 124I-PET, lacking these disadvantages and allowing simultaneous CT, may have greater sensitivity for these purposes. We performed a blinded pilot comparison of 124I-PET(/CT) versus 99mTc-PT planar scintigraphy or its cross-sectional enhancement, 99mTc-PT single-photon emission CT (SPECT), in characterizing the thyroid gland with benign disease. Twenty-one consecutive adults with goiter underwent low-activity (1 MBq/0.027 mCi) 124I-PET/low-dose (30 mAs) CT, 99mTc-PT planar scintigraphy, and 99mTc-PT-SPECT. Endpoints included the numbers of “hot spots” with/without central photopenia and “cold spots” detected, the proportion of these lesions with morphological correlates, the mean volume and diameter of visualized nodules, and the number of cases of lobus pyramidalis or retrosternal thyroid tissue identified. 124I-PET detected significantly more “hot spots” with/without central photopenia (P < 0.001), significantly more nodules (P < 0.001), and more “cold spots” than did 99mTc-PT planar scintigraphy or 99mTc-PT-SPECT, including all lesions seen on the 99mTc-PT modalities. Ultrasonographic correlates were found for all nodules visualized on all 3 modalities and 92.5% of nodules seen only on 124I-PET. Nodules discernible only on 124I-PET had significantly smaller mean volume or diameter (P < 0.001) than did those visualized on 99mTc-PT planar scintigraphy or 99mTc-PT-SPECT. 124I-PET(/CT) identified significantly more patients with a lobus pyramidalis (P < 0.001) or retrosternal thyroid tissue (P < 0.05). 124I-PET(/CT) may provide superior imaging of benign thyroid disease compared to planar or cross-sectional 99mTc-PT scintigraphy.

Diversification of 99Mo/99mTc separation: non–fission reactor production of 99Mo as a strategy for enhancing 99mTc availability.

Science.gov (United States)

Pillai, Maroor R A; Dash, Ashutosh; Knapp, Furn F Russ

2015-01-01

This paper discusses the benefits of obtaining (99m)Tc from non-fission reactor-produced low-specific-activity (99)Mo. This scenario is based on establishing a diversified chain of facilities for the distribution of (99m)Tc separated from reactor-produced (99)Mo by (n,γ) activation of natural or enriched Mo. Such facilities have expected lower investments than required for the proposed chain of cyclotrons for the production of (99m)Tc. Facilities can receive and process reactor-irradiated Mo targets then used for extraction of (99m)Tc over a period of 2 wk, with 3 extractions on the same day. Estimates suggest that a center receiving 1.85 TBq (50 Ci) of (99)Mo once every 4 d can provide 1.48-3.33 TBq (40-90 Ci) of (99m)Tc daily. This model can use research reactors operating in the United States to supply current (99)Mo needs by applying natural (nat)Mo targets. (99)Mo production capacity can be enhanced by using (98)Mo-enriched targets. The proposed model reduces the loss of (99)Mo by decay and avoids proliferation as well as waste management issues associated with fission-produced (99)Mo.

WIMS Library updating

Energy Technology Data Exchange (ETDEWEB)

Ravnik, M; Trkov, A [Inst. Jozef Stefan, Ljubljana (Slovenia); Holubar, A [Ustav Jaderneho Vyzkumu CSKAE, Rez (Serbia and Montenegro)

1992-07-01

At the end of 1990 the WIMS Library Update Project (WLUP) has been initiated at the International Atomic Energy Agency. The project was organized as an international research project, coordinated at the J. Stefan Institute. Up to now, 22 laboratories from 19 countries joined the project. Phase 1 of the project, which included WIMS input optimization for five experimental benchmark lattices, has been completed. The work presented in this paper describes also the results of Phase 2 of the Project, in which the cross sections based on ENDF/B-IV evaluated nuclear data library have been processed. (author) [Slovenian] Konec 1990 se je na Mednarodni agenciji za atomsko energijo zacel projekt obnove knjiznice presekov programa WIMS (WIMS Library Updating Project, WLUP). V projektu sodeluje 22 laboratorijev iz 19 drzav, koordiniramo pa ga na Institutu Jozef Stefan. Doslej je koncana faza 1 tega projekta, ki obsega optimizacijo vhodnega modela programa WIMS za pet eksperimentalnih testnih problemov. Podani so tudi rezultati faze 2, v kateri so se procesirali preseki na osnovi ENDF/B-IV datoteke. (author)

Status of Tc-99m and 99Mo/99mTc generator production in Bangladesh

International Nuclear Information System (INIS)

Abedin, Md. Zainul; Haque, Md. Azizul; Ali, Md. Ramjan; Hossain, Md. Anwar; Razzaque, Md. Abdur; Yasmin, Lyzu; Waheed, M. Fatima; Akhter, Rabeya; Mondal, Rafiuddin

2007-01-01

Radioisotope Production Division (RIPD) produced instant technetium-99m by solvent extraction method for several years. On R and D basis, the division produced portable sterile Tc-99m sublimation generator by irradiating titanium molybdate in the reactor. The division produced (4/batch) from imported fission Mo-99 till June 2005. Since August 2005, as per demand of the government hospitals, the division have been producing 12-14 pieces of 15 GBq chromatographic 99m Tc-generators weekly by using the new generator production plant installed last year having online Mo-99 loading system with the of producing 50 generator per batch. Development of PZC and (n,γ) 99 Mo based generator holds potential in Bangladesh. (author)

Pharmaceutical grade sodium (99mTc) pertechnetate from 99Mo/99mTc-TCM-Autosolex generator

International Nuclear Information System (INIS)

Chattopadhyay, Sankha; Barua, Luna; Das, Sujata Saha

2014-01-01

Technetium-99m (T 1/2 = 6.02h; 140.51 keV (89%)) is the most useful radioisotope in diagnostic nuclear medicine. More than 80% of all diagnostic procedures done worldwide in nuclear medicine centre are performed with 99m Tc. Worldwide crisis of fission 99 Mo based generator in recent past had put the nuclear medicine fraternity in very harsh situation. In order to have an indigenous solution of this problem, we tried to develop a computer controlled semi automated 99 Mo/ 99m Tc generator using MEK solvent extraction technique, which utilizes abundantly available 99 Mo produced by (n,γ) reaction in BARC reactors. The aim of this work is to provide a more reliable, computer controlled module (TCM- AUTOSOLEX) for the recovery of pharmaceutical grade 99m Tc from low specific activity 99 Mo based on solvent extraction methodology

Human reliability assessment in a 99Mo/99mTc generator production facility using the standardized plant analysis risk-human (SPAR-H) technique.

Science.gov (United States)

Eyvazlou, Meysam; Dadashpour Ahangar, Ali; Rahimi, Azin; Davarpanah, Mohammad Reza; Sayyahi, Seyed Soheil; Mohebali, Mehdi

2018-02-13

Reducing human error is an important factor for enhancing safety protocols in various industries. Hence, analysis of the likelihood of human error in nuclear industries such as radiopharmaceutical production facilities has become more essential. This cross-sectional descriptive study was conducted to quantify the probability of human errors in a 99 Mo/ 99m Tc generator production facility in Iran. First, through expert interviews, the production process of the 99 Mo/ 99m Tc generator was analyzed using hierarchical task analysis (HTA). The standardized plant analysis risk-human (SPAR-H) method was then applied in order to calculate the probability of human error. Twenty tasks were determined using HTA. All of the eight performance shaping factors (PSF S ) were evaluated for the tasks. The mean probability of human error was 0.320. The highest and the lowest probability of human error in the 99 Mo/ 99m Tc generator production process, related to the 'loading the generator with the molybdenum solution' task and the 'generator elution' task, were 0.858 and 0.059, respectively. Required measures for reducing the human error probability (HEP) were suggested. These measures were derived from the level of PSF S that were evaluated in this study.

Endogenous Quantification of Abscisic Acid and Indole-3-Acetic Acid in Somatic and Zigotic Embryos of Nothofagus alpina (Poepp. & Endl. Oerst Cuantificación Endógena de Ácido Abscísico y Ácido Indol-3 Acético en Embriones Somáticos y Cigóticos de Nothofagus alpina (Poepp. & Endl. Oerst

Directory of Open Access Journals (Sweden)

Pricila Cartes Riquelme

2011-12-01

Full Text Available Abscisic acid (ABA and indole-3-acetic acid (IAA participate in the propagation of plants by somatic embryogenesis, causing polar structural differentiation of the embryo. The goal of the assay was to compare endogenous levels of ABA and IAA between somatic embryos (SE and zygotic embryos (ZE of Nothofagus alpina (Poepp. & Endl. Oerst. In this study, a somatic embryo maturation assay involving the addition of varying concentrations of exogenous ABA was performed on cotyledonary-stage of N. alpina. Furthermore, the endogenous levels of ABA and IAA were quantified in the immature ZE, the mature ZE, and the embryonic axis of a mature embryo of N. alpina. The current study utilized high performance liquid chromatography (HPLC for quantification. The maturation treatments performed did not present significant differences in the endogenous ABA levels in SE. However, significant differences did exist in levels of ABA and IAA between SE submitted to the different maturation treatments and mature ZE of N. alpina. The application of exogenous ABA to the culture medium increased endogenous ABA levels, therefore, increasing the number of germinated somatic embryos. Thus, the plant conversion process was also successfully completed in somatic embryos of N. alpina.El ácido abscísico (ABA y el ácido indol 3 acético (IAA participan en el proceso de propagación de plantas mediante embriogénesis somática, ya que permiten la diferenciación de la estructura polar del embrión, órganos y regiones meristemáticas de éste. En este estudio se llevó a cabo un ensayo de maduración de embriones somáticos en estado cotiledonar con la adición de diferentes concentraciones de ABA exógeno, además se determinaron niveles endógenos entre ZE inmaduro, ZE maduro, y eje embrionario aislado desde el embrión maduro para luego comparar niveles endógenos de ABA e IAA en embriones somáticos (SE y cigóticos (ZE de raulí, Nothofagus alpina (Poepp. & Endl. Oerst. La

Self-shielding models of MICROX-2 code: Review and updates

International Nuclear Information System (INIS)

Hou, J.; Choi, H.; Ivanov, K.N.

2014-01-01

Highlights: • The MICROX-2 code has been improved to expand its application to advanced reactors. • New fine-group cross section libraries based on ENDF/B-VII have been generated. • Resonance self-shielding and spatial self-shielding models have been improved. • The improvements were assessed by a series of benchmark calculations against MCNPX. - Abstract: The MICROX-2 is a transport theory code that solves for the neutron slowing-down and thermalization equations of a two-region lattice cell. The MICROX-2 code has been updated to expand its application to advanced reactor concepts and fuel cycle simulations, including generation of new fine-group cross section libraries based on ENDF/B-VII. In continuation of previous work, the MICROX-2 methods are reviewed and updated in this study, focusing on its resonance self-shielding and spatial self-shielding models for neutron spectrum calculations. The improvement of self-shielding method was assessed by a series of benchmark calculations against the Monte Carlo code, using homogeneous and heterogeneous pin cell models. The results have shown that the implementation of the updated self-shielding models is correct and the accuracy of physics calculation is improved. Compared to the existing models, the updates reduced the prediction error of the infinite multiplication factor by ∼0.1% and ∼0.2% for the homogeneous and heterogeneous pin cell models, respectively, considered in this study

WIMS Library updating

International Nuclear Information System (INIS)

Ravnik, M.; Trkov, A.; Holubar, A.

1992-01-01

At the end of 1990 the WIMS Library Update Project (WLUP) has been initiated at the International Atomic Energy Agency. The project was organized as an international research project, coordinated at the J. Stefan Institute. Up to now, 22 laboratories from 19 countries joined the project. Phase 1 of the project, which included WIMS input optimization for five experimental benchmark lattices, has been completed. The work presented in this paper describes also the results of Phase 2 of the Project, in which the cross sections based on ENDF/B-IV evaluated nuclear data library have been processed. (author) [sl

Accuracy of 99Molybdenum assays in /sup 99m/Technetium solutions

International Nuclear Information System (INIS)

Williams, C.C.; Kereiakes, J.G.; Grossman, L.W.

1981-01-01

A study was performed to determine the accuracy of 99 Mo measurements using three commercial dose calibrators with their 99 Mo assay shields. One 99 Mo assay shield allowed excessive penetration by the lower energy /sup 99m/Tc photons, resulting in the calibrator's falsely high interpretation of the activity of 99 Mo present in the high-activity /sup 99m/Tc eluates. All three calibrators performed adequately with a National Bureau of Standards 99 Mo standard in equilibrium with /sup 99m/Tc. By using low-activity aliquots of 99 Mo and /sup 99m/Tc, a low-level linearity test was performed. Only one of the calibrators was found to reflect accurately the activity of 99 Mo present under all conditions tested

A method for measuring light ion reaction cross-sections

International Nuclear Information System (INIS)

Carlson, R.F.; Ingemarsson, A.; Lantz, M.; Arendse, G.J.; Auce, A.; Cox, A.J.; Foertsch, S.V.; Jacobs, N.M.; Johansson, R.; Nyberg, J.; Peavy, J.; Renberg, P.-U.; Sundberg, O.; Stander, J.A.; Steyn, G.F.; Tibell, G.; Zorro, R.

2005-01-01

An experimental procedure for measuring reaction cross-sections of light ions in the energy range 20-50 MeV/nucleon, using a modified attenuation technique, is described. The detection method incorporates a forward detector that simultaneously measures the reaction cross-sections for five different sizes of the solid angle in steps from 99.1% to 99.8% of the total solid angle. The final reaction cross-section values are obtained by extrapolation to the full solid angle

A method for measuring light ion reaction cross sections

International Nuclear Information System (INIS)

Carlson, R.F.; Ingemarsson, A.; Lantz, M.

2005-03-01

An experimental procedure for measuring reaction cross sections of light ions in the energy range 20-50 MeV/nucleon, using a modified attenuation technique, is described. The detection method incorporates a forward detector that simultaneously measures the reaction cross sections for five different sizes of the solid angles in steps from 99.1 to 99.8% of the total solid angle. The final reaction cross section values are obtained by extrapolation to the full solid angle

Updating of the LEOPARD data library

International Nuclear Information System (INIS)

Henrique Claro, L.; Cunha Menezes Filho, A. da

1984-01-01

The LEOPARD library is being updated and tested for typical PWR unit cells with enrichments ranging from 1.0 to 4.1%(W/o) and H 2 O:U ratios varying from 1.0 to 10.0. A reasonably good agreement with experimental values for some spectral indices is obtained if the fission cross-section of 235 U is reduced by 0.6% in the thermal range and by 20% in the epithermal range, the epithermal capture cross-section for 235 U is increased by about 20% and the number of neutrons per fission in the thermal range of 235 U is increased by 0.8%. (author)

Study of methodologies for quality control of 99Mo used in 99Mo/99mTc generators

International Nuclear Information System (INIS)

Said, Daphne de Souza

2016-01-01

99m Tc is the most used radionuclide in nuclear medicine. In Brazil, the 99 Mo/ 99m Tc generators are exclusively produced by Radiopharmacy Center at IPEN-CNEN/ SP, by importing 99 Mo from different suppliers. 99 Mo (t 1/2 = 66 h) is a fission product of 235 U and it can have radionuclidic impurities that are prejudicial for human health. For safe use of generators, it is necessary to perform the evaluation of 99 Mo by quality control tests in order to assess if 99 Mo complies with the specifications. The European Pharmacopoeia (EP) presents a monograph for evaluation of the quality of the [ 99 Mo] solution as sodium molybdate,that is used as raw material for 99 Mo/ 99m Tc generators production, including specification parameters (identification, radiochemical purity and radionuclidic purity), analysis methods and limits. However, it has been observed difficulties on the execution and implementation of these methods by the generators producers, with a few literature about this subject, probably due to complexity of the proposed methods. In this work, many quality control parameters of 99 Mo described in the EP monograph were evaluated. Separation methods for 99M o from its radionuclidic impurities by solid phase extraction (SPE) and TLC were studied. After SPE separation, the quantification of metals by ICP-OES to evaluate the percentage of retention of Mo and the percentage of recovery of Ru, Te and Sr using different types of cartridges were proposed, replacing radiotracers use. It was observed that the specific type of SPE cartridge recommended by the EP for separation of 99 Mo presented low recoveries for Ru, compared to other available anion exchange SPE cartridges. 99 Mo samples from different worldwide suppliers were analyzed. It was observed that quantification of 103 Ru in 99 Mo samples with decay time higher than 4 weeks is possible. An alternative method for separation of 131 I from 99 Mo showed promising results by TLC. The quantification of beta and

Evaluated cross-section libraries and kerma factors for neutrons up to 100 MeV on 12C

International Nuclear Information System (INIS)

Chadwick, M.B.; Blann, M.; Cox, L.; Young, P.G.; Meigooni, A.

1995-01-01

A program is being carried out at Lawrence Livermore National Laboratory to develop high-energy evaluated nuclear data libraries for use in Monte Carlo simulations of cancer radiation therapy. In this report we describe evaluated cross sections and kerma factors for neutrons with incident energies up to 100 MeV on 12 C. The aim of this effort is to incorporate advanced nuclear physics modeling methods, with new experimental measurements, to generate cross section libraries needed for an accurate simulation of dose deposition in fast neutron therapy. The evaluated libraries are based mainly on nuclear model calculations, benchmarked to experimental measurements where they exist. We use the GNASH code system, which includes Hauser-Feshbach, preequilibrium, and direct reaction mechanisms. The libraries tabulate elastic and nonelastic cross sections, angle-energy correlated production spectra for light ejectiles with A≤and kinetic energies given to light ejectiles and heavy recoil fragments. The major steps involved in this effort are: (1) development and validation of nuclear models for incident energies up to 100 MeV; (2) collation of experimental measurements, including new results from Louvain-la-Nueve and Los Alamos; (3) extension of the Livermore ENDL formats for representing high-energy data; (4) calculation and evaluation of nuclear data; and (5) validation of the libraries. We describe the evaluations in detail, with particular emphasis on our new high-energy modeling developments. Our evaluations agree well with experimental measurements of integrated and differential cross sections. We compare our results with the recent ENDF/B-VI evaluation which extends up to 32 MeV

ZZ MCNPDATA, Standard Neutron, Photon and Electron Data Libraries for MCNP-4C and MCB1C

International Nuclear Information System (INIS)

2002-01-01

1 - Description: These cross-section libraries are released by the Diagnostics Applications Group, X-5, at Los Alamos National Laboratory for use with the MCNP Monte Carlo code package. This release includes all of the X-5 distributed neutron data libraries, the photon libraries MCPLIB1 and MCPLIB02, the electron libraries EL1 and EL03, an updated XSDIR file, and information files Readme.txt and Readme e ndf60.txt. This release is intended to completely replace previous RSICC releases DLC-105, DLC-181, and DLC-189 as well as the cross sections previously included with CCC-200/MCNP4A, and will be updated as new libraries become available. The README file provides information regarding each data library of this release. Additional documentation for some of the individual libraries and example SPECS files for use with MAKXSF are also provided. The XSDIR file is specific to this release and may not work with previous packages. Currently the neutron data library ENDF60 (based on ENDF/B-VI, up through and including release 2) is the default library for continuous-energy neutron transport. Additionally, the libraries MCPLIB02 and EL03 are the default libraries for photon and electron transport respectively. More information on the data libraries contained in this release is available in Appendix G of the MCNP4C manual. 2 - Description of program or function: ZZ-MCB-DLC200 contains the same cross section tables as the DLC-0200/03 package for the MCNP-4C code, except that the installation procedures are adapted to the MCB1C code system (NEA 1643/01). 3 - Application of the data: DLC-200/MCNPDATA is for use with Version 4C and later of the MCNP transport code. This data library provides a comprehensive set of cross sections for a wide range of radiation transport applications using the Monte Carlo code package CCC-700/MCNP4C. See Appendix G of the MCNP report LA-13709-M for information on the libraries and how to select specific nuclides for use in MCNP. 4 - Source and scope

Current status of production and supply of molybdenum-99 and 99Mo/99mTc generators in Indonesia

International Nuclear Information System (INIS)

Mutalib, A.

2003-01-01

Production of high-specific activity molybdenum-99 and 99 Mo/ 99m Tc Generators in Indonesia commenced when a new production facility supported by the presence of a 30 MW multipurpose reactor (RSG-GAS) was established in Serpong in 1990. This report describes the current production and supply of molybdenum-99m devoted mainly to fulfill the domestic demands in supplying 99 Mo/ 99m Tc Generators. Recent development on the use of LEU (Low Enriched Uranium) targets for replacing current HEU (High Enriched Uranium) targets in the production of 99 Mo will be reviewed briefly. (author)

Measurement of Mo-99 column activity in the evaluation of Mo-99/Tc-99m generator

International Nuclear Information System (INIS)

Kuster, Z.

1994-01-01

In order to calculate the real elution efficiency of Mo-99/Tc-99m generator the Mo-99 content on the column has to be previously determined. As found in this work, the external measurement of Mo-99-column activity by means of Geiger-Mueller counter is a simple, fast and reliable method. Generally, Mo-99-column is placed slightly out of the center of the generator; therefore the externally measured flux of photons (φ) is an angular-dependent function. If the thickness of the lead container is radially uniform, the flux measured at some distance from the generator (which is rotated in 2π/3 steps) is given by the equation φ = A (1 + Bcos (α-2π(i - 2)/3)) -1 , i=1,2 or 3 (Eq.1) where A is a numerical constant depending on the Mo-99-column activity, B is a numerical constant depending on the Mo-99- column position within the lead container, the angle α depends on the initial orientation of the generator. A total of 20 generator were studied. The measured Mo-99-column activities (Capintec dose calibrator) were in the range 13.1- 35.11 GBq. Contrary to the findings of Vinberg and Kristensen (Eur J Nucl Med 1/1976(219), values of A (Eq. 1) are in good correlation (r 2 =0.9794) with the measured Mo-99-column activities. (author)

Antibacterial efficacy of nisin, pediocin 34 and enterocin FH99 against L. monocytogenes, E. faecium and E. faecalis and bacteriocin cross resistance and antibiotic susceptibility of their bacteriocin resistant variants.

Science.gov (United States)

Kaur, Gurpreet; Singh, Tejinder Pal; Malik, Ravinder Kumar; Bhardwaj, Arun; De, Sachinandan

2014-02-01

The bacteriocin susceptibility of Listeria monocytogenes MTCC 657, Enterococcus faecium DSMZ 20477, E. faecium VRE, and E. faecalis ATCC 29212 and their corresponding bacteriocin resistant variants was assessed. The single and combined effect of nisin and pediocin 34 and enterocin FH99 bacteriocins produced by Pediococcus pentosaceus 34, and E. faecium FH99, respectively, was determined. Pediocin34 proved to be more effective in inhibiting L. monocytogenes MTCC 657. A greater antibacterial effect was observed against E. faecium DSMZ 20477 and E. faecium (VRE) when the a combination of nisin, pediocin 34 and enterocin FH99 were used whereas in case of L. monocytogenes MTCC 657 a combination of pediocin 34 and enterocin FH99 was more effective in reducing the survival of pathogen. Bacteriocin cross-resistance and the antibiotic susceptibility of wild type and their corresponding resistant variants were assessed and results showed that resistance to a bacteriocin may extend to other bacteriocins within the same class and also the acquired resistance to bacteriocins can modify the antibiotic susceptibility/resistance profile of the bacterial species used in the study. According to the hydrophobicity nisin resistant variant of L. monocytogenes was more hydrophobic (p enterocin FH99 resistant variants were less hydrophobic than the wild type strain. Nisin, pediocin 34 and enterocin FH99 resistant variants of E. faecium DSMZ 20477 and E. faecium VRE were less hydrophobic than their wild type counterparts. Nisin resistant E. faecalis ATCC 29212 was less hydrophobic than its wild type counterpart.

Soil-to-Plant Transfer Factors of {sup 99}Tc for Korean Major Upland Crops

Energy Technology Data Exchange (ETDEWEB)

Choi, Yong Ho; Lim, Kwang Muk; Jun, In; Keum, Dong Kwon [Korea Atomic Energy Reserach Institute, Daejeon (Korea, Republic of)

2011-12-15

In order to investigate the soil-to-plant transfer factor (TF) of {sup 99}Tc for Korean major upland crops (soybean, radish and Chinese cabbage), pot experiments were performed in a greenhouse. Soils were collected from four upland fields (two for soybean and two for radish and Chinese cabbage) around Gyeongju radioactive-waste disposal site. Three to four weeks before sowing, dried soils were mixed with a {sup 99}Tc solution and the mixtures were put into pots and irrigated. TF values were expressed as the ratios of the {sup 99}Tc concentrations in plants (Bq kg{sup -1}-dry or fresh) to those in soils (Bq kg{sup -1}-dry). There was no great difference in the TF value between soils. The TF values for soybean seeds were extremely lower than those for the straws, indicating a very low mobility of {sup 99}Tc to seeds. As representative TF values of{sup 99}Tc,1.8 X 10{sup -1}, 1.2 X 10{sup 1}, 3.2 X 10{sup 2} and 1.3 X 10{sup 2} (for dry plants), arithmetic means for two soils, were proposed for soybean seeds, radish roots, radish leaves and Chinese cabbage leaves, respectively. In the case of the vegetables, proposals for fresh plants were also made. The proposed values are not sufficiently representative so successive updates are needed.

Updated RENORM/MBR Predictions for Diffraction at the LHC

CERN Document Server

Goulianos, K

2015-01-01

Updated RENORM/MBR-model predictions of diffractive, total, and total-inelastic cross sections at the LHC are presented and compared with experimental results and predictions from other models. In addition, expectations for diffraction at the upcoming LHC run at √s = 13 TeV are discussed.

Quality assurance of Mo-99/Tc-99m radionuclide generators

Science.gov (United States)

Uzunov, Nikolay; Yordanova, Galina; Salim, Seniha; Stancheva, Natalya; Mineva, Vanya; Meléndez-Alafort, Laura; Rosato, Antonio

2018-03-01

Gamma-ray spectrometry analyses of the radionuclide content of eluate from two Mo-99/Tc-99m radionuclide generators POLTECHNET have been performed. The relative activities of 99Mo 103Ru and 131I radioisotopes with respect to the activity of 99mTc at different time intervals after the primary pertechnetate elution of the generators have been analyzed. The relative activities of the isotopes were determined and compared to the radionuclidic purity requirements for 99mTc.

Bone turnover markers are correlated with total skeletal uptake of 99mTc-methylene diphosphonate (99mTc-MDP)

International Nuclear Information System (INIS)

Lenora, Janaka; Norrgren, Kristina; Thorsson, Ola; Wollmer, Per; Obrant, Karl J; Ivaska, Kaisa K

2009-01-01

Skeletal uptake of 99m Tc labelled methylene diphosphonate ( 99m Tc-MDP) is used for producing images of pathological bone uptake due to its incorporation to the sites of active bone turnover. This study was done to validate bone turnover markers using total skeletal uptake (TSU) of 99m Tc-MDP. 22 postmenopausal women (52–80 years) volunteered to participate. Scintigraphy was performed by injecting 520 MBq of 99m Tc-MDP and taking whole body images after 3 minutes, and 5 hours. TSU was calculated from these two images by taking into account the urinary loss and soft tissue uptake. Bone turnover markers used were bone specific alkaline phosphatase (S-Bone ALP), three different assays for serum osteocalcin (OC), tartrate resistant acid phosphatase 5b (S-TRACP5b), serum C-terminal cross-linked telopeptides of type I collagen (S-CTX-I) and three assays for urinary osteocalcin (U-OC). The median TSU of 99m Tc-MDP was 23% of the administered activity. All bone turnover markers were significantly correlated with TSU with r-values from 0.52 (p = 0.013) to 0.90 (p < 0.001). The two resorption markers had numerically higher correlations (S-TRACP5b r = 0.90, S-CTX-I r = 0.80) than the formation markers (S-Total OC r = 0.72, S-Bone ALP r = 0.66), but the difference was not statistically significant. TSU did not correlate with age, weight, body mass index or bone mineral density. In conclusion, bone turnover markers are strongly correlated with total skeletal uptake of 99m Tc-MDP. There were no significant differences in correlations for bone formation and resorption markers. This should be due to the coupling between formation and resorption

Updated Covariance Processing Capabilities in the AMPX Code System

International Nuclear Information System (INIS)

Wiarda, Dorothea; Dunn, Michael E.

2007-01-01

A concerted effort is in progress within the nuclear data community to provide new cross-section covariance data evaluations to support sensitivity/uncertainty analyses of fissionable systems. The objective of this work is to update processing capabilities of the AMPX library to process the latest Evaluated Nuclear Data File (ENDF)/B formats to generate covariance data libraries for radiation transport software such as SCALE. The module PUFF-IV was updated to allow processing of new ENDF covariance formats in the resolved resonance region. In the resolved resonance region, covariance matrices are given in terms of resonance parameters, which need to be processed into covariance matrices with respect to the group-averaged cross-section data. The parameter covariance matrix can be quite large if the evaluation has many resonances. The PUFF-IV code has recently been used to process an evaluation of 235U, which was prepared in collaboration between Oak Ridge National Laboratory and Los Alamos National Laboratory.

Molybdenum-99/technetium-99M generators

International Nuclear Information System (INIS)

Morcos, N.A.; Bruno, G.A.; Haney, T.A.

1981-01-01

A 99 Mo/sup(99m)Tc generator is described which has an alumina support medium consisting of multiple beds of controlled pH and in which no bed has a pH value higher than the bed preceding it. It is claimed that by using this method low yield problems of such generators can be mitigated. (U.K.)

Generators of 99Mo-99mTc

International Nuclear Information System (INIS)

Robles, A.M.

1994-01-01

Between the radioisotopes family pairs we find the 99 Molibdenum - 99m technetium pairs. Such as isotope production,decay and chemical toxic, humid and dry generators,radiation protection handling practice and blinding had been sudied in this work.Tabs

Simultaneous 99mTC and 123I Dual-Isotope Brain Striatal Phantom Single Photon Emission Computed Tomography: Validation of 99mTC-Trodat-1 and 123I-IBZM Simultaneous Dopamine System Brain Imaging

OpenAIRE

Pan-Fu Kao; Shiaw-Pyng Wey; An-Shoei Yang

2009-01-01

[2[[2-[[[3-(4-chlorophenyl)-8-methyl-8-azabicyclo[3,2,1]-oct-2-yl]-methyl](2-mercaptoethyl)amino]ethyl]amino]ethanethiolato(3-)-N2,N2′,S2,S2]oxo-[1R-exo-exo)])-[99mTc]-technetium (99mTc-TRODAT-1) and 123I-iodobenzamide (123I-IBZM) are radiotracers for brain dopamine preand postsynaptic neuron imaging. The purpose of this study was to evaluate imaging parameters and crossed energy interference using simultaneous single photon emission computed tomography (SPECT) 99mTc and 123I data acquisition...

Development of 99Mo/99mTc Generator System for Production of Medical Radionuclide 99mTc using a Neutron-activated 99Mo and Zirconium Based Material (ZBM as its Adsorbent

Directory of Open Access Journals (Sweden)

I. Saptiama

2016-12-01

Full Text Available Molybdenum produced from fission of U-235 is the most desirable precursor for 99Mo/99mTc generator system as it is non-carrier added and has high specific activity. However, in the last decade there has been short supply of 99Mo due to several constrains. Therefore, there have been many works performed for development of 99Mo/99mTc generator system using 99Mo which is not produced from either LEU or HEU. This report deals with development of 99Mo/99mTc generator system where zirconium-based material (ZBM is used as adsorbent of neutron-activated 99Mo. The system was prepared by firstly irradiating natural Mo in the G. A. Siwabessy reactor to produce neutron-activated 99Mo. The target was dissolved in NaOH 4N and then neutralized with 12 M HCl. The 99Mo solution was then mixed with a certain amount of ZBM followed by heating at 90°C for three hours to allow the 99Mo adsorbed on ZBM. The 99Mo-ZBM (9.36 GBq of 99Mo was Mo/ 4.2 g ZBM was packed on a fritz-glass column. This column was then fitted serially with an alumina column for trapping 99Mo breakthrough. The columns were then eluted daily with saline solution for up to one week. The yield of 99mTc was found to be between 53.7 – 74% (n= 5. All 99mTc eluates were clear solutions with pH of 5. Breakthrough of 99Mo in 99mTc eluates was found to be 0.031 ± 0.019 μCi 99Mo/ mCi 99mTc (n= 5 which was less than the maximum activity of 99Mo allowed in 99mTc solution ( 99%. Radiolabeling of this 99mTc towards methylene diphosphonate (MDP kit gave a radiolabelling efficiency of 99%. In summary, a new 99Mo/99mTc generator system that used neutron-activated 99Mo and ZBM as its adsorbent has been successfully prepared. The 99mTc produced from this new 99Mo/99mTc generator system attained the quality of 99mTc required for medical purposes.

Sapwood Amount and its Predictive Equations for Young Hinoki Cypress (Chamaecyparis obtusa) Trees

OpenAIRE

ADU-BREDU, Stephen; HAGIHARA, Akio; 萩原, 秋男

1996-01-01

Sapwood, which is peripheral to heartwood in tree trunks, serves as a water conduction and storage organ, and energy is needed to maintain the living ray parenchyma cells. The sapwood amount in hinoki cypress (Chamaecyparis obtusa (Sieb. et Zucc.) Endl.) was examined in relation to tree size on the basis of 14 sampled trees. The sapwood cross-sectional area was related to the over-bark stem cross-sectional area by a generalized allometric function, with an asymptotic value of 212.4 c㎡. The sa...

Compilation of cross-sections. Pt. 1

International Nuclear Information System (INIS)

Flaminio, V.; Moorhead, W.G.; Morrison, D.R.O.; Rivoire, N.

1983-01-01

A compilation of integral cross-sections for hadronic reactions is presented. This is an updated version of CERN/HERA 79-1, 79-2, 79-3. It contains all data published up to the beginning of 1982, but some more recent data have also been included. Plots of the cross-sections versus incident laboratory momentum are also given. (orig.)

The new 99mTc myocardial perfusion imaging agents: 99mTc-sestamibi and 99mTc-teboroxime

International Nuclear Information System (INIS)

Berman, D.S.; Kiat, H.; Maddahi, J.

1991-01-01

The two new 99m (99mTc) labeled myocardial perfusion agents, 99mTc-Sestamibi and 99mTc-Teboroxime, are now available for routine clinical application. Both agents allow assessment of ejection fraction by the first-pass technique at rest or during exercise, thus providing additional information not available with thallium-201. 99mTc-Sestamibi has long myocardial residence time, as well as adequate myocardial extraction, providing images of higher count density and superior quality compared with thallium-201. 99mTc-Teboroxime has excellent myocardial uptake characteristics but is cleared very rapidly from the myocardium. Both tracers have shown results similar to those obtained with thallium-201 for detection of coronary artery disease and the assessment of defect reversibility. 99mTc-Sestamibi studies using the rest/stress imaging sequence can be accomplished in approximately 5 hours; studies using dual-isotope imaging (rest thallium-201 and stress 99mTc-Sestamibi injection) can be completed in 1 to 2 hours. Gated stress images can be performed with 99mTc-Sestamibi, providing simultaneous information of myocardial perfusion at stress and resting wall motion or thickening and allowing rapid differentiation of ischemic from infarcted tissue. Because of its slow myocardial clearance and absence of redistribution, 99mTc-Sestamibi allows uncoupling of the time of injection from the time of imaging and thus can be valuable in the evaluation of acute myocardial infarction and outcome of thrombolytic therapy. With 99mTc-Teboroxime, rapid serial studies are feasible. Pharmacologic stress and rest studies with 99mTc-Teboroxime single photon emission computed tomography potentially can be completed in under 30 minutes. 73 references

ROSFOND based heating-damage cross sections sub-library: Preliminary uncertainty assessment

International Nuclear Information System (INIS)

Sinitsa, V.V.

2016-01-01

The accuracy of radiation damage calculations for the most important LWR component, the reactor pressure vessel (RPV), directly linked with the RPV End-of-Life (EoL) prediction which is in its turn connected with fundamental nuclear safety aspects and relevant economic impacts. In this connection, for nearly ten years the ENEA-Bologna Nuclear Data Group conducts the nuclear data processing and validation activities addressed to update the specialized broad-group coupled neutron/photon working cross section libraries for shielding and radiation damage calculations through NJOY and Bologna revised version of SCAMPI data processing systems. A number of working group-wise data libraries has been prepared and transferred to the ENEA Data Bank for dissemination. Several years ago the NRC ”Kurchatov Institute” has reset the GRUCON project, originally designed to provide group constants for fast nuclear reactor calculations [12], with aim to expand its application area and to use in the WWER safety tasks, in particular, in the RPV radiation damage analyses. By means of updated GRUCON and NJOY-99 processing codes, and calculation procedure, developed in the NDG of ENEA Bologna, a sample of kerma&damage energy point-wise data sub-libraries from different evaluated data libraries has been generated. On the base of this sample, the quantitative assessment of kerma/dpa data precision in the RPV calculations is obtained

99Mo-99mTc production development by (n, γ) reaction

International Nuclear Information System (INIS)

Izumo, Hironobu; Nishikata, Kaori; Kimura, Akihiro; Tanimoto, Masataka; Tsuchiya, Kunihiko; Ishihara, Masahiro; Kaminaga, Masanori

2012-01-01

The renewed JMTR will be started from the later half of JFY2012, and it is expected to various fields. Supply of 99 Mo in Japan depends only on imports from foreign countries. JAEA has a plan to produce 99 Mo, a parent nuclide of 99m Tc. JMTR will contribute to produce 99 Mo by (n, r) method as one of effective uses of the JMTR. In this paper, outline of the technical study items for production method of 99 Mo- 99m Tc in JMTR will be described. (author)

CAREN-4, ENDF/B Utility, Discontinuity Check at Resonance Region Boundary. CHECK-4, ENDF/B Utility, Structure Consistency Check and Format Check. CRECT, ENDF/B Utility, Data Correlation and Data Update. DICT-4, ENDF/B Utility, Section Table of Contents Generator. LISTF-4, ENDF/B Utility, Data Listing. RIGEL-4, ENDF/B Utility, Data Retrieval, BCD to BIN Conversion. SUMUP-4, ENDF/B Utility, Partial Cross-Sections Sum Check Against Tot Cross-Sections

Energy Technology Data Exchange (ETDEWEB)

NONE

1975-08-01

Description of problem or function: These programs are updated versions of ENDF/B checking, retrieval, and display codes capable of processing the Version-IV data files. RIGEL4 retrieves ENDF/B data and changes mode (BCD-BIN) or arrangement. Updated version processes decay data (mf=1, mt=457) and error files. CHECK4 checks the structure, consistency, and formats of ENDF data files. Updated version recognizes newly defined mt and mf numbers, checks mt=457 and the formats of the error files, contains RSIC photon file changes. SUMUP4 checks whether partial cross sections add up to the total. Updated version flags grid points present in the partial cross section, absent in the total. LISTF4 produces interpreted listings of ENDF/B data. Updated version lists mt=457, skips over error files, contains minor corrections. PLOTF4 produces plots of ENDF/B data. Updated version plots mt=457, skips over error files, contains minor corrections. RESEND processes ENDF materials with resonance parameters into a pointwise form. Capability of processing Adler-Adler parameters added. CRECT corrects ENDF/B data files. DICT4 generates a section table of contents (dictionary) for ENDF/B materials. CAREN4 tests for discontinuities across the limits of resonance ranges of an ENDF/B material. Updated version contains minor corrections.

A modified {sup 99} Mo- {sup 99} Tc generator on Zirconium molybdo- phosphate-{sup 99} Mo gel. Vol. 3

Energy Technology Data Exchange (ETDEWEB)

El-Kolaly, M T; Talaat, H [Labelled Compounds Department, Cairo (Egypt); Botros, N [Radioistspe and Generator Department, Radioisotope Production and Sealed Source Division, Hot Laboratories Center, Atomic Energy Authority, Cairo (Egypt)

1996-03-01

A modified {sup 99} Mo - {sup 99} Tc gel generator is described. The new generator is based on the use of zirconium molybdophosphate - {sup 99} Mo gel in which {sup 99} Mo chemically combined in the gel structure, where {sup 99m}Tc can be easily eluted with distilled water or saline. The gel was prepared via chemical reaction between zirconyl chloride and molybdophosphate - {sup 99} Mo solution. The PH of the reaction mixture was adjusted with NaOH. Different gels have been prepared by varying the molar ratio of Mo:Zr:p. The PH and time of digeston on complete gel formation was also investigated in order to optimize the condition of gel preparation. Molybdophosphate {sup 32} P solution was used to determine the phosphorous content in the gel and in the {sup 99m}Tc eluate. The temperature and time of drying of the gel and their effect on {sup 99m}Tc elution efficiency were also studied. From the data obtained, the optimum conditions for routine production of {sup 99} Mo - {sup 99m}Tc generator are presented and discussed. 2 figs., 6 tabs.

Concentration of sup(99m)Tc from the eluate of 99Mo-sup(99m)Tc generators

International Nuclear Information System (INIS)

Saucedo, T.; Mora, M.; Fraga de Suarez, A.H.; Mitta, A.E.A.

1976-04-01

A method is described to concentrate sup(99m)Tc solutions, originated in 99 Mo-sup(99m)Tc generators, independent of its age. The techniques of preparation of the different radiopharmaceuticals used in nuclear medicine are also described. (author) [es

Problems in clinical practice of domestic supply of 99Mo/99mTc. Considerations on the domestic production of 99Mo/99mTc

International Nuclear Information System (INIS)

Yamabayashi, Hisamichi

2012-01-01

At present, a bulky import product, 99 Mo supplied in Japan is produced by a nuclear fission method which enables to produce a generator system with no need of commercially preparing 99m Tc-labeled radiopharmaceuticals due to its high specific activity. However its usage of enriched uranium target leads to avoiding the fission method from the option of domestic production. In order to secure the domestic supply of 99 Mo/ 99m Tc, the neutron activation method, aiming to meet about 20% of domestic demand, is under development along with the re-start program of JMTR. Development of various production methods using accelerators are also in progress. In those non-fission methods with reactors or accelerators, rapid and effective procedures for concentration and refinement of 99m Tc solution eluted from 99 Mo of low specific activity are the subjects to be considered for attaining the stable labeling performances. (author)

Cross-Talk in Comp Theory: A Reader. Second Edition, Revised and Updated.

Science.gov (United States)

Villanueva, Victor, Ed.

This revised and updated resource contains a total of 43 essays that serve to initiate graduate students and more experienced teachers into the theories that inform composition studies. Under Section One--The Givens in Our Conversations: The Writing Process--are these essays: "Teach Writing as a Process Not Product" (Donald M. Murray);…

Labelled Preformed liposomes with 99MTC-DTPA, 99 MTC-ECD, 99MTC-MDP and 99MTC-MIBI : Labelling procedures and stability studies

International Nuclear Information System (INIS)

Savio, E.O.; Teran, M.A.; Vales, M.E.; Frier, M.

2004-01-01

Liposomes labelled with gamma e miters like 99mTc, can be used for scintigraphic imaging to non-invasively track and quantify the distribution of liposomes in the body. In vitro studies were done to choose a suitable radiopharmaceutical (RF) to be attached to performed liposomes. 99mTc-Complexes (DTPA, ECD, MDP, MIBI) were used to label collagen liposomes. Commercial kits were labelled with 99mTc04-(TechnoNuclear). Quality controls of the RF were performed. Collagen liposomes suspended in saline 0.9% were incubated at 4.25.37 and 60 for 30 min. Efficiency of the labelling procedure was determined by gel filtration using Sephadex G25 (Pharmacia) and NaC10.9%. Samples of 100mL (74MBq), were seeded and fractions of 0.5mL were colleted and measured in an ionisation chamber (Capintec CRC). Stability of the labelled liposomes was assessed incubating 0.5mL, of the suspension with 1mL of human serum during 30 min at 37 . Dialysis was performed using dialysis bags of 64 K pore size and NaCI 0.9% at room temperature. Samples of the saline bath were collected at 30.60 and 90 min. and measured in a solid scintillation counter Ortec.Liposomes labelled with 99mTc-DTPA and 99mTcMIBI showed a labelling efficiency of 80%; liposomes incubated with 99mTc-MDP were labelled in a 50% and 99mTc-ECD did not bind to liposomes in the conditions of study. Incubation of labelled liposomes with human serum showed 50% of strong binding to the plasmatic proteins for 99mTc-DTPA but low values (5%) for the other specimens. Labelled liposomes were achieved, with different RF, showing a suitable in vitro stability to perform in vivo studies

Comparative study of 99Mo/99mTc generators at base of synthesized gels starting from activation and fission 99Mo

International Nuclear Information System (INIS)

Lopez M, I.Z.; Monroy G, F.; Rivero G, T.; Rojas N, P.

2007-01-01

The 99m Tc is used for diagnostic and therapy. It is produced starting from 99 Mo, absorbed in chromatographic columns, loaded with alumina that absorb only 0.2% of 99 Mo with high specific activities of 99 Mo, obtained from the 235 U fission. Given these conditions and limitations, new preparation procedures of 99 Mo/ 99m Tc generators, its have been developed, using zirconium molybdates gels that incorporates until 30% of 99 Mo, conserve similar characteristics of quality and purity that the traditional generator. The radiochemical characteristics of the 99m Tc elution, depend strongly on the gel preparation conditions. In particular, the present work has by object to determine the influence of the 99 Mo used type, fission or activation product, during the gels synthesis, as well as the used air flow for the agitation in the gels preparation and its influence in the 99 Mo/ 99m Tc generators quality. When diminishing the flow of agitation air the efficiency it increases and in the radionuclide purity of the eluates and when using 99 Mo from fission for the gels production it increases in an important way the elutriation efficiency, the radiochemical and radionuclide purity of the 99m Tc eluates. (Author)

[99mTc]/[123I] Simultaneous dual-isotope brain striatum phantom SPECT study: preparing for simultaneous [99mTc]TRODAT-1/[123I]-IBZM pre- and post-synaptic dopamine imaging

International Nuclear Information System (INIS)

Kao, PF; Hsu, HT; Tzen, KY; Wey, SP

2004-01-01

Introduction: The brain dopamine transporters (DAT) and dopamine D2 receptors are implicated in all kinds of movement disorders. Both sites are also targets for drug treatment, Therefore, brain dopamine system is important in both basic and clinical neurological researches. Kung HF et al. developed [ 99m Tc]TRODAT-l for DAT and [ 123 I]IBZM for D2 receptor SPECT imaging in living human brain. In this work, the possibility of doing [ 99m Tc]TRODAT-1/[ 123 I]IBZM simultaneous dual-isotope SPECT for both DAT/D2 receptor imaging was studied. The SPECT acquisition protocol, the percent of 99m Tc/ 123 I energy cross contamination, and the reproducibility of striatal /background ratios were studied with a striatal phantom to confirm the accuracy of 99m Tc/ 123 I dual-isotope simultaneous SPECT technique. Materials and Methods: In each set of experiment, the 4 striatum (target) chambers and the rest of the brain (background) were filled with solutions containing 99m Tc only, 123 I only, and both isotopes. Several sets of experiment with different target/background ratios were tested. For SPECT image acquisition, a triple-head gamma camera equipp with high resolution fan-beam collimators (Siemens Multi-SPECT3). Energy window settings of a 15% centered window at 140KeV for 99m Tc and a 10% asymmetric window with a lower bound at 159KeV for 123 I were used. After filtered backprojection and Chang's attenuation correction, regions of interest were defined at the bilateral basal ganglia and occipital areas. The reproducibility of counting activity and the different target/background ratios from each isotope were observed. Results: The results of the study revealed that the energy crossed contaminations from I-123 into Tc- 99m and vice verse were 22±12.4 % and 0.4±1.0 %, respectively. The correlation of striatum/background ratios between single isotope and simultaneous was excellent (R2 = 0.99). The success of this simultaneous dual-isotope SPECT technique is suggestive of the

Gentc99m, computational system for the technetium-99m generator

International Nuclear Information System (INIS)

Suparman, I.

1997-01-01

The technetium-99m generator is one of the main products of the PPR, as the continuity of the technetium-99m generator production is important for supporting the development of nuclear medicine. GENTC99M has been made for computational for the technetium-99m generator and includes data processing, documentation and information GENTC99M is also very useful in quality control application especially for the determinations of yield and radionuclidic impurities which consume much time. microsoft visual basic for MS-DOS and visual basic for windows have been used for making GENTC99M. Microsoft visual basic has several features that make it an ideal development language for both MS-DOS and Microsoft Windows. These features not only increase productivity, they also provide all the tools and hooks needed to develop some very sophisticated applications. for a production centre like PPR, GENTC99M is very useful to support the data processing, documentation and information system of the technetium-99m generator and it can also be modified for other products

Development of fine-group (315n/42γ) cross section library ENDL3.0/FG for fusion-fission hybrid systems

International Nuclear Information System (INIS)

Zeng Qin; Zou Jun; Xu Dezhen; Jiang Jieqiong; Wang Minghuang; Wu Yican; Qiu Yuefeng; Chen Zhong; Chen Yan

2011-01-01

To improve the accuracy of the neutron analyses for subcritical systems with thermal fission blanket, a coupled neutron and photon (315 n + 42γ) fine-group cross section library HENDL3.0/FG based on ENDF/B-Ⅶ. 0 has been produced by FDS team. In order to test the availability and reliability of the HENDL3.0/FG data library, shielding and critical safety benchmarks were performed with VisualBUS code. The testing results indicated that the discrepancy between calculation and experimental values of nuclear parameters fell in a reasonable range. (authors)

Mismatched uptake of Tc-99m-ECD and Tc-99m-HMPAO in subacute cerebral infarction: Tc-99m-ECD for viability and Tc-99m-HMPAO for flow restoration

Energy Technology Data Exchange (ETDEWEB)

Lee, D. S.; Hyun, I. Y.; Kim, S. K. [College of Medicine, Seoul National Univ., Seoul (Korea, Republic of)] [and others

1997-07-01

Tc-99m-HMPAO reflects tissue perfusion but Tc-99m-ECD uptake is affected by tissue viability in addition to tissue perfusion which the varied state of cellular retention of Tc-99m-ECD reflects. Luxuriously perfused area on Tc-99m-HMPAO SPECT implies that this cortex was already reperfused either spontaneously or after thrombolysis and that accompanied paralysis of vascular reactivity in those zones warms progressive deterioration. We tried to find out if we can use sequential Tc-99m-ECD/Tc-99m-HMPAO SPECT to reveal cortical perfusion and severity and range of risky areas of cerbral cortex despite reperfusion in sub-acute infarction. In 13 patients (M ; F =7 : 6, mean age 57 (range: 26-84)) with cortical (n=12) and basal ganglia infarction (1), we performed sequential Tc-99m-ECD/Tc-99m-HMPAO SPECT at the same position. At first, 555 MBq of Tc-99m-ECD was injected and imaged and then 1110 MBq of Tc-99m-HMPAO was injected again and imaged with the patients in situ, and the first image (Tc-99m-ECD) and the subtracted image (2nd- 1st : Tc-99m-HMPAO) were compared slice by slice. Study was done from 3 days to 31 days (16{+-}9) after ictus. Tc-99m-ECD uptake was always less than or equal to Tc-99m-HMPAO uptake at the lesion in all cases. Luxury perfusion was prominent in four patients. Mismatched uptake was found in 10 patients. Severity of mismatch showed diverse spectrum and was ranged from total middle cerebral artery territory (1 case) to peripheral thin zones around infarction (2 cases). The other 7 showed intermediate amount of tissues with mismatch , i.e., Tc-99m-ECD defects where Tc-99m-HMPAO uptake is in part increased, normal or decreased. Upon discharge, patients having more uptake with Tc-99m-ECD predicted improvement. Patients having mismatched uptake went dichotomous way. In conclusion, Tc-99m-ECD/Tc-99m-HMPAO sequential SPECT is feasible and reveal both tissue perfusion (Tc-99m-HMPAO ) and discrepant Tc-99m-ECD uptake probably reflecting viability in acute

Updated ozone absorption cross section will reduce air quality compliance

Directory of Open Access Journals (Sweden)

E. D. Sofen

2015-12-01

et al. (2015 as 1.8 % smaller than the accepted value (Hearn, 1961 used for the preceding 50 years. Thus, ozone measurements that applied the older cross section systematically underestimate the amount of ozone in air. We correct the reported historical surface data from North America and Europe and find that this modest change in cross section has a significant impact on the number of locations that are out of compliance with air quality regulations if the air quality standards remain the same. We find 18, 23, and 20 % increases in the number of sites that are out of compliance with current US, Canadian, and European ozone air quality health standards for the year 2012. Should the new cross-section value be applied, it would impact attainment of air quality standards and compliance with relevant clean air acts, unless the air quality target values themselves were also changed proportionately. We draw attention to how a small change in gas metrology has a global impact on attainment and compliance with legal air quality standards. We suggest that further laboratory work to evaluate the new cross section is needed and suggest three possible technical and policy responses should the new cross section be adopted.

Preparation of 99Mo/99mTc generators based on 99Mo zirconium molybdates in the Gel Synthesis Device for Generators

International Nuclear Information System (INIS)

Lopez M, I. Z.; Monroy G, F.; Rivero G, T.; Rojas N, P.

2008-01-01

The 99m Tc is used for diagnosis and therapy. It is produced commercially from 99 Mo obtained from the fission of 235 U, which is retained in chromatographic columns filled with alumina whose maximum capacity is 0.2%. Given these constraints new methods of preparation 99 Mo/ 99m Tc generators have been developed using zirconium molybdates gels containing up to 30% of Mo, which is part of the generator matrix, and retaining quality and purity similar characteristics to those commercial generators. The present study aims to determine the flow of agitation, temperature and drying time optimal to prepare 99 Mo/ 99m Tc generators based on 99 Mo zirconium molybdates in the Gel Synthesis Device 99 Mo/ 99m Tc Generators designed and built by groups of the Radioactive Materials Research Laboratory and Automation and Instrumentation Department of the National Institute of Nuclear Research. (Author)

Altered [99mTc]Tc-MDP biodistribution from neutron activation sourced 99Mo.

Science.gov (United States)

Demeter, Sandor; Szweda, Roman; Patterson, Judy; Grigoryan, Marine

2018-01-01

Given potential worldwide shortages of fission sourced 99 Mo/ 99m Tc medical isotopes there is increasing interest in alternate production strategies. A neutron activated 99 Mo source was utilized in a single center phase III open label study comparing 99m Tc, as 99m Tc Methylene Diphosphonate ([ 99m Tc]Tc-MDP), obtained from solvent generator separation of neutron activation produced 99 Mo, versus nuclear reactor produced 99 Mo (e.g., fission sourced) in oncology patients for which an [ 99m Tc]Tc-MDP bone scan would normally have been indicated. Despite the investigational [ 99m Tc]Tc-MDP passing all standard, and above standard of care, quality assurance tests, which would normally be sufficient to allow human administration, there was altered biodistribution which could lead to erroneous clinical interpretation. The cause of the altered biodistribution remains unknown and requires further research.

Status and Performance Updates for the Cosmic Origins Spectrograph

Science.gov (United States)

Snyder, Elaine M.; De Rosa, Gisella; Fischer, William J.; Fix, Mees; Fox, Andrew; Indriolo, Nick; James, Bethan; Oliveira, Cristina M.; Penton, Steven V.; Plesha, Rachel; Rafelski, Marc; Roman-Duval, Julia; Sahnow, David J.; Sankrit, Ravi; Taylor, Joanna M.; White, James

2018-01-01

The Hubble Space Telescope's Cosmic Origins Spectrograph (COS) moved the spectra on the FUV detector from Lifetime Position 3 (LP3) to a new pristine location, LP4, in October 2017. The spectra were shifted in the cross-dispersion direction by -2.5" (roughly -31 pixels) from LP3, or -5" (roughly -62 pixels) from the original LP1. This move mitigates the adverse effects of gain sag on the spectral quality and accuracy of COS FUV observations. Here, we present updates regarding the calibration of FUV data at LP4, including the flat fields, flux calibrations, and spectral resolution. We also present updates on the time-dependent sensitivities and dark rates of both the NUV and FUV detectors.

Preparation and biological profile of 99mTc-lidocaine as a cardioselective imaging agent using 99mTc eluted from 99Mo/99mTc generator based on Al-Mo gel

International Nuclear Information System (INIS)

Sakr, T.M.; October University of Modern Sciences and Arts; Ibrahim, A.B.; Rashed, H.M.; Fasih, T.W.

2017-01-01

The current study is aimed to prepare 99m Tc-lidocaine as a new myocardial perfusion-imaging agent. The used 99m Tc was obtained from Al- 99 Mo-molybdate(VI) gel matrix. 99m Tc-lidocaine showed higher (15.4 ± 0.11% ID/g) and faster (15 min post injection) cardiac uptake than the recently studied 99m Tc-valsartan and 99m Tc-procainamide. Consequently, 99m Tc-lidocaine will be a valuable myocardial SPECT agent for diagnosis of emergency patients. Besides, the receptor affinity study confirmed the selectivity of 99m Tc-lidocaine for sodium channels in the heart. (author)

Comparative study of 99Mo/99mTc generators at base of synthesized gels starting from 99Mo of activation and of fission

International Nuclear Information System (INIS)

Lopez M, I.Z.; Monroy G, F.; Rivero G, T.; Rojas N, P.

2007-01-01

At the present time the more used and diffused radionuclide in nuclear medicine it is the Technetium 99 metastable ( 99 mTc) it is used for diagnostic and therapy. It is produced starting from molybdenum 99 ( 99 Mo), which is absorbed in chromatographic columns, loaded with alumina that absorb only 0.2% of 99 Mo situation that forces to use high specific activities of 99 Mo that it is obtained starting from the fission of the 235 U. Given these conditions and limitations, new preparation procedures of 99 Mo/ 99m Tc generators, of low or medium specific activity, its have been developed, using gels of zirconium molybdates that incorporates until 30% in weight of 99 Mo in the gel, and also conserve similar characteristics of quality and purity that those obtained by the traditional generator; reducing by this way the cost of production of the 99m Tc, when using 99 Mo of low specific activity, in the preparation of 99 Mo/ 99m Tc generators. The radiochemical characteristics of the elution of 99m Tc, depends strongly on the gel preparation conditions. In particular, the present work has for object to determine the influence of the used type of 99 Mo, fission or activation product, during the gels synthesis, as well as the used air flow for the agitation in the gels preparation and its influence in the quality of the 99 Mo/ 99m Tc generators. When diminishing the agitation air flow the efficiency it increases and in the radionuclide purity of the eluates and when using 99 Mo of fission for the gels production it increases in an important way the elution efficiency, the radiochemical purity and radionuclide of the eluates of 99m Tc. (Author)

Technetium-99 in ''instant'' sup(99m)Tc-pertechnetate

International Nuclear Information System (INIS)

Mattsson, S.

1978-01-01

The 99 Tc-content in sup(99m)Tc-pertechnetate separated from 99 Mo by distillation or extraction has been studied with a plastic scintillation detector. The identification of the measured activity was achieved by beta-spectrometry, chemical separation and half-life studies. The frequency distribution of the sup(99)Tc/sup(99m)Tc-ratios in the different samples was observed to be log-normal. The most likely activity ratio was 0.4x10 -6 , the maximum value being 5x10 -6 . The specific activity of ''instant'' pertechnetate is approximately a factor of 60 lower than that normally recorded in pertechnetate derived from daily eluted column generators. The low specific activity of ''instant'' pertechnetate is primarily explained by the long time between separation and usage and secondly by the low yield of Tc in the distillation and extraction processes. In several of the ''instant'' pertechnetate solutions the carrier concentration exceeded the reductive capacity of the stannous ions in ''kits'' with small amounts of Sn(II) in usable form. (T.G.)

Potential Ways to Address Shortage Situations of 99Mo/99mTc.

Science.gov (United States)

Filzen, Leah M; Ellingson, Lacey R; Paulsen, Andrew M; Hung, Joseph C

2017-03-01

99m Tc, the most common radioisotope used in nuclear medicine, is produced in a nuclear reactor from the decay of 99 Mo. There are only a few aging nuclear reactors around the world that produce 99 Mo, and one of the major contributors, the National Research Universal (Canada), ceased production on October 31, 2016. The National Research Universal produced approximately 40% of the world's 99 Mo supply, so with its shut down, shortages of 99 Mo/ 99m Tc are expected. Methods: Nuclear pharmacies and nuclear medicine departments throughout the United States were contacted and asked to provide their strategies for coping with a shortage of 99 Mo/ 99m Tc. Each of these strategies was evaluated on the basis of its effectiveness for conserving 99m Tc while still meeting the needs of the patients. Results: From the responses, the following 6 categories of strategies, in order of importance, were compiled: contractual agreements with commercial nuclear pharmacies, alternative imaging protocols, changes in imaging schedules, software use, generator management, and reduction of ordered doses or elimination of backup doses. Conclusion: The supply chain of 99 Mo/ 99m Tc is quite fragile; therefore, being aware of the most appropriate coping strategies is crucial. It is essential to build a strong collaboration between the nuclear pharmacy and nuclear medicine department during a shortage situation. With both nuclear medicine departments and nuclear pharmacies implementing viable strategies, such as the ones proposed, the amount of 99m Tc available during a shortage situation can be maximized. © 2017 by the Society of Nuclear Medicine and Molecular Imaging.

In vitro effect of cyclophosphamide on the binding of radiopharmaceuticals (99m Tc O4- and 99m Tc-MDP) to blood elements

International Nuclear Information System (INIS)

Ripoll-Hamer, E.; Paula, E.F. de; Bernardo Filho, M.; Freitas, L.C.; Fonseca, L.M.; Gutfilen, B.

1995-01-01

Using an in vitro model, it was evaluated the effect of cyclophosphamide on percent radioactivity of 99m Tc O - 4 and methylene diphosphonic acid ( 99m Tc-MDP) bound to isolated blood elements. Blood samples were incubated with the two radiopharmaceuticals, plasma and blood cells were separated and precipitated, and soluble and insoluble fractions were separated. To evaluate the effect of cyclophosphamide, blood was incubated with this drug 1 h prior to the addition of the radiopharmaceuticals. The fraction of 99m Tc O - 4 radioactivity was slightly higher in plasma (61.2 to 53.8%) than in blood cells (38.8 to 46.2%) up to 6 h. The amount of 99m Tc - MDP radioactivity was higher in plasma (91.1 to 87.2%) than in blood cells (8.9 to 12.8%) up to 24 h. The binding of 99m Tc O - 4 to the insoluble fraction of plasma (4.9 to 6.1%) was low. But a small blockade (9.8 to 4.8%) was observed at 24 h. From 3 h on, cyclophosphamide slightly inhibited 99m Tc O - 4 binding to blood cells (23.1 to 16.6%) and increased it at 24 h (31.2 to 14.3%). The effect of cyclophosphamide was strongest at 24 h, with decreased radioactivity binding to the insoluble fraction of plasma (47.6 to 27.0%) and blood cells (51.2 to 23.2%). The fact that cyclophosphamide can bind to plasma proteins and/or cross the cell membrane explains in part the results obtained. (author). 20 refs., 2 tabs

Nanostructured metal oxides: promise opportunity and challenge to develop clinically useful 99Mo/99mTc generators using (n, gamma)99Mo

International Nuclear Information System (INIS)

Dash, Ashutosh

2014-01-01

The role of 99m Tc diagnostic nuclear medicine needs hardly to be reiterated. Today, it is the most widely used radionuclide for single photon emission computed tomography (SPECT) imaging procedures. The current strategy of availing 99m Tc is ensured from column chromatographic 99 Mo/ 99m Tc generators using a bed of acidic alumina. While the column chromatographic 99 Mo/ 99m Tc generator constitute a successful exemplar of availing 99m Tc, the limited capacity of alumina (2-20 mg Mo per g of alumina) for taking up molybdate ions necessitates the use of 99 Mo of the highest specific activity available, as can be found in fission produced 99 Mo (F 99 Mo). In order to reduce dependence of F 99 Mo, the scope of using low specific activity (n,γ) 99 Mo along with high capacity adsorbent is an interesting prospect. In this context, the scope of using nanomaterials as a viable adsorbent seemed attractive by virtue of their huge surface to volume ratios, altered physical properties, tailored surface chemistry, favorable adsorption characteristics, and enhanced surface reactivity resulting from the nanoscale dimensions. This emerging class of adsorbent represents an innovative paradigm and is expected to play an important role in the development of 99 Mo/ 99m Tc generators adaptable to the existing and foreseeable demands. This talk outlines a critical assessment on the role of nanostructured metal oxides, recent developments, the contemporary status, and key challenges and apertures to the near future. (author)

Updated Photonuclear Data Library and Database for Photon Strength Functions

Directory of Open Access Journals (Sweden)

Dimitriou Paraskevi

2015-01-01

Full Text Available Photonuclear cross sections and gamma-ray data used to extract Photon Strength Functions are important for a large range of applications including basic sciences. The recommendations of an IAEA Consultant’s Meeting to update the IAEA Photonuclear Data Library and create a Reference Database for Photon Strength Functions are presented.

21 CFR 582.20 - Essential oils, oleoresins (solvent-free), and natural extractives (including distillates).

Science.gov (United States)

2010-04-01

.... Clover Trifolium spp. Coca (decocainized) Erythroxylum coca Lam. and other spp. of Erythroxylum. Coffee Coffea spp. Cola nut Cola acuminata Schott and Endl., and other spp. of Cola. Coriander Coriandrum... Cola acuminata Schott and Endl., and other spp. of Cola. Laurel berries Laurus nobilis L. Laurel leaves...

Decay of 99Mo

International Nuclear Information System (INIS)

Dickens, J.K.; Love, T.A.

1976-01-01

Relative intensities for K x-rays and gamma rays emanating from 99 Mo in equilibrium with its 99 Tc* daughter have been measured using several Ge photon detectors. Combining these intensities with an evaluated set of electron-conversion coefficients has provided a set of absolute intensities for the observed gamma rays. The absolute intensity for the dominant 140.5-keV gamma ray in 99 Tc was determined to be 90.7 +- 0.6/100 99 Mo disintegrations for 99 Mo decay in equilibrium with decay of the 99 Tc* daughter

Comparative study of {sup 99}Mo/{sup 99m}Tc generators at base of synthesized gels starting from activation and fission {sup 99}Mo; Estudio comparativo de generadores {sup 99}Mo/{sup 99m}Tc a base de geles sintetizados a partir de {sup 99}Mo de activacion y de fision

Energy Technology Data Exchange (ETDEWEB)

Lopez M, I Z [UAEM, Paseo Colon esq. Paseo Tollocan, 50120 Toluca, Estado de Mexico (Mexico); Monroy G, F; Rivero G, T; Rojas N, P [ININ, Carretera Mexico -Toluca S/N, 52045 La Marquesa Ocoyoacac, Estado de Mexico (Mexico)

2007-07-01

The {sup 99m}Tc is used for diagnostic and therapy. It is produced starting from {sup 99}Mo, absorbed in chromatographic columns, loaded with alumina that absorb only 0.2% of {sup 99}Mo with high specific activities of {sup 99}Mo, obtained from the {sup 235}U fission. Given these conditions and limitations, new preparation procedures of {sup 99}Mo/{sup 99m}Tc generators, its have been developed, using zirconium molybdates gels that incorporates until 30% of {sup 99}Mo, conserve similar characteristics of quality and purity that the traditional generator. The radiochemical characteristics of the {sup 99m}Tc elution, depend strongly on the gel preparation conditions. In particular, the present work has by object to determine the influence of the {sup 99}Mo used type, fission or activation product, during the gels synthesis, as well as the used air flow for the agitation in the gels preparation and its influence in the {sup 99}Mo/{sup 99m}Tc generators quality. When diminishing the flow of agitation air the efficiency it increases and in the radionuclide purity of the eluates and when using {sup 99}Mo from fission for the gels production it increases in an important way the elutriation efficiency, the radiochemical and radionuclide purity of the {sup 99m}Tc eluates. (Author)

Results of regular study on radionuclidic purity of sup(99m)Tc obtained from 99Mo-sup(99m)Tc generators

International Nuclear Information System (INIS)

Vlcek, J.; Rohacek, J.; Husak, V.

1979-01-01

A total of 39 sup(99m)Tc eluates obtained from 9 99 Mo-sup(99m)Tc generators delivered by The Radiochemical Centre Amersham during one year was studied with regard to their radionuclide purity. Using a Ge(Li) spectrometer the contaminants 60 Co, 103 Ru, 131 I, 134 Cs, 140 La and 188 Re were found in sup(99m)Tc-eluates with average levels ranging from 2.9 x 10 -3 to 2.8 x 10 -1 per cent of sup(99m)Tc activity. The additional total body absorbed dose caused by these contaminants, as calculated from their average content in sup(99m)Tc eluates, was less than 1% of the dose due to sup(99m)Tc pertechnetate. (orig.) 891 MG/orig. 892 CS [de

Radionuclidic contamination of 99Mo, 131I and 103Ru in the eluate of 99Mo-99mTc chromatographic generator: comparision on fission produced 99Mo from RPC, Nordio and ARI

International Nuclear Information System (INIS)

Soenarjo, Sunarhadijoso; Gunawan, Adang Hardi

1996-01-01

The 99 Mo- 99m Tc Chromatographic generators is the most popular system to provide 99m Tc medical radioisotope. Radioisotope Production Centre (RPC)- BATAN has routinely produced the generator loaded with 99 Mo prepared by 235 U fission. By using fission produced 99 Mo, the resulting 99m Tc is potentially contaminated by other fission products which are difficult to eliminate completely. In order to study the characteristic of the generator and radionuclidic impurity pattern of the 99m Tc eluates, an evaluation of gamma spectrometric determination has been carried out. The bulk solutions of 99 Mo produced by RPC BATAN (Indonesia), Nordion (Canada) and ARI (Australia) were loaded to generators manufactured between July 1993 to May 1994. The saline-eluate 99m Tc, in a total volume of 10 ml each, was subjected to gamma spectrometric determination. The radiation of 99m Tc was eliminated by lead shield of 0.6913 cm thickness. The 99m Tc yield fluctuation from 28 generators indicated that the characteristics of the generator columns were very good. The 99m Tc eluates were consistently contaminated by 99 Mo, 131 I and 103 Ru, although the contamination level in all cases did not exceed the maximum permissible levels. The fluctuation of radionuclidic impurities were probably caused by variation in the irradiation parameter or by variation in the 99 Mo separation methods. (author), 23 refs, 1 tab, 3 figs

Magnesium-Molybate Compounds as Matrix for 99Mo/99mTc Generators

Directory of Open Access Journals (Sweden)

Fabiola Monroy-Guzman

2011-01-01

Full Text Available This work reports the preparation of a 99mTc generator based on conversion of 99Mo produced by neutron irradiation, into insoluble magnesium 99Mo-molybdates compounds as matrix. The effect of magnesium salt types and concentration, Mg:Mo molar ratios, pH of molybdate solutions, eluate volume as well as the addition order of molybdate and magnesium solutions’ influences on the final 99mTc were evaluated. Polymetalates and polymolybdates salts either crystallized or amorphous were obtained depending on the magnesium salt and Mg:Mo molar ratio used in matrix preparation. 99Mo/99mTc generator production based on magnesium-99Mo molybdate compounds allow reduction of preparation time and eliminates the use of specialized installations. The best generator performances were attained using matrices prepared from 0.1 mol/L MgCl2·6H2O solutions, ammonium molybdate solutions at pH 7 and at a Mg:Mo molar ratio of 1:1.

Radionuclide Basics: Technetium-99

Science.gov (United States)

Technetium-99 (chemical symbol Tc-99) is a silver-gray, radioactive metal. It occurs naturally in very small amounts in the earth's crust, but is primarily man-made. Technetium-99m is a short-lived form of Tc-99 that is used as a medical diagnostic tool.

99Mo-99mTc generator - study of their performance and quality

International Nuclear Information System (INIS)

Acar, M.E.D.

1987-01-01

In this work the performance of the 99 Mo - 99m Tc generators produced at IPEN-CNEN/SP as well as the quality of the eluted solutions were analysed. The following parameters were studied: elution efficiency, chemical radiochemical, radionuclidic and microbiological purities and pH of the eluates. The 99m Tc yield ranged from 84,7 to 98,5%. The radioactivity due to the pertechnetate ion in the studied solutions was higher than 97,5%. The aluminium content in eluates, determined by spectrophotometry, was lower than 2,5 μg/ml and the pH of the solutions between 4,5 and 5,1. Radioactive impurities of the order of 10 -3 KBq 99 Mc/MBq 99m Tc and 10 -5 KBq 131 I/MBq 99m Tc were found in the eluates at the time of elution. Other γ emitting radioactive impurities were order of 10 -3 KBq/MBq 99m Tc. The eluates were sterile and pyrogen-free. From the results obtained in this work one can state that the IPEN-TEC generator is a reliable source of good quality 99m Tc-pertechnetate. (author) [pt

99Mo production by 100Mo(n,2n)99Mo using accelerator neutrons

International Nuclear Information System (INIS)

Sato, Nozomi; Kawabata, Masako; Nagai, Yasuki; Hashimoto, Kazuyuki; Hatsukawa, Yuichi; Saeki, Hideya; Motoishi, Shoji; Kin, Tadahiro; Konno, Chikara; Ochiai, Kentaro; Takakura, Kosuke; Minato, Futoshi; Iwamoto, Osamu; Iwamoto, Nobuyuki; Hashimoto, Shintaro

2013-01-01

We proposed a new route to produce a medical radioisotope 99 Mo by the 100 Mo(n,2n) 99 Mo reaction using accelerator neutrons. A high-quality 99 Mo with a minimum level of radioactive waste can be obtained by the proposed reaction. The decay product of 99 Mo, 99m Tc, is separated from 99 Mo by the sublimation method. The proposed route could bring a major breakthrough in the solution of ensuring a constant and reliable supply of 99 Mo. (author)

Present status of Mo-99/Tc-99m generator in Thailand

International Nuclear Information System (INIS)

Khongpetch, Pranom

2007-01-01

Isotop Production Program, Office of Atoms for Peace had produced technetium-99m by MEK extraction of Mo-99 obtained from (n,γ) reaction in TRIGA Mark III reactor and supplied to nuclear medicine centers in Bangkok from 1980 to 1997. Because of the difficulty to meet the increased demand and limitation of reactor operation, the production of technetium-99m was stopped in 1997. Presently, there are 21 nuclear medicine centers with 25 SPECT, 7 gamma camera and 3 PET. All nuclear medicine centers are currently using imported Tc-99m generator. (author)

Quality control studies of 99Mo used in 99Mo/99mTc generators produced at IPEN/CNEN-SP, Brazil

International Nuclear Information System (INIS)

Said, Daphne S.; Brambilla, Tania P.; Matsuda, Margareth M.N.; Osso Junior, Joao A.

2015-01-01

99m Tc is the most used radionuclide in nuclear medicine. In Brazil, the 99 Mo/ 99m Tc generators are produced exclusively by the Center of Radiopharmacy at IPEN-CNEN/SP, by importing 99 Mo from different suppliers. 99 Mo (t 1/2 = 66 h) is a fission product of 235 U, therefore, it can be accompanied by several radioisotopes that are highly prejudicial for human health, demanding a strict quality control of this product for generators safe use. The European Pharmacopoeia established some parameters and limits that evaluate the quality of the solution of sodium [ 99 Mo]molybdate, that is used as raw material for generator's production. The European Pharmacopoeia also recommends some analytical methods to perform these evaluations, however, it has been observed difficulties on the implementation of these methods by the generator's producers. These difficulties are probably related to the lack of practicability of the proposed methods and the extensive list of utilized reagents. In this work some procedures of the European Pharmacopoeia's quality control method for 99 Mo were evaluated. Different types of solid phase exchanger cartridges were tested for retention of 99 Mo in 3 different conditions. Cartridges that presented percentages of retention higher than 90% were also tested for separation of 99 Mo from possible contaminants (Ru e Te). The results shown that solid phase exchanger cartridges that presented percentages of retention of Mo higher than 90% also presented significant percentages of retention of Ru and Te. An alternative method for separation of 99 Mo from 131 I (other contaminant) are also proposed. (author)

49 CFR 1242.33 - Other expenses and casualties and insurance (accounts XX-17-99, XX-18-99, XX-19-99, 50-17-00, 50...

Science.gov (United States)

2010-10-01

... (accounts XX-17-99, XX-18-99, XX-19-99, 50-17-00, 50-18-00, and 50-19-00). 1242.33 Section 1242.33....33 Other expenses and casualties and insurance (accounts XX-17-99, XX-18-99, XX-19-99, 50-17-00, 50... separation of administrative—other (account XX-19-06). Operating Expenses—Equipment locomotives ...

Spumaretroviruses: Updated taxonomy and nomenclature.

Science.gov (United States)

Khan, Arifa S; Bodem, Jochen; Buseyne, Florence; Gessain, Antoine; Johnson, Welkin; Kuhn, Jens H; Kuzmak, Jacek; Lindemann, Dirk; Linial, Maxine L; Löchelt, Martin; Materniak-Kornas, Magdalena; Soares, Marcelo A; Switzer, William M

2018-03-01

Spumaretroviruses, commonly referred to as foamy viruses, are complex retroviruses belonging to the subfamily Spumaretrovirinae, family Retroviridae, which naturally infect a variety of animals including nonhuman primates (NHPs). Additionally, cross-species transmissions of simian foamy viruses (SFVs) to humans have occurred following exposure to tissues of infected NHPs. Recent research has led to the identification of previously unknown exogenous foamy viruses, and to the discovery of endogenous spumaretrovirus sequences in a variety of host genomes. Here, we describe an updated spumaretrovirus taxonomy that has been recently accepted by the International Committee on Taxonomy of Viruses (ICTV) Executive Committee, and describe a virus nomenclature that is generally consistent with that used for other retroviruses, such as lentiviruses and deltaretroviruses. This taxonomy can be applied to distinguish different, but closely related, primate (e.g., human, ape, simian) foamy viruses as well as those from other hosts. This proposal accounts for host-virus co-speciation and cross-species transmission. Published by Elsevier Inc.

Homogeneous SLOWPOKE reactors for Mo-99/Tc-99m production in North America

Energy Technology Data Exchange (ETDEWEB)

Hilborn, J.W., E-mail: hilbovanw@sympatico.ca [Deep River, Ontario (Canada); Bonin, H.W. [Royal Military College of Canada, Kingston, Ontario (Canada)

2014-07-01

The 15 month shutdown of NRU in 2009 - 2010 caused an overall isotope shortage of approximately 30%; and in North America, the annual Tc-99m demand decreased from an estimated 20 million unit doses to about 15 million unit doses. Mo-99/Tc-99m is produced from HEU targets, irradiated in NRU for 11 days, and after chemical removal of uranium it is shipped to Nordion in Kanata, Ontario. Nordion further purifies the material and sends it to Lantheus Medical Imaging in the USA for manufacture of Mo-99 generators, which are then distributed to hundreds of hospital radiopharmacies throughout North America. One other American company, Covidien, manufactures and distributes Mo-99 generators like Lantheus, but they import bulk Mo-99 from Europe or South Africa. At the hospitals, Tc-99m is chemically extracted daily from the Mo-99 generators and loaded into syringes for immediate clinical use. Fortuitously, the 66 hour half-life of Mo-99 allows the replenishment of Tc-99m in the generator over a growth period of about 20 hours; and a generator can be 'milked' daily for up to two weeks. A more efficient model is the direct production and distribution of Tc-99m unit doses to regional hospitals from 10 'industrial' radiopharmacies located at existing licensed reactor sites in North America. A 20 kW homogeneous SLOWPOKE reactor at each site would deliver 15 litres of irradiated uranyl sulphate fuel solution daily to industrial-scale hot cells for extraction of Mo-99, which would be incorporated in large Mo-99/Tc-99m generators for extraction of Tc-99m five days a week; and the Low Enriched Uranium (LEU) would be recycled. Each automated hot-cell facility would be designed to load up to 7,000 Tc-99m syringes daily, for courier delivery to all of the Nuclear Medicine hospitals within a 3 hour average range by road transport. Typically, the delivered doses would be in the range 10 to 30 mCi. Assuming an average unit dose of 25 mCi at the hospital and 5 x 52

Iliac renal ectopia explored by {sup 99m}Tc-DTPA and {sup 99m}Tc-DMSA scintigraphy. Report of one case; Ectopie renale iliaque exploree par scintigraphie au {sup 99m}Tc-DTPA et au {sup 99m}Tc-DMSA. A propos d'un cas

Energy Technology Data Exchange (ETDEWEB)

Ghfir, I.; Ben Rais, N. [Hopital Ibn Sina, CHU de Rabat, Service de Medecine Nucleaire de Rabat (Morocco)

2008-11-15

Introduction Renal ectopia is a malposition by anomaly of migration during the embryonic development. It can be high, low or crossed. Association with an obstructive malformation is rather frequent. The objective of this work is to highlight the interest of {sup 99m}Tc-DTPA and {sup 99m}Tc-DMSA scintigraphy in the exploration of this type of malformation through the observation of a patient presenting an iliac right renal ectopia associated with an ureteral-pelvic junction syndrome. Observation A 38-year-old patient with an ureteral-pelvic junction syndrome on a right iliac renal ectopia revealed by intravenous urography. The dynamic renal scintigraphy using {sup 99m}Tc-DTPA with furosemide test evidenced an organic obstruction in the right urinary tract with a right renal function estimated at 40% on the {sup 99m}Tc-DMSA scintigraphy. A right pyelo-plasty was carried out. The evolution was marked by the disappearance of pain and a remarkable improvement of the permeability of the right urinary tract on the follow-up scintigraphy. Discussion Renal ectopia is not an unfrequent urinary malformation. It is generally low, pelvic or iliac. Association with an ureteral-pelvic junction obstruction is rather frequent. In this purpose, renal scintigraphy intervenes as a means of functional exploration, with low ionizing radiation and non-invasive to assess the permeability of the urinary tracts of the ectopic kidney and to appreciate the relative renal function. This contributes to the orientation of diagnosis and the improvement of therapeutic strategy.

99Mo production for using in the nuclear medicine in 99mTc generators

International Nuclear Information System (INIS)

Kurenkov, N.V.; Chuvilin, D.Yu.

1999-01-01

The review of methods and advanced technologies for obtaining 99 Mo in nuclear reactors is presented. The 99 Mo isotope is used for preparing the 99m Tc generators, widely applied in nuclear medicine. The reactor method for obtaining 99 Mo is based on the 98 Mo(n, γ) 99 Mo radiation capture reaction and 235 U fission reaction under the effect of the 235 U (n, f) 99 Mo reaction. The results of studies on obtaining 99 Mo on the charged particles accelerators, mainly, on the proton beam and under the effect of photonuclear reaction is also described. The data on the 99 Mo real consumption and forecast for its application in different regions of the world from 1994 up to 2006 are presented [ru

Development of 99mTc extraction techniques from 99Mo by (n,γ) reaction

International Nuclear Information System (INIS)

Kimura, Akihiro; Hori, Naohiko; Tsuchiya, Kunihiko; Ishihara, Masahiro; Yamabayashi, Hisamichi; Tanase, Masakazu; Fujisaki, Saburo; Sato, Yuichi

2010-11-01

Investigation of production method of 99 Mo by (n, γ) reaction, where the processing is relatively simple and generating less amount of radioactive waste, is conducted in the Neutron Irradiation and Testing Reactor Center. The 99 Mo is adsorbed to highly efficient adsorbent PZC after neutron irradiation and 99m Tc is eluted. However, radioactivity concentration of the 99m Tc solution obtained from PZC column loaded with 99 Mo derived by (n, γ) method is lower than that obtained from alumina column with 99 Mo by (n, f) method due to extremely low specific activity of (n, f) 99 Mo. Therefore, it is necessary to develop technique for increasing the amount of 99 Mo and the 99m Tc solution of high radioactivity concentration (minimum: 1Ci/ cm 3 ). In this study, the preliminary fabrication tests using high density MoO 3 pellets were carried out to increase the production of 99 Mo. The method of concentrating 99m Tc solution through solvent extraction with MEK was investigated and a device for this concentration process was also developed. In the preliminary tests of the MoO 3 pellets, the pellets having high density were successfully fabricated by the SPS method. Additionally, it was ascertained that the pellets can be dissolved with 6M-NaOH solution completely. The test for 99 Mo adsorption followed by 99m Tc elution using PZC was carried out. As the result, amount of Mo adsorbed to 1g-PZC was about 250mg, and 99m Tc yield was about 80%. In the concentration test using Re solution instead of 99m Tc solution, it was ascertained that the concentration efficiency is higher than 80% of the theoretical value. A concentration device for 99m Tc solution could be realized based on the method employed in the present experiments. The outcomes of development of 99m Tc extraction techniques from 99 Mo by (n,γ) reaction was reviewed in this paper, and the contents were presented in the 3rd International Symposium on Material Test Reactors. (author)

Update of the NNLO PDFs in the 3-, 4- and 5-flavour schemes

International Nuclear Information System (INIS)

Alekhin, Sergey; Bluemlein, Johannes; Moch, Sven-Olaf

2010-07-01

We report on an update of the next-to-next-to-leading order (NNLO) ABKM09 parton distributions functions. They are obtained with the use of the combined HERA collider Run I inclusive deep-inelastic scattering (DIS) data and the partial NNLO corrections to the heavy quark electro-production taken into account. The value of the strong couplig constant α NNLO s (M Z )=0.1147(12) is obtained. The standard candle cross sections for the Tevatron collider and the LHC estimated with the updated PDFs are provided. (orig.)

14 CFR 99.1 - Applicability.

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 2 2010-01-01 2010-01-01 false Applicability. 99.1 Section 99.1... AND GENERAL OPERATING RULES SECURITY CONTROL OF AIR TRAFFIC General § 99.1 Applicability. (a) This... Identification Zone (ADIZ) designated in subpart B. (b) Except for §§ 99.7, 99.13, and 99.15 this subpart does...

Use of 99mTc from a commercial 99Mo/9mTc generator as yield tracer for the determination of 99Tc at low levels

DEFF Research Database (Denmark)

Hou, Xiaolin; Jensen, Mikael; Nielsen, Sven Poul

2007-01-01

The concentrations of Tc-99 and impurity radionuclides in the Tc-99m tracer solution obtained from a commercial Mo-99/Tc-99m generator were measured by gamma spectrometry and liquid scintillation counting. Mo-99 and Ru-103 were found in the Tc-99m eluate. A simple separation using two extra alumina...... cartridges was investigated to purify the eluate to obtain a suitable Tc-99m tracer with low Tc-99 concentration. The activity ratio of Tc-99/Tc-99m in the prepared Tc-99m solution is lower than 15 x 10(-9), which is higher than the theoretical ratio of less than 10 x 10(-9). The possible reason is discussed....... The Tc-99 in the 20 kBq spiked Tc-99m tracer was found to be less than 0.3mBq, which is lower than the detection limit of the radiometric method used for environmental samples. The purified Tc-99m eluate is used as yield tracer for the determination of low levels of Tc-99 in environmental samples. (c...

Preparation of a gel of zirconium molybdate for use in the generators of 99 Mo - 99m Tc prepared with 99 Mo produced by the 98 Mo(n,γ)99 Mo reaction

International Nuclear Information System (INIS)

Osso Junior, Joao A.; Lima, Ana Lucia V.P.; Silva, Nestor C. da; Nieto, Renata C.; Velosa, Adriana C. de

1998-01-01

IPEN develops a project concerning the preparation of a gel of Zirconium Molybdate for use in the generators of 99 Mo- 99m Tc . 99m Tc is the most used radioisotope in nuclear medicine diagnosis procedures and nowadays the generators are being prepared with imported 99 Mo, produced by 235 U fission. The production of 99 Mo by the 98 Mo(n, γ) 99 Mo reaction is now possible because of the power upgrade of IPEN's IEA-R1 reactor, from 2 to 5 MW. This work describes the preparation method of Zirconium Molybdate gel that will be used in the 99 Mo- 99m Tc generators. The gel is prepared by the chemical reaction between Mo, in Mo O 3 form, and Zr, in Zr O Cl 2 .8H 2 O form. After the reaction, the gel is filtered, dried and cracked with saline solution. The product is then loaded into glass columns for use as 99m Tc generator. The results showed the good quality of the gel prepared at laboratory level and of the generators evaluated. (author)

Preparation of i.v. 99mTc radiopharmaceuticals from spent moly 99Mo

International Nuclear Information System (INIS)

Noronha, O.P.D.

1998-01-01

Full text: Expiry dating is an important quality assurance precept in (radio) pharmacy. There are occasions when for the sake of patient service one may be forced to continue using an over aged source of 99 Mo to generate 99m Tc beyond 7d, especially when there is short/no supply of 99 Mo, (In the early days the expiry date was 3 d or 3 extractions, whichever one was earlier). With the passage of time a few physico-chemical changes (apart from decay) do occur in the 99 Mo/ 99m Tc milieu. The cocktail also begins to contain traces of carried over MEK which is subjected to strong β-, γ irradiation. These impurity (in trace amounts) is soluble in MEK and even, to an extent, in aqueous media. Furthermore, the concentrated impurity tends to seemingly increase in the bulk 99m TcO 4 - since one is compelled to leach TcO 4 - in lower volume of saline. On many occasions we have been constrained to extend the use of 99 Mo beyond 7 - 14 d. Adequate activities were obtained by pooling the previous week's lot of 99 Mo with the current over aged lot. On a few occasions over the past 26 years we have used 99 Mo much beyond 14 d and 2 - 3 occasions for 26 - 28 d (i.e. >10 t 1 /2 of 99 Mo). On each of these occasions the purity of 99m TcO- 4 was ascertained by pharmacopoeial procedures. It was found that despite depleting activities, the purity was not compromised and the trace impurities, even if present, did not cause any interference. We have profitably utilised the bulk TcO- 4 to formulate a variety of i.v. dosage forms of 99m Tc radiodiagnostics. The following strategy was adopted for the patient services - the agents requiring larger activity levels/patients dose were made available in the earlier period, the other during the latter half. It is concluded that pure 99m TcO- 4 can be obtained over the entire useful life-period of 99 Mo, even > 10t l/2

A comparative study of 99Tcm-tetrofosmin and 99Tcm-MIBI myocardial imaging

International Nuclear Information System (INIS)

Zhao Kui; Chen Peng; Zhang Furong; Shen Wenhua

2001-01-01

Objective: To evaluate the value of 99 Tc m -tetrofosmin myocardial imaging for detecting coronary artery disease. Methods: Twenty-seven patients underwent 99 Tc m -tetrofosmin SPECT, twenty-six patients underwent 99 Tc m -MIBI SPECT; coronary angiography was performed on patients included in both groups (≥50% luminal diameter stenosis was considered significant coronary stenosis). Results: 99 Tc m -tetrofosmin produced high quality myocardial images from 30 min to several hours postinjection, the outlines of myocardial perfusion images provided by 99 Tc m -tetrofosmin imaging were clearly discernible. One-day exercise/rest 99 Tc m -tetrofosmin myocardial perfusion imaging was feasible and had a high sensitivity for detection of coronary artery disease. Sensitivities of 99 Tc m -tetrofosmin SPECT and 99 Tc m -MIBI SPECT for detecting coronary artery disease were 90% and 94%, respectively. The 95% confidence limits of both sensitivities were 68.65% - 98.77% and 72.33% - 99.86%, respectively; the positive predictive values of both imaging agents were 90.0% and 89.5%, respectively, the 95% confidence limits of those were 68.38% - 98.77% and 72.33% - 99.86% respectively; the positive predictive values of both imaging agents were 90.0% and 89.5%, respectively, the 95% confidence limits of those were 68.38% - 98.77% and 66.38% - 98.70%, respectively; efficiencies of both imaging agents were 85.2% and 88.5%, respectively. The 95% confidence limits of both efficiencies were 65.81% - 95.78% and 69.44 - 98.70%, respectively. The specificity for both imaging agents was 71% and 75%. There was no significant difference among above results (P > 0.05). No ECG abnormalities were found following the injection of 99 Tc m -tetrofosmin SPECT. There were no drug-related effects on blood pressure, heart rate and body temperature. This experiment failed to provide the negative predictive value of the myocardial perfusion imaging with 99 Tc m -tetrofosmin because that few patients with

Preliminary studies of 99mTc-memantine derivatives for NMDA receptor imaging

International Nuclear Information System (INIS)

Zhou Xingqin; Zhang Jiankang; Yan Chenglong; Cao Guoxian; Zhang Rongjun; Cai Gangming; Jiang Mengjun; Wang Songpei

2012-01-01

Introduction: Novel technetium-labeled ligands, 99m Tc-NCAM and 99m Tc-NHAM were developed from the N-methyl-D-aspartate (NMDA) receptor agonist memantine as a lead compound by coupling with N 2 S 2 . This study evaluated the binding affinity and specificity of the ligands for the NMDA receptor. Methods: Ligand biodistribution and uptake specificity in the brain were investigated in mice. Binding affinity and specificity were determined by radioligand receptor binding assay. Three antagonists were used for competitive binding analysis. In addition, uptake of the complexes into SH-SY5Y nerve cells was evaluated. Results: The radiochemical purity of 99m Tc-labeled ligands was more than 95%. Analysis of brain regional uptake showed higher concentration in the frontal lobe and specific uptake in the hippocampus. 99m Tc-NCAM reached a higher target to nontarget ratio than 99m Tc-NHAM. The results indicated that 99m Tc-NCAM bound to a single site on the NMDA receptor with a K d of 701.21 nmol/l and a B max of 62.47 nmol/mg. Specific inhibitors of the NMDA receptor, ketamine and dizocilpine, but not the dopamine D 2 and 5HT 1A receptor partial agonist aripiprazole, inhibited specific binding of 99m Tc-NCAM to the NMDA receptor. Cell physiology experiments showed that NCAM can increase the viability of SH-SY5Y cells after glutamate-induced injury. Conclusions: The new radioligand 99m Tc-NCAM has good affinity for and specific binding to the NMDA receptor, and easily crosses the blood–brain barrier; suggesting that it might be a potentially useful tracer for NMDA receptor expression.

Synthesis and characterization of zirconium molybdates of 99 Mo/99m Tc generators

International Nuclear Information System (INIS)

Contreras R, A.; Monroy G, F.; Diaz A, L.V.

2002-01-01

The zirconium molybdates are gels which are used as cation exchangers in the production of 99 Mo/ 99m Tc generators. The synthesis method and the characterization of these gels by thermogravimetry, infrared spectroscopy and X-ray diffraction is presented with the purpose of finding which the factors are that influence in the efficiency of the 99m Tc production. The results show that the quantity of molecular water contained in gel, is possibly the cause of variations of the efficiencies of the 99 Mo/ 99m Tc generator. (Author)

Physician use of updated anti-virus software in a tertiary Nigerian hospital.

Science.gov (United States)

Laabes, E P; Nyango, D D; Ayedima, M M; Ladep, N G

2010-01-01

While physicians are becoming increasingly dependent on computers and the internet, highly lethal malware continue to be loaded into cyberspace. We sought to assess the proportion of physicians with updated anti-virus software in Jos University Teaching Hospital Nigeria and to determine perceived barriers to getting updates. We used a pre-tested semi-structured self-administered questionnaire to conduct a cross-sectional survey among 118 physicians. The mean age (+/- SD) of subjects was 34 (+/- 4) years, with 94 male and 24 female physicians. Forty-two (36.5%) of 115 physicians with anti-virus software used an updated program (95% Cl: 27, 45). The top-three antivirus software were: McAfee 40 (33.9%), AVG 37 (31.4%) and Norton 17 (14.4%). Common infections were: Trojan horse 22 (29.7%), Brontok worm 8 (10.8%), and Ravmonlog.exe 5 (6.8%). Internet browsing with a firewall was an independent determinant for use of updated anti-virus software [OR 4.3, 95% CI, 1.86, 10.02; P malware producers and anti-virus software developers.

Synthesis and characterization of zirconium molybdates of {sup 99} Mo/{sup 99m} Tc generators; Sintesis y caracterizacion de molibdatos de zirconio de generadores {sup 99} Mo/{sup 99m} Tc

Energy Technology Data Exchange (ETDEWEB)

Contreras R, A.; Monroy G, F.; Diaz A, L.V. [Instituto Nacional de Investigaciones Nucleares, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

2002-07-01

The zirconium molybdates are gels which are used as cation exchangers in the production of {sup 99} Mo/{sup 99m} Tc generators. The synthesis method and the characterization of these gels by thermogravimetry, infrared spectroscopy and X-ray diffraction is presented with the purpose of finding which the factors are that influence in the efficiency of the {sup 99m} Tc production. The results show that the quantity of molecular water contained in gel, is possibly the cause of variations of the efficiencies of the {sup 99} Mo/{sup 99m} Tc generator. (Author)

Inheritance of Hairiness of Stem and Petiole in a Selection from Local (Nigeria Germoplasm of Sesame

Directory of Open Access Journals (Sweden)

Funmi, FM.

2002-01-01

Full Text Available Character differences were studied in inter specific crosses involving Sesamum indicum L. and Ceratotheca sesamoides Endl. Results show that inheritance of many hairs on stem and petiole was controlled by two independently assorting genes with both dominant alleles S- and P- producing many hairs in stem and petiole respectively. Only the genotypes sspp homozygous for both recessive alleles were plants with few hairs. The implications of these findings in the species evolution are discussed.

Seleção para a resistência à ferrugem em progênies das cultivares de café IPR 99 e IPR 107 Selection for resistance to rust in progenies of coffee cultivars IPR 99 and IPR 107

Directory of Open Access Journals (Sweden)

Gustavo Hiroshi Sera

2010-01-01

Full Text Available As cultivares de café IPR 99 ("Sarchimor" e IPR 107 ('IAPAR 59' x 'Mundo Novo IAC 376-4' eram no passado resistentes à ferrugem (Hemileia vastatrix. Os objetivos deste estudo foram: a Identificar progênies dessas duas cultivares com resistência à ferrugem; b Identificar progênies com resistência incompleta; c Verificar a eficiência dos cruzamentos testes na seleção dessas cultivares. A avaliação da resistência em campo foi realizada em cafeeiros adultos expostos à população local de raças presentes no IAPAR. Foram avaliados 23 cruzamentos testes com progênies F3 de 'IPR 107' e 5 com progênies F4 de 'IPR 99'. Além disso, foram avaliadas 11 progênies F4 de 'IPR 107' e 5 progênies F5 de 'IPR 99', provenientes de autofecundação. Várias progênies das cultivares IPR 99 e 107 apresentaram alta freqüência de plantas com resistência completa e são portadoras de mais genes de resistência não quebrados pelas raças de ferrugem. Progênies das cultivares IPR 99 e IPR 107 com a resistência quebrada apresentaram resistência incompleta à população local de raças. Cruzamentos testes foram eficientes na seleção de progênies de café com mais genes de resistência não quebrados.All plants of the coffee cultivars IPR 99 ("Sarchimor" and IPR 107 ('IAPAR 59' x 'Mundo Novo IAC 376-4' were resistant to rust (Hemileia vastatrix in the past. Currently, susceptible plants were observed in the two cultivars due to the breakdown of resistance by new rust races. The aims of this study were: a to identify coffee (Coffea arabica L. progenies of the two cultivars with resistance to rust; b to identify progenies with incomplete resistance; c to investigate the efficiency of test-crosses for selection from these cultivars. Evaluation for field resistance was carried out in adult plants subjected to natural infection by the local leaf rust population at IAPAR. Twenty-three test-crosses with F3 progenies of 'IPR 107' and five with F4

Evaluation of the absorbed dose to the kidneys due to Tc99m (DTPA) / Tc99m (Mag3) and Tc99m (Dmsa)

International Nuclear Information System (INIS)

Vasquez A, M.; Murillo C, F.; Castillo D, C.; Rocha J, J.; Sifuentes D, Y.; Sanchez S, P.; Idrogo C, J.; Marquez P, F.

2015-10-01

The absorbed dose in the kidneys of adult patients has been assessed using the biokinetics of radiopharmaceuticals containing Tc 99m (DTPA) / Tc 99m (Mag3) or Tc 99m (Dmsa).The absorbed dose was calculated using the formalism MIRD and the Cristy-Eckerman representation for the kidneys. The absorbed dose to the kidneys due to Tc 99m (DTPA) / Tc 99m (Mag3), are given by 0.00466 mGy.MBq -1 / 0.00339 mGy.MBq -1 . Approximately 21.2% of the absorbed dose is due to the bladder (content) and the remaining tissue, included in biokinetics of Tc 99m (DTPA) / Tc 99m (Mag3). The absorbed dose to the kidneys due to Tc 99m (Dmsa) is 0.17881 mGy.MBq -1 . Here, 1.7% of the absorbed dose is due to the bladder, spleen, liver and the remaining tissue, included in biokinetics of Tc 99m (Dmsa). (Author)

Updated predictions for the total production cross sections of top and of heavier quark pairs at the Tevatron and at the LHC

CERN Document Server

Cacciari, Matteo; Mangano, Michelangelo L; Nason, Paolo; Ridolfi, Giovanni

2008-01-01

We present updated predictions for the total production cross section of top-quark pairs at the Tevatron and at the LHC, and, at the LHC, of heavy-quark pairs with mass in the range 0.5-2 TeV. For t\\bar{t} production at the LHC we also present results at \\sqrt{S}= 10 TeV, in view of the expected accelerator conditions during the forthcoming 2008 run. Our results are accurate at the level of next-to-leading order in alpha_s, and of next-to-leading threshold logarithms (NLO+NLL). We adopt the most recent parametrizations of parton distribution functions, and compute the corresponding uncertainties. We study the dependence of the results on the top mass, and we assess the impact of missing higher-order corrections by independent variations of factorisation and renormalisation scales.

Efeitos da poluição por petróleo na estrutura da folha de Podocarpus lambertii Klotzsch ex Endl., Podocarpaceae Effects of oil pollution on leaf structure of Podocarpus lambertii Klotzsch ex Endl., Podocarpaceae

Directory of Open Access Journals (Sweden)

Leila Teresinha Maranho

2006-09-01

Full Text Available Podocarpus lambertii, popularmente conhecida como pinheiro-bravo é uma Podocarpaceae típica da região Sul do Brasil, família que se distingue de outras coníferas por possuir uma estrutura de suporte para o óvulo denominada "epimatium". O presente estudo teve como objetivo investigar, por meio de parâmetros morfológicos e anatômicos, os efeitos da poluição por petróleo na estrutura das folhas de Podocarpus lambertii Klotzsch ex Endl. (Podocarpaceae, popularmente conhecida por pinheiro-bravo. As folhas foram coletadas no município de Araucária, Paraná, Brasil, na Refinaria de petróleo Presidente Getúlio Vargas (REPAR um ano após exposição à poluição provocada pelo derramamento de petróleo. Esta espécie foi selecionada, porque além de ser nativa, apresentou um comportamento diferenciado dentre as demais diante da poluição. Folhas de nove indivíduos (seis expostos ao petróleo e três controle foram coletadas. Foram avaliadas em microscopia fotônica as dimensões foliares (comprimento, largura e área foliar, a espessura dos tecidos e a densidade estomática. Os dados obtidos foram analisados estatisticamente. Nos indivíduos expostos à poluição, a superfície foliar foi menor, a densidade estomática e espessura dos tecidos foliares foram maiores quando comparados aos indivíduos controle. Os resultados obtidos permitem concluir que P. lambertti reagiu quando de sua exposição à poluição por petróleo.Podocarpus lambertii, locally known as "pinheiro-bravo", is a typical Podocarpaceae from Southern Brazil. This family is the most diverse of conifers; it has a distinguishing characteristic, namely the presence of an ovule support structure, called an epimatium. The aim of this study was to investigate the effect of oil pollution on the leaf structure of P. lambertii through morphology and anatomy. Leaves were collected in Araucária Municipality, Paraná, Brazil, at the Presidente Getúlio Vargas Petroleum

Separation of sup(99m)Tc from 99Mo through a hydrous zirconium oxide column

International Nuclear Information System (INIS)

Mengatti, J.

1980-01-01

The preparation of 99 Mo-,sup(99m)Tc generator based on the adsorption of 99 Mo on hydrous zirconium oxide column, employing the in exchange technique, is described. The adsorption of 99 Mo on hydrous zirconium oxide (HZO) and the separation of sup(99m)Tc, generated by the decay of 99 Mo with saline solution, are analised. The sup(99m)Tc separation yield, pH of the eluted solution, aspect of the elution curve and the adsorption of 99 Mo on hydrous zirconium oxide calcined at 800 0 C are studied. The chemical and radioactive purities of the final product are analysed and the variation of the elution yield for successive elutions is studied. (Author) [pt

Studies of techniques for the post-elution concentration of 99mTc obtained from gel type 99Mo/99mTc generators

International Nuclear Information System (INIS)

Suzuki, Katia Noriko

2009-01-01

On average 80% of the radiopharmaceuticals used in Nuclear Medicine are labeled with 99 mTc due to its physical properties and easy attainment through of 99 Mo/ 99 mTc generators. The Directory of Radiopharmacy (DIRF) of IPEN-CNEN/SP developed a gel type chromatographic generator of MoZr with 99 Mo produced by 98 Mo(n,γ) 99 Mo reaction that occurs at the IEA-R1 Nuclear Reactor. The gel is composed of zirconium molybdate with elution volume of 12 mL with an activity of 11100 MBq (300 mCi) producing a radioactive concentration of 925 MBq (25 mCi)/mL. The fission generator gives a higher radioactive concentration around 1850 MBq (50 mCi)/mL. The aim of this work is to study a system of post-elution concentration of 99 mTc for the attainment of a high enough radioactive concentration to meet the demands of the market, with a proved quality. Two types of systems of post-elution concentration were developed: the single and the tandem. The most appropriate system for the gel generator of 99 Mo/ 99 mTc, being at the same time sterile and vacuum automated, was the tandem system using Dionex 2.5 cc/QMA cartridges. The gel generator is eluted with 10 mL of solution of 0.1% NaCl and the pertechnetate anion is retained in the QMA cartridge and further eluted with 4 mL of saline. The process takes no more than 30 minutes. The elution efficiency of the system of concentration was 90 %. At the beginning of 2009 a global crisis in the supply of 99 Mo took place making it necessary the development of alternative technologies for the production of 99 Mo/ 99 mTc generators using fission produced 99 Mo and the development of an appropriate method to extend the useful life of this generator. The results of this study showed that the same system developed for the post- concentration of the gel generator can be employed for the fission generator, using the tandem system, giving a concentration factor of 3 for the elution of 99 mTc. (author)

The preparation of {sup 99m}Tc from {sup 99}Mo-{sup 99m}Tc using Poly-Zirconium Compound (PZC)

Energy Technology Data Exchange (ETDEWEB)

Laohawilai, S [Isotope Production Div., Office of Atomic Energy for Peace (Thailand)

1998-10-01

The process of for providing the {sup 99m}Tc-gel generator followed the protocol that received from Department of Radioisotopes, Tokai Research Establishment, JAERI. Sodium molybdate (molybdenum-99), pH 7 with concentration 20 mg/ml and activity nearly 1 mCi/ml was added into the adsorbent (PZC). The total activity of {sup 99}Mo was about 10 mCi and the heating time was varied from 3-18 hours at 70degC. The properties of the gel were studied for elution profile and elution efficiency. The molybdenum breakthrough in sodium pertechnetate (technetium-99m) was also performed. (author)

A comparative study of 99Tcm-MDP, 99Tcm(V)-DMSA and 99Tcm-Citrate in diagnosis of bone malignant tumors and bone/joint infections

International Nuclear Information System (INIS)

Wu Zhaozhong; Wu Boyi; Lin Wei; Wei Xueli; Wu Hengfu; Fan Ziwen; Ouyang Zhi; Wu Changwei; Yuan Gewen

2003-01-01

The purpose of this study was to assess the diagnostic value of scans with 99 Tc m (V)-dimercaptosuccinic acid (DMSA) to localize bone metastases and to evaluate the capability to diagnose bone/joint infections with scans using 99 Tc m -Citrate. Eighteen patients referred to bone metastases and eighteen patients referred to bone and joint infection were studied. In all patients, a bone scan of 99 Tc m -MDP was obtained initially. Subsequently, comparative scans with 99 Tc m (V)-DMSA and 99 Tc m -Citrate were conducted successively. Pathologic finding and/or microbiological finding, X-ray CT and/or MRI, and/or clinical follow-up (until symptoms disappeared) were considered to be proof of the presence of bone metastases and bone/joint infection. All of the eighteen patients with diagnosed bone metastases and of the eighteen patients with diagnosed bone and joint infection had positive 99 Tc m -MDP scintigraphy. The fifteen patients with diagnosed bone metastases and the fifteen patients with diagnosed bone/joint infection had increased 99 Tc m (V) -DMSA accumulation at certain areas matched with those shown in 99 Tc m -MDP scans, and only one patient with diagnosed bone metastases and the fifteen patients with diagnosed bone and joint infection had increased 99 Tc m -Citrate accumulation at certain areas matched with those shown in 99 Tc m -MDP scans. 99 Tc m -MDP scans show 64 bone lesions in the bone metastases while 49 lesions by the 99 Tc m (V)-DMSA scans and only one lesion by the 99 Tc m -Citrate scans respectively. And 99 Tc m -MDP scans show 22 bone lesions in the bone and joint infection while 17 lesions by the 99 Tc m (V)-DMSA imaging and 16 lesions by the 99 Tc m -Citrate imaging respectively. For bone metastases diagnosis, the sensitivity of 99 Tc m (V)-DMSA imaging and 99 Tc m -Citrate imaging were 76.56% and 1.56%, respectively, and the specificity were only 22.73% and 27.27%, respectively. For bone and joint infection diagnosis, the sensitivity of two

Generator of 99m Tc with MnO2 as support of 99 Mo

International Nuclear Information System (INIS)

Granados C, F.; Serrano G, J.

2002-01-01

The generator of 99m Tc with MnO 2 as support of 99 Mo was studied. By mean of static experiments the retention of 99 Mo in MnO 2 in function of the stirring time and of the p H value of the solution of 99 Mo. It was found that the 99 Mo presents 100% of retention in MnO 2 in the rank of p H 3-11 and the balance was reached before of 10 minutes. In dynamic conditions the retention of 99 Mo in MnO 2 at p H=5 was also higher: 99.72%. The generated 99m Tc can be separated from 99 Mo, adsorbed in MnO 2 packed in the column, using distilled water at p H=5 or NaCl solution at 0.9%. With saline solution the elution yields were greater than 80% and only an aliquot of 5 ml was necessary for obtaining this yield. The better results were obtained when the column was packed with 1 g of MnO 2 . The water and the saline solution were passed through of the column with a flux of 1.25 ml/min. (Author)

Status of {sup 99}Mo-{sup 99m}Tc production development by (n, {gamma}) reaction

Energy Technology Data Exchange (ETDEWEB)

Tsuchiya, Kunihiko; Kaminaga, Masanori; Ishihara, Masahiro; Kawamura, Hiroshi [Japan Atomic Energy Agency, Oarai Research and Development Center, Oarai, Ibaraki (Japan); Mutalib, Abdul [National Nuclear Energy Agency of Indonesia (BATAN), Tangerang (Indonesia); Chakrov, Petr [Institute of Nuclear Physics, National Nuclear Center of Republic of Kazakhstan (INP-NNC-RK), Almaty (Kazakhstan)

2012-03-15

Technetium-99m ({sup 99m}Tc) is one of the most commonly used radioisotopes in the field of nuclear medicine. As one of effective uses of the JMTR, JAEA has a plan to produce {sup 99}Mo by (n, {gamma}) method, a parent nuclide of {sup 99m}Tc. JAEA has performed R and D on production method of {sup 99}Mo-{sup 99m}Tc in JMTR cooperating with foreign organizations and relevant Japanese enterprises under the cooperation programs. In this paper, present status of R and D for production of {sup 99}Mo-{sup 99m}Tc in JMTR under international cooperation is introduced and constructions of the irradiation and PIE facilities at the JMTR site are also described. (author)

99mTc-EDTA and 99mTc-DTPA complexes as hydrological tracers

International Nuclear Information System (INIS)

Dominguez, J.; Borroto, J.; Nazco, J.; Perez, E.; Gamboa, R.; Cruz, J.

2002-01-01

The [ 99m Tc-DTPA] 2- and [ 99m Tc-EDTA] 1- were evaluated as radiotracers for short time hydrological studies. Their complex stability after labelling with 9.25 GBq of 99m Tc, the behaviour against pH variations, from 5 to 9, in simulated solutions and in natural river waters and the sorption of these compounds on the river sediments, were tested in laboratory experiments. Finally field double tracing experiments were carried out for each of labelling complexes and Rhodamine WT. From recovery calculations not losses of the 99m Tc activity were observed. The shape of the RTD curves of the [ 99m Tc-DTPA] 2- and [ 99m Tc-EDTA] 1 were quite similar to the Rhodamine Wt ones. May be concluded that both complexes behaved conservatively on the studied environmental conditions. (author)

Novel Tc-99m radiotracers for brain imaging

Directory of Open Access Journals (Sweden)

Alessandra Boschi

2007-09-01

Full Text Available A novel class of Tc-99m complexes able to cross the blood brain barrier has been investigated and described here. These compounds are formed by reacting the bis-substituted nitrido precusors [99mTc(N(PS2] (PS = phosphino-thiol ligand with triethylborane (BEt3 under strictly anhydrous conditions and using non-aqueous solvents. The molecular structure of these tracers was not fully established, but preliminary experimental evidence suggests that they result from the interaction of the Lewis base [99mTc(N(PS2] with the Lewis acid BEt3, which leads to the formation of the novel -B-Nº Tc- adduct. After purification and recovery in a physiological solution, the new borane-nitrido Tc-99m derivatives were injected in rats for evaluating their in vivo biological behavior. Results showed a significant accumulation in brain tissue, thus indicating that these complexes are capable of penetrating the intact blood brain barrier. Uptake in the central nervous system was confirmed by imaging the distribution of activity on the integrated living animal using a YAP(SSPECT small animal scanner.Uma nova classe de complexos de Tc-99m capazes de atravessar a barreira hemato-encefálica foi investigada e descrita neste trabalho. Estes compostos são formados reagindo os precursores bissubstituídos do nitrido [99mTc(N(PS2] (PS = phosphino-tiol ligante com trietillborano (BEt3 sob restritas condições anidras e usando solventes não aquosos. A estrutura molecular desses traçadores não foi totalmente estabelecida, mas evidências experimentais preliminares sugerem que eles resultam da interação da base de Lewis [99mTc(N(PS2] com o ácido de Lewis BEt3, levando a formação do novo aducto -B-Nº Tc-. Após purificação e recuperação em uma solução fisiológica, os novos derivados borano-nitrido-Tc-99m foram injetados em ratos para avaliação de seu comportamento biológico in vivo. Os resultados mostraram uma acumulação significativa no tecido cerebral

Basis for revision 2 of the U.S. Nuclear Regulatory Commission's Regulatory Guide 1.99

International Nuclear Information System (INIS)

Randall, P.N.

1986-01-01

Regulatory Guide 1.99. ''Radiation Damage to Reactor Vessel Materials,'' is being updated to reflect recent studies of the physical basis for neutron radiation damage and efforts to correlate damage to chemical composition and fluence. Revision 2 of the Guide contains several significant changes. Welds and base metal are treated separately. Nickel content is added as a variable and phosphorus removed. The exponent in the fluence factor is reduced, especially at high fluences. And, guidance is given for calculating attenuation of damage through the vessel wall. This paper describes the basis for these changes in the Guide

Optimization of the 99m Tc generator with hydrotalcite as support of 99 Mo

International Nuclear Information System (INIS)

Aranda O, N.

2004-01-01

In the last years, in the laboratories of the National Institute of Nuclear Investigations (ININ) its have been investigating to the hydrotalcite like a material of support of the 99 Mo with the purpose of developing a new technetium generator. During the development of the investigations it has been demonstrated that when putting in contact to the HTC with an aqueous solution that contains anions of any type, the HTC re hydrate and the structure is regenerated to laminate of the hydrotalcite. If the present anions in the solution are molybdate anions (MoO 4 2- ), these anions passed to be part of the structure of the hydrotalcite (HT-MoO 4 ). These anions can contain, in turn, 99 Mo in their composition ( 99 MoO 4 2- ) and equally they can pass to be part of the structure of the hydrotalcite forming the HT- 99 MoO 4 . When the HT- 99 MoO 4 is packed in a column, the 99m Tc that it takes place when decaying the 99 Mo radioactively can separate the column using aqueous solution of NaCl. This way, in previous studies (Serrano, 2000) it was found that the aqueous solution of NaCl to 0.5% it is the but appropriate for elutriate at the 99m Tc from the column the yield of the elution of the 99m Tc was since high (98%) in the first elution, and the radionuclide contamination caused by the presence of 99 Mo in the eluate it was low ( 4 2- for gram of HTC). These facts, standing out the high capacity of the HTC to retain molybdate ions, they drove from a direct way to investigate the optimization of the generator of 99m Tc, with hydrotalcite like support of the 99 Mo, using 99 Mo of low specific activity. This finishes radioactive material it can be obtained by the irradiation of the 98 Mo (in the chemical form of MoO 3 or (NH 4 ) 2 MoO 4 ), with a flow of thermal neutrons in the nuclear reactor TRIGA Mark lll that one has in the Nuclear Center N abor Carrillo Flores . The technetium generators with alumina like support of the 99 Mo use 99 Mo of high specific activity

Evaluation of 99Mo/99mTc generator experiment using PZC material and irradiated natural molybdenum

International Nuclear Information System (INIS)

Khongpetch, P.; Chingjit, S.; Dangprasert, M.; Rangsawai, W.; Virawat, N.

2006-01-01

Technetium-99m ( 99m Tc) is the most widely used radioisotope in nuclear medicine, accounting for more than 80% of all diagnostic nuclear medicine procedure. 99m Tc is almost exclusively produced from the decay of its parent molybdenum-99 ( 99 Mo). The present sources of 99 Mo are research reactors by using the (n, γ) nuclear reaction with natural molybdenum, resulting in inexpensive but low specific activity 99 Mo, or by neutron-induced fission of uranium-235, which result in expensive but high specific activity 99 Mo. The technology requirement for processing of 99 Mo from the (n, γ) 'activation method' is rather simple, and is within the reach of most developing countries operating research reactors. In the fission method' the technological and infrastructure requirements are some complex, and possibly can be sustained only by countries with advanced nuclear technology. To overcome these difficulties, Japan Atomic Energy Research Institute (JAERI) and KAKEN company have developed alternative technology for 99 Mo/ 99m Tc generator by using a molybdenum absorbent called Poly Zirconium compound (PZC) and irradiated natural molybdenum. The paper describes experiments for evaluation the performance of PZC as a column packing material for 99 Mo/ 99m Tc generator from (n, γ) 99 Mo. (author)

{sup 99m}Tc-labeled chimeric anti-NCA 95 antigranulocyte monoclonal antibody for bone marrow imaging

Energy Technology Data Exchange (ETDEWEB)

Sarwar, M.; Higuchi, Tetsuya; Tomiyoshi, Katsumi [Gunma Univ., Maebashi (Japan). School of Medicine] [and others

1998-09-01

Chimeric mouse-human antigranulocyte monoclonal antibody (ch MAb) against non-specific cross-reacting antigen (NCA-95) was labeled with {sup 99m}Tc (using a direct method) and {sup 125}I (using the chloramine T method), and its binding to human granulocytes and LS-180 colorectal carcinoma cells expressing carcinoembryonic antigen on their surfaces, cross-reactive with anti-NCA-95 chimeric monoclonal antibody, increased in proportion to the number of cells added and reached more than 80% and 90%, respectively. In biodistribution studies, {sup 99m}Tc and {sup 125}I-labeled ch anti-NCA-95 MAb revealed high tumor uptake, and the tumor-to-blood ratio was 2.9 after 24 hours. The tumor-to-normal-organ ratio was also more than 3.0 in all organs except for the tumor-to-kidney ratio. Scintigrams of athymic nude mice confirmed the results of biodistribution studies that showed higher radioactivity in tumor and kidney of the mice administered with {sup 99m}Tc-labeled ch MAb. A normal volunteer injected with {sup 99m}Tc-labeled ch anti-NCA-95 antigranulocyte MAb showed clear bone marrow images, and a patient with aplastic anemia revealed irregular uptake in his lumbar spine, suggesting its utility for bone marrow scintigraphy and for the detection of hematological disorders, infections, and bone metastasis. (author)

Determination of Tc-99 in radioactive wastes; Determinacion de Tc-99 en desechos radiactivos

Energy Technology Data Exchange (ETDEWEB)

Rivera S, A. A.

2015-07-01

Tc-99 is a fission product and one of the most important radionuclides from the view point of safety assessment for the disposal of radioactive waste because of its long half-life (2.1 x 10{sup 5} years) and high mobility in soil-water systems, if this is released into the environment in significant quantities can concentrate on plants and animals. Tc-99 is a pure beta emitter with a maximum energy of 292 KeV, so their quantification imposes destructive methods to be analyzed by liquid scintillation. Therefore the quantification of Tc-99 in ion exchange resins requires of the mineralization of these and separation of Tc-99 of other radioisotopes present in the resin. Therefore the object of this thesis is to develop a quantification method of Tc-99 content in spent exchange resins. So in order to track the behavior of technetium during digestion exchange resins and radiochemical separation, given its high volatility, in this work the {sup 99m}Tc is used. To determine the degree of mineralization of the resins, an analysis was performed by chromatography. Subsequently the method used to determine the percentage of {sup 99m}Tc aerosolized during mineralization of resin is described. After the method for the radiochemical separation of {sup 99m}Tc is presented by liquid-liquid extraction using crown ether as extractant; for this testing was performed by varying the molarity of the extractant, the ratio of solvent extractant, type of digestion of the resin and the presence of Sr-85, in order to study the behavior of {sup 99m}Tc in the presence of this radioisotope. Finally, a track beta spectra of a sample of {sup 99m}Tc eluted from a generator {sup 99}Mo/{sup 99m}Tc function of time was performed. (Author)

Technetium-99 levels in pertechnetate solutions from (n,γ) and (n,f) molybdenum-99 generators

International Nuclear Information System (INIS)

Moore, P.W.

1983-04-01

There is increasing evidence that, in some radiopharmaceutical kits, Tc-99 has an adverse effect on the imaging and labelling performance of Tc-99m. For example, labelling efficiency with red blood cells can be affected when 99/99m ratios exceed about 4:1. The 99/99m ratio in a target is about 13.5:1 after a seven-day irradiation in a nuclear reactor. The ratio increases slightly during the time needed for processing. With the chromatographic generators used in hospitals, up to 90 hours may elapse between the final wash stage of manufacture and the first elution, during which time, 99/99m ratios can increase to about 90:1. If elution efficiencies are high and the time between elutions is between 12 and 24 hours, ratios in the generator, hence in the eluates, may actually increase with each elution. In the case of ready-to-inject pertechnetate solutions, the critical time at which 99/99m ratios increase rapidly is the time between elution and use. If production conditions are poor, ratios may increase to more than 600:1 by the time of use. With better conditions and production schedules Tc-99 levels at the time of use are comparable to those from chromatographic generators

Efficacy of interventions to combat tobacco addiction: Cochrane update of 2012 reviews.

Science.gov (United States)

Hartmann-Boyce, Jamie; Stead, Lindsay F; Cahill, Kate; Lancaster, Tim

2013-10-01

The Cochrane Collaboration is an international not-for-profit organization which produces and disseminates systematic reviews of health-care interventions. This paper is the first in a series of annual updates of Cochrane reviews on tobacco addiction interventions. It also provides an up-to-date overview of review findings in this area to date and summary statistics for cessation reviews in which meta-analyses were conducted. In 2012, the Group published seven new reviews and updated 13 others. This update summarizes and comments on these reviews. It also summarizes key findings from all the other reviews in this area. New reviews in 2012 found that in smokers using pharmacotherapy, behavioural support improves success rates [risk ratio (RR) 1.16, 95% confidence interval (CI) = 1.09-1.24], and that combining behavioural support and pharmacotherapy aids cessation (RR 1.82, 95% CI = 1.66-2.00). Updated reviews established mobile phones as potentially helpful in aiding cessation (RR 1.71, 95% CI = 1.47-1.99), found that cytisine (RR 3.98, 95% CI = 2.01-7.87) and low-dose varenicline (RR 2.09, 95% CI = 1.56-2.78) aid smoking cessation, and found that training health professionals in smoking cessation improves patient cessation rates (RR 1.60, 95% CI = 1.26-2.03). The updated reviews confirmed the benefits of nicotine replacement therapy, standard dose varenicline and providing cessation treatment free of charge. Lack of demonstrated efficacy remained for partner support, expired-air carbon monoxide feedback and lung function feedback. Cochrane systematic review evidence for the first time establishes the efficacy of behavioural support over and above pharmacotherapy, as well as the efficacy of cytisine, mobile phone technology, low-dose varenicline and health professional training in promoting smoking cessation. © 2013 Society for the Study of Addiction.

Scintigraphic findings on 99mTc-MDP, 99mTc-sestamibi and 99mTc-HMPAO images in Gaucher's disease

International Nuclear Information System (INIS)

Mariani, G.; Molea, N.; La Civita, L.; Porciello, G.; Lazzeri, E.; Ferri, C.

1996-01-01

We report here on the use of the lipophilic cationic complex technetium-99m sestamibi ( 99m Tc-MIBI), employed as an indicator of increased cellular density and metabolic activity, to evaluate Gaucher cell infiltrates in the bone marrow; 99m Tc-hexametazime ( 99m Tc-HMPAO) was also employed, as a pure indicator of lipidic infiltration in the bone marrow. A 67-year-old patient with known type 1 Gaucher's disease presented with a painful left hip and knee and difficulty in gait subsequent to traumatic fracture of the left femoral neck that had required implant of a fixation screw-plaque. Bone scan with 99m Tc-methylene diphosphonate revealed reduced uptake at the distal metaphyseal-epiphyseal femoral region. In addition, whole-body maps and spot-view acquisitions of the thighs and legs were recorded at both 30 min and 2.5 h after the injection of 99m Tc-MIBI: the scintigraphic pattern clearly showed increased uptake at several sites involved by Gaucher deposits in the bone marrow (both knees, with variable intensity in different areas), matching the bone changes detected by conventional x-ray. The target to non-target ratios slowly decreased with time, from an average value of 2.25 in the early scan to an average value of 2 in the delayed scan. The lipid-soluble agent 99m Tc-HMPAO exhibited a superimposable scintigraphic pattern of accumulation at the involved sites, though with lower target to non-target ratios (1.27-1.48). The results obtained in this patient suggest a potential role of 99m Tc-MIBI in the scintigraphic evaluation of Gaucher's lipid deposits in the bone marrow. If the results are confirmed in other patients, this radiopharmaceutical would offer clear advantages over 133 Xe because of its wider availability and greater practicality (i.v. administration of 99m Tc-MIBI versus inhalation of 133 Xe, and use of a single gamma camera instead of two as with 133 Xe). (orig.). With 3 figs

Localization diagnosis of hyperfunctional parathyroid gland using 99Tcm-MIBI and 99TcmO4- imaging

International Nuclear Information System (INIS)

Zhang Fenru; Deng Huixing; Duan Xiaoyi; Xue Jianjun; Gao Rui

2010-01-01

Objective: To study the localization diagnosis value of nuclide imaging by 99 Tc m -MIBI double phase parathyroid combined with 99 Tc m O 4 - thyroid imaging in patients with hyperparathyroidism (HPT). Methods: Patients with primary HPT were 36 cases. Control groups were 10 cases with thyroid disease. Early phase imaging was performed in 15 minute after injecting imaging agent 99 Tc m -MIBI. Delay phase imaging was performed in 2 hours. 36 HPT patients and 10 cases control groups were also performed 99 Tc m O 4 - thyroid imaging 24 hours later. The two kinds of imaging were compared with each other, were analyzed, and were underwent imaging subtracted by eyes and imaging results judgment. Results: In 36 cases of HPT patients, 34 cases showed positive result imaging with 99 Tc m -MIBI/ 99 Tc m O 4 - imaging. 2 cases showed false negative result. Positive rate was 94.44 % with 99 Tc m -MIBI/ 99 Tc m O 4 - imaging. The positive result imaging showed abnormal increased uptake of 99 Tc m -MIBI. In 36 cases of HPT patients, 12 cases showed positive result with single 99 Tc m -MIBI imaging. 4 cases showed false negative imaging. 20 cases showed ambiguous positive results. Positive rate was 88.89% (55.56% was ambiguous positive results) with single 99 Tc m -MIBI imaging. In 10 cases control groups, 3 cases showed false positive results with single 99 Tc m -MIBI imaging. 1 case showed ambiguous false positive results. No case showed false positive result with 99 Tc m -MIBI/ 99 Tc m O 4 - imaging. Conclusion: 99 Tc m -MIBI parathyroid double phase imaging combined with 99 Tc m O 4 - thyroid imaging have important value for diagnoses and localization of hyperparathyroidism. 99 Tc m -MIBI/ 99 Tc m O 4 - imaging have higher positive rate and higher specificity than single 99 Tc m -MIBI imaging for diagnoses and localization of hyperfunction parathyroid gland. (authors)

Optimization of the {sup 99m} Tc generator with hydrotalcite as support of {sup 99} Mo; Optimizacion del generador de {sup 99m} Tc con hidrotalcita como soporte del {sup 99} Mo

Energy Technology Data Exchange (ETDEWEB)

Aranda O, N

2004-07-01

In the last years, in the laboratories of the National Institute of Nuclear Investigations (ININ) its have been investigating to the hydrotalcite like a material of support of the {sup 99} Mo with the purpose of developing a new technetium generator. During the development of the investigations it has been demonstrated that when putting in contact to the HTC with an aqueous solution that contains anions of any type, the HTC re hydrate and the structure is regenerated to laminate of the hydrotalcite. If the present anions in the solution are molybdate anions (MoO{sub 4}{sup 2-}), these anions passed to be part of the structure of the hydrotalcite (HT-MoO{sub 4}). These anions can contain, in turn, {sup 99} Mo in their composition ({sup 99}MoO{sub 4}{sup 2-}) and equally they can pass to be part of the structure of the hydrotalcite forming the HT-{sup 99}MoO{sub 4}. When the HT-{sup 99}MoO{sub 4} is packed in a column, the {sup 99m}Tc that it takes place when decaying the {sup 99}Mo radioactively can separate the column using aqueous solution of NaCl. This way, in previous studies (Serrano, 2000) it was found that the aqueous solution of NaCl to 0.5% it is the but appropriate for elutriate at the {sup 99m}Tc from the column the yield of the elution of the {sup 99m}Tc was since high (98%) in the first elution, and the radionuclide contamination caused by the presence of {sup 99}Mo in the eluate it was low (<0.01%). In this investigation it was also found that the HTC has a high capacity to retain molybdate ions (255.1 mg of ions MoO{sub 4}{sup 2-} for gram of HTC). These facts, standing out the high capacity of the HTC to retain molybdate ions, they drove from a direct way to investigate the optimization of the generator of {sup 99m}Tc, with hydrotalcite like support of the {sup 99}Mo, using {sup 99}Mo of low specific activity. This finishes radioactive material it can be obtained by the irradiation of the {sup 98}Mo (in the chemical form of MoO{sub 3} or (NH{sub 4

Evaluation of the absorbed dose to the kidneys due to Tc{sup 99m} (DTPA) / Tc{sup 99m} (Mag3) and Tc{sup 99m} (Dmsa); Evaluacion de la dosis absorbida en los rinones debido al Tc{sup 99m} (DTPA) / Tc{sup 99m} (MAG3) y Tc{sup 99m} (DMSA)

Energy Technology Data Exchange (ETDEWEB)

Vasquez A, M.; Murillo C, F.; Castillo D, C.; Rocha J, J.; Sifuentes D, Y.; Sanchez S, P. [Universidad Nacional de Trujillo, Av. Juan Pablo II s/n, Trujillo (Peru); Idrogo C, J.; Marquez P, F., E-mail: marvva@hotmail.com [Instituto Nacional de Enfermedades Neoplasicas, Av. Angamos 2520, Lima (Peru)

2015-10-15

The absorbed dose in the kidneys of adult patients has been assessed using the biokinetics of radiopharmaceuticals containing Tc{sup 99m} (DTPA) / Tc{sup 99m} (Mag3) or Tc{sup 99m} (Dmsa).The absorbed dose was calculated using the formalism MIRD and the Cristy-Eckerman representation for the kidneys. The absorbed dose to the kidneys due to Tc{sup 99m} (DTPA) / Tc{sup 99m} (Mag3), are given by 0.00466 mGy.MBq{sup -1} / 0.00339 mGy.MBq{sup -1}. Approximately 21.2% of the absorbed dose is due to the bladder (content) and the remaining tissue, included in biokinetics of Tc{sup 99m} (DTPA) / Tc{sup 99m} (Mag3). The absorbed dose to the kidneys due to Tc{sup 99m} (Dmsa) is 0.17881 mGy.MBq{sup -1}. Here, 1.7% of the absorbed dose is due to the bladder, spleen, liver and the remaining tissue, included in biokinetics of Tc{sup 99m} (Dmsa). (Author)

Rechargeable sup(99)MO/sup(99m)TC generator system

International Nuclear Information System (INIS)

Thornton, A.K.; Cerone, F.E.

1980-01-01

A rechargeable radioisotope generator system is described in which the transfer of the parent isotope, molybdenum 99, can be affected safely and easily. Part of the system consists of a shielded shipping vial for the parent isotope. The generator consists of an alumina column upon which molybdenum 99 may be adsorbed and from which technetium 99m may be eluted. The generator is shipped as a cold package to the user and is charged as needed. A transfer mechanism is incorporated in the shipping shield, which allows the septum of the vial to be pierced and the contents to be transferred to the generator essentially automatically. (LL)

Direct production of ^99mTc using a small medical cyclotron

Energy Technology Data Exchange (ETDEWEB)

Lapi, Suzanne [Washington Univ., St. Louis, MO (United States)

2017-10-03

This project describes an investigation towards the production of ^99mTc with a small medical cyclotron. This endeavor addresses the current urgent problem of availability of ^99mTc due to the ongoing production reactor failures and the upcoming Canadian reactor shut down. Currently, ^99mTc is produced via nuclear fission using highly enriched uranium which is a concern due to nuclear proliferation risks. In addition to this, the United States is dependent solely on currently unreliable foreign sources of this important medical isotope. Clearly, a need exists to probe alternative production routes of ^99mTc. In the first year, this project measured cross-sections and production yields of potential pathways to ^99mTc and associated radionuclidic impurities produced via these pathways using a small 15 MeV medical cyclotron. During the second and third years target systems for the production of ^99mTc via the most promising reaction routes were developed and separation techniques for the isolation of ^99mTc from the irradiated target material will be investigated. Systems for the recycling of the enriched target isotopes as well as automated target processing systems were examined in years four and five. This project has the potential to alleviate some of the current crisis in the medical community by developing a technique to produce ^99mTc on location at a university hospital. This technology will be applicable at many other sites in the United States as many other similar, low energy (<20 MeV) cyclotrons (currently used for a few hours per day for the production of [¹⁸F]fluorodeoxyglucose) are available for production of ^99mTc though this method, thus leading to job creation and preservation.

The preparation and biodistribution of a new 99Tcm-nitrito complex 99TcmN-MIBI

International Nuclear Information System (INIS)

Zhang Xianzhong; Wang Xuebin; Zhang Junbo

1997-01-01

The technetium-99m nitrito intermediate is synthesized by using SnCl 2 ·2H 2 O as reductant, and the complex 99 Tc m N-MIBI is obtained through ligand exchange reaction. The labelling yield of 99 Tc m N-MIBI is over 95% by TLC. The conditions of preparing 99 Tc m N-MIBI are optimized. Results of stability and partition coefficient of 99 Tc m N-MIBI indicate that the complex is lipophilic and stable over 10 h at room temperature. The biodistribution of 99 Tc m N-MIBI in mice shows high myocardium uptake, and rather rapid clearance. For 5-min post-injection the heart-to-blood, heart-to-lung and heart-to-liver ratios are 3.18, 1.72 and 1.42, respectively. The new complex may be suitable for instant myocardial imaging. 99 Tc m N-MIBI has significant different biodistribution characteristics from 99 Tc m -MIBI. Based on these promising properties, 99 Tc m N-MIBI should be a new potential myocardial perfusion imaging agent

The use of 99Mo/99mTc generators in the analysis of low levels of 99Tc in environmental samples by radiochemical methods

International Nuclear Information System (INIS)

Dowdall, M.; Selnaes, Oe.G.; Lind, B.; Gwynn, J.P.

2010-01-01

The analysis of low levels of 99 Tc in environmental samples presents special challenges, particularly with respect to the selection of an appropriate and practicable chemical yield tracer. Of all the tracers available, 99m Tc eluted from 99 Mo/ 99m Tc generators appears to be the most practicable in terms of availability, ease of use and cost. These factors have led to an increase in the use of such generators for the provision of 99m Tc as yield tracer for 99 Tc. For the analysis of low levels ( 3 or kg) of 99 Tc in environmental samples, consideration must be given to the radiochemical purity of the tracer solution with respect to contamination with both 99 Tc and other radionuclides. Due to the variable nature of the extent of the interference from tracer solution to tracer solution, it is unwise to try and establish a correction factor for any single generator. The only practical solution to the problem therefore is to run a 'blank' sample with each batch of samples drawn from a single tracer solution. (LN)

Diversification in the Supply Chain of (99)Mo Ensures a Future for (99m)Tc.

Science.gov (United States)

Cutler, Cathy S; Schwarz, Sally W

2014-07-01

The uncertain availability of (99m)Tc has become a concern for nuclear medicine departments across the globe. An issue for the United States is that currently it is dependent on a supply of (99m)Tc (from (99)Mo) that is derived solely by production outside the United States. Since the United States uses half the world's (99)Mo production, the U.S. (99)Mo supply chain would be greatly enhanced if a producer were located within the United States. The fragility of the old (99)Mo supply chain is being addressed as new facilities are constructed and new processes are developed to produce (99)Mo without highly enriched uranium. The conversion to low-enriched uranium is necessary to minimize the potential misuse of highly enriched uranium in the world for nonpeaceful means. New production facilities, new methods for the production of (99)Mo, and a new generator elution system for the supply of (99m)Tc are currently being pursued. The progress made in all these areas will be discussed, as they all highlight the need to embrace diversity to ensure that we have a robust and reliable supply of (99m)Tc in the future. © 2014 by the Society of Nuclear Medicine and Molecular Imaging, Inc.

99mTc gel generators based on zirconium molybdate-99Mo: III: Influence of preparatory conditions of zirconium molybdate-99Mo gel on generator performance

International Nuclear Information System (INIS)

Saraswathy, P.; Sarkar, S.K.; Arjun, G.; Ramamoorthy, N.; Nandy, S.K.

2004-01-01

The effect of subtle variations on zirconium molybdate- 99 Mo gel preparatory conditions, such as stoichiometry of reactants, pH of gel formation, conditioning of gel granules etc., prior to elution were investigated primarily to arrive at the conditions resulting in high 99m Tc release and minimal 99 Mo breakthrough upon elution with normal saline. Zirconium molybdate- 99 Mo gels were prepared by reacting solutions of Zr and Mo in mole ratios of 0.75-1.5. Both water and normal saline were used for gel disintegration, and the release of 99m Tc and 99 Mo from gel columns into eluates was compared. Sharper elution profile of 99m Tc, but with significantly higher 99 Mo breakthrough (5-8 times), was obtained when water alone was used for disintegration and elution, in comparison to when saline was used. Gels exhibiting optimum characteristics were found to be formed at a pH of 4-5 by reacting [Zr]: [Mo] in the mole ratio of 1.25: 1 and after drying, the product was dispersed into granules by disintegration with normal saline. 99m Tc elution efficiency was found to be ∝ 75% and 99 Mo breakthrough ∝ 0.05%. The elution profile was sharp when a 6 g gel column coupled to a 2 g acidic alumina column (to trap 99 Mo) was eluted with 6-9 ml normal saline. Generators containing upto 23 GBq 99 Mo were prepared, eluted extensively without changing the alumina column and found to provide pertechnetate of good quality, commensurate with hospital radiopharmacy requirements. (orig.)

29 CFR 99.400 - Responsibilities.

Science.gov (United States)

2010-07-01

... 29 Labor 1 2010-07-01 2010-07-01 true Responsibilities. 99.400 Section 99.400 Labor Office of the... Pass-through Entities § 99.400 Responsibilities. (a) Cognizant agency for audit responsibilities... the report submission due date required by § 99.320(a). The cognizant agency for audit may grant...

Cyclotron Production of Technetium-99m

Science.gov (United States)

Gagnon, Katherine M.

Technetium-99m (99mTc) has emerged as the most widely used radionuclide in medicine and is currently obtained from a 99Mo/ 99mTc generator system. At present, there are only a handful of ageing reactors worldwide capable of producing large quantities of the parent isotope, 99Mo, and owing to the ever growing shutdown periods for maintenance and repair of these ageing reactors, the reliable supply 99mTc has been compromised in recent years. With an interest in alternative strategies for producing this key medical isotope, this thesis focuses on several technical challenges related to the direct cyclotron production of 99mTc via the 100Mo(p,2n)99mTc reaction. In addition to evaluating the 100Mo(p,2n)99mTc and 100Mo(p,x)99Mo reactions, this work presented the first experimental evaluation of the 100Mo(p,2n) 99gTc excitation function in the range of 8-18 MeV. Thick target calculations suggested that large quantities of cyclotron-produced 99mTc may be possible. For example, a 6 hr irradiation at 500 μA with an energy window of 18→10 MeV is expected to yield 1.15 TBq of 99mTc. The level of coproduced 99gTc contaminant was found to be on par with the current 99Mo/99mTc generator standard eluted with a 24 hr frequency. Highly enriched 100Mo was required as the target material for 99mTc production and a process for recycling of this expensive material is presented. An 87% recovery yield is reported, including metallic target preparation, irradiation, 99mTc extraction, molybdate isolation, and finally hydrogen reduction to the metal. Further improvements are expected with additional optimization experiments. A method for forming structurally stable metallic molybdenum targets has also been developed. These targets are capable of withstanding more than a kilowatt of beam power and the reliable production and extraction of Curie quantities of 99mTc has been demonstrated. With the end-goal of using the cyclotron-produced 99mTc clinically, the quality of the cyclotron

Comparison of 99Tcm(V)-DMSA and 99Tcm-MIBI scintigraphy in medullary thyroid carcinoma

International Nuclear Information System (INIS)

Deng Bo; Xiao Huan; Chen Xiaofeng; Chen Huaming

2004-01-01

SPECT scintigraphy is used in 62 patients with medullary thyroid carcinoma (MTC), which are divided into two groups: 32 patients by 99 Tc m (V)-DMSA and 30 patients by 99 Tc m -MIBI. The qualitative analysis and half quantitative analysis are performed to the early and delayed images. Comparing the results with two groups, there is no difference in the masculine rate of MTC primary focus, but the results of 99 Tc m (V)-DMSA scintigraphy is obviously larger than 99 Tc m -MIBI by half quantitative analysis. The results show that the 99 Tc m (V)-DMSA scintigraphy is more predominant than the 99 Tc m -(V)-DMSA scintigraphy may be superior to 99 Tc m -MIBI in MTC primary focus and metastasis focus before surging for MTC patients. (authors)

Generator of {sup 99m} Tc with MnO{sub 2} as support of {sup 99} Mo; Generador de {sup 99m} Tc con MnO{sub 2} como soporte del {sup 99}Mo

Energy Technology Data Exchange (ETDEWEB)

Granados C, F.; Serrano G, J. [Departamento de Quimica, Instituto Nacional de Investigaciones Nucleares, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

2002-07-01

The generator of {sup 99m} Tc with MnO{sub 2} as support of {sup 99} Mo was studied. By mean of static experiments the retention of {sup 99} Mo in MnO{sub 2} in function of the stirring time and of the p H value of the solution of {sup 99} Mo. It was found that the {sup 99} Mo presents 100% of retention in MnO{sub 2} in the rank of p H 3-11 and the balance was reached before of 10 minutes. In dynamic conditions the retention of {sup 99} Mo in MnO{sub 2} at p H=5 was also higher: 99.72%. The generated {sup 99m} Tc can be separated from {sup 99} Mo, adsorbed in MnO{sub 2} packed in the column, using distilled water at p H=5 or NaCl solution at 0.9%. With saline solution the elution yields were greater than 80% and only an aliquot of 5 ml was necessary for obtaining this yield. The better results were obtained when the column was packed with 1 g of MnO{sub 2}. The water and the saline solution were passed through of the column with a flux of 1.25 ml/min. (Author)

Study of the elution 99Mo-99mTc generators produced at IPEN-CNEN/SP

International Nuclear Information System (INIS)

Lopes, Paula Regina Corain; Osso Junior, Joao Alberto

2007-01-01

Over the last years 99m Tc has become a very important asset in modern nuclear medicine, due to the emission of gamma ray of optimal energy (140 keV) and a suitable half-life (6.04 h). A further attribute of 99m Tc is its formation from the decay of 99 Mo and the availability from 99 Mo- 99m Tc generator systems. The most common and practical generator types consist of a chromatographic column packed with aluminium oxide, onto which the highly purified fission product 99 Mo (imported from Canada) is adsorbed in the form of molybdate. 99m Tc is further eluted with saline solution. The objective of this work is to study the performance and the elution profile of 99m Tc from high activity generators in order to decrease molybdenum and aluminium concentration. The experiments involved the use of paper filters and Sep Pak columns and also the changing in the time interval between elutions. 99 Mo breakthrough was measured using a dose calibrator and aluminium by UV-Vis spectrophotometry. The best results were achieved using a Sep Pak column containing neutral aluminium oxide. (author)

99mTc-Tetrofosmin scintimammography in suspected breast cancer patients: comparison with 99mTc-MIBI

International Nuclear Information System (INIS)

Kim, Seong Jang; Kim, In Ju; Kim, Yong Ki; Bae, Young Tae

2000-01-01

The aim of this study was to investigate the diagnostic role of 99m Tc-Tetrofosmin in detection of breast cancer and compared with that of 99m Tc-MIBI. Forty-eight patients with a clinically palpable mass or abnormal mammographic or ultrasonographic findings had 99m Tc-MIBI and 99m Tc-Tetrofosmin scintimammographies after intravenous injection of 925 MBq of radiopharmaceuticals. The scintimammographs were correlated with histopathologic findings. Thirty-three patients were diagnosed with breast cancer and 15 patients with benign breast diseases. The numbers of true positive, true negative, false positive, and false negative cases of 99m Tc-MIBI scintimammography were 29, 10, 5, and 4 respectively. The sensitivity, specificity, positive predictive value, and negative predictive value of 99m Tc-MIBI scintimammographies were 87.8%, 66.7%, 85.3%, and 71.4% respectively. The numbers of true positive, true negative, false positive, and false negative cases of 99m Tc-Tetrofosmin were 31, 10, 5, and 2 respectively. The sensitivity, specificity, positive predictive value, negative predictive value of 99m Tc-Tetrofosmin were 93.9%, 66.7%, 86.1%, and 73.3% respectively. One patient was false negative in both 99m Tc-Tetrofosmin scintimammographies and its size was 0.5cm. 99m Tc-Tetrofosmin and 99m Tc-MIBI were non-invasive and useful in detection of breast cancer and 99m Tc-Tetrofosmin was comparable to the 99m Tc-MIBI in detection of primary breast cancer.=20

29 CFR 99.105 - Definitions.

Science.gov (United States)

2010-07-01

... 29 Labor 1 2010-07-01 2010-07-01 true Definitions. 99.105 Section 99.105 Labor Office of the Secretary of Labor AUDITS OF STATES, LOCAL GOVERNMENTS, AND NON-PROFIT ORGANIZATIONS General § 99.105 Definitions. Audit finding means deficiencies which the auditor is required by § 99.510(a) to report in the...

Lazy Updating of hubs can enable more realistic models by speeding up stochastic simulations

International Nuclear Information System (INIS)

Ehlert, Kurt; Loewe, Laurence

2014-01-01

To respect the nature of discrete parts in a system, stochastic simulation algorithms (SSAs) must update for each action (i) all part counts and (ii) each action's probability of occurring next and its timing. This makes it expensive to simulate biological networks with well-connected “hubs” such as ATP that affect many actions. Temperature and volume also affect many actions and may be changed significantly in small steps by the network itself during fever and cell growth, respectively. Such trends matter for evolutionary questions, as cell volume determines doubling times and fever may affect survival, both key traits for biological evolution. Yet simulations often ignore such trends and assume constant environments to avoid many costly probability updates. Such computational convenience precludes analyses of important aspects of evolution. Here we present “Lazy Updating,” an add-on for SSAs designed to reduce the cost of simulating hubs. When a hub changes, Lazy Updating postpones all probability updates for reactions depending on this hub, until a threshold is crossed. Speedup is substantial if most computing time is spent on such updates. We implemented Lazy Updating for the Sorting Direct Method and it is easily integrated into other SSAs such as Gillespie's Direct Method or the Next Reaction Method. Testing on several toy models and a cellular metabolism model showed >10× faster simulations for its use-cases—with a small loss of accuracy. Thus we see Lazy Updating as a valuable tool for some special but important simulation problems that are difficult to address efficiently otherwise

Yacon (Smallanthus sonchifolius Poepp. & Endl. as a Novel Source of Health Promoting Compounds: Antioxidant Activity, Phytochemicals and Sugar Content in Flesh, Peel, and Whole Tubers of Seven Cultivars

Directory of Open Access Journals (Sweden)

Forough Khajehei

2018-01-01

Full Text Available The aim of this study was to evaluate the quality characteristics of seven yacon (Smallanthus sonchifolius Poepp. and Endl. cultivars (Cajamarca, Cusco, Early White, Late Red, Morado, New Zealand and Quinault cultivated in the southwest of Germany. The following phyto/chemical traits were investigated in different yacon tuber parts (flesh, peel, and whole tubers: total dry matter, sugar content (fructose, glucose, and sucrose content, total phenolic content (TPC, total flavonoid content (TFC, 2,20-azino-bis(3-ethylbenzothiazoline-6-sulfonic acid (ABTS radical scavenging activity, 2,2-diphenyl-1-picrylhydrazyl (DPPH radical scavenging activity, and Ferric reducing antioxidant power (FRAP. The results indicated a significant interaction between cultivar and tuber part on all of the examined traits (p < 0.0001. Of flesh and whole tuber, cv. Late Red, cv. Morado, and cv. Cajamarca had the highest TPC, TFC, DPPH radical scavenging activity, and FRAP. They also had relatively higher total sugar content. Cv. New Zealand had the lowest amount of sugars, TPC, TFC, DPPH radical scavenging activity, and FRAP, but the highest ABTS radical scavenging activity content in its flesh and whole tuber. Moreover, the results indicated that the peel of yacon tubers contained considerably high amounts of phytochemicals while possessing low sugar contents. Overall, this study provides a broad insight into the phyto/chemical content of yacon tubers from different cultivars, which can be used for further breeding programs, and the selection of proper cultivars for specific food product development.

Preparation of clinical-scale 99Mo/99mTc column generator using neutron activated low specific activity 99Mo and nanocrystalline γ-Al2O3 as column matrix.

Science.gov (United States)

Chakravarty, Rubel; Ram, Ramu; Dash, Ashutosh; Pillai, M R A

2012-10-01

Preparation of clinical-scale (99)Mo/(99m)Tc generator using (n,γ) activated low specific activity (99)Mo and nanocrystalline γ-Al(2)O(3) as a high capacity sorbent matrix is attempted. Nanocrystalline γ-Al(2)O(3) was synthesized by 'solid state mechanochemical' reaction of aluminum nitrate with ammonium bicarbonate. Experimental parameters were optimized to effectively separate (99m)Tc from (99)Mo using this sorbent as the column matrix. The performance features of a 13 GBq (350 mCi) (99)Mo/(99m)Tc generator using this sorbent and (99)Mo produced by (n,γ) route having specific activity 12.9-18.5 GBq/g were evaluated for 10 days. The sorbent possessed the requisite selectivity for (99)Mo and demonstrated a maximum sorption capacity of 200 ± 5mg Mo/g, which is ~10 times higher than that of ordinary acidic alumina. The overall yield of (99m)Tc was >80%, with radionuclidic purity >99.99% and radiochemical purity >99%. The yield of (99m)Tc varied from 7.8 to 2.1 GBq in the eluate for the six days of operation of the generator. The radioactive concentration of (99m)Tc eluted was adequate for the formulation of radiopharmaceuticals. The performance of the generator remained consistent over an extended period of 10 days. The eluted (99m)Tc was suitable for the formulation of (99m)Tc-DMSA and (99m)Tc-EC resulting in high radiolabeling yields (>98%). The effectiveness of γ-Al(2)O(3) as a new generation sorbent in the development of clinically useful (99)Mo/(99m)Tc generator using low specific activity (99)Mo and yielding (99m)Tc with adequate radioactive concentration and high purity suitable for formulation of radiopharmaceuticals is demonstrated. Copyright © 2012 Elsevier Inc. All rights reserved.

Quality control studies of {sup 99}Mo used in {sup 99}Mo/{sup 99m}Tc generators produced at IPEN/CNEN-SP, Brazil

Energy Technology Data Exchange (ETDEWEB)

Said, Daphne S.; Brambilla, Tania P.; Matsuda, Margareth M.N.; Osso Junior, Joao A., E-mail: daphnesaid@usp.br, E-mail: taniabrambilla@yahoo.com.br, E-mail: mmatsuda@ipen.br, E-mail: jaosso@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2015-07-01

{sup 99m}Tc is the most used radionuclide in nuclear medicine. In Brazil, the {sup 99}Mo/{sup 99m}Tc generators are produced exclusively by the Center of Radiopharmacy at IPEN-CNEN/SP, by importing {sup 99}Mo from different suppliers. {sup 99}Mo (t{sub 1/2} = 66 h) is a fission product of {sup 235}U, therefore, it can be accompanied by several radioisotopes that are highly prejudicial for human health, demanding a strict quality control of this product for generators safe use. The European Pharmacopoeia established some parameters and limits that evaluate the quality of the solution of sodium [{sup 99}Mo]molybdate, that is used as raw material for generator's production. The European Pharmacopoeia also recommends some analytical methods to perform these evaluations, however, it has been observed difficulties on the implementation of these methods by the generator's producers. These difficulties are probably related to the lack of practicability of the proposed methods and the extensive list of utilized reagents. In this work some procedures of the European Pharmacopoeia's quality control method for {sup 99}Mo were evaluated. Different types of solid phase exchanger cartridges were tested for retention of {sup 99}Mo in 3 different conditions. Cartridges that presented percentages of retention higher than 90% were also tested for separation of {sup 99}Mo from possible contaminants (Ru e Te). The results shown that solid phase exchanger cartridges that presented percentages of retention of Mo higher than 90% also presented significant percentages of retention of Ru and Te. An alternative method for separation of {sup 99}Mo from {sup 131}I (other contaminant) are also proposed. (author)

A {sup 99m}Tc Generator using PZC for (n,{gamma}) {sup 99}Mo

Energy Technology Data Exchange (ETDEWEB)

Adang, H G; Mutalib, A; Suparman, I; Hamid,; Purwadi, B; Pancoko, M; Setiowati, S; Yulianti, V; Robertus, D H [Radioisotope Production Center, National Atomic Energy Agency Kawasan PUSPIPTEK, Serpong (Indonesia)

1998-10-01

The high performance adsorbent Poly Zirconium Compound (PZC) was produced by Department of Radioisotope, Japan Atomic Energy Research Institute. This compound was developed as an adsorbent for natural Mo (n,{gamma}) {sup 99}Mo-{sup 99m}Tc Generator. In the present paper, we report the performance of the PZC for a {sup 99m}Tc Generator which was focused on the yield, on elution profile and {sup 99}Mo breakthrough. (author)

NEUTRON CROSS SECTION EVALUATIONS OF FISSION PRODUCTS BELOW THE FAST ENERGY REGION

International Nuclear Information System (INIS)

OH, S.Y.; CHANG, J.; MUGHABGHAB, S.

2000-01-01

Neutron cross section evaluations of the fission-product isotopes, 95 Mo, 99 Tc, 101 Ru, 103 Rh, 105 Pd, 109 Ag, 131 Xe, 133 Cs, 141 Pr, 141 Nd, 147 Sm, 149 Sm, 150 Sm, 151 Sm, 152 Sm, 153 Eu, 155 Gd, and 157 Gd were carried out below the fast neutron energy region within the framework of the BNL-KAERI international collaboration. In the thermal energy region, the energy dependence of the various cross-sections was calculated by applying the multi-level Breit-Wigner formalism. In particular, the strong energy dependence of the coherent scattering lengths of 155 Gd and 157 Gd were determined and were compared with recent calculations of Lynn and Seeger. In the resonance region, the recommended resonance parameters, reported in the BNL compilation, were updated by considering resonance parameter information published in the literature since 1981. The s-wave and, if available, p-wave reduced neutron widths were analyzed in terms of the Porter-Thomas distribution to determine the average level spacings and the neutron strength functions. Average radiative widths were also calculated from measured values of resolved energy resonances. The average resonance parameters determined in this study were compared with those in the BNL and other compilations, as well as the ENDF/B-VI, JEF-2.2, and JENDL-3.2 data libraries. The unresolved capture cross sections of these isotopes, computed with the determined average resonance parameters, were compared with measurements, as well as the ENDF/B-VI evaluations. To achieve agreement with the measurements, in a few cases minor adjustments in the average resonance parameters were made. Because of astrophysical interest, the Maxwellian capture cross sections of these nuclides at a neutron temperature of 30 keV were computed and were compared with other compilations and evaluations

Status update on the NIFFTE high precision fission cross section measurement program

International Nuclear Information System (INIS)

Laptev, Alexander B.; Tovesson, Fredrik; Burgett, Eric; Greife, Uwe; Grimes, Steven; Heffner, Michael D.; Hertel, Nolan E.; Hill, Tony; Isenhower, Donald; Klay, Jennifer L.; Kornilov, Nickolay; Kudo, Ryuho; Loveland, Walter; Massey, Thomas; McGrath, Chris; Pickle, Nathan; Qu, Hai; Sharma, Sarvagya; Snyder, Lucas; Thornton, Tyler; Towell, Rusty S.; Watson, Shon

2010-01-01

The Neutron Induced Fission Fragment Tracking Experiment (NIFFTE) program has been underway for nearly two years. The program's mission is to measure fission cross sections of the primary fissionable and fissile materials ( 235 U, 239 Pu, 238 U) as well as the minor actinides across energies from approximately 50 keV up to 20 MeV with an absolute uncertainty of less than one percent while investigating energy ranges from below an eV to 600 MeV. This basic nuclear physics data is being reinvestigated to support the next generation power plants and a fast burner reactor program. Uncertainties in the fast, resolved and unresolved resonance regions in plutonium and other transuranics are extremely large, dominating safety margins in the next generation nuclear power plants and power plants of today. This basic nuclear data can be used to support all aspects of the nuciear renaissance. The measurement campaign is utilizing a Time Projection Chamber or TPC as the tool to measure these cross sections to these unprecedented levels. Unlike traditional fission cross section measurements using time-of-flight and a multiple fission foil configurations in which fission cross sections in relation to that of 235 U are performed, the TPC project uses time-of-flight and hydrogen as the benchmark cross section. Using the switch to hydrogen, a simple, smooth cross section that can be used which removes the uncertainties associated with the resolved and unresolved resonances in 235 U.

Targeting osteomyelitis with complete [99mTc]besilesomab and fragmented [99mTc]sulesomab antibodies: kinetic evaluations

International Nuclear Information System (INIS)

GRATZ, Stefan; KEMKE, Bendix; KEIZE, Patrik; KAMPEN, Wim U.; LUSTER, Markus; HÖFFKEN, Helmut

2016-01-01

The aim of this retrospective study was to compare the targeting of “pure” osteomyelitis (i.e., without surrounding soft tissue infection) by directly 99mTc-labelled complete immunoglobulin G (IgG) monoclonal antibody (MAb) ([99mTc]besilesomab) and by directly 99mTc-labelled fragment antigen-binding (FAb) MAb ([99mTc]sulesomab) in relation to their kinetic fate. A total of 73 patients with “pure” osteomyelitis were examined with [99mTc]besilesomab, (Scintimun®, IBA/CIS bio international, Saclay, France; N.=38) and [99mTc]sulesomab (LeukoScan®, Immunomedics Inc., Morris Plains, NJ, USA; N.=35). Kinetic data were deduced from whole-body and single-photon emission computed tomographic scans, performed 10 minutes to 24 hour p.i. (region-of-interest technique [ROI]). In targeting “pure” osteomyelitis, sensitivities at 1-4 hours were found to be higher for [99mTc]sulesomab (44% and 80% for [99mTc]besilesomab and [99mTc]sulesomab, respectively) but at significantly lower target/background (T/B) ratios than with [99mTc]besilesomab (1.8±0.3 versus 1.4±0.5 for [99mTc]besilesomab and [99mTc]sulesomab respectively; P<0.01). With [99mTc]besilesomab, there was a continuous osteomyelitis uptake over 24 hours, whereas with [99mTc]sulesomab, the maximal uptake occurred mostly within 1-4 hours, with subsequent clearance being slower for antigen-bound activity than for nonspecific background. Hence, diagnosis was possible mostly after 4h with [99mTc]sulesomab but often not before 24 hours with [99mTc]besilesomab, the later increasing significantly (P<0.01) in sensitivity (87% and 84% for [99mTc]besilesomab and [99mTc]sulesomab, respectively). These results show that the higher sensitivity of [99mTc]sulesomab in osteomyelitis targeting at earlier p.i. times does not rely on an increased antibody uptake but on a more rapid clearance of nonspecific background activity due to faster metabolism and excretion. Intact [99mTc]besilesomab show a slow, continuous uptake

Phytochemistry, biological activities and economical uses of the genus S t e r c u l i a and the related genera: A reveiw

Directory of Open Access Journals (Sweden)

Moshera Mohamed El-Sherei

2016-06-01

Full Text Available The genus Sterculia is represented by 200 species which are widespread mainly in tropical and subtropical regions. Some of the Sterculia species are classified under different genera based on special morphological features. These are Pterygota Schott & Endl., Firmiana Marsili, Brachychiton Schott & Endl., Hildegardia Schott & Endl., Pterocymbium R.Br. and Scaphium Schott & Endl. The genus Sterculia and the related genera contain mainly flavonoids, whereas terpenoids, phenolic acids, phenylpropanoids, alkaloids, and other types of compounds including sugars, fatty acids, lignans and lignins are of less distribution. The biological activities such as antioxidant, anti-inflammatory, antimicrobial and cytotoxic activities have been reported for several species of the genus. On the other hand, there is confusion on the systematic position and classification of the genus Sterculia. However, the wide range of the reported flavonoids in the present review is quite significant and can act as a guide for further studies from the chemosystematic point of view. Also the value of the genus Sterculia and its related genera in the traditional medicine and their effective biological activities led to the possibilities of finding new sources of drugs for prospect applications.

Method of producing molybdenum-99

Science.gov (United States)

Pitcher, Eric John

2013-05-28

Method of producing molybdenum-99, comprising accelerating ions by means of an accelerator; directing the ions onto a metal target so as to generate neutrons having an energy of greater than 10 MeV; directing the neutrons through a converter material comprising techentium-99 to produce a mixture comprising molybdenum-99; and, chemically extracting the molybdenum-99 from the mixture.

Synthesis, development and preclinical study of EDDA based 99mTc-5-fluorouracil for brain imaging

International Nuclear Information System (INIS)

Ahmed, N.; Nuclear Medicine, Oncology and Radiotherapy Institute; Saeed, A.M.; Fatima, S.; Irfan, J.; Zia, M.; Zia, N.; Raza, A.

2016-01-01

5-Fluorouracil is used as an antineoplastic agent in solid tumors. The study was conducted to analyze the effect of EDDA on synthesis of 5-fluorouracil with 99m Tc. The 99m Tc-5-flurouracil was formulated using stannous agent, and EDDA. This complex was stable for 4 h, with post labeling efficiency of 92 %. The distribution study in animal model showed that after 30 min 35 ± 8 % of injected dose cross the blood brain barrier and excreted through kidney with no sign of toxicity. It was concluded that the addition of EDDA modified the labeling side in 5-fluorouracil for 99m Tc, which localized in brain and hence can be used further for brain imaging study. (author)

99mTc-MIBI, 99mTc-tetrofosmin and 99mTc-Q12 in vitro and in vivo

International Nuclear Information System (INIS)

Bernard, Bert F.; Krenning, Eric P.; Breeman, Wout A. P.; Ensing, Geert; Benjamins, Harry; Bakker, Willem H.; Visser, Theo J.; Jong, Marion de

1998-01-01

The aim of this study was to compare uptake of 99m Tc-MIBI, 99m Tc-tetrofosmin and 99m Tc-Q12 in vitro and biodistribution in vivo in rats. In vitro, uptake decreased in the order MIBI→tetrofosmin→Q12. Uptake of MIBI and tetrofosmin, but not of Q12, in cultured tumor cells was dependent on the plasma membrane and mitochondrial potential. In vivo, heart uptake of all three compounds was high and stable. Tumor uptake decreased in the order MIBI→Q12→tetrofosmin and the tumor/blood ratio in the order MIBI→tetrofosmin→Q12

Comparison of relative renal function measured with either 99m Tc-DTPA or 99m Tc-EC dynamic scintigraphies with that measured with 99m Tc-DMSA static scintigraphy

Energy Technology Data Exchange (ETDEWEB)

Domingues, F.C.; Fujikawa, G.Y.; Decker, H.; Alonso, G.; Pereira, J.C.; Duarte, P.S. [Centro de Diagnostico Fleury, Sao Paulo, SP (Brazil). Secao de Medicina Nuclear; Sao Paulo Univ. (USP), SP (Brazil). Escola de Saude Publica. Dept. de Epidemiologia]. E-mail: paulo.duarte@fleury.com.br

2006-07-15

Objective: The aim of this study was to compare the renal function measured with either {sup 99m}Tc-DTPA or {sup 99m}Tc-EC dynamic scintigraphies with that measured using {sup 99m}Tc-DMSA static scintigraphy. Methods: the values of relative renal function measured in 111 renal dynamic scintigraphies performed either with {sup 99m}Tc-DTPA (55 studies) or with {sup 99m}Tc-EC (56 studies) were compared with the relative function measured using {sup 99m}Tc-DMSA static scintigraphy performed within a 1-month period. The comparisons were performed using Wilcoxon signed rank test. The number of {sup 99m}Tc-DTPA and {sup 99m}Tc-EC studies that presented relative renal function different by more than 5% from that measured with {sup 99m}Tc-DMSA, using chi square test were also compared. Results: the relative renal function measured with {sup 99m}Tc-EC is not statistically different from that measured with {sup 99m}Tc-DMSA (p = 0.97). The relative renal function measured with {sup 99m}Tc-DTPA was statistically different from that measured using {sup 99m}Tc-DMSA, but with a borderline statistical significance (p = 0.05). The number of studies with relative renal function different by more than 5% from that measured with {sup 99m}Tc-DMSA is higher for the {sup 99m}Tc-DTPA scintigraphy (p 0.04) than for {sup 99m}Tc-EC. Conclusion: the relative renal function measured with {sup 99m}Tc-EC dynamic scintigraphy is comparable with that measured with {sup 99m}Tc-DMSA static scintigraphy, while the relative renal function measured with {sup 99m}Tc-DTPA dynamic scintigraphy presents a significant statistical difference from that measured with {sup 99m}Tc-DMSA static scintigraphy. (author)

Comparison of relative renal function measured with either 99m Tc-DTPA or 99m Tc-EC dynamic scintigraphies with that measured with 99m Tc-DMSA static scintigraphy

International Nuclear Information System (INIS)

Domingues, F.C.; Fujikawa, G.Y.; Decker, H.; Alonso, G.; Pereira, J.C.; Duarte, P.S.; Sao Paulo Univ.

2006-01-01

Objective: The aim of this study was to compare the renal function measured with either 99m Tc-DTPA or 99m Tc-EC dynamic scintigraphies with that measured using 99m Tc-DMSA static scintigraphy. Methods: the values of relative renal function measured in 111 renal dynamic scintigraphies performed either with 99m Tc-DTPA (55 studies) or with 99m Tc-EC (56 studies) were compared with the relative function measured using 99m Tc-DMSA static scintigraphy performed within a 1-month period. The comparisons were performed using Wilcoxon signed rank test. The number of 99m Tc-DTPA and 99m Tc-EC studies that presented relative renal function different by more than 5% from that measured with 99m Tc-DMSA, using chi square test were also compared. Results: the relative renal function measured with 99m Tc-EC is not statistically different from that measured with 99m Tc-DMSA (p = 0.97). The relative renal function measured with 99m Tc-DTPA was statistically different from that measured using 99m Tc-DMSA, but with a borderline statistical significance (p = 0.05). The number of studies with relative renal function different by more than 5% from that measured with 99m Tc-DMSA is higher for the 99m Tc-DTPA scintigraphy (p 0.04) than for 99m Tc-EC. Conclusion: the relative renal function measured with 99m Tc-EC dynamic scintigraphy is comparable with that measured with 99m Tc-DMSA static scintigraphy, while the relative renal function measured with 99m Tc-DTPA dynamic scintigraphy presents a significant statistical difference from that measured with 99m Tc-DMSA static scintigraphy. (author)

In-house cyclotron production of high-purity Tc-99m and Tc-99m radiopharmaceuticals.

Science.gov (United States)

Martini, Petra; Boschi, Alessandra; Cicoria, Gianfranco; Zagni, Federico; Corazza, Andrea; Uccelli, Licia; Pasquali, Micòl; Pupillo, Gaia; Marengo, Mario; Loriggiola, Massimo; Skliarova, Hanna; Mou, Liliana; Cisternino, Sara; Carturan, Sara; Melendez-Alafort, Laura; Uzunov, Nikolay M; Bello, Michele; Alvarez, Carlos Rossi; Esposito, Juan; Duatti, Adriano

2018-05-30

In the last years, the technology for producing the important medical radionuclide technetium-99m by cyclotrons has become sufficiently mature to justify its introduction as an alternative source of the starting precursor [ 99m Tc][TcO 4 ] - ubiquitously employed for the production of 99m Tc-radiopharmaceuticals in hospitals. These technologies make use almost exclusively of the nuclear reaction 100 Mo(p,2n) 99m Tc that allows direct production of Tc-99m. In this study, it is conjectured that this alternative production route will not replace the current supply chain based on the distribution of 99 Mo/ 99m Tc generators, but could become a convenient emergency source of Tc-99m only for in-house hospitals equipped with a conventional, low-energy, medical cyclotron. On this ground, an outline of the essential steps that should be implemented for setting up a hospital radiopharmacy aimed at the occasional production of Tc-99m by a small cyclotron is discussed. These include (1) target production, (2) irradiation conditions, (3) separation/purification procedures, (4) terminal sterilization, (5) quality control, and (6) Mo-100 recovery. To address these issues, a comprehensive technology for cyclotron-production of Tc-99m, developed at the Legnaro National Laboratories of the Italian National Institute of Nuclear Physics (LNL-INFN), will be used as a reference example. Copyright © 2018 Elsevier Ltd. All rights reserved.

a Bottom-Up Geosptial Data Update Mechanism for Spatial Data Infrastructure Updating

Science.gov (United States)

Tian, W.; Zhu, X.; Liu, Y.

2012-08-01

Currently, the top-down spatial data update mechanism has made a big progress and it is wildly applied in many SDI (spatial data infrastructure). However, this mechanism still has some issues. For example, the update schedule is limited by the professional department's project, usually which is too long for the end-user; the data form collection to public cost too much time and energy for professional department; the details of geospatial information does not provide sufficient attribute, etc. Thus, how to deal with the problems has become the effective shortcut. Emerging Internet technology, 3S technique and geographic information knowledge which is popular in the public promote the booming development of geoscience in volunteered geospatial information. Volunteered geospatial information is the current "hotspot", which attracts many researchers to study its data quality and credibility, accuracy, sustainability, social benefit, application and so on. In addition to this, a few scholars also pay attention to the value of VGI to support the SDI updating. And on that basis, this paper presents a bottom-up update mechanism form VGI to SDI, which includes the processes of match homonymous elements between VGI and SDI vector data , change data detection, SDI spatial database update and new data product publication to end-users. Then, the proposed updating cycle is deeply discussed about the feasibility of which can detect the changed elements in time and shorten the update period, provide more accurate geometry and attribute data for spatial data infrastructure and support update propagation.

Evaluation of '99Mo presence in eluates of 99mTc used in nuclear medicine

International Nuclear Information System (INIS)

Ribeiro, Bianca da Silva

2010-01-01

Tc-99m is used for diagnostic imaging in nuclear medicine through SPECT technique. It is obtained by the elution of 99 Mo/ 99m Tc generators. During the elution process 99 Mo can be extracted becoming a radionuclidic impurity. One of the quality parameters of the eluate is the radionuclidic purity, MBT (molybdenum break through), defined as the ratio between 99 Mo and 99m Tc activities in the eluate. The North-American and European pharmacopoeias restrict the 99 Mo content, respectively, in 0.015 e 0.1% and, according to the International Atomic Energy Agency (IAEA), the activity ratio at the moment of administration of the radiopharmaceutical to the patient, should not exceed 0.015%. In Brazil, the control of such parameter is not obliged in official regulations. Thus, the objective of this work is to evaluate the occurrence of 99 Mo in 99m Tc eluates. It was initially optimized a methodology to determine the activity of 99 Mo in eluate samples. Efficiency curves were obtained for a NaI (Tl) 8'' x 4'' scintillation detector installed at the In Vivo Monitoring Laboratory (LABMIV-IRD). The methodology has been validated through the measurement of a 99 Mo standard liquid source calibrated at the National Metrology Laboratory for Ionizing Radiation (LNMRI-IRD). The samples analyzed in this work were gently supplied by 5 Nuclear Medicine Clinics located in the city of Rio de Janeiro. The activities of 99 mTc and 99 Mo in those samples have been measured respectively at the clinics and at the LABMIV. By applying a standardized methodology, the ration between the activities were calculated. The results show that 147 out of 174 samples presented 99 Mo activities above the minimum detectable activity of the technique. On the other hand, only 2 out of 147 samples surpassed the MBT limit suggested by the IAEA and have been detected in samples eluted from generators of 750 mCi. In one of the samples, eluted from a generator of 1000 mCi, the calculated MBT value was very close

A Pebble Bed Reactor cross section methodology

International Nuclear Information System (INIS)

Hudson, Nathanael H.; Ougouag, Abderrafi M.; Rahnema, Farzad; Gougar, Hans

2009-01-01

A method is presented for the evaluation of microscopic cross sections for the Pebble Bed Reactor (PBR) neutron diffusion computational models during convergence to an equilibrium (asymptotic) fuel cycle. This method considers the isotopics within a core spectral zone and the leakages from such a zone as they arise during reactor operation. The randomness of the spatial distribution of fuel grains within the fuel pebbles and that of the fuel and moderator pebbles within the core, the double heterogeneity of the fuel, and the indeterminate burnup of the spectral zones all pose a unique challenge for the computation of the local microscopic cross sections. As prior knowledge of the equilibrium composition and leakage is not available, it is necessary to repeatedly re-compute the group constants with updated zone information. A method is presented to account for local spectral zone composition and leakage effects without resorting to frequent spectrum code calls. Fine group data are pre-computed for a range of isotopic states. Microscopic cross sections and zone nuclide number densities are used to construct fine group macroscopic cross sections, which, together with fission spectra, flux modulation factors, and zone buckling, are used in the solution of the slowing down balance to generate a new or updated spectrum. The microscopic cross-sections are then re-collapsed with the new spectrum for the local spectral zone. This technique is named the Spectral History Correction (SHC) method. It is found that this method accurately recalculates local broad group microscopic cross sections. Significant improvement in the core eigenvalue, flux, and power peaking factor is observed when the local cross sections are corrected for the effects of the spectral zone composition and leakage in two-dimensional PBR test problems.

A novel electrochemical technique for the production of clinical grade 99mTc using (n, γ)99Mo

International Nuclear Information System (INIS)

Chakravarty, Rubel; Dash, Ashutosh; Venkatesh, Meera

2010-01-01

Introduction: In order to meet the growing demand for 99m Tc and to reduce the reliance on fission-produced 99 Mo, an electrochemical pathway for accessing 99m Tc through the (n, γ) 99 Mo was explored as a back-up measure and to supplement 99m Tc supply for radiopharmaceuticals application. Methods: 99m Tc from an equilibrium mixture of 99 Mo/ 99m Tc was selectively deposited on a platinum cathode in an electrochemical cell by applying optimal voltage and stripped back again into the 0.9% saline solution. The radiochemical and radionuclidic purity of the product were determined using standard techniques. 99m Tc thus obtained was used for labeling standard ligands such as dimercaptosuccinic acid (DMSA) and ethylene dicysteine (EC), to ascertain the usability. Results: Selective deposition of 99m Tc on the platinum electrode was achieved at a potential of 5 V over a period of 1 h in NaOH electrobath. The overall yield of 99m Tc was >90%, with >99.99% radionuclidic purity and >99% radiochemical purity. The performance of the generator remained consistent over a period of 10 days. The compatibility of the product in the preparation of 99m Tc-labeled formulations such as 99m Tc-DMSA and 99m Tc-EC was found to be satisfactory in terms of high labeling yields (>98%). Conclusion: A novel and attractive method has been developed to obtain highly concentrated 99m Tc, without using fission-produced 99 Mo.

Separation of sup(99m)Tc from 99MoO3

International Nuclear Information System (INIS)

Tomicic, M.

1977-07-01

At the present time sup(99m)Tc is widely used in nuclear medicine and its uses are increasing. It can be produced by various methods, and of those most frequently used today two have special features making them particularly applicable to the large-scale production of instant sup(99m)Tc - these are solvent extraction with methyl-ethyl-ketone and the sublimation methods. This report presents a bibliographic review of these methods, their main perfomance parameters, and experience obtained from the development and operation of a sublimation generator. Separation of sup(99m)Tc from irradiated MoO 3 was carried out with high yields (75-95%) after multiple repetition of the separation process with molybdenum trioxide heated for half an hour at a maximum temperature of 850-890 deg C in an air flow. The activity ratio of molybdenum in the separated sup(99m)Tc was of the order of 4 x 10 -5 . (author)

Working Memory Updating Latency Reflects the Cost of Switching between Maintenance and Updating Modes of Operation

Science.gov (United States)

Kessler, Yoav; Oberauer, Klaus

2014-01-01

Updating and maintenance of information are 2 conflicting demands on working memory (WM). We examined the time required to update WM (updating latency) as a function of the sequence of updated and not-updated items within a list. Participants held a list of items in WM and updated a variable subset of them in each trial. Four experiments that vary…

Properties of myelin altered peptide ligand cyclo(87-99)(Ala91,Ala96)MBP87-99 render it a promising drug lead for immunotherapy of multiple sclerosis.

Science.gov (United States)

Deraos, George; Rodi, Maria; Kalbacher, Hubert; Chatzantoni, Kokona; Karagiannis, Fotios; Synodinos, Loukas; Plotas, Panayiotis; Papalois, Apostolos; Dimisianos, Nikolaos; Papathanasopoulos, Panagiotis; Gatos, Dimitrios; Tselios, Theodore; Apostolopoulos, Vasso; Mouzaki, Athanasia; Matsoukas, John

2015-08-28

Multiple sclerosis (MS) is an inflammatory, demyelinating disease of the central nervous system, and it has been established that autoreactive T helper (Th) cells play a crucial role in its pathogenesis. Myelin basic protein (MBP) epitopes are major autoantigens in MS, and the sequence MBP87-99 is an immunodominant epitope. We have previously reported that MBP87-99 peptides with modifications at principal T-cell receptor (TCR) contact sites suppressed the induction of EAE symptoms in rats and SJL/J mice, diverted the immune response from Th1 to Th2 and generated antibodies that did not cross react with the native MBP protein. In this study, the linear and cyclic analogs of the MBP87-99 epitope, namely linear (Ala91,Ala96)MBP87-99 (P2) and cyclo(87-99)(Ala91,Ala96)MBP87-99 (P3), were evaluated for their binding to HLA-DR4, stability to lysosomal enzymes, their effect on cytokine secretion by peripheral blood mononuclear cells (PBMC) derived from MS patients or healthy subjects (controls), and their effect in rat EAE. P1 peptide (wild-type, MBP87-99) was used as control. P2 and P3 did not alter significantly the cytokine secretion by control PBMC, in contrast to P1 that induced moderate IL-10 production. In MS PBMC, P2 and P3 induced the production of IL-2 and IFN-γ, with a simultaneous decrease of IL-10, whereas P1 caused a reduction of IL-10 secretion only. The cellular response to P3 indicated that cyclization did not affect the critical TCR contact sites in MS PBMC. Interestingly, the cyclic P3 analog was found to be a stronger binder to HLA-DR4 compared to linear P2. Moreover, cyclic P3 was more stable to proteolysis compared to linear P2. Finally, both P2 and P3 suppressed EAE induced by an encephalitogenic guinea pig MBP74-85 epitope in Lewis rats whereas P1 failed to do so. In conclusion, cyclization of myelin altered peptide ligand (Ala91,Ala96)MBP87-99 improved binding affinity to HLA-DR4, resistance to proteolysis and antigen-specific immunomodulation

FRMAC Updates

International Nuclear Information System (INIS)

Mueller, P.

1995-01-01

This talks describes updates in the following updates in FRMAC publications concerning radiation emergencies: Monitoring and Analysis Manual; Evaluation and Assessment Manual; Handshake Series (Biannual) including exercises participated in; environmental Data and Instrument Transmission System (EDITS); Plume in a Box with all radiological data stored onto a hand-held computer; and courses given

Influence of the electrolyte in the fixation of {sup 99} Mo in hydroxyapatite as matrix of the {sup 99} Mo/ {sup 99m} Tc generator; Influencia del electrolito en la fijacion de {sup 99} Mo en hidroxiapatita coma matriz del generador {sup 99} Mo/ {sup 99m} Tc

Energy Technology Data Exchange (ETDEWEB)

Vazquez G, S.; Badillo A, V.E. [UAZ, Zacatecas (Mexico); Monroy G, F. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)]. e-mail: s_vazgro@hotmail.com

2005-07-01

The more used isotope at the moment in the services of nuclear medicine in the world is the technetium-99m. The {sup 99m} Tc emitts gamma rays of 141 keV and it semi disintegration period is of six hours, given it short half life, to produce it is necessary to order generators that are systems that allow to separate periodically at the {sup 99m}Tc of the {sup 99} Mo by means of chromatographic techniques. In this work it is sought to evaluate the use of the hydroxyapatite, to separate molybdates {sup 99} MoO{sub 4}{sup 2} of pertechnetates {sup 99m}TcO{sub 4}{sup -} and to be able to determine if it is feasible their use for to build generators of {sup 99m} Tc. With this purpose preliminary tests to know the likeness of the hydroxyapatite for the molybdates in function of the pH value, in different solutions were carried out: one of NaCl 0.9%, NaCl 2% and CaCl{sub 2} 0.01 M. The obtained results in a NaCl 0.9% solution and at to 2% to different pH values of the solution, shows that the fixation of the molybdate ions (MoO{sub 4}{sup -2}) it is worthless to basic pH values of (9-11), as long as in solution of CaCI{sub 2} 0.01 M show a considerable retention of molybdate ions. (Author)

32 CFR 99.3 - General definitions.

Science.gov (United States)

2010-07-01

... 32 National Defense 1 2010-07-01 2010-07-01 false General definitions. 99.3 Section 99.3 National... PROCEDURES FOR STATES AND LOCALITIES TO REQUEST INDEMNIFICATION § 99.3 General definitions. For the purposes of §§ 99.1 through 99.9 of this part: Criminal history record information: information collected by...

Environmental behavior of technetium-99

International Nuclear Information System (INIS)

Turcotte, M.D.S.

1982-12-01

This report presents a review of the literature on technetium-99. The chemical and physical properties of some technetium compounds are considered, and a discussion of possible source terms is included. Literature on the environmental behavior of technetium is presented, including its behavior in the bodies of animals and humans. The primary sources of Tc-99 in the environment are fallout from atomic detonations and releases from nuclear fuel reprocessing plants. The environmental behavior of technetium-99 has been studied predominantly with respect to movement in soil and accumulation in plants. There is a surprising scarcity of data on behavior of Tc-99 in the atmosphere and in aquatic systems. Additional work needs to be conducted in these two areas to determine behavior and to acquire baseline concentration data. Much of the soil work has produced contradictory results. In-depth studies of holdup mechanisms for Tc-99 in both geological repositories and soil need to be conducted. Since plants represent a potential bioaccumulation of Tc-99, plant uptake studies of Tc-99 under field conditions also need to be done

{sup 201}Tl, {sup 99m}Tc-MIBI, {sup 99m}Tc-tetrofosmin and {sup 99m}Tc-furifosmin: relative retention and clearance kinetics in retrogradely perfused guinea pig hearts

Energy Technology Data Exchange (ETDEWEB)

Schaefer, Wolfgang M.; Moka, Detlef E-mail: detlef.moka@uni-koeln.de; Brockmann, Holger A.; Schomaecker, Klaus; Schicha, Harald

2002-02-01

Myocellular kinetics of {sup 201}Tl, {sup 99m}Tc-MIBI, {sup 99m}Tc-tetrofosmin and {sup 99m}Tc-furifosmin were investigated using retrogradely-perfused guinea-pig hearts. Relative retention decreased in the order {sup 99m}Tc-MIBI {yields}{yields} implies {sup 99m}Tc-tetrofosmin {yields}{yields} implies {sup 99m}Tc-furifosmin. {sup 201}Tl and {sup 99m}Tc-MIBI exhibited bi- (t1,t2), {sup 99m}Tc-tetrofosmin and {sup 99m}Tc-furifosmin triexponential (t1,t2,t3) time-activity-curves. Latest-phase elimination-half-life increased from {sup 201}Tl (t2) {yields}{yields} implies {sup 99m}Tc-MIBI (t2) {yields}{yields} implies {sup 99m}Tc-tetrofosmin (t3) {yields}{yields} implies {sup 99m}Tc-furifosmin (t3), showing a significant increase in deteriorating myocardium for all tracers but {sup 99m}Tc-furifosmin. Delayed elimination in deteriorating myocardium explains at least partly the redistribution phenomenon of {sup 201}Tl, and suggests a similar phenomenon for {sup 99m}Tc-MIBI and {sup 99m}Tc-tetrofosmin.

Determination of 99Mo in 99mTc eluates used in nuclear medicine centers in Rio de Janeiro

International Nuclear Information System (INIS)

Ribeiro, Bianca da S.; Souza, Raphael S.S.; Lucena, Eder A.; Dantas, Ana Leticia A.; Dantas, Bernardo M.

2009-01-01

99m Tc is used in nuclear medicine for image diagnoses with SPECT. It is obtained from the elution of molybdenum-99/technetium-99m ( 99 Mo/ 99m Tc) generators. During the elution, 99 Mo can detach from the column, passing through the filter and mixing in the solution of pertechnetate eluate and becoming a radionuclidic impurity. The presence of molybdenum in the radiopharmaceutical solution imparts an unnecessary radiation dose to the patient, since its half-life is relatively long (66 hours) and it emits beta particles and high-energy photons of (740 keV). A parameter that indicates the quality of the eluates is the radionuclidic purity, the MBT (molybdenum break through), defined as the ratio between 99 Mo and 99m Tc activities in the eluate. The American and the European Pharmacopoeias restrict 99 Mo content to respectively 0.015% and 0.1% activity ratio 99 Mo/ 99m Tc at the time of the administration to the patient. In Brazil, this parameter is not controlled by official regulations. The objective of this work is to determine the presence of 99 Mo in the eluates used in nuclear medicine centers (NMC). The activity measurements of 99 Mo were performed with a NaI(Tl)8''x4'' scintillation detector installed in the IRD whole body counter. The activity of 99m Tc was measured in the NMC where the eluates were collected and, using the established calculations, it was determined the activity ratio 99 Mo/ 99m Tc. The eluate samples were kindly supplied by the participating NMC of Rio de Janeiro. All measurements indicated the presence of 99 Mo. It is concluded that the technique is sensitive to detect 99 Mo in 99m Tc eluates and permits to verify the quality of the generators used in NMC evaluated in this study. (author)

Influence of the electrolyte in the fixation of 99 Mo in hydroxyapatite as matrix of the 99 Mo/ 99m Tc generator

International Nuclear Information System (INIS)

Vazquez G, S.; Badillo A, V.E.; Monroy G, F.

2005-01-01

The more used isotope at the moment in the services of nuclear medicine in the world is the technetium-99m. The 99m Tc emitts gamma rays of 141 keV and it semi disintegration period is of six hours, given it short half life, to produce it is necessary to order generators that are systems that allow to separate periodically at the 99m Tc of the 99 Mo by means of chromatographic techniques. In this work it is sought to evaluate the use of the hydroxyapatite, to separate molybdates 99 MoO 4 2 of pertechnetates 99m TcO 4 - and to be able to determine if it is feasible their use for to build generators of 99m Tc. With this purpose preliminary tests to know the likeness of the hydroxyapatite for the molybdates in function of the pH value, in different solutions were carried out: one of NaCl 0.9%, NaCl 2% and CaCl 2 0.01 M. The obtained results in a NaCl 0.9% solution and at to 2% to different pH values of the solution, shows that the fixation of the molybdate ions (MoO 4 -2 ) it is worthless to basic pH values of (9-11), as long as in solution of CaCI 2 0.01 M show a considerable retention of molybdate ions. (Author)

Utility of the Static-99 and Static-99R With Latino Sex Offenders.

Science.gov (United States)

Leguízamo, Alejandro; Lee, Seung C; Jeglic, Elizabeth L; Calkins, Cynthia

2017-12-01

The predictive validity of the Static-99 measures with ethnic minorities in the United States has only recently been assessed with mixed results. We assessed the predictive validity of the Static-99 and Static-99R with a sample of Latino sex offenders ( N = 483) as well as with two subsamples (U.S.-born, including Puerto Rico, and non-U.S.-born). The overall sexual recidivism rate was very low (1.9%). Both the Static-99 measures were able to predict sexual recidivism for offenders born in the United States and Puerto Rico, but neither was effective in doing so for other Latino immigrants. Calibration analyses ( N = 303) of the Static-99R were consistent with the literature and provided support for the potential use of the measure with Latinos born in the United States and Puerto Rico. These findings and their implications are discussed as they pertain to the assessment of Latino sex offenders.

Photo-production of (99)Mo/(99m)Tc with electron linear accelerator beam.

Science.gov (United States)

Avagyan, R; Avetisyan, A; Kerobyan, I; Dallakyan, R

2014-09-01

We report on the development of a relatively new method for the production of (99)Mo/(99m)Tc. The method involves the irradiation of natural molybdenum using high-intensity bremsstrahlung photons from the electron beam of the LUE50 linear electron accelerator located at the Yerevan Physics Institute (YerPhi). The production method has been developed and shown to be successful. The linear electron accelerator at YerPhi was upgraded to allow for significant increases of the beam intensity and spatial density. The LUE50 was also instrumented by a remote control system for ease of operation. We have developed and tested the (99m)Tc extraction from the irradiation of natural MoO3. This paper reports on the optimal conditions of our method of (99)Mo production. We show the success of this method with the production and separation of the first usable amounts of (99m)Tc. Copyright © 2014 Elsevier Inc. All rights reserved.

Sapwood area - leaf area relationships for coast redwood

OpenAIRE

Stancioiu, P T; O'Hara, K L

2005-01-01

Coast redwood (Sequoia sempervirens (D. Don) Endl.) trees in different canopy strata and crown positions were sampled to develop relationships between sapwood cross-sectional area and projected leaf area. Sampling occurred during the summers of 2000 and 2001 and covered tree heights ranging from 7.7 to 45.2 m and diameters at breast height ranging from 9.4 to 92.7 cm. Foliage morphology varied greatly and was stratified into five types based on needle type (sun or shade) and twig color. A str...

Performance tests on new chromatographic material for 99Mo-99mTc generators

International Nuclear Information System (INIS)

Sombrito, Elvira Z.; Bulos, Adelina D.M.

2004-01-01

Technetium-99m continues to be the main workhorse of nuclear medicine in the Philippines. Almost 13TBq of 99m Tc was imported to the country in 2002 supplied as 99m Tc- 99 Mo generators. These generators make use of fission molybdenum adsorbed onto an alumina column. Problems associated with the alumina chromatographic generators arise due to safety and economic issues that would be remedied by gel-type generators using low specific activity reactor-produced molybdenum-99 adsorbed on a high capacity gel column material. The Philippine Nuclear Research Institute (PNRI) exerted efforts in this direction by developing a gel-type column, which showed satisfactory molybdenum adsorptive capacity. Likewise, Kaken Co. in Japan in cooperation with Japan Atomic Energy Research Institute (JAERI) developed a dried form of a gel-type polyzirconium compound (PZC). It is a ready-to-use high molybdenum capacity column material for adsorbing reactor-produced molybedum-99. The performance of this material is being tested under the framework of the FNCA project on Research Reactor Utilization. Performance tests on four batches of PZC were performed using fission molybdenum eluted from a 99 Mo- 99m Tc generator. A total of 3.3 GBq 99 Mo was extracted from an alumina column of a commercial generator and mixed with carrier molybdenum solution. About 0.67 GBq was loaded into each of the 12 x 90 mm column. One batch was prepared and distributed in 1999 and tests showed very poor elution yield of 30%. Three recent batches of PZC (2002) gave elution yields of 71% (Range of 69-75). The adsorptive capacity is 99% with about 4% desorption rate. Elution volume is at 5-6 ml. Daily elution for five days gave from 1.6 to 5.5% variability. The tests were performed all at the same time and a trend of improving elution yield and consistency of daily elution yield was observed with the time of testing nearer to the sample preparation date. X-ray diffraction analysis showed an amorphous structure for

22 CFR 99.3 - [Reserved

Science.gov (United States)

2010-04-01

... 22 Foreign Relations 1 2010-04-01 2010-04-01 false [Reserved] 99.3 Section 99.3 Foreign Relations DEPARTMENT OF STATE LEGAL AND RELATED SERVICES REPORTING ON CONVENTION AND NON-CONVENTION ADOPTIONS OF EMIGRATING CHILDREN § 99.3 [Reserved] ...

PHOBINS: an index file of photon production cross section data and its utility code system

International Nuclear Information System (INIS)

Hasegawa, Akira; Koyama, Kinji; Ido, Masaru; Hotta, Masakazu; Miyasaka, Shun-ichi

1978-08-01

The code System PHOBINS developed for reference of photon production cross sections is described in detail. The system is intended to grasp the present status of photon production data and present the information of available data. It consists of four utility routines, CREA, UP-DT, REF and BACK, and data files. These utility routines are used for making an index file of the photon production cross sections, updating the index file, searching the index file and producing a back-up file of the index file. In the index file of the photon production cross sections, a data base system is employed for efficient data management in economical storage, ease of updating and efficient reference. The present report is a reference manual of PHOBINS. (author)

Technetium-99 ({sup 99}Tc) in annual growth segments of knotted wrack (Ascophyllum nodosum)

Energy Technology Data Exchange (ETDEWEB)

Heldal, Hilde Elise, E-mail: Hilde.Heldal@imr.no [Institute of Marine Research (IMR), PO Box 1870 Nordnes, N-5817 Bergen (Norway); Sjotun, Kjersti, E-mail: Kjersti.Sjotun@bio.uib.no [University of Bergen (UoB), Department of Biology, PO Box 7803, N-5020 Bergen (Norway)

2010-10-15

The distribution of technetium-99 ({sup 99}Tc) in annual growth segments of the brown seaweed Ascophyllum nodosum (Fucales, Phaeophyceae) from the southwestern coast of Norway is examined in samples collected from January to November 2006. A twenty-fold increase in the {sup 99}Tc-concentration from the youngest to the oldest growth segments was found. The concentrations ranged from 42 to 98 Bq/kg dry weight (d.w.) and from 964 to 1000 Bq/kg d.w. in growth segments formed in 2006 and 1996, respectively. In addition, a seasonal variation in the {sup 99}Tc concentration was observed in the actively growing 2006-segments: concentrations decreased from 98 Bq/kg d.w. in April to 54 Bq/kg d.w. in June; there was a further reduction from June to August (42 Bq/kg d.w.); and, finally there was an increase from August to November (93 Bq/kg d.w.). In most of the segments formed between 2000 and 2005, there was a tendency of slightly decreasing {sup 99}Tc-concentrations between June and November but this pattern was not observed for the older growth segments. In order to find an explanation for the non-homogenous distribution of {sup 99}Tc within thalli of A. nodosum, different hypotheses are discussed. Uptake and elimination of {sup 99}Tc appears to be most pronounced in the actively growing segments. To date, such non-homogenous distribution of {sup 99}Tc within thalli of A. nodosum has not been taken into consideration, neither in connection with sample collection nor analysis. This paper shows that special protocols must be followed if A. nodosum is going to be used as a bioindicator for {sup 99}Tc in the marine environment. A sampling strategy is proposed.

Preoperative radiological diagnosis by 99mTc·MIBI-99mTc subtraction scintigraphy for primary hyperparathyroidism

International Nuclear Information System (INIS)

Inouye, Takahiro; Tomita, Toshiki; Shinden, Seiichi; Takagi, Hitoshi; Kano, Shigeru.

1996-01-01

Preoperative radiological diagnosis constitutes the most important factor for the surgical treatment of hyperparathyroidism. In this regard, MRI is useful for detecting the abnormal parathyroid, but it is often difficult to localize it using MRI only. It is thus necessary to combine this procedure with excellent subtraction scintigraphy. We performed both 201 Tl- 99m Tc and 99m Tc·MIBI- 99m Tc subtraction scintigraphy in seven patients with primary hyperparathyroidism and compared them the radiological results. Five patients presented parathyroid adenomas and the rest hypertrophy of the parathyroid. We could detect the abnormal parathyroid in four patients (57.1%) by 201 Tl- 99m Tc subtraction scintigraphy and in six patients (85.7%) by 99m Tc·MIBI- 99m Tc subtraction scintigraphy. We therefore believe that 99m Tc·MIBI- 99m Tc subtraction scintigraphy will become an essential examination for primary hyperparathyroidism rather than the presently employed 201 Tl- 99m Tc subtraction scintigraphy. (author)

Problems in clinical practice of domestic supply of 99Mo/99mTc. The direction and problem of stable supply chain of 99Mo in Japan

International Nuclear Information System (INIS)

Inoue, Tomio

2013-01-01

The shortage of supply of 99 Mo caused by trouble of old nuclear reactors in Canada and Europe caused international problem in the field of nuclear medicine, which has not been completely resolved yet. Because all of 99 Mo/ 99m Tc generator in Japan has been imported, Japan Atomic Energy Commission (JAEC) suggested the necessity of establishment of stable supply chain of 99 Mo ( 99 Mo/ 99m Tc generator). According this suggestion, an ad hoc committee appointed to consider the stable supply chain, which consisted of persons concerned with industry, academic society, Japan Isotope Association, Ministry of Education, Culture, Sports, Science, and Technology-Japan (MEXT), Ministry of Health, Labour and Welfare (MHLW), Japan Atomic Energy Agency (JAEA), National Institute of Radiological Science (NIRS) et al., evaluated and compared several ways of production and purification of 99 Mo from the view point of technological maturity, regulation compatibility, economic suitability, and stability for supply. In this review, the summary of the committee report is introduced. For short term strategy, we need to keep the variable import routes for 99 Mo. As a mid-term goal, we need to establish the supply chain inside Japan as a conclusion of the committee report but it seems to be not easy for utility of nuclear reactor after nuclear accident of Fukushima Daiichi Nuclear Power Plant. The development of the method for 99 Mo/ 99m Tc production using accelerator is also expected for the establishment of stable supply chain. (author)

14 CFR 99.12 - [Reserved

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 2 2010-01-01 2010-01-01 false [Reserved] 99.12 Section 99.12 Aeronautics and Space FEDERAL AVIATION ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) AIR TRAFFIC AND GENERAL OPERATING RULES SECURITY CONTROL OF AIR TRAFFIC General § 99.12 [Reserved] ...

The risk analysis used to manufacture 99Mo/99mTc generators

International Nuclear Information System (INIS)

Fano Machín, Yoiz; Alberti Ramírez, Alejandro; Gamboa Marrero, Regla; Suárez Beyríes, Karina; Cruz Morales, Amed

2016-01-01

In this work the steps to be followed for the risk analysis in the process of production of 99 Mo / 99m Tc generators in CENTIS, using the methodology of analysis of modes and effects of failures are collected. The analysis of the type and probability of occurrence of the failures in the process, as well as the impact on the quality of the same and the probability of detection of such failures, were used for the use of techniques used in quality assurance such as: storm Ideas and cause-effect diagram. Scales were established for the determination of severity, probability of occurrence, probability of detection and calculation of the number of risk probabilities. The guidelines were laid down for the future application of this technique, which will establish a decision-making process regarding the risks associated with the production process of 99 Mo / 99m Tc generators. (author)

Fabrication Method of the Mo-99 Target with Advanced Planar Flow Casting

International Nuclear Information System (INIS)

Sim, M. S.; Lee, J. H.; Kim, C. K.; Kim, W. J.

2011-01-01

Mo-99 is a parent isotope of Tc-99m for medical diagnosis and very significant owing to its large fraction over 80% of the whole demand of medical radioisotopes in the all countries. Mo-99 isotope has been produced mainly by 235 U which is extracting fission products. All the major providers of fission Mo have used HEU as a target material. But RERTR program that is nonproliferation policy encourages using HEU to LEU. KAERI has developed a processing to be able to produce a uranium foil continuously at one go. This processing gave an opportunity for LEU target using uranium foil to be commercialized. It correspond RERTR program. KAERI developed a new process of making foil directly from uranium melt by PFC. This process is simple, productive, and cost-effective. But the foil's air-side surface is generally very rough. A typical transverse cross section had a minimum thickness of 65 μm and a maximum thickness of 205 μm. This roughness could affect target fabrication and irradiation behavior. After issuing this problem KAERI launched a further effort since 2008. A new equipment was designed and manufactured in the industry in 2009. While the new equipment being test-operating, some occurrence of appearing problems appeared. Since 2010, Equipment was moved to KAERI, we performed many experiments using depleted uranium, and go get satisfied some results. We have got interesting results and manufactured uranium foil. A typical transverse cross section had a minimum thickness of 87 μm and a maximum thickness of 194 μm. The average thickness is 120 μm as a result of calculation

Preparation of hypoxic imaging agents 99Tcm-MNLS and 99Tcm-MLS and their biodistribution in mice

International Nuclear Information System (INIS)

Zha Zhihao; Wang Jianjun; Zhu Lin

2009-01-01

To develop 99 Tc m labeled hypoxic agents,two phosphate-based chelating agents were coupled to metronidazole, 2- (2-methyl-5-nitro-1H-imidazol-1-yl) ethyl dihydrogen phosphate (MNLS) and its analog 2- (2-methyl-1H-imidazol-1-yl) ethyl dihydrogen phosphate (MLS) were synthesized based on the mechanism of prodrug. Labeling yield of these 99 Tc m complexes were more than 90% as proved by TLC. Paper electrophoresis showed that these complexes were neutral. Biodistribution of these complexes in tumor-bearing mice showed that the uptake of 99 Tc m -MNLS (120 min, 2.99 ± 0.25 ID%/g) in tumor was higher than that of 99 Tc m -HL91 (120 min, 0.93 ± 0.13 ID%/g) and 99 Tc m -MLS (120 min, 1.61 ± 0.13 ID%/g), and the uptake ratio of tumor to muscle and tumor to liver of 99 Tc m -MNLS (120 min, 5.90, 1.03) were higher than that of 99 Tc m -HL91 (120 min, 3.59, 0.17) and 99 Tc m -MLS (120 min, 5.40, 0.13). The higher tumor uptake for 99 Tc m -MNLS than 99 Tc m -MLS suggested that nitroimidazole was a key group for tumor accumulation. 99 Tc m -MNLS had higher tumor uptake and lower liver uptake, which had the potential for tumor imaging and was worth of further vestigation. (authors)

14 CFR 99.41 - General.

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 2 2010-01-01 2010-01-01 false General. 99.41 Section 99.41 Aeronautics and Space FEDERAL AVIATION ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) AIR TRAFFIC AND GENERAL OPERATING RULES SECURITY CONTROL OF AIR TRAFFIC Designated Air Defense Identification Zones § 99...

14 CFR 99.3 - Definitions.

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 2 2010-01-01 2010-01-01 false Definitions. 99.3 Section 99.3 Aeronautics and Space FEDERAL AVIATION ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) AIR TRAFFIC AND GENERAL OPERATING RULES SECURITY CONTROL OF AIR TRAFFIC General § 99.3 Definitions. Aeronautical facility...

Memory updating and mental arithmetic

Directory of Open Access Journals (Sweden)

Cheng-Ching eHan

2016-02-01

Full Text Available Is domain-general memory updating ability predictive of calculation skills or are such skills better predicted by the capacity for updating specifically numerical information? Here, we used multidigit mental multiplication (MMM as a measure for calculating skill as this operation requires the accurate maintenance and updating of information in addition to skills needed for arithmetic more generally. In Experiment 1, we found that only individual differences with regard to a task updating numerical information following addition (MUcalc could predict the performance of MMM, perhaps owing to common elements between the task and MMM. In Experiment 2, new updating tasks were designed to clarify this: a spatial updating task with no numbers, a numerical task with no calculation, and a word task. The results showed that both MUcalc and the spatial task were able to predict the performance of MMM but only with the more difficult problems, while other updating tasks did not predict performance. It is concluded that relevant processes involved in updating the contents of working memory support mental arithmetic in adults.

A simple and sensitive separation technique of 99Mo and 99mTc from their equilibrium mixture

International Nuclear Information System (INIS)

Swadesh Mandal; Ajoy Mandal

2014-01-01

The present work describes a simple and inexpensive separation method of 99 Mo from the equilibrium mixture. The liquid-liquid extraction technique has been employed to separate 99 Mo and 99m Tc using triisooctylamine (TIOA). The 99 Mo and 99m Tc were quantitatively separated out in 2 M TIOA with tripled distilled water; 99m Tc was back extracted from TIOA organic phase to aqueous phase by 0.1 M DTPA. The species information or indirect speciation of molybdenum was also established by the extraction profile of the molybdenum. (author)

The separation of sup(99m)Tc from 99Mo through an aluminium oxide chromatographic columm

International Nuclear Information System (INIS)

Imoto, S.T.

1980-01-01

The separation of sup(99m)Tc from 99 Mo using the chromatographic method is studied. Alumina is used as adsorbent. The pH values for adsorption of carrier-free 99 Mo on columns filled with ordinary alumina and with that thermically treated at 1000 0 C for five hours, and the separation conditions of sup(99m)Tc using physiologic solution as eluent are determined. The sup(99m)Tc separation yields of both columns are compared and the quality of the products obtained by successive elutions for 10 days is analyzed. (Author) [pt

Update of the BIG 1-98 Trial: where do we stand?

Science.gov (United States)

Joerger, Markus; Thürlimann, Beat

2009-10-01

There is accumulating data on the clinical benefit of aromatase inhibitors in the adjuvant treatment of early-stage breast cancer in postmenopausal women. The Breast International Group (BIG) 1-98 study is a randomized, phase 3, double-blind trial comparing four adjuvant endocrine treatments of 5 years duration in postmenopausal women with hormone-receptor-positive breast cancer: letrozole or tamoxifen monotherapy, sequential treatment with tamoxifen followed by letrozole, or vice versa. This article summarizes data presented at the 2009 St. Gallen early breast cancer conference: an update on the monotherapy arms of the BIG 1-98 study, and results from the sequential treatment arms. Implications for daily practice from BIG 1-98 and from other adjuvant trials will be discussed. Despite cross-over from tamoxifen to letrozole by 25% of the patients after unblinding of the tamoxifen monotherapy arm, the improvement of disease-free survival (HR 0.88, 0.78-0.99, p = 0.03) and time to distant recurrence (HR 0.85, 0.72-1.00, p = 0.05) for letrozole monotherapy as compared to tamoxifen monotherapy remained significant in the intention-to-treat (ITT) analysis. A trend for an overall survival advantage for letrozole was seen in the ITT analysis (HR 0.87, 0.75-1.02, p = 0.08). No statistically significant differences were found for the sequential treatment arms versus letrozole monotherapy, with respect to disease-free survival, time to distant recurrence or overall survival. Cumulative incidence analysis of breast cancer recurrence favors the initiation of adjuvant endocrine treatment with letrozole instead of tamoxifen, especially in patients at higher risk for early recurrence. Similarly, data suggest that patients commenced on letrozole can be switched to tamoxifen after 2 years, if required. The BIG 1-98 study update with median follow up of 76 months confirms a significant reduction in the risk of breast cancer recurrence and a trend towards improved overall survival

Evaluation of the utility of 99m Tc-MDP bone scintigraphy versus MIBG scintigraphy and cross-sectional imaging for staging patients with neuroblastoma.

Science.gov (United States)

Gauguet, Jean-Marc; Pace-Emerson, Tamara; Grant, Frederick D; Shusterman, Suzanne; DuBois, Steven G; Frazier, A Lindsay; Voss, Stephan D

2017-11-01

Accurate staging of neuroblastoma requires multiple imaging examinations. The purpose of this study was to determine the relative contribution of 99m Tc-methylene diphosphonate (MDP) bone scintigraphy (bone scan) versus metaiodobenzylguanidine scintigraphy (MIBG scan) for accurate staging of neuroblastoma. A medical record search by the identified patients with neuroblastoma from 1993 to 2012 who underwent both MIBG and bone scan for disease staging. Cross-sectional imaging was used to corroborate the scintigraphy results. Clinical records were used to correlate imaging findings with clinical staging and patient management. One hundred thirty-two patients underwent both MIBG and bone scan for diagnosis. All stage 1 (n = 12), 2 (n = 8), and 4S (n = 4) patients had a normal bone scan with no skeletal MIBG uptake. Six of 30 stage 3 patients had false (+) bone scans. In the 78 stage 4 patients, 58/78 (74%) were both skeletal MIBG(+)/bone scan (+). In 56 of the 58 cases, skeletal involvement detected with MIBG was equal to or greater than that detected by bone scan. Only 3/78 had (-) skeletal MIBG uptake and (+) bone scans; all 3 had other sites of metastatic disease. Five of 78 had (+) skeletal MIBG with a (-) bone scan, while 12/78 had no skeletal involvement by either MIBG or bone scan. In no case did a positive bone scan alone determine a stage 4 designation. In the staging of neuroblastoma, 99m Tc-MDP bone scintigraphy does not identify unique sites of disease that affect disease stage or clinical management, and in the majority of cases bone scans can be omitted from the routine neuroblastoma staging algorithm. © 2017 Wiley Periodicals, Inc.

45 CFR 99.25 - Evidence.

Science.gov (United States)

2010-10-01

... 45 Public Welfare 1 2010-10-01 2010-10-01 false Evidence. 99.25 Section 99.25 Public Welfare DEPARTMENT OF HEALTH AND HUMAN SERVICES GENERAL ADMINISTRATION PROCEDURE FOR HEARINGS FOR THE CHILD CARE AND DEVELOPMENT FUND Hearing Procedures § 99.25 Evidence. (a) Testimony. Testimony shall be given orally under...

22 CFR 99.1 - Definitions.

Science.gov (United States)

2010-04-01

... 22 Foreign Relations 1 2010-04-01 2010-04-01 false Definitions. 99.1 Section 99.1 Foreign Relations DEPARTMENT OF STATE LEGAL AND RELATED SERVICES REPORTING ON CONVENTION AND NON-CONVENTION ADOPTIONS OF EMIGRATING CHILDREN § 99.1 Definitions. As used in this part, the term: (a) Convention means...

45 CFR 99.23 - Discovery.

Science.gov (United States)

2010-10-01

... 45 Public Welfare 1 2010-10-01 2010-10-01 false Discovery. 99.23 Section 99.23 Public Welfare... DEVELOPMENT FUND Hearing Procedures § 99.23 Discovery. The Department, the Lead Agency, and any individuals or groups recognized as parties shall have the right to conduct discovery (including depositions) against...

{sup 99m}Tc generator preparation using (n, {gamma}){sup 99}Mo produced ex-natural molybdenum

Energy Technology Data Exchange (ETDEWEB)

Le, So Van [Nuclear Research Institute, Dalat (Viet Nam)

2003-03-01

Theoretical assessment on the chromatographic {sup 99m}Tc generator preparation using (n, {gamma}) {sup 99}Mo produced ex-natural molybdenum was carried out. The relationship between the neutron flux for MoO{sub 3} target activation, Mo-content or Mo adsorption capacity of column packing material, {sup 99m}Tc pertechnetate concentration and/or {sup 99m}Tc radioactivity of eluate was established. The reasonably lower limit of neutron flux of reactor and Molybdenum content of column packing material were found out to estimate the production of portable chromatographic generators available for nuclear medicine application. The concentration of {sup 99m}Tc pertechnetate eluate of low {sup 99m}Tc concentration using the column elution technique was also evaluate theoretically and conducted successfully in practice. Three options of {sup 99m}Tc generator using Titanium-Molybdate, Zirconium-Molybdate and Zirconium Oxide as generator column-packing materials were prepared and successfully put into use in nuclear medicine application. (author)

ZZ CANDULIB-AECL, Burnup-Dependent ORIGEN-S Cross-Section Libraries for Candu Reactor Fuels

International Nuclear Information System (INIS)

2002-01-01

1 - Historical background and information: - 28-element fuel cross-section library: Format: Designed for use with the ORIGEN-S isotope generation and depletion code. Materials: Co, Ge, As, Se, Br, Kr, Rb, Sr, Y, Zr, Nb, Mo, Tc, Ru, Rh, Pd, Ag, Cd, In, Sn, Sb, Te, I, Xe, Cs, Ba, La, Ce, Pr, Nd, Pm, Sm, Eu, Gd, Tb, Dy, Ho, Er, Lu, Ta, W, Re, Au, Th, Pa, U, Np, Pu, Am, Cm. Origin: ENDSF, ENDF/B-IV, -V and -VI Weighting spectrum: determined using WIMS-AECL transport code. - 37-element fuel cross-section library: Format: Designed for use with the ORIGEN-S isotope generation and depletion code. Materials: Co, Ge, As, Se, Br, Kr, Rb, Sr, Y, Zr, Nb, Mo, Tc, Ru, Rh, Pd, Ag, Cd, In, Sn, Sb, Te, I, Xe, Cs, Ba, La, Ce, Pr, Nd, Pm, Sm, Eu, Gd, Tb, Dy, Ho, Er, Lu, Ta, W, Re, Au, Th, Pa, U, Np, Pu, Am, Cm. Origin: ENDSF, ENDF/B-IV, -V and -VI Weighting spectrum: determined using WIMS-AECL transport code. In 1995, updated ORIGEN-S cross-section libraries were created as part of a program to upgrade and standardize the computer codes and nuclear data employed for used fuel characterization. This effort was funded through collaboration between Atomic Energy of Canada Limited and the Canadian Nuclear Power Utilities, under the Candu Owners Group (COG). The updated cross sections were generated using the WIMS-AECL lattice code and ENDF/B-V and -VI based data to provide cross section consistency with reactor physics codes. 2 - Application of the data: The libraries in this data collection are designed for characterising used fuel from Candu pressurized heavy water reactors. Two libraries are provided: one for the standard 28-element fuel bundle design, the other for the 37-element fuel bundle design. The libraries were generated for typical reactor operating conditions. The libraries are designed for use with the ORIGEN-S isotope generation and depletion code. 3 - Source and scope of data: The Candu libraries are updated with cross sections from a variety of different sources. Capture

Performance tests on column materials for {sup 99}Mo-{sup 99m}Tc generator

Energy Technology Data Exchange (ETDEWEB)

Sombrito, E Z; Bulos, A D; Tangonan, M C [Chemistry Research Section, Atomic Research Div., Philippine Nuclear Research Inst., Quezon (Philippines)

1998-10-01

To meet the need of producing a {sup 99}Mo-{sup 99m}Tc generator, based on low specific activity reactor-produced {sup 99}Mo, different procedures for preparing zirconium molybdate gels were tested. Performance tests were done on molybdate gel columns prepared using the procedures developed by Vietnam and China, and recently, on a polyzirconium compound (PZC) prepared in Japan. The conditions for the batch drying of a large volume of the gel material were studied as well as the conditions in preparing a column to concentrate technetium-99m. The performance of PZC sample as column material for the generator was also evaluated. (author)

Clinical comparison of technetium-99m-EC, technetium-99-m-MAG3 and Iodine-131-OIH in renal disorders

International Nuclear Information System (INIS)

Kabasakal, L.; Turoglu, T.; Oensel, C.

1995-01-01

Technetium-99m-ethylenedicysteine has recently been developed for renal function studies. The pharmacokinetics of 99m Tc-EC were studied by constant infusion technique and compared with 99m Tc-MAG3 and 131 I-OIH in 11 patients with various renal disorders. After giving a 7.4 MBq 131 I-OIH and 90-110 MBq 99m Tc-EC or 99m Tc-MAG3 bolus, a constant infusion (MBq/ml) 99m Tc--agent and 0.07 MBq/m 131 I-OIH was started. Sixteen blood and five urine samples were obtained over three hr. The renal clearance of 99m Tc-EC was higher than than of 99m Tc-MAG3. The 99m Tc-EC/OIH and 99m Tc-MAG3/OIH ratios were 0.75 ± 0.05 and 0.55 ± 0.10 (p=0.00087), respectively. The distribution volume of 99m Tc-EC was also higher than that of 99m Tc-MAG3 (15722 ± 4644 and 9509 ± 2788 ml/1.73m 2 , respectively; p=0.072). The 99m Tc-EC/OIH and 99m Tc-MAG/OIH distribution volume ratios were 1.03 ± 0.14 and 0.55 ± 0.10, respectively (p = 0.0003). The 60-min excretion values of 99m Tc-EC and 99m Tc-MAG3 were compared to that of OIH. The 99m Tc-EC/OIH and 99m Tc-MAG3/OIH excretion ratios were 0.96 ± 0.06 and 1.07 ± 0.10, respectively (p=0.162). The protein binding of 99m -EC and OIH were found to be 34% ±4 and 66% ±5, respectively (p 99m Tc-EC was negligible (3% ±1.2) in comparison to OIH (27% ±3; p 99m Tc-EC. This agent has good potential for renal function evaluation. 32 refs., 5 tabs

21 CFR 99.1 - Scope.

Science.gov (United States)

2010-04-01

... 21 Food and Drugs 1 2010-04-01 2010-04-01 false Scope. 99.1 Section 99.1 Food and Drugs FOOD AND DRUG ADMINISTRATION, DEPARTMENT OF HEALTH AND HUMAN SERVICES GENERAL DISSEMINATION OF INFORMATION ON UNAPPROVED/NEW USES FOR MARKETED DRUGS, BIOLOGICS, AND DEVICES General Information § 99.1 Scope. (a) This...

29 CFR 99.100 - Purpose.

Science.gov (United States)

2010-07-01

... 29 Labor 1 2010-07-01 2010-07-01 true Purpose. 99.100 Section 99.100 Labor Office of the Secretary of Labor AUDITS OF STATES, LOCAL GOVERNMENTS, AND NON-PROFIT ORGANIZATIONS General § 99.100 Purpose. This part sets forth standards for obtaining consistency and uniformity among Federal agencies for the...

Sequential hepatobiliary scintigraphy of the patients with constitutional jaundice, ICG excretory defect disease and hepatocellular carcinoma with 99mTc-PI, 99mTc-HIDA and 99mTc-EHIDA

International Nuclear Information System (INIS)

Mitani, Tsuyoshi

1987-01-01

Sequential 2 min scintiphotos were obtained with a scintilation camera after intravenous injection of 3 mCi of 99m Tc-HIDA or 99m Tc-PI. Digital matrix images were simultaneously recorded with computer. Sequential samples for the blood clearance of 99m Tc-HIDA or 99m Tc-PI were obtained for 120 min following injection to the patient of constitutional hyperbilirubinemia and ICG excretory defect disease. In Dubin-Johnson syndrome, the hepatic uptake of 99m Tc-HIDA was faster or normal but the excretion was extremely slower than in normal cases. Both hepatic uptake and excretion of 99m Tc-PI were almost normal. In Rotor's disease, hepatic uptake of 99m Tc-HIDA or 99m Tc-PI was very poor, showing almost no hepatic images in all time. In Gilbert's disease and ICG excretory defect disease, hepatic uptake and excretion of 99m Tc-HIDA or 99m Tc-PI were within normal limit. From these results, Dubin-Johnson syndrome, Rotor's disease and Gilbert's disease show the different patterns between hepatic uptake and excretion of 99m Tc-HIDA and 99m Tc-PI hepatobiliary scintigraphy and these patterns contribute to the differential diagnosis of constitutional jaundice. The usefulness of hepatobiliary imaging with 99m Tc-EHIDA in diagnosis of hepatocellular carcinoma was studied in 15 patients with histologically verified HCC. In 15 patients, 3 patients (20 %) showed increased radioactivity with 99m Tc-EHIDA image, where liver scan with 99m Tc-Sn colloid showed filling defect. These results indicate that use of 99m Tc-EHIDA scan and 67 Ga-citrate imaging is useful for positive visualization of HCC. (author)

Spectrum of neutrons leaking from an iron sphere with a central 14 MeV neutron source

International Nuclear Information System (INIS)

Borisov, A.A.; Zagryadskij, V.A.; Chuvilin, D.Yu.; Kralik, M.; Pulpan, J.; Tichy, M.

1991-01-01

Following a review of the present state of nuclear data requisite for the calculation of the transport of 14 MeV neutrons through iron of natural isotopic composition, the results are given of the calculation of the energy spectrum of such neutrons after their passage through an iron sphere 240 mm o.d. and 90 mm i.d., the neutron source being accommodated in the centre of the sphere. The calculations were made using the one-dimensional code BLANK working with the nuclear data libraries ENDL-75, ENDL-83, ENDL/B-IV, JENDL-2 and BROND, and using the three-dimensional code BRAND with the library ENDL-78. The calculated spectra were compared with the experimental spectrum measured at a distance of 3 m from the sphere by means of an NE-213 scintillator, which records reflected protons. The reflected proton spectrum was processed by the matrix method (program FORIST), and the result was normalized to one neutron emitted by the source, as were the calculated spectra. The comparison demonstrates that the experiment is best fitted by the spectrum calculated by using the library JENDL-2, where the integrals of the observed and calculated spectra over the 1-15 MeV range differ as little as approximately 10%. (author). 3 figs., 5 tabs., 16 refs

Preperation and performance of {sup 99}Mo/{sup 99m}Tc chromatographic column generator based on zirconium molybdosilicate

Energy Technology Data Exchange (ETDEWEB)

Mostafa, M.; Saber, H.M.; El-Sadek, A.A. [Atomic Energy Authority, Cairo (Egypt). Hot Labs. Center; Nassar, M.Y. [Benha Univ. (Egypt). Chemistry Dept.

2016-08-01

Zirconium molybdosilicate (ZrMoSi) gel prepared using {sup 99}Mo radiotracer via peroxo route was used as a base material for {sup 99}Mo/{sup 99m}Tc column generator. The {sup 99m}Tc elution yield and {sup 99}Mo breakthrough in the eluate were studied as a function of the pH-value of gel precipitation, gel drying temperature and Zr: Mo: Si molar ratio. Precipitation pH-value of 2, drying temperature of 100 C and Zr: Mo: Si molar ratio of 0.5: 0.5: 1 were found to be the optimum conditions achieving {sup 99m}Tc elution yield of 82% and {sup 99}Mo breakthrough of 1.0 x 10{sup -3}%. The gel prepared with the optimum conditions was characterized by BET surface area and pore size analyzer, IR spectroscopy, thermal analysis (TGA and DTA), XRD, XRF and FESEM. Technetium-99m eluted from the optimum ZrMoSi {sup 99}Mo/{sup 99m}Tc generator was found to have a high radiochemical purity (98% as {sup 99m}TcO{sub 4}{sup -}) and chemical purity meeting criteria of clinical grade.

Synthesis and irradiation of titanium molybdates used as matrices of the 99 Mo/ 99m Tc generators

International Nuclear Information System (INIS)

Diaz V, H.; Monroy G, F.

2005-01-01

The 99m Tc is the radioisotope but used in nuclear medicine. Commercially it takes place starting from generators of 99 Mo/ 99m Tc, composed by a chromatography column padded of aluminium oxide of aluminum, where it is deposited the 99 Mo, product of the fission of the 235 U adsorbed and eluted, by means of a saline solution, in form of 99m TcO 4 - . The production of 99 Mo as a result of the fission, imposes radiochemical separations that generate significant quantities of radioactive waste of medium activity, and inflict elaborated radiochemical manipulation. Due to this, its have been carried out intense investigations to substitute the 99 Mo fission product, by chemical compounds that produce 99 Mo via the reaction 98 Mo(n, γ) 99 Mo. Presently work intends the use of gels of titanium molybdates like matrices of these generators. Titanium molybdates were synthesized starting from solutions TiCl 3 and ammonium molybdates and it was studied the effect of the final pH of the gels, the concentration of the Ti +3 and the influence of the laundry of these on the acting of generators. The best efficiencies and chemical purity, radiochemical and radionuclides of the gels like matrices of generators 99 Mo/ 99m Tc were gotten with the washed gel, elaborated with the solution of TiCI 3 0.35M, and to a final pH of 5.9 (Author)

Work Plan for Updating Double Shell Tank (DST) Sub-System Specifications (TBR 120.020)

International Nuclear Information System (INIS)

GRENARD, C.E.

1999-01-01

The DST System stores waste from the processing of nuclear material at the Hanford Nuclear Reservation. The program to dispose of this waste has been divided into several phases with Phase 1 being the demonstration of the waste disposal technology by a private contractor. Subsystem specifications are being prepared providing requirements for the subsystems that are necessary for the continued safe storage of waste in the DST System and the removal of selected waste for processing by the privatized facility during Phase 1. This document provides the detailed plans for updating subsystem specifications developed during EY99

Silica-gel modified with zirconium oxide as a novel 99Mo adsorbent 99mTc generators

International Nuclear Information System (INIS)

Salehi, H.; Mollarazi, E.; Abbasi, H.

2010-01-01

A new 99 Mo adsorbent has been prepared with modified silica gel with zirconium oxide (SiO 2 /ZrO 2 :Na 2 MoO 4 ) and used in technetium-99m generator. The adsorption behaviors of 99 Mo in the form of molybdate and 99m Tc in the form of pertechnetate on the new adsorbent was investigated showed that the adsorption capacity of molybdate on this generator was considerably higher than the usual generator with alumina column. Coating zirconium oxide on the surface of silica gel resulted in higher 99 Mo adsorption of this compound. 99m Tc is eluted with 0.9% NaCl, and the radionuclidic, radiochemical and chemical purities of the eluate were checked. This generator has a great potential as compared to the traditional alumina generators.

29 CFR 99.310 - Financial statements.

Science.gov (United States)

2010-07-01

... 29 Labor 1 2010-07-01 2010-07-01 true Financial statements. 99.310 Section 99.310 Labor Office of the Secretary of Labor AUDITS OF STATES, LOCAL GOVERNMENTS, AND NON-PROFIT ORGANIZATIONS Auditees § 99... have separate audits in accordance with § 99.500(a) and prepare separate financial statements. (b...

29 CFR 99.300 - Auditee responsibilities.

Science.gov (United States)

2010-07-01

... 29 Labor 1 2010-07-01 2010-07-01 true Auditee responsibilities. 99.300 Section 99.300 Labor Office... § 99.300 Auditee responsibilities. The auditee shall: (a) Identify, in its accounts, all Federal awards... the schedule of expenditures of Federal awards in accordance with § 99.310. (e) Ensure that the audits...

29 CFR 99.200 - Audit requirements.

Science.gov (United States)

2010-07-01

... 29 Labor 1 2010-07-01 2010-07-01 true Audit requirements. 99.200 Section 99.200 Labor Office of the Secretary of Labor AUDITS OF STATES, LOCAL GOVERNMENTS, AND NON-PROFIT ORGANIZATIONS Audits § 99.... Guidance on determining Federal awards expended is provided in § 99.205. (b) Single audit. Non-Federal...

Progress on the Development of (n,γ)99Mo/99mTc generator, an Alternative of Conventional Generator

International Nuclear Information System (INIS)

Lee, Jun Sig; Choi, Seung Rag; Nam, Seong Su; Park, Ul Jae; Son, Kwang Jae; Choi, Kang Hyuk; Choi, Sun Ju

2010-01-01

Even though different types of generators have been developed to extract 99m Tc, most of the generators uses 99 Mo from the fission products as the mother radionuclide of 99m Tc. Recently, the crisis of 99 Mo production becomes one of the international issues as 99m Tc is a dominant diagnostic radionuclide. The shortage of 99m Tc has been predicted in the society for more than 10 years. However, actions to prevent such crisis were slow as the initial investment to construct a new research reactor for the production of 99 Mo is high. Currently, it is expected the shortage of 99m Tc will last at least for more than 5 years. As an alternative to minimize such crisis, a new approach is proposed and studied. In this approach, the mother source of 99m Tc comes not from fission products but from the neutron irradiation of molybdenum oxide. Hence, most of the research reactors, which do not have capability to produce fission molybdenum, (n,f) 99 Mo can produce 99 Mo. The key issue in this approach is the uptake capacity of the generator column for (n, γ) 99 Mo, which has extremely low specific activity compared to (n,f) 99 Mo. Currently, the results from the research activities at Korea Atomic Energy Research Institute have shown such approach has enough potential as an alternative of the conventional generator. Hence, the progress of the research is reported in this paper

45 CFR 99.13 - Place.

Science.gov (United States)

2010-10-01

... 45 Public Welfare 1 2010-10-01 2010-10-01 false Place. 99.13 Section 99.13 Public Welfare DEPARTMENT OF HEALTH AND HUMAN SERVICES GENERAL ADMINISTRATION PROCEDURE FOR HEARINGS FOR THE CHILD CARE AND DEVELOPMENT FUND Preliminary Matters-Notice and Parties § 99.13 Place. The hearing shall be held in the city...

29 CFR 99.225 - Sanctions.

Science.gov (United States)

2010-07-01

... 29 Labor 1 2010-07-01 2010-07-01 true Sanctions. 99.225 Section 99.225 Labor Office of the Secretary of Labor AUDITS OF STATES, LOCAL GOVERNMENTS, AND NON-PROFIT ORGANIZATIONS Audits § 99.225 Sanctions. No audit costs may be charged to Federal awards when audits required by this part have not been...

Current status of research and development of 99Mo/99mTc generator in Korea

International Nuclear Information System (INIS)

Park, U.J.; Lee, J.S.; Son, K.J.; Nam, S.S.; Kwak, S.I.; Han, H.S.

2006-01-01

To supply 99m Tc in stable and economical manner in Korea, a chromatographic generator has been under development at KAERI since late 1980's. The chromatographic type of technetium generator is preferred in hospital because it is more convenient and less time-restricted for applications. Hence, the demand of 99m Tc in medical applications is keep increasing. In Korea, there are more than 200 gamma cameras including SPECT in hospitals. For these applications, approximately 100 units/week of 99m Tc generators of which annual cost reached 3 million US dollars were required in 2002. Hence, the development of 99m Tc generators and technology of fission 99 Mo processing were started while installing the generator loading facility (GLF) at KAERI. This facility is currently on a trial run for the commercial production of 99m Tc generators and expected to produce more than 200 generators per week in 2004. For the fission 99 Mo production, an annulus U foil target was considered as the LEU target. The designed LEU target is being used for target manufacturing test and accident analysis. The develop gel type 99m Tc generators by using a poly zirconium complex (PZC) and alumina column, KAERI has cooperated with a Japanese company since late 1990's. In 2003, experimental studies for molybdate adsorption capacity and elution characteristics of the PZC samples from three different batches produced by Kaken Co. were carried out. (author)

29 CFR 99.405 - Management decision.

Science.gov (United States)

2010-07-01

... 29 Labor 1 2010-07-01 2010-07-01 true Management decision. 99.405 Section 99.405 Labor Office of... Agencies and Pass-through Entities § 99.405 Management decision. (a) General. The management decision shall... process available to the auditee. (b) Federal agency. As provided in § 99.400(a)(7), the cognizant agency...

29 CFR 99.510 - Audit findings.

Science.gov (United States)

2010-07-01

... 29 Labor 1 2010-07-01 2010-07-01 true Audit findings. 99.510 Section 99.510 Labor Office of the Secretary of Labor AUDITS OF STATES, LOCAL GOVERNMENTS, AND NON-PROFIT ORGANIZATIONS Auditors § 99.510 Audit... schedule of prior audit findings prepared by the auditee in accordance with § 99.315(b) materially...

How update schemes influence crowd simulations

International Nuclear Information System (INIS)

Seitz, Michael J; Köster, Gerta

2014-01-01

Time discretization is a key modeling aspect of dynamic computer simulations. In current pedestrian motion models based on discrete events, e.g. cellular automata and the Optimal Steps Model, fixed-order sequential updates and shuffle updates are prevalent. We propose to use event-driven updates that process events in the order they occur, and thus better match natural movement. In addition, we present a parallel update with collision detection and resolution for situations where computational speed is crucial. Two simulation studies serve to demonstrate the practical impact of the choice of update scheme. Not only do density-speed relations differ, but there is a statistically significant effect on evacuation times. Fixed-order sequential and random shuffle updates with a short update period come close to event-driven updates. The parallel update scheme overestimates evacuation times. All schemes can be employed for arbitrary simulation models with discrete events, such as car traffic or animal behavior. (paper)

Cross section recondensation method via generalized energy condensation theory

International Nuclear Information System (INIS)

Douglass, Steven; Rahnema, Farzad

2011-01-01

Highlights: → A new method is presented which corrects for core environment error from specular boundaries at the lattice cell level. → Solution obtained with generalized energy condensation provides improved approximation to the core level fine-group flux. → Iterative recondensation of the cross sections and unfolding of the flux provides on-the-fly updating of the core cross sections. → Precomputation of energy integrals and fine-group cross sections allows for easy implementation and efficient solution. → Method has been implemented in 1D and shown to correct the environment error, particularly in strongly heterogeneous cores. - Abstract: The standard multigroup method used in whole-core reactor analysis relies on energy condensed (coarse-group) cross sections generated from single lattice cell calculations, typically with specular reflective boundary conditions. Because these boundary conditions are an approximation and not representative of the core environment for that lattice, an error is introduced in the core solution (both eigenvalue and flux). As current and next generation reactors trend toward increasing assembly and core heterogeneity, this error becomes more significant. The method presented here corrects for this error by generating updated coarse-group cross sections on-the-fly within whole-core reactor calculations without resorting to additional cell calculations. In this paper, the fine-group core flux is unfolded by making use of the recently published Generalized Condensation Theory and the cross sections are recondensed at the whole-core level. By iteratively performing this recondensation, an improved core solution is found in which the core-environment has been fully taken into account. This recondensation method is both easy to implement and computationally very efficient because it requires precomputation and storage of only the energy integrals and fine-group cross sections. In this work, the theoretical basis and development

WIMS library up-date project: first stage results

International Nuclear Information System (INIS)

Prati, A.; Claro, L.H.

1990-01-01

The following benchmarks: TRX1, TRX2, BAPL-UO sub(2)-1, BAPL-UO sub (2)-2, BAPL-UO sub(2)-3 have been calculated with the WIMSD/4 code, as a contribution of CTA/IEAv, to the first stage of the WIMS Library Update Project, coordinated by the International Atomic Energy Agency. The card image input for each benchmark has been attached and the major input options/parameters are commented. The version of the WIMSD/4 code and its multigroup cross section library used to run the benchmarks are specified. Results from the major integral parameters are presented and discussed. (author)

29 CFR 99.505 - Audit reporting.

Science.gov (United States)

2010-07-01

... 29 Labor 1 2010-07-01 2010-07-01 true Audit reporting. 99.505 Section 99.505 Labor Office of the Secretary of Labor AUDITS OF STATES, LOCAL GOVERNMENTS, AND NON-PROFIT ORGANIZATIONS Auditors § 99.505 Audit... is required to report under § 99.510(a); (vii) An identification of major programs; (viii) The dollar...

29 CFR 99.320 - Report submission.

Science.gov (United States)

2010-07-01

... 29 Labor 1 2010-07-01 2010-07-01 true Report submission. 99.320 Section 99.320 Labor Office of the Secretary of Labor AUDITS OF STATES, LOCAL GOVERNMENTS, AND NON-PROFIT ORGANIZATIONS Auditees § 99.320... package pursuant to § 99.320(d)(2). (vii) A yes or no statement as to whether the auditee qualified as a...

29 CFR 99.230 - Audit costs.

Science.gov (United States)

2010-07-01

... 29 Labor 1 2010-07-01 2010-07-01 true Audit costs. 99.230 Section 99.230 Labor Office of the Secretary of Labor AUDITS OF STATES, LOCAL GOVERNMENTS, AND NON-PROFIT ORGANIZATIONS Audits § 99.230 Audit... years ending after December 31, 2003) and is thereby exempted under § 99.200(d) from having an audit...

Comparative evaluation of different nanostructured metal oxides for preparation of clinically useful 99Mo/99mTc generators

International Nuclear Information System (INIS)

Ram, Ramu; Chakravarty, Rubel; Dash, Ashutosh

2015-01-01

The potential of nanostructured metal oxides such as nanotitania, nanozirconia, nanoalumina and mesoporous alumina, as new generation sorbent materials for preparation of 99 Mo/ 99m Tc generator has recently been demonstrated. A comparative assessment of such materials is essential for determination of their suitability for preparation of clinically useful generators using (n,γ) 99 Mo. Characteristics which were compared included the sorption capacity, shelf-life of the generator, radioactive concentration and purity of 99m Tc for radiopharmaceutical applications. Mesoporous alumina was identified as the most suitable sorbent for ensuring sustainable production of clinical grade 99 Mo/ 99m Tc generators using low specific activity 99 Mo. (author)

Accumulation of Tc-99m-MIBI and Tc-99m-tetrofosmin in tumor cells. Uptake and washout studies

International Nuclear Information System (INIS)

Rodrigues, M.; Aghajanian, A.A.; Sinzinger, H.; Kalinowska, W.; Zielinski, C.

2002-01-01

Aim: To investigate in-vitro the uptake and washout of Tc-99m-MIBI and Tc-99m-tetrofosmin in human breast adenocarcinoma and soft tissue sarcoma cell lines. Methods: The uptake of Tc-99m-MIBI and Tc-99m-tetrofosmin (at 37 0 C, 10, 30 and 60 minutes after incubation with 7.4x10E5 Bq each tracer) was investigated in breast adenocarcinoma MCF-7 and SK-BR-3 cells, synovial sarcoma SW 982 cells and chondrosarcoma SW 1353 cells (concentration of 1x10E6 cells/ml incubation medium). Tracer uptake in cells incubated with ouabain (Na/K-ATPase pump inhibitor; 100 μM and 1mM; 15 and 30 minutes), nigericin (increases mitochondrial potential and disrupts cell membrane potential; 5 and 50 μg/ml; 15 minutes) and carbonyl cyanide m-chlorophenylhydrazone (CCCP) (depolarizes mitochondrial membrane; 10 and 100 μM; 30 minutes) was compared to that in cells without incubation with chemical agents (control cells). The washout (at 37 0 C, 10-60 minutes, 30 and 60 minutes after tracer incubation) of Tc-99m-MIBI and Tc-99m-tetrofosmin was studied in MCF-7 cells, SK-BR-3 cells , SW 1353 cells and fibrosarcoma SW 684 cells. Results: Cellular tracer uptake decreased with ouabain (decrease of Tc-99m-tetrofosmin > Tc-99m-MIBI in SK-BR-3 cells and SW 982 cells) and increased with nigericin (increase of Tc-99m-MIBI > Tc-99m-tetrofosmin in all cells) as compared to the uptake in control cells. With CCCP, decrease of Tc-99m-MIBI uptake in cells preincubated with nigericin was higher than that in cells under basal conditions, whereas a similar decrease of Tc-99m-tetrofosmin uptake in these two group of cells was found. Washout of Tc-99m-MIBI from all cells was lower than that of Tc-99m-tetrofosmin. No significant difference in cell-associated activity of both tracers was found between washout after 30 minutes and that after 60 minutes of incubation, in all cells. Washout of Tc-99m-MIBI from SK-BR-3 cells Tc-99m-tetrofosmin) and Na/K-ATPase pump (Tc-99m-tetrofosmin > Tc-99m-MIBI). Tc-99m-MIBI and

Technetium-99 m generator safety simulation

International Nuclear Information System (INIS)

Kang, Sang Koo; Kim, Chong Yeal

2008-01-01

Technetium ( 99m Tc) is one of the most widely used radioactive isotopes for diagnosis in the world. In general, 99m Tc is produced inside the so called technetium generator where 99Mo decays to 99m Tc. And the generator is usually made out of lead to shield relatively high energy radiation from 99m Tc and 99 Mo. In this paper, a GEANT4 simulation is carried out to test the safety of the 99m Tc generators, taking domestic and Japanese products with radioactivity of 18.50 GBq (500 mCi) for example. According to the domestic regulation on radiation safety, the dose at 10 cm and 100 cm away from the surface of radiation shielder should not exceed 2 mSv∙h -1 and 0.02 mSv∙h -1 , respectively. The simulated dose turned out about only 10% of the limit, satisfying the domestic regulation

Analysis of effects of updated decay and fission yield data on ORIGEN 2 results

International Nuclear Information System (INIS)

Daniel, P.R.

1993-01-01

Work has been performed to improve the accuracy of ORIGEN2 results by updating both the decay library and the fission yield data in the cross-section library. This effort was performed under the auspices of Oak Ridge National Laboratory (ORNL) to ensure that ORIGEN2 uses the most up-to-date data. The impact of the new data was then quantitatively evaluated by solving a set of standard light water reactor (LWR) problems solved with ORIGEN2. The ORIGEN code, developed at ORNL in the late 1960's, is a point depletion code used to determine the composition and characteristics of spent fuel. The results from calculations performed with the code often form the basis for the study and design of reprocessing plants, spent-fuel shipping casks, waste treatment systems, and disposal facilities. The decay data were updated using data from ENDF/B-VI; fission yield data were updated using data from ENDF/B-V. The impact of these new data was then evaluated

Comparison of uptake of 99mTc-MIBI, 99mTc-tetrofosmin and 99mT-Q12 into human breast cancer cell lines

International Nuclear Information System (INIS)

Yong, M. de; Bernard, B.F.; Breeman, W.A.P.; Ensing, G.; Benjamins, H.; Bakker, W.H.; Visser, T.J.; Krenning, E.P.

1996-01-01

Technetium-99m hexakis-2-methoxyisobutyl-isonitrile (MIBI), 99m Tc-tetrofosmin and 99m Tc-Q12 were all introduced for myocardial imaging but found additional applications as they are taken up by different tumours, enabling imaging of these lesions in patients. The aim of this study was to compare the uptake characteristics of these compounds in vitro in the human adenocarcinoma breast cell lines MCF-7 and ZR-75. It was shown that 99m Tc-MIBI had the highest cellular uptake (15.9%±0.5% dose/mg protein after 60 min in MCF-7, and 14.2%±0.4% dose/mg protein in ZR-75), followed by 99m Tc-tetrofosmin (6.8%±0.6% dose/mg protein in MCF-7, and 8.2%±0.2% dose/mg protein in ZR-75) and 99m TC-Q12 (3.2%±0.1% dose/mg protein in MCF-7, and 3.5%±0.3% dose/mg protein in ZR-75 cells). For all three compounds tenfold differences in specific activity did not influence total cell-associated radioactivity. Uptake of 99m Tc-MIBI and 99m Tc-tetrofosmin was obviously lower at 4 C than at 37 C, whereas 99m Tc-Q12 uptake showed only slight temperature dependence. When uptake was compared in cells grown to different cell densities (1 mg/ml cellular protein versus 0.3 mg/ml), no differences in uptake were detected when uptake was corrected for the amount of cellular protein present in the dishes. Furthermore, for all compounds it was shown that cellular radioactivity decreased rapidly after washing. Apart from the differences in cellular uptake of the three compounds after 60 min, no differences in residual cellular radioactivity after washing were found between the different compounds when expressed as a percentage of their 60-min uptake, suggesting that the efflux process of the radiolabelled compounds was similar. The differences in cell-associated activity after 60 min were thus presumably caused by differences in uptake. (orig./MG)

99mTc by 99Mo produced at the ENEA-FNG facility of 14MeV neutrons.

Science.gov (United States)

Capogni, M; Pietropaolo, A; Quintieri, L; Fazio, A; De Felice, P; Pillon, M; Pizzuto, A

2018-04-01

A severe supply crisis of 99 Mo, precursor of 99m Tc a diagnostic radionuclide largely used in Nuclear Medicine, occurred in 2008-2009 due to repeated shut-down of the two main (aged) fission reactors. An alternative route for producing 99 Mo by 100 Mo(n,2n) 99 Mo reaction was investigated at ENEA. The experiment, designed according to Monte Carlo simulations performed with the Fluka code, produced 99 Mo by irradiating a natural Molybdenum powdered target with 14MeV neutrons produced at the Frascati Neutron Generator. The 99 Mo specific activity was measured at metrological level by γ-ray spectrometry. Copyright © 2017 Elsevier Ltd. All rights reserved.

Production optimization of {sup 99}Mo/{sup 99m}Tc zirconium molybate gel generators at semi-automatic device: DISIGEG

Energy Technology Data Exchange (ETDEWEB)

Monroy-Guzman, F., E-mail: fabiola.monroy@inin.gob.mx [Instituto Nacional de Investigaciones Nucleares, Carretera Mexico-Toluca S/N, La Marquesa, Ocoyoacac, 52750, Estado de Mexico (Mexico); Rivero Gutierrez, T., E-mail: tonatiuh.rivero@inin.gob.mx [Instituto Nacional de Investigaciones Nucleares, Carretera Mexico-Toluca S/N, La Marquesa, Ocoyoacac, 52750, Estado de Mexico (Mexico); Lopez Malpica, I.Z.; Hernandez Cortes, S.; Rojas Nava, P.; Vazquez Maldonado, J.C. [Instituto Nacional de Investigaciones Nucleares, Carretera Mexico-Toluca S/N, La Marquesa, Ocoyoacac, 52750, Estado de Mexico (Mexico); Vazquez, A. [Instituto Mexicano del Petroleo, Eje Central Norte Lazaro Cardenas 152, Col. San Bartolo Atepehuacan, 07730, Mexico D.F. (Mexico)

2012-01-15

DISIGEG is a synthesis installation of zirconium {sup 99}Mo-molybdate gels for {sup 99}Mo/{sup 99m}Tc generator production, which has been designed, built and installed at the ININ. The device consists of a synthesis reactor and five systems controlled via keyboard: (1) raw material access, (2) chemical air stirring, (3) gel dried by air and infrared heating, (4) moisture removal and (5) gel extraction. DISIGEG operation is described and dried condition effects of zirconium {sup 99}Mo- molybdate gels on {sup 99}Mo/{sup 99m}Tc generator performance were evaluated as well as some physical-chemical properties of these gels. The results reveal that temperature, time and air flow applied during the drying process directly affects zirconium {sup 99}Mo-molybdate gel generator performance. All gels prepared have a similar chemical structure probably constituted by three-dimensional network, based on zirconium pentagonal bipyramids and molybdenum octahedral. Basic structural variations cause a change in gel porosity and permeability, favouring or inhibiting {sup 99m}TcO{sub 4}{sup -} diffusion into the matrix. The {sup 99m}TcO{sub 4}{sup -} eluates produced by {sup 99}Mo/{sup 99m}Tc zirconium {sup 99}Mo-molybdate gel generators prepared in DISIGEG, air dried at 80 Degree-Sign C for 5 h and using an air flow of 90 mm, satisfied all the Pharmacopoeias regulations: {sup 99m}Tc yield between 70-75%, {sup 99}Mo breakthrough less than 3 Multiplication-Sign 10{sup -3}%, radiochemical purities about 97% sterile and pyrogen-free eluates with a pH of 6. - Highlights: Black-Right-Pointing-Pointer {sup 99}Mo/{sup 99m}Tc generators based on {sup 99}Mo-molybdate gels were synthesized at a semi-automatic device. Black-Right-Pointing-Pointer Generator performances depend on synthesis conditions of the zirconium {sup 99}Mo-molybdate gel. Black-Right-Pointing-Pointer {sup 99m}TcO{sub 4}{sup -} diffusion and yield into generator depends on gel porosity and permeability. Black

Study of the elution {sup 99}Mo-{sup 99m}Tc generators produced at IPEN-CNEN/SP

Energy Technology Data Exchange (ETDEWEB)

Lopes, Paula Regina Corain [Pontificia Univ. Catolica de Sao Paulo, SP (Brazil); Instituto de Pesquisas Energeticas e Nucleares IPEN/CNEN-SP, Sao Paulo, SP (Brazil)]. E-mail: corain.lopes@uol.com.br; Osso Junior, Joao Alberto [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)]. E-mail: jaosso@ipen.br

2007-07-01

Over the last years {sup 99m}Tc has become a very important asset in modern nuclear medicine, due to the emission of gamma ray of optimal energy (140 keV) and a suitable half-life (6.04 h). A further attribute of {sup 99m}Tc is its formation from the decay of {sup 99}Mo and the availability from {sup 99}Mo-{sup 99m}Tc generator systems. The most common and practical generator types consist of a chromatographic column packed with aluminium oxide, onto which the highly purified fission product {sup 99}Mo (imported from Canada) is adsorbed in the form of molybdate. {sup 99m}Tc is further eluted with saline solution. The objective of this work is to study the performance and the elution profile of {sup 99m}Tc from high activity generators in order to decrease molybdenum and aluminium concentration. The experiments involved the use of paper filters and Sep Pak columns and also the changing in the time interval between elutions. {sup 99}Mo breakthrough was measured using a dose calibrator and aluminium by UV-Vis spectrophotometry. The best results were achieved using a Sep Pak column containing neutral aluminium oxide. (author)

Precise measurements of neutron capture cross sections for FP

International Nuclear Information System (INIS)

Nakamura, Shoji; Harada, Hideo; Katoh, Toshio

2000-01-01

The thermal neutron capture cross sections (σ 0 ) and the resonance integrals (I 0 ) of some fission products (FP), such as 137 Cs, 90 Sr, 99 Tc, 129 I and 135 Cs, were measured by the activation and γ-ray spectroscopic methods. Moreover, the cross section measurements were done for other FP elements, such as 127 I, 133 Cs and 134 Cs. This paper provides the summary of the FP cross section measurements, which have been performed by authors. (author)

Analyzing power and differential cross section at 9.9, 11.9 and 13.9 MeV for Ca(n,n)Ca

International Nuclear Information System (INIS)

Tornow, W.; Woye, E.; Mack, G.; Clegg, T.

1982-01-01

The analyzing power and differential cross section for elastic neutron scattering from calcium have been measured at 9.9, 11.9 and 13.9 MeV using the 2 H(d,n) 3 He source reaction and neutron time-of-flight (t.o.f.) techniques to detect the scattered neutrons. Polarized neutron beams were produced via the polarization transfer reaction 2 H(d vector,n vector) 3 He at THETA = 0 0 . The data have been corrected for finite geometry and multiple scattering effects. None of the global neutron-nucleus optical model parameter sets usually referred to in the literature reproduces the present cross-section and analyzing power data. Individual as well as energy-averaged fits of the data resulting from new optical model searches are presented. It is shown that the quoted uncertainties of a recent empirical determination of the real part ΔVsub(C) of the Coulomb correction term are probably underestimated. Our imaginary Coulomb correction term ΔWsub(C) agrees quite well with both a very recent empirical determination and theoretical studies. Although the quality of the fits to the data can be improved by adding iota-dependent potentials to the general optical potential, no definite conclusions can be drawn from the present data as to whether or not iota-dependent potentials are important in neutron-calcium scattering in the energy range investigated. The data have also been analyzed using a Fourier-Bessel series description of the real central optical potential. Comparing the chi 2 values, the experimental data are better reproduced by the Fourier-Bessel method than by our Woods-Saxon optical model analyses. The Fourier-Bessel potentials obtained show strong deviations from the standard Woods-Saxon shape but are in good agreement with calculations using the nuclear structure approach. (orig.)

The Fission-Based  99Mo Production Process ROMOL-99 and Its Application to PINSTECH Islamabad

Directory of Open Access Journals (Sweden)

Rudolf Muenze

2013-01-01

Full Text Available An innovative process for fission based 99Mo production has been developed under Isotope Technologies Dresden (ITD GmbH (former Hans Wälischmiller GmbH (HWM, Branch Office Dresden, and its functionality has been tested and proved at the Pakistan Institute of Nuclear Science and Technology (PINSTECH, Islamabad. Targets made from uranium aluminum alloy clad with aluminum were irradiated in the core of Pakistan Research Reactor-1 (PARR-1. In the mean time more than 50 batches of fission molybdenum-99 (99Mo have been produced meeting the international purity/pharmacopoeia specifications using this ROMOL-99 process. The process is based on alkaline dissolution of the neutron irradiated targets in presence of NaNO3, chemically extracting the 99Mo from various fission products and purifying the product by column chromatography. This ROMOL-99 process will be described in some detail.

Discordant results in Tc-99m tetrofosmin and Tc-99m sestamibi parathyroid scintigraphies; Resultados discordantes em cintilografias das paratireoides realizadas com tetrofosmin-99mTc e com sestamibi-99mTc

Energy Technology Data Exchange (ETDEWEB)

Duarte, Paulo Schiavom; Domingues, Fernanda C.; Santi Costa, Michele; Brandao, Cynthia; Oliveira, Marco A.C. de; Vieira, Jose G.H. [Fleury - Centro de Medicina Diagnostica, Sao Paulo, SP (Brazil)]. E-mail: paulo.duarte@fleury.com.br

2007-10-15

Parathyroid scintigraphies have been used to detect pathological parathyroid glands either before as well as after the parathyroid resection surgery in patients with hyperparathyroidism. One of the most utilized techniques to perform the studies is the double-phase images with Tc-99m sestamibi, which has been shown to be very accurate in the localization of enlarged parathyroid glands. Similar to Tc-99m sestamibi, Tc-99m tetrofosmin is a radiopharmaceutical initially developed to perform myocardial perfusion study that has been used to perform parathyroid scintigraphies. Although most of the papers suggest that the overall sensitivities of both radiopharmaceuticals are similar, there are some papers questioning the accuracy of Tc-99m tetrofosmin to detect abnormal parathyroid glands. In the present article, we report a case with discordant results by both methods. (author)

Problems in clinical practice of domestic supply of 99Mo/99mTc. Current status and action plans on domestic production of 99Mo raw materials for medical use

International Nuclear Information System (INIS)

Nakamura, Yoshihide

2012-01-01

NRU in Canada and HFR in the Netherlands which had been producing the most important medical isotope, 99 Mo, were shut down in 2009-2010. As the production of more than 95% of global 99 Mo supply were performed in only five research reactors in the world including the two reactors mentioned above, these shutdowns resulted in global supply shortage of 99 Mo. Although the medical isotope crisis were alleviated after the two reactors returning to service, all of these five 99 Mo producing reactors are approximately 50 years old. Because the remaining life time of these reactors is not so long, the construction of new reactors or the development of new technologies to produce bulk 99 Mo, such as the neutron activation of 98 Mo in a reactor or charged particle reaction by accelerator, are proposed for the long-term security of supply of 99 Mo. The methods using the molybdenum target lead to much lower specific activity of 99 Mo compared to the production with fission method. The new chemical processing technologies, such as manufacturing 99m Tc-labeled radiopharmaceuticals from such low specific activity 99 Mo, are required for the development of domestic practical production of 99 Mo. (author)

Fabrication Method of the Mo-99 Target with Advanced Planar Flow Casting

Energy Technology Data Exchange (ETDEWEB)

Sim, M. S.; Lee, J. H. [Chungnam University, Green Energy Technology, Daejeon (Korea, Republic of); Kim, C. K.; Woo, Y. M. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2011-05-15

Mo-99 is a parent isotope of Tc-99m for medical diagnosis and very significant owing to its large fraction over 80% of the whole demand of medical radioisotopes in the all countries. Mo-99 isotope has been produced mainly by {sup 235}U which is extracting fission products. All the major providers of fission Mo have used HEU as a target material. But RERTR program that is non-proliferation policy encourages using HEU to LEU. KAERI has developed a processing to be able to produce a uranium foil continuously at one go. This processing gave an opportunity for LEU target using uranium foil to be commercialized. It correspond RERTR program. KAERI developed a new process of making foil directly from uranium melt by PFC. This process is simple, productive, and cost-effective. But the foil{center_dot}{center_dot}{center_dot}s air-side surface is generally very rough. A typical transverse cross section had a minimum thickness of 65 {mu}m and a maximum thickness of 205 {mu}m. This roughness could affect target fabrication and irradiation behavior. After issuing this problem KAERI launched a further effort since 2008. A new equipment was designed and manufactured in the industry in 2009. While the new equipment being test-operating, some occurrence of appearing problems appeared. Since 2010, Equipment was moved to KAERI, we performed many experiments using depleted uranium, and go get satisfied some results. We have got interesting results and manufactured uranium foil. A typical transverse cross section had a minimum thickness of 87 {mu}m and a maximum thickness of 194 {mu}m. However, the average thickness is 130 {mu}m as a result of measurement by a micrometer

Update on J /ψ regeneration in a hadron gas

Science.gov (United States)

Abreu, L. M.; Khemchandani, K. P.; Torres, A. Martínez; Navarra, F. S.; Nielsen, M.

2018-04-01

In heavy-ion collisions, after the quark-gluon plasma there is a hadronic gas phase. Using effective Lagrangians, we study the interactions of charmed mesons which lead to J /ψ production and absorption in this gas. We update and extend previous calculations introducing strange meson interactions and also including the interactions mediated by the recently measured exotic charmonium resonances Z (3900 ) and Z (4025 ) . These resonances open new reaction channels for the J /ψ , which could potentially lead to changes in its multiplicity. We compute the J /ψ production cross section in processes such as D(s) (*)+D¯(*)→J /ψ +(π ,ρ ,K ,K*) and also the J /ψ absorption cross section in the corresponding inverse processes. Using the obtained cross sections as input to solve the appropriate rate equation, we conclude that the interactions in the hadron gas phase lead to a 20-24% reduction of the J /ψ abundance. Within the uncertainties of the calculation, this reduction is the same at the Relativistic Heavy Ion Collider and the large Hadron Collider.

Comparison of carrier-added [99mTc] EDTMP and carrier-free preparations of [99mTc] EDTMP and [99mTc] DPD

International Nuclear Information System (INIS)

Krcal, A.; Kletter, K.; Dudczak, R.; Pirich, C.; Mitterhauser, M.

2002-01-01

Full text: High uptake of bone-seeking radiopharmaceuticals in malignant bone lesions is a prerequisite for adequate bone scanning. Visual image analysis is impaired due to high soft-tissue activity with currently available [ 99m Tc]-EDTMP-kits. This study aimed to compare carrier-added [ 99m Tc]-EDTMP with carrier-free [ 99m Tc]-EDTMP and [ 99m Tc]-DPD preparations in clinical routine. 15 μg and 150 μg perrhenic acid respectively were added to [ 99m Tc]-pertechnetate (>6 GBq in 3 ml phys. saline). The solution was then transferred into a vial, containing 1 mg of EDTMP, 3.6 mg stannous(II)chloride and 10 mg ascorbic acid under inert conditions. Under vigorous stirring the reaction mixture was heated to 45 o C for 10 min. After cooling down to room temperature the labelling mixture was sterile filtrated (millipore 0.22 μm). Quality control was performed using radio-ITLC (Whatman SG; acetone or ethanol: R f perrhenate/pertechnetate 0.87, colloid/product 0.05; phys. saline: R f colloid 0.00, perrhenate/pertechnetate and product 0.9) allowing rapid and efficient assessment of the product. Carrier free [ 99m Tc]-EDTMP and [ 99m Tc]-DPD were prepared according to instructions of the manufacturer. Clinical studies were performed in 29 patients according to a routine bone scanning protocol by injecting 700-800 MBq of the respective tracer and whole body imaging 3 h thereafter. Radiochemical purity and radiochemical yield relied on various parameters such as concentration of carrier and reducing agent and reaction conditions (pH, reaction time, temperature). Means of the labelling yield were 22 % for the preparation using 150 μg of carrier (5 preparations), 80 % for the preparation using 15 μpg of carrier (10 preparations) and 91 % for the carrier free products (5 preparations). Radiochemical purity was >96 % in all experiments. Colloid was formed in very low amounts, and was completely removed by sterile filtration. In clinical studies quantitative analysis

99mTc-MAG3: can it be a viable alternative to 99mTc-DTPA ?

International Nuclear Information System (INIS)

Bal, C.S.; Padhy, A.K.; Nair, R.; Gopinath, P.G.

1991-01-01

The purpose of this study was to assess the potentials of 99m Tc MAG 3 to replace universally used 99m Tc-DTPA as a routine renal agent. Five patients with different nephrological problems were first studied with 99m Tc MAG 3 and then reinvestigated with 99m Tc-DTPA two to seven days later. Renal MAG 3 gamma camera images were found to be almost identical with those of 99m Tc-DTPA images except high hepatic and splenic uptake of the former compound in four out of five patients (80%) irrespective of kidney function. MAG 3 and DTPA renograms showed identical differential renal uptake function (r=0.87) with slightly higher uptake in right kidneys. Time to reach the peak correlated well (r=0.91). Time to reach half maximum renal activity was also found to be almost identical (r=0.97) for MAG 3 and DTPA. It was felt that the age old 99m Tc-DTPA is as good a compound as 99m Tc MAG 3 with regard to imaging and assessment of renal uptake, drainage and differential renal functions. 99m Tc-DTPA is much cheaper, readily available in India and stable to suit the logistics in a busy nuclear medicine department for routine renography. (author). 10 refs., 2 figs., 3 tabs

A study on 99Tcm-citrate and 99Tcm (V)-DMSA imaging in the diagnosis of acute purulent osteoarthritis

International Nuclear Information System (INIS)

Wu Zhaozhong; Lin Wei; Wu Hengfu; Wu Changwei; Yuan Gewen; Fan Ziwen; Wu Boyi

2003-01-01

Objective: To assess the clinical diagnostic value of 99 Tc m -citrate and 99 Tc m (1/2ae)-dimercaptosuccinic acid (DMSA) imaging in the acute purulent osteoarthritis. Methods: Seventeen patients with confirmed acute purulent osteoarthritis and nineteen patients with non-purulent osteoarthritis were studied. In all patients, 99 Tc m -methylene diphosphonic acid (MDP), 99 Tc m -citrate and 99 Tc m (1/2ae)-DMSA imaging were sequentially performed and the images were analyzed semiquantitatively. Results: In the acute purulent osteoarthritis group, there were positive bonetactic accumulations at certain areas on the three kinds of imaging. In the non-purulent osteoarthritis group, 99 Tc m -MDP and 99 Tc m (1/2ae)-DMSA imaging showed clear bonetactic accumulation, but 99 Tc m -citrate imaging showed only light bonetactic accumulation in addition to the accumulations in soft tissue at certain areas. Lesion to nonlesion ratio (L/N=2.300±0.094) of acute purulent osteoarthritis was greater than that in non-purulent osteoarthritis group (1.298±0.054, P 99 Tc m -citrate imaging, and there was no significant difference between two groups on 99 Tc m (1/2ae)-DMSA imaging (L/N ratio of acute purulent osteoarthritis group was 3.495±0.180, and L/N ratio of non-purulent osteoarthritis group was 3.091±0.091, P>0.05). Conclusions: To diagnose the bone inflammation, 99 Tc m -citrate imaging coalesced with 99 Tc m -MDP or 99 Tc m (1/2ae)-DMSA imaging can help to evaluate the pathologic and physiologic progresses in bone inflammatory areas, at the same time , the information by 99 Tc m -citrate imaging is telling the actual inflammation areas, and that by 99 Tc m (1/2ae)-DMSA and 99 Tc m -MDP imaging is about the response to the increase of bone metabolism

Advanced Neutron Source Cross Section Libraries (ANSL-V): ENDF/B-V based multigroup cross-section libraries for advanced neutron source (ANS) reactor studies

International Nuclear Information System (INIS)

Ford, W.E. III; Arwood, J.W.; Greene, N.M.; Moses, D.L.; Petrie, L.M.; Primm, R.T. III; Slater, C.O.; Westfall, R.M.; Wright, R.Q.

1990-09-01

Pseudo-problem-independent, multigroup cross-section libraries were generated to support Advanced Neutron Source (ANS) Reactor design studies. The ANS is a proposed reactor which would be fueled with highly enriched uranium and cooled with heavy water. The libraries, designated ANSL-V (Advanced Neutron Source Cross Section Libraries based on ENDF/B-V), are data bases in AMPX master format for subsequent generation of problem-dependent cross-sections for use with codes such as KENO, ANISN, XSDRNPM, VENTURE, DOT, DORT, TORT, and MORSE. Included in ANSL-V are 99-group and 39-group neutron, 39-neutron-group 44-gamma-ray-group secondary gamma-ray production (SGRP), 44-group gamma-ray interaction (GRI), and coupled, 39-neutron group 44-gamma-ray group (CNG) cross-section libraries. The neutron and SGRP libraries were generated primarily from ENDF/B-V data; the GRI library was generated from DLC-99/HUGO data, which is recognized as the ENDF/B-V photon interaction data. Modules from the AMPX and NJOY systems were used to process the multigroup data. Validity of selected data from the fine- and broad-group neutron libraries was satisfactorily tested in performance parameter calculations

Integrated system for production of neutronics and photonics calculational constants. Supplemental neutron-induced interactions (Z less than or equal to 35): graphical, experimental data

International Nuclear Information System (INIS)

Cullen, D.E.; Howerton, R.J.; MacGregor, M.H.; Perkins, S.T.

1976-01-01

This report (Vol. 8) presents graphs of supplemental neutron-induced cross sections in the Experimental Cross Section Information Library (ECSIL) as of July 4, 1976. It consists of interactions where more than one data set is needed to show cross-section behavior. In contrast, Vol. 7 of this UCRL-50400 series consists primarily of interactions where a single data set contains enough points to show cross-section behavior. In Vol. 7 can be found the total, elastic, capture, and fission cross sections (along with the parameters anti ν, α, and eta). Volume 8 contains all other reactions. Data are plotted with associated cross-section error bars (when given) and compared with the Evaluated Nuclear Data Library (ENDL) as of July 4, 1976. The plots are arranged in ascending order of atomic number (Z) and atomic weight (A). Part A contains the plots for Z = 1 to 35; Part B contains the plots for Z greater than 35

Integrated system for production of neutronics and photonics calculational constants. Major neutron-induced interactions (Z less than or equal to 55): graphical, experimental data

International Nuclear Information System (INIS)

Cullen, D.E.; Howerton, R.J.; MacGregor, M.H.; Perkins, S.T.

1976-01-01

This report (vol. 7) presents graphs of major neutron-induced interaction cross sections in the Experimental Cross Section Information Library (ECSIL) as of July 4, 1976. It consists primarily of interactions where a single data set contains enough points to show cross-section behavior. In contrast, vol. 8 of this UCRL-50400 series consists of interactions where more than one data set is needed to show cross section behavior. Thus, you can find the total, elastic, capture, and fission cross sections (along with the parameters anti ν, α, and eta) in vol. 7 and all other reactions in vol. 8. Data are plotted with associated cross section error bars (when given) and compared with the Evaluated Nuclear Data Library (ENDL) as of July 4, 1976. The plots are arranged in ascending order of atomic number (Z) and atomic weight (A). Part A contains the plots for Z = 1 to 55; Part B contains the plots for Z greater than 55

Integrated system for production of neutronics and photonics calculational constants. Major neutron-induced interactions (Z less than or equal to 55): graphical, experimental data

Energy Technology Data Exchange (ETDEWEB)

Cullen, D.E.; Howerton, R.J.; MacGregor, M.H.; Perkins, S.T.

1976-07-04

This report (vol. 7) presents graphs of major neutron-induced interaction cross sections in the Experimental Cross Section Information Library (ECSIL) as of July 4, 1976. It consists primarily of interactions where a single data set contains enough points to show cross-section behavior. In contrast, vol. 8 of this UCRL-50400 series consists of interactions where more than one data set is needed to show cross section behavior. Thus, you can find the total, elastic, capture, and fission cross sections (along with the parameters anti ..nu.., ..cap alpha.., and eta) in vol. 7 and all other reactions in vol. 8. Data are plotted with associated cross section error bars (when given) and compared with the Evaluated Nuclear Data Library (ENDL) as of July 4, 1976. The plots are arranged in ascending order of atomic number (Z) and atomic weight (A). Part A contains the plots for Z = 1 to 55; Part B contains the plots for Z greater than 55.

Revisions to Conventional Clock Domain Crossing Methodologies in Triple Modular Redundant Circuits

Science.gov (United States)

Berg, Melanie D.; LaBel, Kenneth A.

2018-01-01

We present updates to the conventional methodology of triple modular redundancy (TMR) insertion as it pertains to clock domain crossings (CDCs). Three types of TMR schemes and their suggested corresponding CDC revisions are discussed.

Installation of Tc-99m generator manufacturing facilities

International Nuclear Information System (INIS)

Shin, B. C.; Choung, W. M.; Park, J. H.; Park, S. H.; Kim, S. J.; Park, K. B.

2004-01-01

For the characteristics of radiopharmaceuticals, the manufacturing facility should be complied with the radiation safety standards for operators as well as GMP (Good Manufacturing Practice) cleanness standards for production. We intensively modified the existing Radioisotope production facilities, which were installed only in radiation safety points of view, to meet cleanness criteria. And the concept of multi-barrier buffer zones was introduced to apply negative air pressure for hot cell with first priority and to continue relative positive air pressure for clean room. The manufacturing area for Tc-99m Generator can be entered only through a second change. The doors of each change area are interlocked to maintain air pressure differentials. The pass box for material transfer are also interlocked so that only one side may be opened at any one time to keep cleanness. Two door-type autoclave was installed crossing the wall between preparing room and aseptic room to keep cleanness after sterilization. Three lead hot cells were installed and final inspection including gamma survey test were performed. The clean room was installed and TAB for this facility was performed in order to acquire the necessary air flow. The filter bank for filtration of exhausted radiation air was installed and its efficiency test was performed. In this facility, radiation shielding utilities and manufacturing instruments were set up and their operating manuals were documented. Efficiency tests for every utilities and instruments were satisfied and the approval for use of the facilities was achieved from MOST (Ministry of Science and Technology). The Sam Young Unitech, the lessee of the facilities set up the equipment in the hot cell, which is needed to produce Tc-99m Generator, supported by IPPE in Russia. They are composing the systems complied with the guidelines and the regulations, and keep in contact to KFDA for acquiring its approval. It is expected to produce Tc-99m Generator within

99mTc-ECD and 99mTc-HM-PAO SPECT in five patients with MELAS

International Nuclear Information System (INIS)

Katagiri, Shinako; Nishimaki, Hiroshi; Kitano, Masashi; Horiike, Shigeharu; Kan, Shinichi; Ishii, Katsumi; Matsubayashi, Takashi; Sakai, Fumihiko

1998-01-01

Cerebral perfusion was studied in five patients with mitochondrial encephalomyopathy with lactic acidosis and stroke-like episodes syndrome (MELAS), using single photon emission computed tomography (SPECT) with 99m Tc-ethyl cysteinate dimer ( 99m Tc-ECD) or 99m Tc-hexamethyl propyleneamine oxime ( 99m Tc-HM-PAO). In four cases, regional cerebral blood flow (rCBF) was evaluated by the method reported by Mastuda et al. Immediately after the stroke-like episodes, accumulation of the tracer was relatively increased in the temporooccipital lobe, and also increased rCBF was shown in the same area. However, the region showed decreased radioactivity at the chronic stage, and rCBF decreased also. These findings are consistent with positron emission tomography (PET) at the acute stage and autopsy. 99m Tc-ECD SPECT and 99m Tc-HM-PAO SPECT may be useful in the diagnosis and assessment of the progress of the MELAS. (author)

Determination of radionuclidic impurities in ^99mTceluate from ⁹⁹Mo/^99mTc generator for quality control

DEFF Research Database (Denmark)

Hou, Xiaolin

2017-01-01

, 89Sr and 90Sr. Radioactive decay for removal of 99mTc, ion exchange and extraction chromatography for removal of 99Mo and 99Tc are effective for separation of interferences. Gamma spectrometry, LSC with alpha/beta discrimination, and Cherenkov counting using LSC are sensitive methods for measurement...... of the impurity radionuclides. The detection limits of this method are well meet the requirement of the quality control according to the limitation of the pharmacopoeia....

Experimental study of 99Tcm-HL91 and 99Tcm-MIBI in mice bearing Lewis lung cancer

International Nuclear Information System (INIS)

Han Chunqi; Li Yaming; Ren Yangang; Yi Lijie

2000-01-01

Objective: To evaluate the ability of detecting lung cancer by 99 Tc m -HL91 and 99 Tc m -MIBI in mice bearing Lewis lung cancer. Methods: Four model mice underwent whole body planar imaging at 2 h, 4 h after injection of 99 Tc m -MIBI; four mice underwent whole body planar imaging at 2 h and 4 h after injection of 99 Tc m -HL91, and the mice of the 99 Tc m -HL91 group were then killed, the tumor, blood and organs were removed, weighted and the radioactivity was measured. ROIs were drawn around the tumor, head and chest in whole body planar images, and radioactivity ratios of tumor to head (T/H), chest (T/C) and contralateral limbs (T/L) were calculated. Results: No significant tumor radioactivity in 2 h and 4 h images of 99 Tc m -MIBI mice (T/C: 0.20 +- 0.08 and 0.14 +- 0.07) was found; increased tumor radioactivity was identified in images of 99 Tc m -HL91 mice (T/C: 3.25 +- 1.25 and 2.44 +- 1.07), and there was significant difference (t = 4.8 - 7.5, P 99 Tc m -HL91 in tumor tissue of mice is higher and clearance rate is slower. 99 Tc m -HL91 is a valuable tumor imaging agent for clinical diagnosis for the cancer

Preparation of 99Mo for 99mTc generators and the issue of further development. A survey report

International Nuclear Information System (INIS)

Malek, Z.

1998-01-01

The following topics are dealt with: World production of Mo-99 for technetium generators; Typical procedures for the preparation of Mo-99; Current and expected decline in the production of Mo-99; and Directions of further development (Water reactors-irradiation systems for the preparation of Mo-99; Homogeneous reactor systems for the preparation of Mo-99 based on molten salts; Systems with accelerators; Thermal processes for the reprocessing of irradiated target material). (P.A.)

Neutron cross section measurements for the Fast Breeder Program

International Nuclear Information System (INIS)

Block, R.C.

1979-06-01

This research was concerned with the measurement of neutron cross sections of importance to the Fast Breeder Reactor. The capture and total cross sections of fission products ( 101 102 104 Ru, 143 145 Nd, 149 Sm, 95 97 Mo, Cs, Pr, Pd, 107 Pd, 99 Tc) and tag gases (Kr, 78 80 Kr) were measured up to 100 keV. Filtered neutron beams were used to measure the capture cross section of 238 U (with an Fe filter) and the total cross section of Na (with a Na filter). A radioactive neutron capture detector was developed. A list of publications is included

Synthesis and irradiation of titanium molybdates used as matrices of the {sup 99} Mo/ {sup 99m} Tc generators; Sintesis e irradiacion de molibdatos de titanio utilizados como matrices de los generadores de {sup 99} Mo/ {sup 99m} Tc

Energy Technology Data Exchange (ETDEWEB)

Diaz V, H. [Facultad de Quimica, UAEM 50000 Toluca, Estado de Mexico (Mexico); Monroy G, F. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

2005-07-01

The {sup 99m} Tc is the radioisotope but used in nuclear medicine. Commercially it takes place starting from generators of {sup 99} Mo/{sup 99m} Tc, composed by a chromatography column padded of aluminium oxide of aluminum, where it is deposited the {sup 99} Mo, product of the fission of the {sup 235} U adsorbed and eluted, by means of a saline solution, in form of {sup 99m} TcO{sub 4}{sup -}. The production of {sup 99} Mo as a result of the fission, imposes radiochemical separations that generate significant quantities of radioactive waste of medium activity, and inflict elaborated radiochemical manipulation. Due to this, its have been carried out intense investigations to substitute the {sup 99} Mo fission product, by chemical compounds that produce {sup 99} Mo via the reaction {sup 98} Mo(n, {gamma}){sup 99} Mo. Presently work intends the use of gels of titanium molybdates like matrices of these generators. Titanium molybdates were synthesized starting from solutions TiCl{sub 3} and ammonium molybdates and it was studied the effect of the final pH of the gels, the concentration of the Ti{sup +3} and the influence of the laundry of these on the acting of generators. The best efficiencies and chemical purity, radiochemical and radionuclides of the gels like matrices of generators {sup 99} Mo/{sup 99m} Tc were gotten with the washed gel, elaborated with the solution of TiCI{sub 3} 0.35M, and to a final pH of 5.9 (Author)

Update of CERN exchange network

CERN Multimedia

2003-01-01

An update of the CERN exchange network will be done next April. Disturbances or even interruptions of telephony services may occur from 4th to 24th April during evenings from 18:30 to 00:00 but will not exceed more than 4 consecutive hours (see tentative planning below). CERN divisions are invited to avoid any change requests (set-ups, move or removals) of telephones and fax machines from 4th to 25th April. Everything will be done to minimize potential inconveniences which may occur during this update. There will be no loss of telephone functionalities. CERN GSM portable phones won't be affected by this change. Should you need more details, please send us your questions by email to Standard.Telephone@cern.ch. DateChange typeAffected areas April 11 Update of switch in LHC 4 LHC 4 Point April 14 Update of switch in LHC 5 LHC 5 Point April 15 Update of switches in LHC 3 and LHC 2 Points LHC 3 and LHC 2 April 22 Update of switch N4 Meyrin Ouest April 23 Update of switch  N6 Prévessin Site Ap...

Radiopharmaceuticals to 99mTc

International Nuclear Information System (INIS)

Leon Cabana, Alba

1994-01-01

Studies about 99m Tc had demonstrated that have favorable properties for support diagnostic proceedings in nuclear medicine. This physical and chemical properties used for obtain another radiopharmaceuticals have been employed through re actives kits labelled with Tc 99m . A brief description was given about 99m utilities in diagnostic techniques such as endothelium reticular system,renal and hepatic studies,bone scintillators,cardiac diagnostic and cerebral perfusion

Imaging of irradiated liver with Tc-99m-sulfur colloid and Tc-99m-IDA

International Nuclear Information System (INIS)

Gelfand, M.J.; Saha, S.; Aron, B.S.

1981-01-01

In three cases, irradiated regions of liver failed to concentrate Tc-99m-sulfur colloid. In two of these three, imaging with Tc-99m-acetanilide iminodiacetic acid (IDA) agents within five days showed near normal hepatic uptake of this hepatobiliary imaging agent. The hepatic parenchymal cells may be imaged with Tc-99m-IDA in some irradiated regions of liver, despite loss of reticuloendothelial cell function

The technetium-99m DTPA partition test in the diagnosis of tuberculous meningitis

International Nuclear Information System (INIS)

Von Wenzel, K.S.; Klopper, J.F.; Wasserman, H.J.

1989-01-01

Although the blood/cerebrospinal fluid (CSF) bromide concentration ratio is sensitive and specific in the diagnosis of tuberculous meningitis (TBM), bromide-82 is not always available since it is not generally used in nuclear medicine. The use of technetium-99m diethylenetriamine penta-acetic acid (DTPA) for a partition test was compared with that of 82 Br in 22 cases. Seven patients were diagnosed as having TBM, 9 patients had viral meningitis and 5 patients had septic meningitis. One normal control subject was also studied. Although the mechanism of transfer of substances across the blood-brain barrier as well as the factors affecting it are still unclear, both 82 Br and 99m Tc-DTPA cross the blood-brain barrier to a greater extent in TBM than in viral meningitis. Both tracers thus yield decreased serum/CSF concentration ratios in TBM. The accuracy of the 82 Br partition test was found to be 90,9% if a critical serum/CSF ratio of 1,3 was chosen, compared with 86,9% for the 99m Tc-DTPA partition test if a critical value of 3 was chosen. The use of 99m Tc D TPA offers various advantages, including general availability, lower cost and radiation dose per MBq, as well as the possibility of concomitant brain scintigraphy. 1 tab., 9 refs

Precise Measurement of the $\\bar{p}p$ Total Cross-Section in the ISR Energy Range

CERN Multimedia

2002-01-01

The major aim of this experiment is the precise measurement of the antiproton-proton total cross-section in the ISR energy range, using the total-rate method. The proton-proton total cross-section is remeasured with the same method and the same apparatus, and a precision of 0.5\\% is expected for both cross-sections. The total-rate method consists in the simultaneous measurement of the total interaction rate and the ISR luminosity. This is done with a set of scintillation-counter hodoscopes covering over 99.99\\% of the solid angle, which are sensitive to over 95\\% of all interactions. In addition to these detectors, small-angle drift-tube hodoscopes are used to measure the differential elastic cross-section as a function of the momentum transfert t. The total cross-section can be measured independently by extrapolating this differential cross-section to the forward direction and invoking the optical theorem. A study of the general features of charged-particle production is performed using finely divided scinti...

Biodistribution of 99Mo in rats

International Nuclear Information System (INIS)

Souza, Raphael Sancho Sisley de; Ribeiro, Bianca da Silva; Dantas, Ana Leticia Almeida; Dantas, Bernardo Maranhao; Bernardo Filho, Mario

2009-01-01

The modification of 99 Mo standard metabolism in the presence of MDP would alter the dosimetry of this radionuclide in nuclear medicine patients. Therefore, the objective of this work is to evaluate the influence of MDP in the biodistribution of 99 Mo. Wistar rats were divided in two groups of six animals, being inoculated respectively 99 Molibdate and 99 Mo+MDP via plex ocular. The biodistribution study was carried out after 10 and 120 minutes respectively. The organs were counted with a NaI(Tl) detector. The uptake values did not present significant differences among the groups. An in vitro study through planar chromatography was carried out to determine the affinity between molybdenum and MDP. The results show that 99 Mo has low affinity both to propanone and NaCl-0.9% solution. However, 99 Mo in the presence of MDP presented affinity to NaCl-0.9% solution and low affinity to propanone suggesting that 99 Mo was bound to MDP under the conditions of the experiment. (author)

Kinetic study on ligand exchange reaction between ethylenedicysteine and 99mTc- glucoheptonate (99mTc-GH)

International Nuclear Information System (INIS)

Wu, C.Y.; Ji, S.R.; Lu, C.X.; Ding, S.Y.; Chen, Z.P.; Lin, X.T.

2002-01-01

Aim: 99m Tc-L,L-ethylenedicysteine( 99m Tc-EC)is a new type of renal imaging agent. It can be labeled very easily and efficiently at room temperature through direct labeling at pH 12. The need for direct labeling at pH 12 does not compromise the simplicity and ease of preparation of 99m Tc-EC and its practical usefulness in daily routine. On the basis of the labeling experiments, we developed a ligand exchange labeling method, in which the labeling EC with 99m Tc can be performed at pH 8. In order to provide a theoretic basis, a detailed kinetic study of ligand exchange reaction between 99m Tc- glucoheptonate( 99m Tc-GH) and EC was carried out. Materials and Methods: 99m Tc-EC is prepared as follows: 99m Tc-GH + EC → 99m Tc-EC + GH, labeling can be easily performed by adding 99m TcO 4 - (2∼6ml generator elute) to glucoheptonate solution containing SnCl 2 .2H 2 O solution to form 99m Tc-GH, then freshly prepared 99m Tc-GH is transferred to the aqueous solution of different concentrations of EC at different pH value, after being shaken, 99m Tc-EC was formed. Radiolabeling yield(RLY) and radiochemical purity(RCP) of 99m Tc-GH and 99m Tc-EC were measured by Xinhua No.1 paper with developing system of Me 2 CO/H 2 O/con.NH 3 .H 2 O=9/3/1(V/V). 99m Tc-GH(RCP must be over 98%, 80ul, 3.6∼7.4MBq) was added to 1ml of 0.5mol/L phosphate buffer(pH 12) containing different amount of EC(150, 75, 50 and 15ug), the sample was taken out at different time intervals and RCP was determined. The solution of EC(30ul, 5g/L) was added to 1ml of 0.5mol/L phosphate buffer at different pH value(pH11, 10, 9, 8, 7), after completely vortexed, 99m Tc-GH(RCP must be over 98%, 80ul, 3.6∼7.4MBq) was then added, the sample was taken out and RCP was determined as above. The rate constant(k) of ligand exchange reaction at different concentrations of EC and different reaction pH values were calculated out by integrating. Plot ln[1/(1-RLY)] vs t(time) showed a liner relationship, and the rate

99mTc generator preparation using (n, γ)99Mo produced using natural molybdenum

International Nuclear Information System (INIS)

Kim, Hark Rho; Park, Jin Ho; Lee, Kye Hong

2003-01-01

The Mo-99 is a widely used radioisotope in Korea. To fulfill the demand, we are producing Mo-99 using a specially designed and fabricated rig containing MoO 3 target. We are using natural molybdenum so far. But considering the utilization of the enriched molybdenum to increase the specific activity further, we desire the realization of PZC with (n, γ)Mo-99 as early as possible. To make the generator loading facility, we are in progress of construction work for the related hot cell facilities. (author)

Comparison of biological behavior of 99Tcm-ciprofloxacin (Infecton) and 99Tcm-HIgG in rabbit models of inflammation

International Nuclear Information System (INIS)

He Wei; Chen Shaoliang; Mao Jinlei; Jiang Maosong

2008-01-01

Objective: 99 Tc m -ciprofloxacin(Infecton) and 99 Tc m -HIgG are both radiopharmaceuticals for inflammation and infectious disease imaging. It was reported that 99 Tc m -ciprofloxacin (Infecton)was able to distinguish inflammation from infection, while 99 Tc m -HIgG was a nonspecific agent. The study was designed to compare the in vivo characteristics between 99 Tc m -ciprofloxacin(Infecton) and 99 Tc m -HIgC in rabbit model of inflammation. Methods: Eight rabbits were grouped as inflammation model (the first group), infection mod- el (the second group), concomitant inflammation and infection model (the third group), and control (the fourth group) groups. A total of 185 MBq (0.5 ml) 99 Tc m -ciprofloxacin (Infecton) was administered intravenously to each rabbit, a serious dynamic images were acquired till 24 h post-injection. Repeated examination with 99 Tc m -HIgG was carried out 2 d later. Results: 99 Tc m -ciprofloxacin (Infecton) scan was negative in the inflammation models and controls, and was positive in the infection models. In the third group 99 Tc m - ciprofloxacin (Infecton) showed infection focus in the left thigh but negative uptake at inflammation focus in the right thigh. 99 Tc m -HIgG scan were positive in all models. The optimal image time for 99 Tc m -ciproftoxacin (Infecton) was 3 h after administration, but positive image could still be observed 24 h later. Conclusion 99 Tc m -ciprofloxacin (Infecton) appears to specifically accumulate in the infective lesion. (authors)

14 CFR 61.99 - Aeronautical experience.

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 2 2010-01-01 2010-01-01 false Aeronautical experience. 61.99 Section 61.99 Aeronautics and Space FEDERAL AVIATION ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) AIRMEN CERTIFICATION: PILOTS, FLIGHT INSTRUCTORS, AND GROUND INSTRUCTORS Recreational Pilots § 61.99...

Direct {sup 99m}Tc labeling of Herceptin (trastuzumab) by {sup 99m}Tc(I) tricarbonyl ion

Energy Technology Data Exchange (ETDEWEB)

Chen, W.-J.; Yen, C.-L.; Lo, S.-T.; Chen, K.-T. [Department of Biomedical Engineering and Environmental Sciences, National Tsing Hua University, Hsinchu 30013, Taiwan (China); Lo, J.-M. [Department of Biomedical Engineering and Environmental Sciences, National Tsing Hua University, Hsinchu 30013, Taiwan (China)], E-mail: jmlo@mx.nthu.edu.tw

2008-03-15

By simply incubating Herceptin (trastuzumab) with [{sup 99m}Tc(CO){sub 3}(OH{sub 2}){sub 3}]{sup +} ion in saline, a significant yield of {sup 99m}Tc-labeled trastuzumab was found to be achievable. The effective labeling may be based on that trastuzumab is inherent with endogenous histidine group to which {sup 99m}Tc(I) tricarbonyl ion can be strongly bound. For practical {sup 99m}Tc labeling processing, trastuzumab was purified beforehand from the commercial product, Herceptin (Genentech) via size exclusion chromatography to remove the excipient, {alpha}-histidine and a high-labeled yield could be obtained by incubating the purified trastuzumab with [{sup 99m}Tc(CO){sub 3}(OH{sub 2}){sub 3}]{sup +}. Retention of bioactivity of the {sup 99m}Tc(I)-labeled trastuzumab was validated using a cell binding test.

Clinical application of 99mTc-DTPA-HSA

International Nuclear Information System (INIS)

Kawamura, Yasuaki; Yamazaki, Junichi; Okuzumi, Ichio

1989-01-01

A newly developed blood pool imaging agent, Tc-99m DTPA-HSA (Tc-99m HSA-D), was clinically assessed in blood pool studies of patients with heart disease. Twenty mCi of Tc-99m HSA-D was iv injected to the patients. Similarly, conventional Tc-99m HSA was injected one week later for comparison. Blood counts of Tc-99m HSA-D were significantly higher than those of Tc-99m HSA at 30 minutes after iv injection (p<0.01) and at one, 3, and 6 hours (p<0.001). For the heart, liver, and lungs, sequential counts of Tc-99m HSA-D were also significantly higher than those of Tc-99m HSA. Free Tc-99m uptake in the stomach, thyroid gland, and kidneys was higher on Tc-99m HSA images than Tc-99m HSA-D images. Hepatic and pulmonary uptake of free Tc-99m that were visualized on Tc-99m HSA-D did not influence the diagnostic ability. None of the patients had clinical toxicity of Tc-99m HSA-D. The results indicate that Tc-99m HSA-D is a stable blood pool imaging agent. (Namekawa, K)

Tank 241-U-102, Grab Samples 2U-99-1, 2U-99-2 and 2U-99-3 Analytical Results for the Final Report

International Nuclear Information System (INIS)

STEEN, F.H.

1999-01-01

This document is the final report for tank 241-U-102 grab samples. Five grab samples were collected from riser 13 on May 26, 1999 and received by the 222-S laboratory on May 26 and May 27, 1999. Samples 2U-99-3 and 2U-99-4 were submitted to the Process Chemistry Laboratory for special studies. Samples 2U-99-1, 2U-99-2 and 2U-99-5 were submitted to the laboratory for analyses. Analyses were performed in accordance with the Compatibility Grab Sampling and Analysis Plan for Fiscal year 1999 (TSAP) (Sasaki, 1999) and the Data Quality Objectives for Tank Farms Waste Compatibility Program (DQO) (Fowler 1995, Mulkey and Miller 1998). The analytical results are presented in the data summary report. None of the subsamples submitted for differential scanning calorimetry (DSC), total organic carbon (TOC) and plutonium 239 (Pu239) analyses exceeded the notification limits as stated in TSAP

A mutation in the envelope protein fusion loop attenuates mouse neuroinvasiveness of the NY99 strain of West Nile virus

International Nuclear Information System (INIS)

Zhang Shuliu; Li Li; Woodson, Sara E.; Huang, Claire Y.-H.; Kinney, Richard M.; Barrett, Alan D.T.; Beasley, David W.C.

2006-01-01

Substitutions were engineered individually and in combinations at the fusion loop, receptor-binding domain and a stem-helix structure of the envelope protein of a West Nile virus strain, NY99, and their effects on mouse virulence and presentation of epitopes recognized by monoclonal antibodies (MAbs) were assessed. A single substitution within the fusion loop (L107F) attenuated mouse neuroinvasiveness of NY99. No substitutions attenuated NY99 neurovirulence. The L107F mutation also abolished binding of a non-neutralizing MAb, 3D9, whose epitope had not been previously identified. MAb 3D9 was subsequently shown to be broadly cross-reactive with other flaviviruses, consistent with binding near the highly conserved fusion loop

Spectroscopy of deep doping levels in Cd{sub 0.99}Mn{sub 0.01}Te:Ga; Spektroskopia glebokich poziomow domieszkowych w Cd{sub 0.99}Mn{sub 0.01}Te:Ga

Energy Technology Data Exchange (ETDEWEB)

Szatkowski, J.; Placzek-Popko, E.; Sieranski, K. [Politechnika Wroclawska, Wroclaw (Poland); Bieg, B. [Wyzsza Szkola Morska, Szczecin (Poland)

1997-12-01

The investigation results of deep energy levels in Cd{sub 0.99}Mn{sub 0.01}Te (n-type) doped with gallium have been presented. Deep level transient spectroscopy (DLTS) measurements have been carried out in temperature range 80-420 K. The results show five types of electron traps. The activation energy of trapping levels and electron trapping cross-sections have been determined for observed traps. 2 refs, 3 figs, 1 tab.

Biological properties of 99Tcm-HMIBP and its usefulness for bone scintigraphy by comparing with 99Tcm-MDP

International Nuclear Information System (INIS)

Luo Shineng; Ye Wanzhong; Xie Minhao; Yu Yanhua; Zhao Yan; Cao Guoxian; Guo Xuehua; Zhou Lian

2008-01-01

Objective: Zoledronate has been extensively used for the treatment of tumor-induced hypercalcaemia and osteolytic bone metastases. 1-hydroxy-2-(1-methylimidazol-2-yl) ethylidene-1,1-bisphos- phonic acid (HMIBP) with similar chemical structure as Zoledronate, was therefore considered to be useful as bone imaging agent. In this study the usefulness of 99 Tc m labeled HMIBP for bone imaging was evaluated and the results with the well-established 99 Tc m -methylene diphosphonic acid (MDP) imaging was compared. Methods: Labeled with 99 Tc m , the SnCl 2 ·2H 2 O quantity, radiochemical purity, pH value and stability at 4 degree C of 99 Tc m -HMIBP were measured. Besides, the partition coefficient, plasma protein binding rate, hemodynamic parameters of 99 Tc m -HMIBP and median lethal dose (LD 50 ) of HMIBP were determined. 99 Tc m -HMIBP bone imaging was performed in normal New Zealand rabbits and compared with 99 Tc m -MDP bone imaging. Results: The kit composed of 5 mg HMIBP and 0.05 mg SnCl 2 ·2H 2 O. The labeling rate was 96% after 180 d storage at 4 degree C. The radiochemical purity of 99 Tc m -HMIBP was 98% at pH 5 and the partition coefficients were 0.0125 and 0.0054 at pH 7.0 and 7.4 respectively. The plasma protein binding rate of 99 Tc m -HMIBP was 44.77%. The hemodynamic parameter C valued 3.0979 e -0.0721t +0.1250 e -0.0076t and LD 50 was 8.2 mg/kg. The bone images of 99 Tc m -HMIBP were fairly well 3 h after the injection, which was comparable to 99 Tc m -MDP bone imaging. Conclusions: 99 Tc m -HMIBP had good biological properties and comparable bone imaging quality with 99 Tc m -MDP. It might be a potential agent for both treatment and imaging. (authors)

Comparative study of gated myocardial perfusion imaging using 99Tcm-tetrofosmin and 99Tcm-sestamibi

International Nuclear Information System (INIS)

Wang Ruihua; Ruan Qiao; Sun Ke; Han Xingmin; Sun Bingqi; Xie Xinli; Cheng Bing; Chen Yanlin; Liu Baoping

2013-01-01

Objective: To compare the results of 99 Tc m -tetrofosmin (TF) and 99 Tc m -MIBI G-MPI in evaluating left ventricular myocardial perfusion and other functional parameters. Methods: TF and MIBI were both labeled by 99 Tc m and the radiochemical purities were tested. During December 2011 to May 2012, 112 patients who had examinations of CAG and echocardiograph in one week after G-MPI were divided into 99 Tc m -TF group (47 patients) and 99 Tc m -MIBI group (65 patients) by simple random sampling. Patients who suffered from severe arrhythmia, clinically suspicious of myocarditis or cardiomyopathy were excluded. The research was approved by the ethics committee, and all patients signed informed consents. One-day 99 Tc m -TF G-MPI and two-day 99 Tc m -MIBI G-MPI were performed. The left ventricular functional parameters were acquired automatically by Cedars quantitative gated SPECT (QGS) software, including LVEF, EDV, ESV, peak filling rate (PFR), peak ejection rate (PER) and phase standard difference (SD). The data were analyzed using χ 2 test, two-sample t test, paired t test and linear correlation analysis by SPSS 17.0. Results: The radiochemical purities of 99 Tc m -TF and 99 Tc m -MIBI were (97.5±0.4) % and (99.1±0.2) % respectively. The coincidence rates of 99 Tc m -TF and 99 Tc m -MIBI G-MPI with CAG were 88.9% (40/45) and 90.5% (57/63), respectively. There was no significant difference between G-MPI results of the two agents (χ 2 =0.389, P>0.05). There was also no significant difference between left ventricular functional parameters of the two agents (LVEF:(62.60±13.56)% vs (60.52±7.08)%, t=0.940; EDV: (103.3±17.29) ml vs (98.52±19.37) ml, t=1.348; ESV: (41.73±12.69) ml vs (46.05±10.81) ml, t=0.851; PER: (2.73±0.67)EDV/s vs (2.61±1.04) EDV/s, t=0.725; PFR: (2.13±0.80) EDV/s vs (2.07±1.09) EDV/s, t=0.339; phase SD: (5.58±4.16)° vs (5.97±4.64)°, t=0.450; all P>0.05). There was no significant difference between left ventricular functional

Technetium-99m-human fibrinogen

International Nuclear Information System (INIS)

Wong, D.W.; Mishkin, F.S.

1975-01-01

Exogenous fibrinogen has been successfully labeled with /sup 99m/Tc using a modified electrolytic method. The exact labeling mechanism has not been determined. Experimental data suggest that the labeling process of /99m/Tc-fibrinogen is quite similar to that of /sup 99m/Tc-human serum albumin as reported earlier by Benjamin. Technetium-99m-fibrinogen is stable in human plasma or in 1 percent buffered human serum albumin. A binding efficiency of 76 percent has been achieved with approximately 25 percent clottable protein. The entire labeling procedure requires less than 1 hr of preparation time. This short labeling time in a closed system may allow development of a practical method for labeling autologous fibrinogen, thus eliminating the risk of hepatitis transmission. (U.S.)

7 CFR 27.99 - Values; expression.

Science.gov (United States)

2010-01-01

... 7 Agriculture 2 2010-01-01 2010-01-01 false Values; expression. 27.99 Section 27.99 Agriculture Regulations of the Department of Agriculture AGRICULTURAL MARKETING SERVICE (Standards, Inspections, Marketing... CLASSIFICATION UNDER COTTON FUTURES LEGISLATION Regulations Price Quotations and Differences § 27.99 Values...

A draft business plan for the production of PZC 99Mo-99mTc generator in the Philippines

International Nuclear Information System (INIS)

Sombrito, Elvira Z.; Cabalfin, Estelita G.; Calix, Virginia S.; Dela Rosa, Alumanda M.; Borras, Ma. Teresa L.; Bulos, Adelina dM.

2007-01-01

Technetium-99m ( 99m Tc) remains as the main workhorse of nuclear medicine in the country. Alone or conjugated with other ligands, it is being used to show the function of major organs and other tissues such as the lung, brain, kidney, liver and bone. It is imported to the country as 99 Mo- 99m Tc generator. These commercial generators use fission molybdenum adsorbed onto alumina column. The FNCA project has shown the feasibility of using a PZC column-reactor 99 Mo generator for commercial applications, citing mainly the cheaper cost of the PZC generator than the imported alumina column-fission 99 Mo generator. PNRI proposes in this draft business plan, the commercial production of PZC generator through the establishment of a facility for the in-house production of 99 Mo- 99m Tc generator. The generator will use PZC coming from Japan as the column material, 99 Mo sourced from neighboring countries and an automatic loading and adsorption machine. Because the PNRI has no local production of the generator, the requirements for successfully venturing into this business activity may differ from the other FNCA members. A careful assessment based on verified data will be needed to refine the business plan. (author)

NEUTRON CROSS SECTION EVALUATIONS OF FISSION PRODUCTS BELOW THE FAST ENERGY REGION

Energy Technology Data Exchange (ETDEWEB)

OH,S.Y.; CHANG,J.; MUGHABGHAB,S.

2000-05-11

Neutron cross section evaluations of the fission-product isotopes, {sup 95}Mo, {sup 99}Tc, {sup 101}Ru, {sup 103}Rh, {sup 105}Pd, {sup 109}Ag, {sup 131}Xe, {sup 133}Cs, {sup 141}Pr, {sup 141}Nd, {sup 147}Sm, {sup 149}Sm, {sup 150}Sm, {sup 151}Sm, {sup 152}Sm, {sup 153}Eu, {sup 155}Gd, and {sup 157}Gd were carried out below the fast neutron energy region within the framework of the BNL-KAERI international collaboration. In the thermal energy region, the energy dependence of the various cross-sections was calculated by applying the multi-level Breit-Wigner formalism. In particular, the strong energy dependence of the coherent scattering lengths of {sup 155}Gd and {sup 157}Gd were determined and were compared with recent calculations of Lynn and Seeger. In the resonance region, the recommended resonance parameters, reported in the BNL compilation, were updated by considering resonance parameter information published in the literature since 1981. The s-wave and, if available, p-wave reduced neutron widths were analyzed in terms of the Porter-Thomas distribution to determine the average level spacings and the neutron strength functions. Average radiative widths were also calculated from measured values of resolved energy resonances. The average resonance parameters determined in this study were compared with those in the BNL and other compilations, as well as the ENDF/B-VI, JEF-2.2, and JENDL-3.2 data libraries. The unresolved capture cross sections of these isotopes, computed with the determined average resonance parameters, were compared with measurements, as well as the ENDF/B-VI evaluations. To achieve agreement with the measurements, in a few cases minor adjustments in the average resonance parameters were made. Because of astrophysical interest, the Maxwellian capture cross sections of these nuclides at a neutron temperature of 30 keV were computed and were compared with other compilations and evaluations.

Cerebral uptake and retention of 99Tcsup(m)-hexamethylpropyleneamine oxime (99Tcsup(m)-HM-PAO)

International Nuclear Information System (INIS)

Holmes, R.A.; Chaplin, S.B.; Royston, K.G.; Missouri Univ., Columbia

1985-01-01

A new radiopharmaceutical, 99 Tcsup(m)-hexamethylpropyleneamine oxime ( 99 Tcsup(m)-HM-PAO) is described. This agent displays considerable promise for imaging cerebral blood flow. In studies in rats and one human volunteer, 99 Tcsup(m)-HM-PAO demonstrates good brain uptake, prolonged retention of activity in the brain, and slow regional redistribution. These properties suggest that this new radiopharmaceutical is ideal for single photon emission tomographic (SPECT) imaging of cerebral blood flow. (author)

Updating Recursive XML Views of Relations

DEFF Research Database (Denmark)

Choi, Byron; Cong, Gao; Fan, Wenfei

2009-01-01

This paper investigates the view update problem for XML views published from relational data. We consider XML views defined in terms of mappings directed by possibly recursive DTDs compressed into DAGs and stored in relations. We provide new techniques to efficiently support XML view updates...... specified in terms of XPath expressions with recursion and complex filters. The interaction between XPath recursion and DAG compression of XML views makes the analysis of the XML view update problem rather intriguing. Furthermore, many issues are still open even for relational view updates, and need...... to be explored. In response to these, on the XML side, we revise the notion of side effects and update semantics based on the semantics of XML views, and present effecient algorithms to translate XML updates to relational view updates. On the relational side, we propose a mild condition on SPJ views, and show...

Comparison of sup(99m)Tc-MDP to sup(99m)Tc-pertechnetate by computerized quantitative joint scintigraphy

International Nuclear Information System (INIS)

Rekonen, A.; Moettoenen, T.; Oka, M.

1982-01-01

99mTc-pertechnetate was compared to 99mTc-MDP in joint pairs with asymmetric arthritis. Markedly elevated joint activity ratios (inflamed/uninflamed joint) were measured in all the joint pairs studied. In the joints affected by reactive arthritis and without roentgenologic changes the mean joint activity was the same with both tracers. A very high activity ratio with 99mTc-MDP was found in septic arthritis. In rheumatoid arthritis the sensitivity of 99mTc-MDP as an indicator of active arthritis seemed to be better than that of 99mTc-pertechnetate. Even in joints without erosions in roentgenograms the joint activity ratios were markedly elevated with 99mTc-MDP. This suggests, that high activity in 99mTc-MDP scanning might be prognostic of erosive joint changes. In this work a profile curve was used for quantitation differences between joints

Dissociating Working Memory Updating and Automatic Updating: The Reference-Back Paradigm

Science.gov (United States)

Rac-Lubashevsky, Rachel; Kessler, Yoav

2016-01-01

Working memory (WM) updating is a controlled process through which relevant information in the environment is selected to enter the gate to WM and substitute its contents. We suggest that there is also an automatic form of updating, which influences performance in many tasks and is primarily manifested in reaction time sequential effects. The goal…

99m-technetium tetrofosmin and 99mTc-methylene diphosphonate in pre-surgical breast cancer

International Nuclear Information System (INIS)

Piperkova, E.; Gavrilov, I.; Timcheva, K.; Garanina, Z.; Aleksandrova, E.; Katerinski, K.; Dimitrova, M.

2004-01-01

Full text: The aim of this study was to assess the role of the Tc-99m Tetrofosmin (TF) in conjunction with Tc-99m methylenediphosphonate (MDP) in pre-surgical breast cancer (BC) staging. Thirty-six female patients, age range was 32-70 years (average 51.45 years), where the clinical examination, mammography (MG) and fine-needle aspiration cytology were inconclusive were subjected to Tc-99m TF Scintimammography (SMM). All the patients were examined in a specialized breast clinic by experienced surgeons and radiologists. Of the 36 patients, 24 had hyperdense breasts, 8 had undergone lumpectomy or mastectomy due to cancer in one of the breasts and were included in the present study because of suspicion of lesion in the contra lateral breast, 2 had palpable axillary lymph nodes (LN) but no palpable breast lump and 2 patients were of mastitis carcinomatosis. All biopsies were histopathologically verified 740 MBq of Tc-99m TF (Myoview-Amersham) was injected in the arm opposite to the side of the breast lesion. In patients with bilateral breast lesions (BL) radiopharmaceutical was injected in a pedal vein. Planar imaging in prone position was done 10-15 min later. Two lateral views of the left and right breasts including axilla were acquired followed by an anterior view in supine position with arm in an upright position so as to include both breasts and axillary region in the field of imaging view. Imaging was done using a large field of view single-head gamma camera (Diacam-Siemens) coupled with low-energy high-resolution collimator. In patients with locally advanced BC who were to receive pre-operative neo-adjuvant chemotherapy, cardiac GATED SPECT was also acquired using standard protocol. After few days, Tc-99m MDM scintimammography and whole-body bone scintigraphy was also performed. SMM, using the same acquisition protocol as with 99mTc-TF, was done 5-10 min after intravenous injection of 555-740 MBq 99mTc MDP. Standard WBBS was acquired two to three hours later. SMM

14 CFR 99.47 - Guam ADIZ.

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 2 2010-01-01 2010-01-01 false Guam ADIZ. 99.47 Section 99.47 Aeronautics and Space FEDERAL AVIATION ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) AIR TRAFFIC AND GENERAL OPERATING RULES SECURITY CONTROL OF AIR TRAFFIC Designated Air Defense Identification Zones § 99...

45 CFR 99.31 - Posthearing briefs.

Science.gov (United States)

2010-10-01

... 45 Public Welfare 1 2010-10-01 2010-10-01 false Posthearing briefs. 99.31 Section 99.31 Public Welfare DEPARTMENT OF HEALTH AND HUMAN SERVICES GENERAL ADMINISTRATION PROCEDURE FOR HEARINGS FOR THE CHILD CARE AND DEVELOPMENT FUND Posthearing Procedures, Decisions § 99.31 Posthearing briefs. The...

99Mo Yield Using Large Sample Mass of MoO3 for Sustainable Production of 99Mo

Science.gov (United States)

Tsukada, Kazuaki; Nagai, Yasuki; Hashimoto, Kazuyuki; Kawabata, Masako; Minato, Futoshi; Saeki, Hideya; Motoishi, Shoji; Itoh, Masatoshi

2018-04-01

A neutron source from the C(d,n) reaction has the unique capability of producing medical radioisotopes such as 99Mo with a minimum level of radioactive waste. Precise data on the neutron flux are crucial to determine the best conditions for obtaining the maximum yield of 99Mo. The measured yield of 99Mo produced by the 100Mo(n,2n)99Mo reaction from a large sample mass of MoO3 agrees well with the numerical result estimated with the latest neutron data, which are a factor of two larger than the other existing data. This result establishes an important finding for the domestic production of 99Mo: approximately 50% of the demand for 99Mo in Japan could be met using a 100 g 100MoO3 sample mass with a single accelerator of 40 MeV, 2 mA deuteron beams.

Breast-milk radioactivity after a Tc-99m DTPA aerosol/Tc-99m MAA lung study

International Nuclear Information System (INIS)

Mountford, P.J.; Hall, F.M.; Wells, C.P.; Coakley, A.J.

1984-01-01

Measurements were made of the concentration of Tc-99m activity in samples of breast milk following an administration of Tc-99m DTPA aerosol for a lung ventilation image and one of Tc-99m MAA for lung perfusion. The activity was 222 nCi/ml of milk (8.2 kBq/ml) at 2 hr after the MAA injection, and it was found to be excreted exponentially with an effective half-life of 4.6 hr. There was a small incorporation of Tc-99m into breast-milk protein. The authors conclude that the combined use of these two Tc-99m agents did not indicate the interruption of breast feeding beyond 24 hr after administration of the MAA, and that for an aerosol ventiliation study alone, breast feeding need not be interrupted for more than 4 hr after the test

Experimental cross-sections for proton-induced nuclear reactions on Mo-nat

Czech Academy of Sciences Publication Activity Database

Červenák, Jaroslav; Lebeda, Ondřej

2016-01-01

Roč. 380, AUG (2016), s. 32-49 ISSN 0168-583X R&D Projects: GA MŠk(CZ) LM2011019 Institutional support: RVO:61389005 Keywords : cross-sections * excitation functions * proton-induced nuclear reactions * natural molybdenum * Mo-99 * Tc-99m * Tc96m+g * Tc-95m * thick target yields * U-120M cyclotron Subject RIV: BG - Nuclear, Atomic and Molecular Physics, Colliders Impact factor: 1.109, year: 2016

sup(99)Tcsup(m)-ascorbate

International Nuclear Information System (INIS)

Persson, R.B.R.; Strand, S.E.; White, T.

1975-01-01

The sup(99)Tcsup(m)-ascorbate preparation used in this investigation contained FeCl 3 4mN, asorbic acid 110 mM and had an initial pH-value of 7.4 and a final pH-value of 6.8. Studies of the complex-formation were performed with gel-chromatography column-scanning (GCS), which is the analytical method to be preferred for this type of compound, indicated that the complex was formed in two steps. First reduced hydrolyzed sup(99)Tcsup(m) was formed rapidly and the sup(99)Tcsup(m)-ascorbate was formed by a slower reaction (k = 3, 10 -2 min -1 ). The renal uptake of sup(99)Tcsup(m)- was studied in 29 patients with a gamma-camera. The time-course of radio-activity in kidneys, 'tissue background'-areas and in blood suggested that optimal conditions for kidney-imaging were reached 3 to 6 hr after injection. About 20% of the sup(99)Tcsup(m)-ascorbate was bound to plasma-proteins, and only a small fraction to red blood-cells. The disappearance of the sup(99)Tcsup(m)-ascorbate from plasma followed a three-exponential curve: 40% with a half-life of 0.2 hr, 30% with a half-life of 20 hr. The absorbed radiation dose to the kidneys was about 200 (SE +- 60) mrad mCi -1 and to the whole-body 10 (SE +- 3) mrad mCi -1 of administered activity. There was a close correlation (r + 0.98) of the separate renal uptake (dx:(dx +sin)) of sup(99)Tcsup(m)-ascorbate to the separate renal function as determined with 131 I-Hippuran. (author)

Spectroscopy of deep doping levels in Cd0.99Mn0.01Te:Ga

International Nuclear Information System (INIS)

Szatkowski, J.; Placzek-Popko, E.; Sieranski, K.; Bieg, B.

1997-01-01

The investigation results of deep energy levels in Cd 0.99 Mn 0.01 Te (n-type) doped with gallium have been presented. Deep level transient spectroscopy (DLTS) measurements have been carried out in temperature range 80-420 K. The results show five types of electron traps. The activation energy of trapping levels and electron trapping cross-sections have been determined for observed traps. 2 refs, 3 figs, 1 tab

45 CFR 99.24 - Evidentiary purpose.

Science.gov (United States)

2010-10-01

... 45 Public Welfare 1 2010-10-01 2010-10-01 false Evidentiary purpose. 99.24 Section 99.24 Public Welfare DEPARTMENT OF HEALTH AND HUMAN SERVICES GENERAL ADMINISTRATION PROCEDURE FOR HEARINGS FOR THE CHILD CARE AND DEVELOPMENT FUND Hearing Procedures § 99.24 Evidentiary purpose. The purpose of the...

14 CFR 99.5 - Emergency situations.

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 2 2010-01-01 2010-01-01 false Emergency situations. 99.5 Section 99.5 Aeronautics and Space FEDERAL AVIATION ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) AIR TRAFFIC AND GENERAL OPERATING RULES SECURITY CONTROL OF AIR TRAFFIC General § 99.5 Emergency situations. In an...

14 CFR 99.15 - Position reports.

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 2 2010-01-01 2010-01-01 false Position reports. 99.15 Section 99.15 Aeronautics and Space FEDERAL AVIATION ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) AIR TRAFFIC AND GENERAL OPERATING RULES SECURITY CONTROL OF AIR TRAFFIC General § 99.15 Position reports. (a) The...

14 CFR 99.9 - Radio requirements.

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 2 2010-01-01 2010-01-01 false Radio requirements. 99.9 Section 99.9 Aeronautics and Space FEDERAL AVIATION ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) AIR TRAFFIC AND GENERAL OPERATING RULES SECURITY CONTROL OF AIR TRAFFIC General § 99.9 Radio requirements. (a) A...

45 CFR 99.27 - Official transcript.

Science.gov (United States)

2010-10-01

... 45 Public Welfare 1 2010-10-01 2010-10-01 false Official transcript. 99.27 Section 99.27 Public Welfare DEPARTMENT OF HEALTH AND HUMAN SERVICES GENERAL ADMINISTRATION PROCEDURE FOR HEARINGS FOR THE CHILD CARE AND DEVELOPMENT FUND Hearing Procedures § 99.27 Official transcript. The Department will...

14 CFR 99.49 - Hawaii ADIZ.

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 2 2010-01-01 2010-01-01 false Hawaii ADIZ. 99.49 Section 99.49 Aeronautics and Space FEDERAL AVIATION ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) AIR TRAFFIC... Zones § 99.49 Hawaii ADIZ. (a) Outer boundary. The area included in the irregular octagonal figure...

Under used technetium-99m generators

International Nuclear Information System (INIS)

Mushtaq, A.

2001-01-01

Health care reform truly has become a global issue and it will undoubtedly have a dramatic impact on the future of nuclear medicine business in particular. A bigger concern within the nuclear medicine community is its competitiveness with other modalities and cost effectiveness.Technetium-99m and its generators are playing key role for the majority of diagnostic scans performed in the world today. Availability of ''9''9''mTc can be increased if it is separated from ''9''9Mo after much shorter growth times. After proper planning with the extra ''9''9''mTc, a significant number of scans can be performed or we would be able to order approximately 30% low activity ''9''9Tc generators to fulfill our requirements

Measurement of 107Ag(α,γ)111In cross sections

International Nuclear Information System (INIS)

Baglin, Coral M.; Norman, Eric B.; Larimer, Ruth-Mary; Rech, Gregory A.

2004-01-01

Cross sections have been measured for the 107 Ag(α,γ) 111 In reaction at several α-particle energies between 7.8 MeV and 11.9 MeV. This reaction is of interest because it can provide a check on calculations of low-energy (α,γ) cross sections required for stellar nucleosynthesis predictions. Stacks of natural Ag foils of 1 (micro)m thickness and 99.97% purity were bombarded with 4 He + beams. Following irradiation, the yields of the 171-keV and 245-keV photons produced in the 2.805 day electron-capture decay of the 111 In product nucleus were measured off-line. The Ag foils were interleaved with 99.6% purity, 6 (micro)m thick natural Ti foils so that known cross sections for the 48 Ti(α,n) reaction could be used to check the accuracy of the beam current integration. For any given beam energy, beam energy degradation in the foils resulted in lower effective bombarding energies for successive foils in the stack, enabling measurements to be made for several energies per irradiation. The measured cross sections are compared with published statistical-model calculations

Preclinical evaluation of technetium 99m-labeled P1827DS for infection imaging and comparison with technetium 99m IL-8

Energy Technology Data Exchange (ETDEWEB)

Krause, Sabine [Bayer Schering Pharma AG, Global Drug Discovery, D-13342 Berlin (Germany); Rennen, Huub J.; Boerman, Otto C. [Radboud University, Nijmegen Medical Centre, 6500 HB Nijmegen (Netherlands); Baumann, Sabine; Cyr, John E.; Manchanda, Rajesh; Lister-James, John [Bayer Schering Pharma AG, Global Drug Discovery, D-13342 Berlin (Germany); Corstens, Frans C. [Radboud University, Nijmegen Medical Centre, 6500 HB Nijmegen (Netherlands); Dinkelborg, Ludger M. [Bayer Schering Pharma AG, Global Drug Discovery, D-13342 Berlin (Germany)], E-mail: sabine.krause@bayerhealthcare.com

2007-11-15

Background: The technetium 99 m ({sup 99m}Tc)-radiolabeled, leukocyte-avid peptide-glycoseaminoglycan complex, [{sup 99m}Tc]P1827DS, has been synthesized as an improved infection/inflammation imaging agent to [{sup 99m}Tc]P483H (LeukoTect, Diatide). In a phase I/II clinical trail, [{sup 99m}Tc]P483H images were equivalent to those obtained with {sup 111}In ex vivo labeled leukocytes. However, there was physiologic accumulation of radioactivity in the body that could hamper interpretation of the images. In this study, the potential of [{sup 99m}Tc]P1827DS for infection imaging was assessed in comparison with [{sup 99m}Tc]P483H and the well-described imaging agent [{sup 99m}Tc] hydrazinonicotinamide (HYNIC)-interleukin 8 (IL-8). Methods: The binding of [{sup 99m}Tc]P1827DS to human blood cell was studied in vitro. A rabbit Escherichia coli infection model was used to perform the biodistribution and imaging studies with [{sup 99m}Tc]P1827DS, [{sup 99m}Tc]P483H and [{sup 99m}Tc]HYNIC-IL-8. Results: [{sup 99m}Tc]P1827DS binds to leukocytes but not to erythrocytes. The leukocyte binding was not saturable up to an investigated concentration of 10 {mu}M. The accumulation of [{sup 99m}Tc]P1827/DS at the infection site strongly depends on the P1827/DS ratio and was optimal at a molar ratio of 10:1. [{sup 99m}Tc]P1827DS shows improved biodistribution over [{sup 99m}Tc]P483H with similar uptake at the infection site. Abscess uptake of [{sup 99m}Tc]HYNIC-IL-8 was approximately three times higher than that of [{sup 99m}Tc]P1827DS. [{sup 99m}Tc]HYNIC-IL-8 showed high accumulation in the kidneys, whereas [{sup 99m}Tc]P1827DS showed high lung uptake and slightly higher accumulation in the liver and spleen. Conclusion: [{sup 99m}Tc]P1827DS is a potential new inflammation imaging agent, which clearly visualized the abscess in the rabbit E. coli infection model and showed improved biodistribution compared to [{sup 99m}Tc]P483H. However, the infection uptake and biodistribution of

Preclinical evaluation of technetium 99m-labeled P1827DS for infection imaging and comparison with technetium 99m IL-8

International Nuclear Information System (INIS)

Krause, Sabine; Rennen, Huub J.; Boerman, Otto C.; Baumann, Sabine; Cyr, John E.; Manchanda, Rajesh; Lister-James, John; Corstens, Frans C.; Dinkelborg, Ludger M.

2007-01-01

Background: The technetium 99 m ( 99m Tc)-radiolabeled, leukocyte-avid peptide-glycoseaminoglycan complex, [ 99m Tc]P1827DS, has been synthesized as an improved infection/inflammation imaging agent to [ 99m Tc]P483H (LeukoTect, Diatide). In a phase I/II clinical trail, [ 99m Tc]P483H images were equivalent to those obtained with 111 In ex vivo labeled leukocytes. However, there was physiologic accumulation of radioactivity in the body that could hamper interpretation of the images. In this study, the potential of [ 99m Tc]P1827DS for infection imaging was assessed in comparison with [ 99m Tc]P483H and the well-described imaging agent [ 99m Tc] hydrazinonicotinamide (HYNIC)-interleukin 8 (IL-8). Methods: The binding of [ 99m Tc]P1827DS to human blood cell was studied in vitro. A rabbit Escherichia coli infection model was used to perform the biodistribution and imaging studies with [ 99m Tc]P1827DS, [ 99m Tc]P483H and [ 99m Tc]HYNIC-IL-8. Results: [ 99m Tc]P1827DS binds to leukocytes but not to erythrocytes. The leukocyte binding was not saturable up to an investigated concentration of 10 μM. The accumulation of [ 99m Tc]P1827/DS at the infection site strongly depends on the P1827/DS ratio and was optimal at a molar ratio of 10:1. [ 99m Tc]P1827DS shows improved biodistribution over [ 99m Tc]P483H with similar uptake at the infection site. Abscess uptake of [ 99m Tc]HYNIC-IL-8 was approximately three times higher than that of [ 99m Tc]P1827DS. [ 99m Tc]HYNIC-IL-8 showed high accumulation in the kidneys, whereas [ 99m Tc]P1827DS showed high lung uptake and slightly higher accumulation in the liver and spleen. Conclusion: [ 99m Tc]P1827DS is a potential new inflammation imaging agent, which clearly visualized the abscess in the rabbit E. coli infection model and showed improved biodistribution compared to [ 99m Tc]P483H. However, the infection uptake and biodistribution of [ 99m Tc]P1827DS is not superior to that of [ 99m Tc]HYNIC-IL-8 in this animal model

99mTc-HYNIC-derivatized ternary ligand complexes for 99mTc-labeled polypeptides with low in vivo protein binding

International Nuclear Information System (INIS)

Ono, Masahiro; Arano, Yasushi; Mukai, Takahiro; Fujioka, Yasushi; Ogawa, Kazuma; Uehara, Tomoya; Saga, Tsuneo; Konishi, Junji; Saji, Hideo

2001-01-01

6-Hydrazinopyridine-3-carboxylic acid (HYNIC) is a representative agent used to prepare technetium-99m ( 99m Tc)-labeled polypeptides with tricine as a coligand. However, 99m Tc-HYNIC-labeled polypeptides show delayed elimination rates of the radioactivity not only from the blood but also from nontarget tissues such as the liver and kidney. In this study, a preformed chelate of tetrafluorophenol (TFP) active ester of [ 99m Tc](HYNIC)(tricine)(benzoylpyridine: BP) ternary complex was synthesized to prepare 99m Tc-labeled polypeptides with higher stability against exchange reactions with proteins in plasma and lysosomes using the Fab fragment of a monoclonal antibody and galactosyl-neoglycoalbumin (NGA) as model polypeptides. When incubated in plasma, [ 99m Tc](HYNIC-Fab)(tricine)(BP) showed significant reduction of the radioactivity in high molecular weight fractions compared with [ 99m Tc](HYNIC-Fab)(tricine) 2. When injected into mice, [ 99m Tc](HYNIC-NGA)(tricine)(BP) was metabolized to [ 99m Tc](HYNIC-lysine)(tricine)(BP) in the liver with no radioactivity detected in protein-bound fractions in contrast to the observations with [ 99m Tc](HYNIC-NGA)(tricine) 2. In addition, [ 99m Tc](HYNIC-NGA)(tricine)(BP) showed significantly faster elimination rates of the radioactivity from the liver as compared with [ 99m Tc](HYNIC-NGA)(tricine) 2. Similar results were observed with 99m Tc-labeled Fab fragments where [ 99m Tc](HYNIC-Fab)(tricine)(BP) exhibited significantly faster elimination rates of the radioactivity not only from the blood but also from the kidney. These findings indicated that conjugation of [ 99m Tc](HYNIC)(tricine)(BP) ternary ligand complex to polypeptides accelerated elimination rates of the radioactivity from the blood and nontarget tissues due to low binding of the [ 99m Tc](HYNIC)(tricine)(BP) complex with proteins in the blood and in the lysosomes. Such characteristics would render the TFP active ester of [ 99m Tc](HYNIC)(tricine)(BP) complex

sup(99m)Tc-2-mercaptopropionylglycine

International Nuclear Information System (INIS)

Saji, Hideo; Odori, Teruo; Morita, Rikushi; Yokoyama, Akira; Tanaka, Hisashi.

1979-01-01

Labeling of 2-mercaptopropionylglycine (2-MPG) with sup(99m)Tc, was studied and its chemical characteristics were examined. Further, biliary excretion behavior of this complex was comparatively estimated in mice, rats and rabbits. sup(99m)Tc-2-MPG was rapidly excreted in large quantities into the bile in mice and rats: within 1 hr after injection, 51% of the injected dose was recovered from the bile in rats. On the other hand, the ligand exchange reaction between this complex and penicillamine indicates that a low hydrolyzed sup(99m)Tc species is coordinated with 2-MPG. These results suggest that a low hydrolyzed sup(99m)Tc state is an effective feature in biliary excretion behavior of sup(99m)Tc compounds. Another interesting in vivo behavior of sup(99m)Tc-2-MPG is the difference observed in mice and rabbits: in mice, very high sup(99m)Tc activity is concentrated in the gallbladder and the clearance from tissues other than the gallbladder is rapid, whereas in rabbits, although a rapid and high excretion into the gallbladder is observed, a considerable high sup(99m)Tc activity is retained in the liver and the kidney. One reason for this different in vivo behavior is the low stability of this complex at high dilution: a big animal has the large dilution volume which lead to higher decomposition estimated by the higher liver and kidney retention or the lower bile excretion. In conclusion, studies carried on sup(99m)Tc-2-MPG showed a good biliary excretion behavior but an in vivo unstableness in big animals. (author)

Studies of the effect of irradiation in a nuclear reactor, of targets containing Mo used for the preparation of 99Mo gel, material that constitutes the 99Mo - 99mTc generators

International Nuclear Information System (INIS)

Nieto, Renata Correa

2004-01-01

The most used radioisotope in Nuclear Medicine is 99m Tc, obtained in the 99 Mo - 99m Tc generator form. 99 Mo can be produced by several nuclear reactions in Cyclotron and Reactor. The production in Cyclotron is not technically and commercially feasible. The production in Nuclear Reactor can be made in two ways: 235 U fission and 99 Mo (n,γ) 99 Mo reaction. A project aiming the production of 99 Mo by activation of Mo is under way at IPEN, producing a gel type MoZr generator. There are two ways of preparing the gel and the generators: by irradiating MoO 3 and preparing the gel or by the preparation of the gel and further irradiation. This work consists in the study of the irradiation effects in several targets containing Mo for the production of 99 Mo by the 98 Mo (n,γ) 99 Mo reaction and further preparation of the gel for use as a gel type 99 Mo - 99m Tc generator. Three rinds of gel were studied: zirconium, titanium and cerium molybdate, and their morphology, infrared structure and elution yield of 99m Tc were analysed. The best results were achieved with the generators prepared with MoZr post formed gel, with amorphous structure and better elution yields. The pre formed gel induced crystallinity and worst performance of the generators. (author)

Channel stability in the Mackenzie Delta, NWT: 1992/93 update

Energy Technology Data Exchange (ETDEWEB)

Carson, M A

1992-12-01

An update is presented of a previous report on channel stability in the Mackenzie Delta, prepared as part of a program dealing with sediment-related aspects of northern hydrocarbon development. The report presents an overview of proprietary literature from industry in the 1970s dealing with channel stability in the outer delta, a review of work of the Geological Survey of Canada in 1990-91 dealing with channel stability at proposed pipeline crossings in the Niglintgak, Taglu and Swimming Point areas, and a search of Russian literature dealing with hydrothermal erosion. 45 refs., 46 figs.

Preparation and characterization of iron(III) 99Mo-molybdate(VI) gels for the assessment of 99mTc elution performance

International Nuclear Information System (INIS)

Amin, Mahmoud; Fasih, Tharwat W.; El-Absy, Mohamed A.

2018-01-01

New iron(III) 99 Mo-molybdate(VI) gels (Fe 99 Mo) of high Mo content were prepared by the precipitation/filtration method. 99 Mo-MoO 3 dissolved in NaOH was added to aqueous solutions of Fe(NO 3 ) 3 at Mo/Fe mole fractions ∝2.21 and 1.99 with continuous stirring at ambient room temperature. Two different Fe 99 Mo were precipitated from the mixed solutions adjusted at pH 2 and 4.7. The amount of water of hydration increased with the increasing the gel settling time and pH of the mixed solution. The matrices were characterized by radiometric, XRD, SEM, XRF, FT-IR, TGA, and DTA measurements. Small chromatographic columns of 2.0 g Fe 99 Mo containing ≥800 mg Mo tagged with 740 MBq 99 Mo were eluted with 5 mL saline solution. Highly reproducible 99m Tc elution indices suitable for preparation of 99 Mo/ 99m Tc generators were achieved from generator supported with 0.5 g Al 2 O 3 filter. Elution performance of 99m Tc radionuclide was highly dependent on the gel structural properties.

Comparison of Tc-99m maraciclatide and Tc-99m sestamibi molecular breast imaging in patients with suspected breast cancer.

Science.gov (United States)

O'Connor, Michael K; Morrow, Melissa M B; Hunt, Katie N; Boughey, Judy C; Wahner-Roedler, Dietlind L; Conners, Amy Lynn; Rhodes, Deborah J; Hruska, Carrie B

2017-12-01

Molecular breast imaging (MBI) performed with 99m Tc sestamibi has been shown to be a valuable technique for the detection of breast cancer. Alternative radiotracers such as 99m Tc maraciclatide may offer improved uptake in breast lesions. The purpose of this study was to compare relative performance of 99m Tc sestamibi and 99m Tc maraciclatide in patients with suspected breast cancer, using a high-resolution dedicated gamma camera for MBI. Women with breast lesions suspicious for malignancy were recruited to undergo two MBI examinations-one with 99m Tc sestamibi and one with 99m Tc maraciclatide. A radiologist interpreted MBI studies in a randomized, blinded fashion to assign an assessment score (1-5) and measured lesion size. Lesion-to-background (L/B) ratio was measured with region-of-interest analysis. Among 39 analyzable patients, 21 malignant tumors were identified in 21 patients. Eighteen of 21 tumors (86%) were seen on 99m Tc sestamibi MBI and 19 of 21 (90%) were seen on 99m Tc maraciclatide MBI (p = 1). Tumor extent measured with both radiopharmaceuticals correlated strongly with pathologic size ( 99m Tc sestamibi, r = 0.84; 99m Tc maraciclatide, r = 0.81). The L/B ratio in detected breast cancers was similar for the two radiopharmaceuticals: 1.55 ± 0.36 (mean ± S.D.) for 99m Tc sestamibi and 1.62 ± 0.37 (mean ± S.D.) for 99m Tc maraciclatide (p = 0.53). No correlation was found between the L/B ratio and molecular subtype for 99m Tc sestamibi (r s  = 0.12, p = 0.63) or 99m Tc maraciclatide (r s  = -0.12, p = 0.64). Of 20 benign lesions, 10 (50%) were seen on 99m Tc sestamibi and 9 of 20 (45%) were seen on 99m Tc maraciclatide images (p = 0.1). The average L/B ratio for benign lesions was 1.34 ±0.40 (mean ±S.D.) for 99m Tc sestamibi and 1.41 ±0.52 (mean ±S.D.) for 99m Tc maraciclatide (p = 0.75). Overall diagnostic performance was similar for both radiopharmaceuticals. AUC from ROC

15 CFR 9.9 - Consumer education.

Science.gov (United States)

2010-01-01

... 15 Commerce and Foreign Trade 1 2010-01-01 2010-01-01 false Consumer education. 9.9 Section 9.9 Commerce and Foreign Trade Office of the Secretary of Commerce PROCEDURES FOR A VOLUNTARY LABELING PROGRAM FOR HOUSEHOLD APPLIANCES AND EQUIPMENT TO EFFECT ENERGY CONSERVATION § 9.9 Consumer education. The...

45 CFR 99.2 - Presiding officer.

Science.gov (United States)

2010-10-01

... 45 Public Welfare 1 2010-10-01 2010-10-01 false Presiding officer. 99.2 Section 99.2 Public Welfare DEPARTMENT OF HEALTH AND HUMAN SERVICES GENERAL ADMINISTRATION PROCEDURE FOR HEARINGS FOR THE CHILD CARE AND DEVELOPMENT FUND General § 99.2 Presiding officer. (a) (1) The presiding officer at a...

25 CFR 700.99 - Salvage value.

Science.gov (United States)

2010-04-01

... 25 Indians 2 2010-04-01 2010-04-01 false Salvage value. 700.99 Section 700.99 Indians THE OFFICE OF NAVAJO AND HOPI INDIAN RELOCATION COMMISSION OPERATIONS AND RELOCATION PROCEDURES General Policies and Instructions Definitions § 700.99 Salvage value. Salvage value means the probable sale price of an...

A new inorganic adsorbent of (n, {gamma}){sup 99}Mo for the practical {sup 99m}Tc generator

Energy Technology Data Exchange (ETDEWEB)

Hasegawa, Y; Nishino, M [Kaken Co., Asahi, Ibaraki (Japan). Functional Materials Inst.; Ishikawa, K; Tatenuma, K; Kurosawa, K; Tanase, M; Yamabayashi, H

1998-10-01

Technetium-99m is used most widely in diagnostic nuclear medicine. By the milking procedure, it is normally eluted as the daughter nuclide from {sup 99}Mo adsorbed in an alumina column as a generator. Molybdenum-99 with high specific activity has been produced in large quantities from the fission of irradiated {sup 235}U. However, the production process involves the troublesome handling process of various fission products in the high radiation field and generates highly radioactive and poisonous wastes. To avoid these drawbacks, some gel generators have been proposed. They are of zirconium molybdate, zirconium molybdophosphate or titanium molybdate gel, which are able to be applied to {sup 99}Mo obtained easily by (n, {gamma}) reaction of natural Mo. However, it has become apparent that the gel has been prepared only under certain strict conditions such as concentrations and reaction temperature, and eventually the elution rate of {sup 99m}Tc was unstable because of any influences of the gel preparation conditions. We have developed and reported a new inorganic adsorbent (Polyinorganic Zirconium Compound: PZC) of {sup 99}Mo with a low specific activity obtained by (n, {gamma}) reaction to overcome the problems of gel generators above mentioned. PZC was prepared from ZrCl{sub 4} and isopropyl alcohol. The adsorbed amount of {sup 99}Mo (Mo) to PZC was about 200 mg/g-PZC, and the yield of {sup 99m}Tc was about 80%. And the breakthrough of {sup 99}Mo was less than 0.5%. In this paper, the properties of the improved PZC, performance of generators with {sup 99}Mo loaded from 0.5 to 470 MBq, and a method to reduce the breakthrough of {sup 99}Mo are described. (author)

Assessment of the direct cyclotron production of (99m)Tc: An approach to crisis management of (99m)Tc shortage.

Science.gov (United States)

Rovais, Mohammad Reza Aboudzadeh; Aardaneh, Khosro; Aslani, Gholamreza; Rahiminejad, Ali; Yousefi, Kamran; Boulouri, Fatemeh

2016-06-01

Nowadays, the cyclotron production of technetium-99m ((99m)Tc) has been increased, due to the worldwide (99m)Tc generator shortage. In the present work, an improved strategy for the production of (99m)Tc, using the proton irradiation of the enriched (100)Mo was developed. The performance of this method in terms of the production yield, chemical purity, radiochemical purity, as well as radionuclide purity was evaluated. The average production yield was measured to be 356MBqμA(-1)h(-1). A good agreement was found between the calculated production yield and the experimental one. The radiochemical separation and total recovery yields of (99m)Tc were 92% and 69%, respectively. The radiochemical and the radionuclide purities of the (99m)Tc were 99% and >99.99% at the end of purification, respectively. The results of quality control tests (QC) support the concept that cyclotron-produced (99m)Tc is suitable for preparation of USP-compliant. Copyright © 2016 Elsevier Ltd. All rights reserved.

Radiopharmacokinetic data for 99mTc-ABP - A new radiopharmaceutical for bone scanning: Comparison with 99mTc-MDP

International Nuclear Information System (INIS)

Murphy, Consuelo Arteaga de; Melendez-Alafort, Laura; Montoya-Molina, Carlos E.; Sepulveda-Mendez, Jesus

1997-01-01

Technetium-99m-labeled alendronate is a new radiopharmaceutical for bone scanning developed under strict quality control at the INNSZ. The purpose of this work was to compare the radiopharmacokinetic data and the dosimetry of 99m Tc-ABP and 99m Tc-MDP in 10 volunteers, after it was tested in laboratory animals. 99m Tc-ABP has shorter mean residence time (MRT) and t (1(2)) β; is less protein bound; has a higher renal clearance; smaller Vdss, and similar bone uptake at 1 and 2 h. 99m Tc-ABP gives less radiation exposure to the patient with a 740 MBq dose, and the quality of the bone scan is excellent. 99m Tc-ABP is a better radiopharmaceutical than 99m Tc-MDP for bone scanning

The role of Tc-99m IDA hepatobiliary and Tc-99m colloid hepatic imaging in primary biliary cirrhosis

International Nuclear Information System (INIS)

Aburano, T.; Yokoyama, K.; Shuke, N.; Kinuya, S.; Takayama, T.; Tonami, N.; Hisada, K.

1991-01-01

To assess the presence of primary biliary cirrhosis, 15 patients at various histopathologic stages were studied by Tc-99m IDA hepatobiliary and/or Tc-99m colloid hepatic imaging. In the earlier stages (I and II), seven of eight patients (88%) showed uniform hepatic retention of Tc-99m IDA. Of seven patients in the same stage, however, four (57%) showed no abnormality on Tc-99m colliod imaging. In three of these four negative patients (75%), uniform hepatic retention of Tc-99m IDA was noted. In the later stages (III and IV), all seven patients showed decreased clearance with or without delayed tracer appearance in the intestine and prominent hepatic retention on Tc-99m IDA imaging; with Tc-99m colloid imaging there was enlargement of the spleen and increased activity in the spleen and bone marrow. Thus, Tc-99m IDA imaging is considered to be more useful in revealing this functional disorder at the earlier stage of primary biliary cirrhosis and in evaluating progression from an earlier to a later stage of disease. Tc-99m colloid imaging also effectively evaluated progression

Determination of Tc-99 in radioactive wastes

International Nuclear Information System (INIS)

Rivera S, A. A.

2015-01-01

Tc-99 is a fission product and one of the most important radionuclides from the view point of safety assessment for the disposal of radioactive waste because of its long half-life (2.1 x 10 5 years) and high mobility in soil-water systems, if this is released into the environment in significant quantities can concentrate on plants and animals. Tc-99 is a pure beta emitter with a maximum energy of 292 KeV, so their quantification imposes destructive methods to be analyzed by liquid scintillation. Therefore the quantification of Tc-99 in ion exchange resins requires of the mineralization of these and separation of Tc-99 of other radioisotopes present in the resin. Therefore the object of this thesis is to develop a quantification method of Tc-99 content in spent exchange resins. So in order to track the behavior of technetium during digestion exchange resins and radiochemical separation, given its high volatility, in this work the 99m Tc is used. To determine the degree of mineralization of the resins, an analysis was performed by chromatography. Subsequently the method used to determine the percentage of 99m Tc aerosolized during mineralization of resin is described. After the method for the radiochemical separation of 99m Tc is presented by liquid-liquid extraction using crown ether as extractant; for this testing was performed by varying the molarity of the extractant, the ratio of solvent extractant, type of digestion of the resin and the presence of Sr-85, in order to study the behavior of 99m Tc in the presence of this radioisotope. Finally, a track beta spectra of a sample of 99m Tc eluted from a generator 99 Mo/ 99m Tc function of time was performed. (Author)

29 CFR 99.235 - Program-specific audits.

Science.gov (United States)

2010-07-01

... 29 Labor 1 2010-07-01 2010-07-01 true Program-specific audits. 99.235 Section 99.235 Labor Office... § 99.235 Program-specific audits. (a) Program-specific audit guide available. In many cases, a program... schedule of prior audit findings consistent with the requirements of § 99.315(b), and a corrective action...

An embedded system based computer controlled process automation for recovery and purification of 99mTc from (n,γ)99Mo

International Nuclear Information System (INIS)

De, Anirban; Pal, S.S.; Bhaskar, P.; Kumari, S.; Khare, V.K.; Duttaroy, A.; Garai, M.; Thakur, S.K.; Saha, S.; Chattopadhyay, Sankha; Barua, Luna; Das, Sujata Saha; Kumar, U.; Das, M.K.

2012-01-01

99 Mo produced 99 mTc (t 1/2 = 6 hr, 140 KeV γ-ray) is the most useful radioisotope for nuclear diagnostics. High specific activity 99 Mo is supplied globally mainly by five old reactors whose routine or unscheduled maintenance shutdown causes supply irregularities that adversely affects patient management in nuclear medicine centres. 99m Tc may also be produced via 98 Mo(n,γ) in a natural MoO 3 target in reactor or by 100 Mo(n,2n) 99 Mo or 100 Mo(p,2n) 99 mTc reaction in cyclotron. To meet the crisis proposals are there to produce 99 Mo by 100 Mo(n,2n) 99 Mo or 99m Tc directly by 100 Mo(p,2n) 99m Tc in a cyclotron. Of the several separation methods of 99 mTc from molybdenum, the most common are adsorption column chromatography, sublimation and liquid-liquid solvent extraction. The conventional methods besides being cumbersome are often hazardous, polluting, require skilled manpower and facilities like fume hood and so are not always practically feasible for hospitals. To address these, VECC and BRIT, Kolkata have collaborated to develop an embedded system based automated 99 Mo/ 99m Tc generator from low specific activity 99 Mo using solvent extraction technique, supervised by a PC based GUI. (author)

Thalamocortical dysrhythmia: a theoretical update in tinnitus