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PubMed2006

Activity standardization and nuclear decay data of 109Cd.

The activity of a (109)Cd solution has been accurately determined without using (109)Cd nuclear decay data such as emission probabilities. An ampoule containing this calibrated (109)Cd solution was sent to the Bureau International des Poids et Mesures to include the activity result in the database of the International Reference System (SIR). The emission rate of conversion electrons was measured by means of pressurized proportional counters as well as by a liquid scintillation spectrometer. The combination of the results with the photon emission rate measured with the aid of gamma-ray spectrometers yields the activity concentration. The measurement results were also used to deduce emission probabilities with high accuracy. For the 88 keV transition, a photon emission probability of p(gamma)=0.03663(33) and a total internal conversion coefficient of alpha(t)=26.30(25) were determined.

Journal Article↗
PubMed1991

Composition of pork carcasses by potassium-40 liquid scintillation detection: estimation and validation.

Liquid scintillation detection of potassium-40 was used to estimate pork carcass composition of 124 boars, barrows and gilts. Pigs were fed to five live weights (23, 45, 68, 91 and 114 kg) and 40K emissions were determined on live pigs in a whole body counter (WBC) equipped with a two-pi liquid scintillation detector. Then, pigs were slaughtered conventionally and the right side of each carcass was weighed, 40K emissions of this carcass side was determined in the WBC and total grams of potassium were calculated. The right side of each carcass was ground, sampled and analyzed for fat, protein, moisture and potassium. Fat, protein, moisture and overall potassium percentage means were 23.9 +/- 7.2, 16.5 +/- .94, 57.0 +/- 6.5 and .25 +/- .02, respectively. Whole body counter carcass potassium was highly correlated (P less than .01) to chemically determined carcass potassium (r = .70). Percentage of fat, protein and moisture prediction equations were formed by stepwise regression using the linear, quadratic and interactive effects of live animal and carcass side weight. Whole body counter live animal and carcass potassium and sex were utilized as independent variables. Carcass weight and 40K determined potassium of the carcass explained more of the variation in carcass composition than did live animal weight and 40K determined potassium of the live animal.

Adipose Tissue↗
PubMed2005

Measurements of neutron effective doses and attenuation lengths for shielding materials at the heavy-ion medical accelerator in Chiba.

The effective doses and attenuation lengths for concrete and iron were measured for the design of heavy ion facilities. Neutrons were produced through the reaction of copper, carbon, and lead bombarded by carbon ions at 230 and 400 MeV.A, neon ions at 400 and 600 MeV.A, and silicon ions at 600 and 800 MeV.A. The detectors used were a Linus and a Andersson-Braun-type rem counter and a detector based on the activation of a plastic scintillator. Representative effective dose rates (in units of 10(-8) microSv h(-1) pps(-1) at 1 m from the incident target surface, where pps means particles per second) and the attenuation lengths (in units of m) were 9.4 x 10(4), 0.46 for carbon ions at 230 MeV.A; 8.9 x 10(5), 0.48 for carbon ions at 400 MeV.A; 9.3 x 10(5), 0.48 for neon ions at 400 MeV.A; 3.8 x 10(6), 0.50 for neon ions at 600 MeV.A; 3.9 x 10(6), 0.50 for silicon ions at 600 MeV.A; and 1.1 x 10(7), 0.51 for silicon ions at 800 MeV.A. The attenuation provided by an iron plate approximately 20 cm thick (nearly equal to the attenuation length) corresponded to that of a 50-cm block of concrete in the present energy range. Miscellaneous results, such as the angular distributions of the neutron effective dose, narrow beam attenuation experiments, decay of gamma-ray doses after the bombardment of targets, doses around an irradiation room, order effects in the multi-layer (concrete and iron) shielding, the doses from different targets, the doses measured with a scintillator activation detector, the gamma-ray doses out of walls and the ratio of the response between the Andersson-Braun-type and the Linus rem counters are also reported.

Construction Materials↗
PubMed1991

A high performance liquid chromatography method for the analysis of glycosphingolipids using galactose oxidase/NaB3H4 labeling of intact cells and synaptosomes.

The major objective of this study was to combine an HPLC method with a galactose oxidase/NaB3H4 labeling method to allow both a chemical quantitation of individual glycolipids and analysis of their 3H labeling. Neutral glycolipids in whole cells were oxidized with galactose oxidase, and the resultant aldehydes were radiolabeled by reduction with tritiated sodium borohydride. Gangliosides, oxidized with galactose oxidase, either were reduced while in the native state in the whole cell or were first extracted and then reduced. Tritiated glycolipids were perbenzoylated and separated by HPLC. Ultraviolet detection of the derivatives was at 230 nm. Incorporated radioactivity was determined either by collecting fractions from the HPLC separation and counting on a liquid scintillation spectrometer or with a flow-through counter. The order of the derivatization and reduction is critical. Reduction of glycolipids prior to derivatization yielded sharp uv and radioactive peaks. Perbenzoylation of the oxidized glycolipids prior to reduction yielded multiple uv peaks, a noisy baseline, and broad radioactive peaks which did not always have a corresponding uv peak. The labeled neutral glycolipids were stable at -40 degrees C for at least 14 days, and gangliosides were stable at -15 degrees C for at least 14 days. When samples were stored at 20 degrees C there was a time-dependent decrease in the glycolipid/internal standard uv peak area ratio for GbOse4 and GbOse3 apparent by 28 days after perbenzoylation. The distribution of radiolabel among peaks showed no change with time or temperature. We adapted the technique to allow 3H labeling of glycolipids from monolayers of cultured glioma cells and from mouse brain synaptosomes.(ABSTRACT TRUNCATED AT 250 WORDS)

Animals↗
PubMed2005

Estimation of paclitaxel biodistribution and uptake in human-derived xenografts in vivo with (18)F-fluoropaclitaxel.

UNLABELLED: Paclitaxel (PAC) is widely used as a chemotherapy drug in the treatment of various malignancies, including breast, ovarian, and lung cancers. We examined the biodistribution of (18)F-fluoropaclitaxel ((18)F-FPAC) in mice with and without human breast cancer tumor xenografts by use of small-animal-dedicated PET (microPET) and clinically practical semiquantitative methods. We compared the PET data to data derived from direct harvesting and analysis of blood, organs, and breast carcinoma xenografts. METHODS: PET data were acquired after tail vein injection of (18)F-FPAC in nude mice. Tracer biodistribution in reconstructed images was quantified by region-of-interest analysis. Biodistribution also was assessed by harvesting and analysis of dissected organs, tumors, and blood after coadministration of (18)F-FPAC and (3)H-PAC. (18)F content in each tissue was assessed with a gamma-well counter, and (3)H content was quantified by scintillation counting of solubilized tissue after (18)F radioactive decay. RESULTS: The distributions of (18)F-FPAC and (3)H-PAC were very similar, with the highest concentrations in the small intestine, the lowest concentrations in the brain, and intermediate concentrations in tumor. Uptake in these and other tissues was not inhibited by the presence of more pharmacologic doses of unlabeled PAC. Administration of the P-glycoprotein modulator cyclosporine doubled the uptake of both (18)F-FPAC and (3)H-PAC into tumor. CONCLUSION: PET studies with (18)F-FPAC can be used in conjunction with clinically practical quantification methods to yield estimates of PAC uptake in breast cancer tumors and normal organs noninvasively.

Animals↗
PubMed2004

Comparison of benchtop microplate beta counters with the traditional gamma counting method for measurement of chromium-51 release in cytotoxic assays.

The most traditional method used to measure the lytic activity of cytotoxic T lymphocytes or natural killer (NK) cells is the chromium release assay (CRA). No study has been reported that systematically compares the traditional gamma counting method with various benchtop microplate scintillation formats to measure chromium release. Here we investigated the utilization of microplate beta counters in comparison with the traditional gamma counting method to quantitate antigen-specific cytolysis, lymphokine-activated killer (LAK) activity, and NK activity in the CRA. Supernatants from standard CRA (n = 7) were directly transferred to a 96-well microplate containing either a solid scintillant (Lumaplate) or a liquid scintillant (flexible beta plate). Samples were quantified by using two benchtop microplate beta counters, Wallac Microbeta Trilux (Lumalux and Trilux methods, respectively) and Packard TopCount instruments (TopCount method). These results were then compared with data from an identical assay run in parallel using the traditional gamma counting method (LKB). The lytic activity for influenza virus-stimulated effectors measured in the benchtop microplate beta counters using Lumalux and Trilux methods exhibited excellent correlations with the one measured in the traditional LKB (r = 0.967 and 0.968, respectively). The TopCount method demonstrated a similar correlation (r = 0.966). Similar findings were observed for LAK and NK activity. The 96-well microplate format, specifically the dry-scintillant Lumaplates, offers several advantages over the traditional gamma counting format. Most notable are the reductions in sample volume needed and in the total sample preparation and counting time. Furthermore, this system reduces the amount of dry and mixed radioactive waste generated while using the same instrument for gamma- and beta-emitting isotopes.

CD8-Positive T-Lymphocytes↗
PubMed1997

Detecting strontium-89 removable contamination using a sodium iodide well counter.

UNLABELLED: Monitoring for 89Sr removable contamination is required for incoming DOT-labeled packages and work areas containing radioactivity. However, few nuclear medicine departments are equipped for liquid scintillation counting, which is the preferred method for detecting beta emitters. We investigated using a sodium iodide well counter to detect 89Sr through its bremsstrahlung photon production. METHODS: We used a manufacturer's 89Sr-chloride solution of known concentration and tested various parameters: type of tube, access of tube contents to air, volume of sample, type of wipe material and counting geometry. Liquid scintillation samples also were obtained. RESULTS: Initial counting efficiencies were 0.10-0.14 cpm/dpm for small volume (10-microliter) samples. The various parameters tested had either positive or negative effects on the system's efficiency to detect 89Sr. One set of samples, counted over time, demonstrated a calculated mean half-life of 50.8 days, which is similar to the 89Sr reported half-life of 50.5 days. Liquid scintillation samples demonstrated efficiencies of almost 1.0 cpm/dpm and a calculated mean half-life of 50.8 days, both as expected. CONCLUSION: This study demonstrates that 89Sr removable contamination can be detected sensitively using a sodium iodide well counter, but special considerations must be made when determining the system's counting efficiency.

Air Pollutants, Radioactive↗
PubMed2006

Standardization of radionuclide by beta(LS)-gamma coincidence counting using the geometry-efficiency variation method.

A liquid scintillation counting method consisting of three photomultiplier tubes for beta counters and a NaI(Tl) gamma counter has been developed for the standardization of radionuclides with the beta-gamma coincidence technique. The beta detection efficiency functions are obtained by means of a geometry-variation method developed in the present work; an array of beta detectors is moved uniformly at the same time from a centrally located counting vial to 50 mm. The method has been applied in the standardization of 60Co and 134Cs. Unquenched liquid scintillation samples with nominal count rates from 1000 to 6000 s-1 were prepared. The observed beta detection efficiencies with this method are from 90 to 45% in the case of 60Co, and from 84 to 50% for 134Cs. The output of each beta channel is summed together and compared with gamma data by the coincidence analyzer. The dead time of each counting channel is adjusted to be 20 micros, sufficiently long to suppress the afterpulses in the beta counting channel. The activity of each sample is determined by using the Cox and Isham formula. The obtained results are in good agreement with KRISS certified values.

Beta Particles↗
PubMed2005

Determination of disintegration rates and gamma-ray emission probabilities of 65Zn and 241Am.

Radioactive solutions of (65)Zn and (241)Am were standardized within the frame of the CCRI (II)/BIPM key comparisons carried out recently in 2003. The activity concentrations (in Bqg(-1)) were determined using the 4pi(proportional counter)-gamma coincidence counting method with efficiency extrapolation. Liquid scintillation methods were also used for (241)Am activity determination. The 1115.5 keV of (65)Zn and the 26.35 and 59.54 keV of (241)Am gamma-ray emission probabilities were determined as 0.4971, 0.0206 and 0.3587, respectively, using a planar germanium detector. The associated relative uncertainties were 0.33%, 1.56% and 0.47%, respectively.

Journal Article↗
PubMed1990

A proposed multi-detector method for prompt 90Sr detection in post-accident environmental matrices.

Strontium-90 is of relevant biological importance among fission products released during a fission reactor accident. Rapid information on its concentration in environmental matrices is extremely valuable, yet this implies chemical separations and handling with a shift in daughter equilibrium and therefore the need to wait a sufficient time for the equilibrium to be reestablished. The work concerns a feasibility study of a multi-detector system for a prompt evaluation of the 90Sr activity or, at least, a prompt determination of its order of magnitude in the presence of other pure beta and beta-gamma emitters; their interferences are examined on the basis of the Chernobyl releases and their decay properties. The technique is based on a plastic scintillator beta detector and a guard ring of BGO counters which can be logically connected in coincidence and anticoincidence. The evaluations show that a few hours are sufficient to determine a specific activity comparable with the Maximum Permissible Concentration in air by sampling 10 m3.

Accidents↗
PubMed1998

ASIC-based event-driven 2D digital electron counter for TEM imaging.

A two-dimensional application specific integrated circuit (ASIC) based detector, designed for X-ray protein crystallography, has been tested to determine its suitability as a direct electron detector for TEM imaging in the voltage range of 20-400 keV. Several markedly different properties of this device distinguish it from the charge coupled device (CCD) detectors: (1) the ASIC detector can be used directly under electron bombardment in the voltage range stated above, therefore requiring no scintillator screen; (2) each active pixel of the device is an electron counter and generates digital output independently; (3) the readout of the device is frameless and event driven; (4) the device can be operated at the room temperature and is nearly noise free; and (5) the counting dynamic range of the device is virtually unlimited. It appears that an imaging system based on this type of device would be ideal for low-dose TEM imaging and online diffraction observation and recording, as well as more conventional imaging, providing the many advantages of direct digital readout for almost all applications.

Crystallography, X-Ray↗
PubMed1996

A novel system for intracoronary beta-irradiation: description and dosimetric results.

PURPOSE: A dosimetric evaluation of a new device dedicated to intravascular irradiation, associating a beta source and a centering device, was carried out before initiation of a clinical pilot study. METHODS AND MATERIALS: A 29-mm-long 90Y coil, coated with titanium and fixed to the end of a thrust wire, was introduced into the inner lumen of purpose-built centering balloons of different diameters (2.5, 3, 3.5, and 4 mm). Dose homogeneity was evaluated by studying both axial and circumferential dose variations, based on readings from thermoluminescent dosimeters (TLDs) placed on the balloon surface. Axial homogeneity was determined by comparing the readout values of dosimeters located on peripheral balloon segments with those located on segments adjacent to the midpoint of the source. The centering ability of the device was studied by comparing measurements on opposing surfaces of the balloon. The dose attenuation by water and contrast medium was evaluated and compared with that in air. The balloon contamination was studied using a contamination counter. The total 90Y coil activity was measured by liquid scintillation to relate activity to surface dose. RESULTS: Activity-surface dose correlation showed that for a linear coil activity of 1 mCi/mm, the mean dose rate at the surface of a 2.5-mm balloon filled with contrast medium was 8.29 Gy/min. The doses at the surface of larger balloons (3, 3.5, and 4 mm) filled with contrast were 78%, 59%, and 47%, respectively, of the dose measured at the surface of the 2.5-mm balloon. The coefficient of variation (CV) in surface dose for 2.5-, 3-, 3.5-, and 4-mm centering devices filled with contrast medium were 9%, 8%, 9%, and 12%, respectively. There was no statistically significant difference between readouts from central and peripheral balloon segments or among rows of dosimeters facing each other. For a 2.5-mm balloon, compared with air the dose attenuation by water and contrast medium was similar (0.70 and 0.69, respectively), but a significant difference was seen between the readouts of water- and contrast-filled balloons when the diameter was larger than 3 mm (p < 0.001). No contamination was found in the balloon shaft after source retrieval. CONCLUSION: The dosimetric tests showed very good surface dose homogeneity, demonstrating satisfactory centering of the source within the centering balloons. The achievable dose rates will permit intravascular irradiation within a short time interval. The absence of residual balloon contamination after source retrieval meets the requirements for a sealed source used in a clinical setting.

Brachytherapy↗