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At least 127 records · Page 7Linked to original sources
PubMed1981

A precision flow-controlled Rb-82 generator for bolus or constant-infusion studies of the heart and brain.

A precision flow-controlled rubidium-82 generator has been constructed to deliver 76-sec Rb-82 at either fast or slow flow rates for bolus or constant-infusion studies. A stepping motor drive is interfaced to a microprocessor for pulsed control of flow rate to deliver the saline eluant solution from a large-volume (150 ml) machined pumping syringe through an alumina column that retains the 25-day Sr-82 parent. The generator system delivers 70-90% of the maximum Rb-82 activity in a 20-25 ml bolus elution of 2% NaCl. The Sr-82/Sr-85 breakthrough is 10(-7) - 10(-6). both yield and breakthrough are functions of column length and flow rate. Six separate Sr-82 loadings of the generator were evaluated over a period of nearly 2 yr in studies of myocardial blood perfusion and permeability changes in the blood-brain barrier. Sterility and apyrogenicity of the Rb-82 eluate were maintained during multiple elutions and long-term use of 3-4 mo for each generator loading.

Brain↗
PubMed1982

Gold- 195m, a new generator-produced short-lived radionuclide for sequential assessment of ventricular performance by first pass radionuclide angiocardiography.

The feasibility of performing rapid sequential first pass radionuclide angiocardiography using a new short-lived radiotracer, gold-195m (195mAu) half-life 30.5 seconds) was evaluated. This radionuclide emits a 262 keV gamma ray and is the daughter of mercury-195 (195mHg) (half-life 41.6 hours). The prototype tabletop 195mHg/195mAu generator produced 20 to 25 mCi of 195mAu in 2 ml of eluate (yield of 40 percent). The breakthrough of 195mHg in the eluate was 0.02 percent of the amount of 195mHg in the generator. The eluate contained 20 microCi of 195mHg per study, resulting in an estimated human radiation dose of 0.007 rad/study to the whole body and 0.34 rad/study to the kidney. Four dogs each had 15 to 20 sequential first pass studies performed with 195mHg at 3 to 10 minute intervals using a computerized multicrystal gamma camera. During the left ventricular phase, 160,000 to 190,000 counts/s were acquired. The end-diastolic left ventricular region of interest contained 3,000 to 6,000 counts (background- and decay-corrected). Multiple reproducible values for left ventricular ejection fraction were obtained during stable conditions. The mean (+/- standard deviation) interstudy variability was 4 +/- 2 percent. During infusion of isoproterenol, rapid increase of left ventricular ejection fraction was demonstrated. Excellent agreement was observed between studies performed with technetium-99m diethylenetriaminepentaacetic acid (99mTc-DTPA) and 195mAu. The mean interstudy difference was 4 +/- 3 percent. Thus, sufficiently high yield and dose are obtained from the 195mHg/195mAu generator for reliable high count rate first pass determination of left ventricular ejection fraction. This new short-lived radiotracer makes possible rapid sequential assessments of ventricular function at greatly reduced patient exposure to radiation.

Angiocardiography↗
PubMed1982

Tc-generators - yield of 99mTc and ratio to 'inactive' 99Tc.

A large amount of inactive 99Tc in some delicate labeling techniques may adversely affect the results obtained. Therefore, it is important to know the ratio Q(t) of inactive 99Tc to active 99mTc, which is dependent on the time (t) elapsed since the last elution. On the other hand, in optimizing the use of Tc-generators it is desirable to know the actual yield Y(t) at any time (t) after a preceding elution. It this paper, formulas both for Q(t) and for Y(t) are derived and numerical values are tabulated. In combination with a table of the amount of 99Mo left, M(t), all the properties of a Tc-generator and of its eluates may be derived and theoretical and practical results compared. This information will help in both optimizing the use of Tc-generators and improving quality control in radiopharmaceutical laboratories.

Molybdenum↗
PubMed1997

Reinvestigation of a physiological eluate of the 52Fe/52mMn generator.

We have achieved a significant step forward in the potential application of 52mMn2+ (T1/2 = 0.35 h, beta + = 97%) as a myocardial imaging agent with positron emission tomography (PET) by the introduction of a 5% (physiological) glucose solution as an eluent for the 52Fe/52mMn generator. Our experiments have demonstrated the favourable properties of a glucose solution with minimal breakthrough (< 0.3%) of 52Fe and yields of up to 90% 52mMn2+. Although it has been shown that lower 52Fe breakthrough is attainable using other eluents, due to the short half life of 52Fe (8.27 h) breakthrough up to 1% would not appear to significantly alter the efficacy of the 52mMn eluted with this 5% glucose solution. The primary advantage of this approach lies in its convenience of application, in that a 5% glucose solution may be administered directly into patients thereby circumventing the major problem of non-injectable eluates previously associated with this generator.

Anion Exchange Resins↗
PubMed1987

Essentials of a rubidium-82 generator for nuclear medicine.

The use of generator-produced 82Rb for positron emission tomography studies in clinical nuclear medicine requires a number of factors to be considered. These include 82Sr availability, methods of recharging the generator with fresh 82Sr, adequate elution yield of 82Rb, low breakthrough of 82-85Sr, simple and reliable operation of the generator, and delivery of a sterile and pyrogen free eluate of 82Rb.

Electrons↗
PubMed2001

Technetium generator log form.

Technetium generators are loaded with molybdenum-99 (99Mo), that has a 66-h half life and decays to technetium-99 m (9mTc). 99Tc with a single 140 keV gamma photon emission and a 6-h half life is an ideal isotope for nuclear medicine imaging. Many nuclear medicine units receive generators and use the 99Tc elution to label a variety of prepared chemical species for the majority of the studies they perform. Other options are receiving bulk 99mTc and doing the same tagging or getting unit doses of already labeled pharmaceuticals. Units using generators must meet requirements spelled out in regulations of the Nuclear Regulatory Commission, Title 10, CFR, parts 20, 35, and 71 as well as the Department of Transportation, Title 49, CFR, part 173. The form described in this paper was an attempt to get all of the required records for each individual generator on a single sheet of paper.

Forms and Records Control↗
PubMed1993

Effect of source and age of sodium pertechnetate Tc 99m on radiochemical purity of technetium Tc 99m exametazime.

The radiochemical purities of technetium Tc 99m exametazime prepared with one-hour-old or six-hour-old sodium pertechnetate Tc 99m from two manufacturers' generators were compared. Eluates from each manufacturer's generators were diluted immediately to provide two solutions of sodium pertechnetate Tc 99m. For the one-hour-old solution, eluate was diluted with 0.9% sodium chloride injection to a concentration of radioactivity of 38 mCi in 5.5 mL and used one hour later. For the six-hour-old solution, eluate was diluted to 65 mCi in 5.5 mL and used six hours later. Technetium Tc 99m exametazime was prepared by injecting 5.0 mL of one of the solutions into an exametazime kit to provide 30 mCi of technetium Tc 99m in 5.0 mL. At 2, 30, and 60 minutes after reconstitution of each kit, the radiochemical purity was measured by high-performance liquid chromatography with radiation detection. At two minutes, all the preparations retained high radiochemical purities. However, at 30 and 60 minutes, the radiochemical purities of technetium Tc 99m exametazime prepared with six-hour-old sodium pertechnetate Tc 99m were significantly lower than those of technetium Tc 99m exametazime prepared with one-hour-old sodium pertechnetate Tc 99m. Similar results were found for each manufacturer's generators. The radiochemical purity of technetium Tc 99m exametazime was affected by the age of the sodium pertechnetate Tc 99m from which it was prepared but not by the generator from which the sodium pertechnetate Tc 99m was obtained.

Humans↗
PubMed1981

Residual activity of Tc-generators.

Owing to contamination by long-lived radio-isotopes, the residual activity of an old 99Mo-99mTc generator may be large enough to prevent its disposal. The long-lived impurities of one generator were determined by energy spectrum and half-life measurements. In this generator 46Sc, 51Cr, 60 Co, 92mNb, 95Nb and 124Sb nuclides were found. Only the half-life of 60Co exceeds 3 months, thus a moderately long storage of the generator reduces the activity, and its disposal is then safe.

Radioactive Waste↗