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

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.

Replacement of 137Cs irradiators with x-ray irradiators.

Self-shielded 137Cs irradiators have been used for many years to irradiate blood products to prevent graft vs. host disease and to irradiate cells and small animals in research. A report by the National Academy of Sciences recommends that careful consideration be given to replacement of 137Cs irradiators with x-ray irradiators. Several manufacturers and users of x-ray irradiators were contacted to determine costs of replacing and maintaining 137Cs irradiators with x-ray units and to assess users' experience with x-ray irradiators. Purchase costs of x-ray units are similar to 137Cs irradiators, but maintenance costs are significantly higher if annual service contracts are used. Performance of the two irradiator types appears to be equivalent, but in some cases x-ray irradiations may need to be performed in multiple configurations to achieve adequate uniformity in dose. No literature reports were found that evaluated the biological effectiveness of x rays vs. 137Cs gamma rays; therefore, a careful study should be conducted to determine the biological effectiveness of x rays vs. 137Cs gamma rays for biological responses relevant to transfusion medicine and immunological research. Throughput may be problematic for large transfusion medicine programs, and back-up plans may be necessary in case the x-ray unit needs to be taken out of service for extended maintenance. Disposition of a 137Cs irradiator will add to the cost of replacement with an x-ray unit, but disposal may be possible through the U.S. Department of Energy's Off-Site Source Recovery Program.

Extending the life of a 99Tcm generator: a simple and convenient method for concentrating generator eluate for clinical use.

99Tcm-pertechnetate can conveniently be concentrated 5-20-fold by passing up to 20 ml through a sequence of two (or three) disposable columns, one (or two) to remove chloride and one to concentrate the pertechnetate for subsequent elution with a small volume of saline. This procedure is useful for utilizing eluates with low radioactive concentration in applications that require high radioactive concentration.

Feasibility of fractionating MAG3 cold kit for cost reduction.

99Tcm-MAG3 is the first 99Tcm-labelled radiopharmaceutical with a renal clearance similar to that of 131I-OIH. The cost of a unit dose of 99Tcm-MAG3 is comparatively less expensive than the cost of a combined 99Tcm-DTPA and 131I-OIH study dose. However, this cost-saving is dramatically reduced when only a few doses are withdrawn from a 99Tcm-MAG3 kit. Our goal in this study was to subdivide the MAG3 kit into fractions to reduce expense. By dissolving the lyophilized ingredients of MAG3 kits with either 5 or 10 ml N2-purged normal saline, the resultant liquid was divided into 1-ml aliquot vials filled with N2. The MAG3 aliquot vials were then frozen at -70 degrees C for future use. The radiochemical purity (RCP) of each vial was evaluated using the recommended Sep-Pak C18 column chromatography at different time periods. Over the entire 28-day evaluation period, the average RCP of the 5:1 dilution MAG3 vials after reconstitution with 3.7 GBq 99Tcm was maintained at 95.6 +/- 2.7% (n = 100) for 6 h, whereas the 10:1 fractionation MAG3 kits after labelling with 740 MBq 99Tcm showed an average RCP value of 98.4 +/- 2.1% (n = 100) for 6 h. Based upon these results, it is concluded that the fractionation of MAG3 kits and frozen storage in an N2 atmosphere not only maintains the stability of MAG3 but also provides a cost-effective method for using 99Tcm-MAG3.