Development of multiple-elution cartridge-based radioisotope concentrator device for increasing the 99mTc and 188Re concentration and the effectiveness of 99mTc/99Mo utilisation

Abstract

A self-shielded, sterile and cartridge-based radioisotope concentrator device coupled to 99m Tc/ 188 Re generators to increase the 99m Tc/ 188 Re-concentration of the generator eluate was developed based on new aminoalkylfunctionalized silica sorbent which conditionally catches and release 99m Tc/ 188 Re to concentrate the daughter nuclide of the generator eluates. The cartridge can be used for multiple elutions with an overall concentration factor of [100 and daughter nuclide recovery yield of [85 %. This device can be used for 10 days extension of 99m Tc-generator life-time, saving about 20 % of the generator activity and for ''early'' generator-elution programs, under which the generator is eluted at an optimized build-up time for increasing the effectiveness of 99m Tc/ 99 Mo utilisation.

TcGenerator Development: Up-to-DateTcRecovery Technologies for Increasing the Effectiveness ofLe1 2014Science and Technology of Nuclear InstallationsSelf Cite18080View full textAdd to dashboardCite

“…Besides that about 20% of the generator 99m Tc-activity can be saved as a result of the extension of 99m Tc-generator life time, the use of radioisotope concentrator for the optimization of generator elution to increasing the 99m Tc-activity yield and the effectiveness of 99 Mo utilization was reported by Le (2013) [58,61]. This fact is shown as follows.…”

“…The use of nonchloride eluent in replacement of saline normally used in a commercial generator may not be preferable due to legal issues of the amended registration requirement. Unfortunately, no concentrator device prototypes developed based Tc specific radioactivity (Ci/ mol) Mo utilisation: (a) kinetics of radioactive decay/ 99m Tc-activity buildup in the generator eluted with an early elution regime (A: 99 Mo-activity; B: 99m Tc-activity buildup from beginning; C: 99m Tc-activity growth after first elution; D: 99m Tc-activity growth/eluted at 6-hour elutions; E: 99m Tc-SA in the system of 99m Tc-radioactivity buildup from beginning) [58]; (b) effectiveness of "early" elution regime for increasing 99m Tc-elution yield of the generator compared with that normally eluted at the time point of maximal 99m Tc-buildup (square is experimental and dashed line is theoretical calculation result) [58]; (c) ULTRALUTE concentrator device [41,61]; (d) ULTRALUTE concentrator device inline-coupled with a 99m Tc generator.…”

“…With the utilization of 99m Tc concentrator device which gives a final 99m Tc-solution of 1.0 mL volume, the experimental results obtained from a 525 mCi generator, as an example, confirmed that the concentration and the yield of 99m Tc solution eluted with a 6-hour elution regime is much better than that obtained from the elution regime performed at the maximal build-up time (22.86 hours). Within first 6 days of elution, 99m Tc-concentration of the generator eluates is in the range 200-44 mCi/mL and total 99m Tc-activity eluted is 1715.7 mCi for a 6-hour elution regime (including the zero day elution) while the concentration of 83-18.2 mCi/mL and the total activity of 1015.1 mCi are for the elution regime performed at the maximal build-up time, respectively [58,61]. The effectiveness of this early elution mode was also confirmed experimentally in the prior-of-art of 68 Ga/ 68 Ge generator [62][63][64].…”

“…Performance of 99m Tc radioisotope concentrator device ULTRALUTE (effect of concentrator on generator useful life)[41,61].…”

PEMBUATAN RADIONUKLIDA MOLIBDENUM-99 (99Mo) HASIL AKTIVASI NEUTRON DARI MOLIBDENUM ALAM UNTUK MEMPEROLEH TEKNESIUM-99m (99mTc)

“…Dalam usahan untuk memperoleh aktivitas maksimum dari radionuklida 99m Tc, kolom MBZ kemudian dielusi dengan menggunakan larutan saline sebanyak 25 mL dalam selang waktu 24 jam, tetapi selang waktu ini bukan merupakan selang waktu optimum. Selang waktu untuk memperoleh aktivitas yang maksimum dari radionuklida 99m Tc adalah 22,9 jam [23] . Jumlah radionuklida 99m Tc yang telah berhasil dielusi dapat dilihat pada Tabel 2.…”