Large scale production of fission 99Mo by using fuel elements of a research reactor as starting material

Separation of Fission 99Mo on Charcoal Columns Impregnated with Tin(IV) Chloride for Use in Preparation of 99mTc Generators

“…The quality results of the 99m Tc eluates proved that fission 99 Mo separated and purified on charcoal impregnated with tin(IV) chloride columns is suitable for preparation of 99 Mo/ 99m Tc generators [5 -10]. It is suggested that, before 99m Tc elution from alumina loaded with non-purified fission 99 Mo columns it may be carefully washed with 0.01 Μ HCl to get rid of radioiodine [12,24,28]. In comparison with other separation procedures for recovery of mCi quantities of fission "Mo, with > 86% yield and «99.66% radionuclidic purity in small volumes of eluate (10 cm 3 0.75 Μ NaOH) and high active waste from a single adsorption-desorption cycle, use of C/ Sn(IV) chloride columns is reasonable [9,10].…”

“…The obtained "Mo eluates are usually seriously contaminated with the radionuclides 131,132^ 132 Τβ) 95^ 95^ 103 Ru> ^ ^ 2γ> 29]. Therefore, additional purifications of "Mo are needed using repeated cyclings on different adsorbents and high temperature volatilization [10,12,20,21,24,25,28,[30][31][32][33], In previous work, the sorption behaviour of "Mo(VI) and some relevant fission products on charcoal impregnated with tin(IV) chloride in HCl solutions was investigated [34,35], The aim of this work is to investigate the separation of "Mo from fission products on impregnated charcoal columns and to evaluate the separated "Mo for use in preparations "Mo/ 99m Tc generators.…”

“…Chromatographic column techniques are generally preferred for the separation of fission-"Mo than solvent extraction [14][15][16][17][18] and precipitation [19 -22]. In this respect, "Mo was separated from different fission solutions by adsorption on alumina [23,24], silver-coated alumina [10,25], silver-coated charcoal [26,27] and organic exchangers [12,28]. The obtained "Mo eluates are usually seriously contaminated with the radionuclides 131,132^ 132 Τβ) 95^ 95^ 103 Ru> ^ ^ 2γ> 29].…”

Production of fission 99Mo at the VVR-ts nuclear reactor in a closed-loop process with respect to U

“…The main radionuclide impurities (amounts relative to 99 Mo activity) detectable with a γ-ray spectrometer are as follows: 95 Zr (<4 × 10 -4 ), 95 Nb (<4 × 10 -6 ), 103 Ru (<4 × 10 -7 ), 131 I (<7 × 10 -4 ), 132 Te (<1 × 10 -4 ), 140 Ba( 140 La) (<1 × 10 -8 ), 141 Ce (<3 × 10 -7 ), 143 Ce (<1.5 × 10 -6 ), total of other γ-emitters no more than 1 × 10 -4 ; β-activity ( 89 Sr + 90 Sr) <3 × 10 -6 ; total α-activity <1 × 10 -11 . The content of inactive impurities, μg ml -1 , determined with an atomic emission spectrometer, was as follows: The amount of high-level liquid waste formed per gram of 235 U being processed was 300 ml of the aqueous phase (HNO 3 , H 2 C 2 O 4 , fission products) and 100 ml of the organic phase (HDEHP, toluene, FP, U), which is smaller by an order of magnitude than in processing of the UAl x target [6]. The aqueous waste was solidified for the subsequent disposal.…”

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

“…Quartz and glass apparatus was used in chemical processing, and yield of 99 Mo was ∼70% [2]. In 1980, this process was replaced by the AMOR process (AMOR: Anlage zur Mo Production Rossendorf), developed in the same institute [3]. The AMOR process made use of original fuel elements of the RF-reactor as qualified target which was dissolved in HNO 3 /Hg.…”