scholarly journals Recovery of high specific activity molybdenum-99 from accelerator-induced fission on low-enriched uranium for technetium-99m generators

2021 ◽  
Vol 11 (1) ◽  
Author(s):  
M. Alex Brown ◽  
Nathan Johnson ◽  
Artem V. Gelis ◽  
Milan Stika ◽  
Anna G. Servis ◽  
...  
Keyword(s):  
Specific Activity ◽  
High Specific Activity ◽  
Fission Products ◽  
Uranyl Sulfate ◽  
New Process ◽  
Extraction Scheme ◽  
Induced Fission ◽  
Enriched Uranium ◽  
No Carrier Added ◽  
Final Purification

AbstractA new process was developed to recover high specific activity (no carrier added) 99Mo from electron-accelerator irradiated U3O8 or uranyl sulfate targets. The process leverages a novel solvent extraction scheme to recover Mo using di(2-ethylhexyl) phosphoric acid following uranium and transuranics removal with tri-n-butyl phosphate. An anion-exchange concentration column step provides a final purification, generating pure 99Mo intended for making 99Mo/99mTc generators. The process was demonstrated with irradiated uranium targets resulting in more than 95% 99Mo recovery and without presence of fission products or actinides in the product.

Experimental Study of the Cadmium Effects on Iodine Transport in the Primary Circuit During Severe Nuclear Accident

2014 ◽  
Author(s):  
M. Gouëllo ◽  
J. Kalilainen ◽  
P. Rantanen ◽  
T. Kärkelä ◽  
A. Auvinen
Keyword(s):  
Experimental Study ◽  
Specific Activity ◽  
High Specific Activity ◽  
Fission Products ◽  
Nuclear Accident ◽  
Severe Accident ◽  
Primary Circuit ◽  
Free Atmosphere ◽  
Gaseous Species ◽  
Severe Nuclear Accident

In case of a severe accident in a light water reactor, iodine is one of the most important fission products in the context of reactor safety because of its significant total fuel inventory, high specific activity and radiotoxicity. Consequently, understanding its behavior under severe accident transient conditions is a major point in the optimization of the accident management and mitigation. An experimental study has been launched at VTT investigating the behavior of iodine on primary circuit surfaces during a severe nuclear accident. The paper presents results obtained from the heating of metallic cadmium and caesium iodide in a crucible at temperature below 400°C under three different atmospheres. Aerosols and gaseous species released from the reaction crucible were sampled at 150°C on filters and liquid scrubbers and analyzed with HR-ICP-MS. At first, experiments were conducted with one precursor (cadmium or caesium iodide). It was observed that cadmium is predominantly present as aerosol in all atmospheres but represents less than 1% of mass what has been recovered from the facility leaching. To the contrary, caesium iodide experiment showed that sampled iodine exists mainly as gaseous species. By comparison to one-precursor studies, a change in the behavior of element was noticed when cadmium was added to caesium iodide. Different observations let to suggest a reaction between caesium iodide and cadmium in the crucible. The reaction would lead to the formation of compound made of cadmium and iodine in condensed phase below 150°C. More gaseous iodine was found from the sampling line with Ar/H2O/H2 atmosphere than in Ar/H2O atmosphere, suggesting that the cadmium is more reactive toward iodine in hydrogen-free atmosphere.

Irradiation methods for production of high specific activity radionuclides in no carrier added form

1995 ◽  
Vol 195 (2) ◽  
pp. 227-236 ◽  
Author(s):  
M. Bonardi ◽  
M. Gallorini ◽  
C. Birattari ◽  
F. Groppi ◽  
L. Magon ◽  
...  
Keyword(s):  
Specific Activity ◽  
High Specific Activity ◽  
No Carrier Added

scholarly journals Synthesis and Characterization of Molybdenum Phthalocyanine as Target Material for High Specific Activity Molybdenum-99 Production

2019 ◽  
Vol 19 (3) ◽  
pp. 556 ◽  
Author(s):  
Muhamad Basit Febrian ◽  
Duyeh Setiawan ◽  
Hilda Hidayati
Keyword(s):  
Optimum Condition ◽  
Trifluoroacetic Acid ◽  
Specific Activity ◽  
High Specific Activity ◽  
Target Material ◽  
Radioisotope Generators ◽  
Promising Target ◽  
Band Absorption ◽  
Enriched Uranium

High specific activity is a necessity in the fabrication of 99Mo/99mTc radioisotope generators. Recoil reaction, or the Szilard-Chalmers effect, is a method that could be used as an alternative method for increasing specific activity in radioisotope production in light of tightening regulation of highly enriched uranium (HEU) irradiation. Phthalocyanine compounds are usually used as the target material in recoil reactions for the production of high specific radioisotope activity via the (n,γ) reaction. Molybdenum phthalocyanine (Mo-Pc) could be a promising target material in recoil reactions for producing high specific activity of 99Mo. Mo-Pc was synthesized via solid-state reaction between ammonium heptamolybdate and phthalonitrile in a reflux system at 300 °C for 3 h. This optimum condition was identified after performing several variations of temperature and time of reaction, considering FTIR spectra, the yield of product and melting point of the product. XRD measurement showed that Mo-Pc synthesized at optimum condition was free from MoO2, phthalimide and unreacted molybdenum. Mo-Pc has UV-vis properties of Q-band absorption between 600 and 750 nm when dissolved in tetrahydrofuran, dimethylformamide and trifluoroacetic acid. Splitting at absorption peak in tetrahydrofuran and dimethylformamide solution indicated that protonation had occurred. This split peak did not appear in a trifluoroacetic acid solution. In the preliminary study of irradiation of 1 g Mo-Pc at 3.5x1012 n cm–2 s–1 neutron flux, followed by dissolution in tetrahydrofuran and extraction of Mo-99 into NaOH, we obtained Mo-99 solution with a specific activity of 682.35 mCi/g Mo, this being 254.61 times higher than in the regular MoO3 target.

Production And Characterization Of A Plutonium-238 Loaded Ceramic Waste Form For The Study Of The Effects Of Alpha Decay Damage

1999 ◽  
Vol 556 ◽  
Author(s):  
M. Steven ◽  
Steven M. Frank ◽  
David W. Esh ◽  
Stephen G. Johnson ◽  
Marianne Noy ◽  
...  
Keyword(s):  
Ceramic Material ◽  
Spent Nuclear Fuel ◽  
Specific Activity ◽  
National Laboratory ◽  
Argonne National Laboratory ◽  
High Specific Activity ◽  
Fission Products ◽  
Alpha Decay ◽  
Waste Form ◽  
Ceramic Waste

AbstractArgonne National Laboratory has developed a glass-bonded sodalite ceramic waste form to immobilize fission products and plutonium that accumulate during the electrometallurgical conditioning of spent nuclear fuel. To investigate the effects of alpha decay damage on the structure and leaching characteristics of the ceramic material, 238Pu has been incorporated into the ceramic waste form. The 238pu,with its high specific activity, significantly increases the rate of alpha damage to the waste form. Long term studies have begun with periodic examination of the 238Pu loaded ceramic material. A number of characterization techniques are used to study the alpha decay damage on the structure of the waste form. In addition, PCT type leachate studies will be performed to determine the effect of alpha decay damage on the durability of the ceramic waste form. Preliminary results from this study are presented.

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