The MoRe project: an alternative route to the production of high specific activity 99Mo

Lapi, Suzanne E.; Ladouceur, Keith; Ruth, Thomas J.; D’Auria, J.M.

doi:10.1016/j.nucmedbio.2010.03.015

Cited by 5 publications

(4 citation statements)

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“…It is, therefore, interesting to contemplate the possibility of using EM isotope separation as the technology of choice to remove isotopic impurities. Recently, Lapi et al [24] and D'Auria et al [25] demonstrated efficient EM isotope separation for 99 Mo. These authors also speculated about using EM isotope separation for many other medically important radionuclides, some of which can be produced in sufficient quantities via reactions such (n,γ) and (γ,n) but which result in products with a low specific activity.…”

Section: Electromagnetic Isotope Separationmentioning

confidence: 99%

Cross sections of proton-induced reactions on 152Gd, 155Gd and 159Tb with emphasis on the production of selected Tb radionuclides

Steyn

Vermeulen

Szelecsényi

et al. 2014

Nuclear Instruments and Methods in Physics Research Section B:

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Cross sections are presented for various Dy, Tb and Gd radionuclides produced in the proton bombardment of 159 Tb as well as for the reactions 152 Gd(p,4n) 149 Tb and 155 Gd(p,4n) 152 Tb up to 66 MeV. The experimental excitation functions are compared with theoretical predictions by means of the geometrydependent hybrid (GDH) model as implemented in the code ALICE/ASH, as well as with values from the TENDL-2012 library and previous literature experimental data, where available. Physical yields have been derived for the production of some of the medically important radioterbiums, namely 149 Tb (radionuclide therapy), 152 Tb (PET) and 155 Tb (SPECT). The indirect production of high-purity 155 Tb via the decay of its precursor 155 Dy is reported. The possibility of a large-scale production facility based on a commercial 70 MeV cyclotron is also discussed.

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Section: Electromagnetic Isotope Separationmentioning

confidence: 99%

Cross sections of proton-induced reactions on 152Gd, 155Gd and 159Tb with emphasis on the production of selected Tb radionuclides

Steyn

Vermeulen

Szelecsényi

et al. 2014

Nuclear Instruments and Methods in Physics Research Section B:

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“…The fission of 235 U for the 99 Mo production can be performed with neutrons generated from the >2.224 MeV photon-induced breakup of D 2 O in a subcritical LEU solution target. Accelerator-driven photon-fission 238 U( ,f) 99 Mo is also proposed as an approach to produce high SA 99 Mo using natural uranium target [2,[23][24][25]. Under the consultation for the fission 99 Mo plant in ANSTO, the author of this review paper has proposed a project of "Automated modular process for LEU-based production of fission 99 " [26].…”

Section: High Specific Activity 99 Mo: Current Issues Of Production Amentioning

confidence: 99%

“…The W impurity in the natural Mo target material should be <10 ppm and that is not detectable in the enriched 98 Mo targets. Due to high cost of highly enriched 98 Mo, the economical use of this target material requires a well-established recycling of irradiated target material [2,24,25,66,67,[72][73][74]. 99 Mo/ 99m Tc Production.…”

Section: Low Specific Activity 99 Mo: Current Issues Of Production Anmentioning

confidence: 99%

TcGenerator Development: Up-to-DateTcRecovery Technologies for Increasing the Effectiveness of
Le¹
2014
Science and Technology of Nuclear Installations
18
0
8
0
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A review on theMosources available today and on theTcgenerators developed up to date for increasing the effectiveness ofMoutilisation is performed in the format of detailed description of the features and technical performance of the technological groups of theMoproduction andTcrecovery. The latest results of the endeavour in this field are also surveyed in regard of the technical solution for overcoming the shortage ofMosupply. The technological topics are grouped and discussed in a way to reflect the similarity in the technological process of each group. The following groups are included in this review which are high specific activityMo: the current issues of production, the efforts of more effective utilisation, and the high specific activityMo-basedTcgenerator andTcconcentration units; low specific activityMo: theMoproduction based on neutron capture and accelerators and the direct production ofTcand the methods of increasing the specific activity ofMousing Szilard-Chalmers reaction and high electric power isotopic separator; up-to-date technologies ofTcrecovery from low specific activityMo: the solvent extraction-basedTcgenerator, the sublimation methods forMo/Tcseparation, the electrochemical method forTcrecovery, and the column chromatographic methods forTcrecovery. Besides the traditionalTc-generator systems, the integratedTcgenerator systems (Tcgenerator column combined with postelution purification/concentration unit) are discussed with the format of process diagram and picture of real generator systems. These systems are the technetium selective sorbent column-based generators, the high Mo-loading capacity column-based integratedTcgenerator systems which include the saline-eluted generator systems, and the nonsaline aqueous and organic solvent eluent-eluted generator systems using high Mo-loading capacity molybdategel and recently developed sorbent columns.Tcconcentration methods used in theTcrecovery from low specific activityMoare also discussed with detailed process diagrams which are surveyed in two groups forTcconcentration from the saline and nonsalineTc-eluates. The evaluation methods for the performance ofTc-recovery/concentration process and for theTc-elution capability versus Mo-loading capacity of generator column produced using low specific activityMosource are briefly reported. Together with the theoretical aspects ofTc/Moand sorbent chemistry, these evaluation/assessment processes will be useful for any further development in the field of theTcrecovery andMo/Tcgenerator production.

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“…However, this disadvantage may be overcome with techniques to isolate Re-186. Lapi et al patented a method to isolate Re-186 by vaporizing a compound containing Re-185 and Re-186, ionizing it to form negatively charged molecules, and then using a positively charged collector to separate and recover the molecules by mass difference [8].…”

Section: Introductionmentioning

confidence: 99%

Feasibility Study on Production of High-Purity Rhenium-185 by Nuclear Transmutation of Natural Tantalum

Tanoue,

Yokoyama,

Ozawa

2023

JNE

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Rhenium-186 (Re-186) has attracted attention as a medical isotope. The feasibility of producing Re-185, the raw material for Re-186, using a fast reactor was evaluated using a continuous energy Monte Carlo code. The irradiation of natural tantalum (Ta) in the fast reactor can produce Re-185 with an isotopic purity of 99%. A two-step irradiation process with different moderators was found to improve the production rate of Re-185. Specifically, this can be achieved by using zirconium hydride (ZrH1.7) as a moderator in the first transmutation process from natural Ta to tungsten (W), and then zirconium deuteride (ZrD1.7) as a moderator in the second transmutation process from W to Re-185. Due to the two-step irradiation, the production rate of Re-185 from Ta can be increased up to a maximum of 470 times compared with irradiation without a moderator, and 2.3 g of Re-185 can be obtained from 1571 g of Ta in 1 year of irradiation. The proposed isotope production method is a new method that is different from the conventional electromagnetic enrichment process.

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The MoRe project: an alternative route to the production of high specific activity 99Mo

Cited by 5 publications

References 0 publications

Cross sections of proton-induced reactions on 152Gd, 155Gd and 159Tb with emphasis on the production of selected Tb radionuclides

Cross sections of proton-induced reactions on 152Gd, 155Gd and 159Tb with emphasis on the production of selected Tb radionuclides

TcGenerator Development: Up-to-DateTcRecovery Technologies for Increasing the Effectiveness of
Le¹
2014
Science and Technology of Nuclear Installations
18
0
8
0
View full text Add to dashboard Cite

Feasibility Study on Production of High-Purity Rhenium-185 by Nuclear Transmutation of Natural Tantalum

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The MoRe project: an alternative route to the production of high specific activity 99Mo

Cited by 5 publications

References 0 publications

Cross sections of proton-induced reactions on 152Gd, 155Gd and 159Tb with emphasis on the production of selected Tb radionuclides

Cross sections of proton-induced reactions on 152Gd, 155Gd and 159Tb with emphasis on the production of selected Tb radionuclides

TcGenerator Development: Up-to-DateTcRecovery Technologies for Increasing the Effectiveness ofLe1 2014Science and Technology of Nuclear Installations18080View full textAdd to dashboardCite

Feasibility Study on Production of High-Purity Rhenium-185 by Nuclear Transmutation of Natural Tantalum

Contact Info

Product

Resources

About

TcGenerator Development: Up-to-DateTcRecovery Technologies for Increasing the Effectiveness of
Le¹
2014
Science and Technology of Nuclear Installations
18
0
8
0
View full text Add to dashboard Cite