Production of Molybdenum-99 using Neutron Capture Methods

Toth, James J.; Greenwood, Lawrence R.; Soderquist, Chuck Z.; Wittman, Richard S.; Pierson, Bruce D.; Burns, Kimberly; Lavender, Curt A.; Painter, Chad L; Love, Edward; Wall, Donald E.

doi:10.2172/1004126

Cited by 8 publications

(9 citation statements)

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“…Whereas the use of a neutron generator for producing 99 Mo/ 99m Tc from Mo targets for the consideration of commercial application has been previously reported upon [ 23 ], it is not apparent that this has been the case for 101 Mo/ 101 Tc. Historically, the 101 Mo/ 101 Tc pair has served as a signature in neutron activation studies, and in the context of 99 Mo/ 99m Tc it has been considered an impurity coinciding from the use of Mo targets [ 24 , 25 ]. Similarly, 101 Tc has been reported for cyclotron production of 99m Tc, although only as an impurity generated via the 100 Mo(p, γ ) reaction.…”

Section: Discussionmentioning

confidence: 99%

Fusion-Based Neutron Generator Production of Tc-99m and Tc-101: A Prospective Avenue to Technetium Theranostics

Mausolf¹,

Johnstone²,

Mayordomo

et al. 2021

Pharmaceuticals

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Presented are the results of 99mTc and 101Tc production via neutron irradiation of natural isotopic molybdenum (Mo) with epithermal/resonance neutrons. Neutrons were produced using a deuterium-deuterium (D-D) neutron generator with an output of 2 × 1010 n/s. The separation of Tc from an irradiated source of bulk, low-specific activity (LSA) Mo on activated carbon (AC) was demonstrated. The yields of 99mTc and 101Tc, together with their potential use in medical single-photon emission computed tomography (SPECT) procedures, have been evaluated from the perspective of commercial production, with a patient dose consisting of 740 MBq (20 mCi) of 99mTc. The number of neutron generators to meet the annual 40,000,000 world-wide procedures is estimated for each imaging modality: 99mTc versus 101Tc, D-D versus deuterium-tritium (D-T) neutron generator system outputs, and whether or not natural molybdenum or enriched targets are used for production. The financial implications for neutron generator production of these isotopes is also presented. The use of 101Tc as a diagnostic, therapeutic, and/or theranostic isotope for use in medical applications is proposed and compared to known commercial nuclear diagnostic and therapeutic isotopes.

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Section: Discussionmentioning

confidence: 99%

Fusion-Based Neutron Generator Production of Tc-99m and Tc-101: A Prospective Avenue to Technetium Theranostics

Mausolf¹,

Johnstone²,

Mayordomo

et al. 2021

Pharmaceuticals

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“…Once the 99 Mo is separated and purified, it is sent to generator manufacturers. From there, the generator manufacturers sell the packaged generators in different quantities (1)(2)(3)(4)(5)(6)(7)(8)(9)(10)(11)(12)(13)(14)(15)(16)(17)(18)(19)(20) to large hospitals and centralized radiopharmacies, where individual doses are dispensed in syringes for single patient injections.…”

Section: Overview Of Production and Processing Of 99 Momentioning

confidence: 99%

“…The (n,γ ) approach was first used over three decades ago (19). It can be used with natural molybdenum where the abundance of 98 Mo is 24% (yield is 750 six-day Ci/week) or with enriched 98 Mo with >99% 98 Mo (yield is 3,000 six-day Ci/week-a potential fourfold increase in production).…”

Section: Mo(nγ) 99 Momentioning

confidence: 99%

The Shortage of Technetium-99m and Possible Solutions

Ruth

2020

Annu. Rev. Nucl. Part. Sci.

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Following a major shortage of 99Mo in the 2009–2010 period, concern grew that the aging reactor production facilities needed to be replaced. Most producers were using highly enriched 235U (HEU) as the target material. The Organisation for Economic Co-operation and Development and the International Atomic Energy Agency sought to remedy these issues by removing HEU from medical isotope production and implementing full cost recovery to enable new production entities to compete with the existing multipurpose reactor facilities, which were heavily subsidized by their respective governments. This review examines the various approaches to producing 99Mo and/or 99mTc with a critical eye toward their potential success in ( a) producing the medical isotopes and ( b) being able to successfully enter and compete in the market. Because many of the new approaches are adapting existing technologies for commercial businesses, some of the details are of a proprietary nature and not available for in-depth technical review. Expected final online publication date for the Annual Review of Nuclear and Particle Science, Volume 70 is October 19, 2020. Please see http://www.annualreviews.org/page/journal/pubdates for revised estimates.

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“…Yields of 99 Mo can be significantly enhanced by the epithermal neutron activation, hence the selection of the irradiation position is critical particularly in lower flux reactors [12,20]. Toth et al [22] reported that there are several factors such as self-shielding, parasitic absorption, and depletion of the product that must be accounted to identify the effective cross-section as these factors may change the results by 10 to 50%. Blaauw et al [17] reported that the careful estimation of the epithermal neutron contribution and neutron self-shielding correction can provide specific saturation activity of 99 Mo with good accuracy for the 98 Mo(n, γ) 99 Mo reaction.…”

Section: Neutron Activationmentioning

confidence: 99%

“…Mo/ 99m Tc generator with 30 mCi 99 Mo activity level demonstrated 80% 99m Tc recovery and the data was reported to be consistent over a period of one week using this adsorbent. Toth et al [22] has proposed the use of self-absorbed monolayers on mesoporous support (SAMMS) materials for its proven ability to selectively remove ionic species from aqueous solutions and complex liquids as a potential separation mechanism for 99 Mo/ 99m Tc. It was reported that SAMMS material can adsorb almost 70 mg molybdenum/ gram of resin.…”

mentioning

confidence: 99%

Molybdenum-99 production pathways and the sorbents for 99Mo/99mTc generator systems using (n, γ) 99Mo: a review

Hasan

Prelas

2020

SN Appl. Sci.

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Technetiun-99 m (99m Tc) is a widely used and versatile radioisotope obtained from the beta decay of molybdenum (99 Mo). 99 Mo can be produced by thermal fission or neutron activation process. Production of 99 Mo via the neutron capture method draws attention as an alternative to fission derived 99 Mo due to non-proliferation issues. The main concern with neutron capture-produced 99 Mo (n, γ) over the common fission-produced involves both lower Curie yield and lower specific activity. In this work, different adsorbents using low specific activity 99 Mo for 99m Tc generator have been discussed.

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Production of Molybdenum-99 using Neutron Capture Methods

Cited by 8 publications

References 0 publications

Fusion-Based Neutron Generator Production of Tc-99m and Tc-101: A Prospective Avenue to Technetium Theranostics

Fusion-Based Neutron Generator Production of Tc-99m and Tc-101: A Prospective Avenue to Technetium Theranostics

The Shortage of Technetium-99m and Possible Solutions

Molybdenum-99 production pathways and the sorbents for 99Mo/99mTc generator systems using (n, γ) 99Mo: a review

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