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Research ArticleSpecial Contribution

Sustained Availability of 99mTc: Possible Paths Forward

Maroor Raghavan Ambikalmajan Pillai, Ashutosh Dash and F.F. (Russ) Knapp
Journal of Nuclear Medicine February 2013, 54 (2) 313-323; DOI: https://doi.org/10.2967/jnumed.112.110338
Maroor Raghavan Ambikalmajan Pillai
1Radiopharmaceuticals Division, Bhabha Atomic Research Centre (BARC), Mumbai, India; and
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Ashutosh Dash
1Radiopharmaceuticals Division, Bhabha Atomic Research Centre (BARC), Mumbai, India; and
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F.F. (Russ) Knapp Jr.
2Nuclear Medicine Program, Isotope Development Group, Oak Ridge National Laboratory (ORNL), Oak Ridge, Tennessee
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  • FIGURE 1.
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    FIGURE 1.

    Decay scheme of 99Mo and 99mTc. T1/2 = half-life.

  • FIGURE 2.
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    FIGURE 2.

    99Mo production by 100Mo(γ,n)99Mo photon-induced reaction.

  • FIGURE 3.
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    FIGURE 3.

    Schematic view of ADS concept for 99Mo production.

Tables

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    TABLE 1

    Designations for Uranium Enrichment

    Uranium gradeDesignation235U content (%)
    NUNatural uranium0.7
    LEULow enriched uranium≤20
    HEUHigh enriched uranium≤20
    HEUWeapons-grade uranium≥85
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    TABLE 2

    Operating Research Reactors Used for Large-Scale 99Mo Production

    CountryReactor namePower (MWt)Thermal neutron flux (n·cm−2·s−1)Target type
    CanadaNRU1354.0 × 1014HEU
    NetherlandsHFR452.7 × 1014HEU
    BelgiumBR-21001.0 × 1015HEU
    South AfricaSafari-1202.4 × 1014HEU
    FranceOSIRIS701.7 × 1014HEU
    PolandMARIA303.5 × 1014HEU
    AustraliaOPAL203.0 × 1014LEU
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    TABLE 3

    Key Strategies for 99Mo and 99mTc Production

    Production methodTargetProductComment
    Reactor-based strategies
     HEU235U99MoCurrent commercial technology
     LEU235U99MoTransition for routine production
     98Mo98Mo99MoLow-specific-activity product
     Use of power reactors98Mo99MoLow-specific-activity product; under consideration
     Aqueous homogeneous reactor–based technology235U99MoUnder development as major alternative
    Accelerator-based strategies
     Photo-fission238U99MoAll are under development as major alternatives
     Photo transmutation of 100Mo100Mo99Mo
     Direct production of 99mTc100Mo99mTc
     Subcritical hybrid intense neutron emitterLEU99Mo
     ADSLEU99Mo
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    TABLE 4

    Comparison of Fission and Neutron Activation Production Routes for 99Mo

    Fission 99Mo(n,γ)99Mo
    Target235U (HEU or LEU); enriched 235U in the form of uranium–aluminum alloy, foil, or pellet98Mo (natural or enriched) in the form of MoO3, molybdenum metal, or pellet
    Nuclear reactionn + 235U → 99Mo + F.P. + 2.5 n; σfission = 586 b; fission yield of 99Mo = 6%n + 98Mo → 99Mo; σth = 0.14 b
    Availability of targetLimited producers/suppliersWidely available
    99Mo specific activityHigh (185–370 TBq/g); independent of reactor neutron fluxLow (7.4–130 GBq/g) depending on the reactor neutron flux
    Postirradiation processComplex chemical process consists of a series of precipitation and ion exchange proceduresSimple dissolution of the irradiated solid targets
    Processing facilityExpensiveEconomical
    Radioactive wasteSignificant amount of radioactive waste including fission products, uranium, and plutoniumNegligible
    Security and nonproliferation concernsHighNegligible
    Production capabilityRestricted to few countriesWidely distributed
    Cost of productionHighLow
    Quality of 99mTcNo carrier added; suitable for nuclear medicine applicationsNo carrier added; suitable for nuclear medicine applications
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    TABLE 5

    Methods for Obtaining No-Carrier-Added 99mTc from Low-Specific-Activity 99Mo

    MethodStatus/comments
    Extraction from methyl ethyl ketoneEstablished/high-yield technology
    Postelution concentrationWidespread verification
    Solid-phase column extractionPromising technologies but only small-scale experimental verification
    Zirconium-molybdate gel
    High-binding adsorbents
    Electrochemical generator
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    TABLE 6

    Accelerator Production of 99Mo and 99mTc

    ProcessNuclear reactionFission cross-section, σ (barn)*
    Photo-fission†γ + 238U → 99Mo+ fission products + 2n0.16
    Photo-transmutationγ + 100Mo → 99Mo + n0.16
    Proton-induced reactionp + 100Mo → 99Mo + p + n0.15
    Direct production of 99mTcp + 100Mo → 99mTc + 2n0.20
    • ↵* 1 barn = 10−24 cm2.

    • ↵† Fission yield of 99Mo = 6%.

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Journal of Nuclear Medicine: 54 (2)
Journal of Nuclear Medicine
Vol. 54, Issue 2
February 1, 2013
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Sustained Availability of 99mTc: Possible Paths Forward
Maroor Raghavan Ambikalmajan Pillai, Ashutosh Dash, F.F. (Russ) Knapp
Journal of Nuclear Medicine Feb 2013, 54 (2) 313-323; DOI: 10.2967/jnumed.112.110338

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Sustained Availability of 99mTc: Possible Paths Forward
Maroor Raghavan Ambikalmajan Pillai, Ashutosh Dash, F.F. (Russ) Knapp
Journal of Nuclear Medicine Feb 2013, 54 (2) 313-323; DOI: 10.2967/jnumed.112.110338
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    • REACTOR-BASED 99MO PRODUCTION
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Keywords

  • 99mTc
  • 99Mo production
  • reactor production
  • accelerator production
  • aqueous homogeneous reactor (AHR)
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