% IMPORTANT: The following is UTF-8 encoded.  This means that in the presence
% of non-ASCII characters, it will not work with BibTeX 0.99 or older.
% Instead, you should use an up-to-date BibTeX implementation like “bibtex8” or
% “biber”.

@INPROCEEDINGS{Shabani:1027077,
      author       = {Shabani, Doruntin and Langer, Christoph and Mauerhofer,
                      Eric and Gutberlet, Thomas},
      title        = {{I}nvestigation of the 99{M}o production via neutron
                      capture 98{M}o(n,γ)99{M}o with a high-current
                      accelerator-based neutron source},
      reportid     = {FZJ-2024-03629},
      year         = {2024},
      abstract     = {The demand for 99mTc, the most widely used radioisotope in
                      medical imaging, is steadilyincreasing, with approximately
                      $80\%$ of all nuclear medicine procedures relying on it [1].
                      Theprecursor, 99Mo, is primarily produced through the
                      fission of 235U in high neutron flux reactors[2]. This poses
                      challenges in supply chain disruptions and radioactive waste
                      management andas aging reactors face potential shutdowns,
                      alternative production methods become crucial.This study
                      explores an alternative approach to 99Mo production
                      utilizing a high-currentaccelerator-based neutron source, as
                      proposed in the ambitious HBS (Jülich High
                      BrillianceSource) project [3]. The method involves the (n,
                      γ) reaction with fast neutrons generated by70 MeV protons
                      interacting with a tantalum target, moderated in water and
                      reflected by lead.Numerical simulations, employing the PHITS
                      code, investigate various target parametersand proton beam
                      currents while limiting the target power density to 3
                      kW/cm2.Compared to traditional methods, this
                      accelerator-based neutron source offers potentialadvantages,
                      such as simplified processing schemes and reduced
                      radioactive waste. The studyassesses the thermal and
                      epithermal neutron flux, crucial for 99Mo activity,
                      considering differenttarget and molybdenum plates' surfaces
                      and thicknesses. Analytical methods,
                      incorporatingcorrections for thermal and epithermal neutron
                      self-shielding, complement the simulationresults.As current
                      reactor-based 99Mo production faces challenges, especially
                      in regions like Germanywith substantial demand [4], the
                      pursuit of alternative, sustainable methods gains
                      significance.The ongoing developments in accelerator-based
                      technologies, exemplified by theHBS project, signify a
                      promising avenue for securing the supply of critical medical
                      isotopes,addressing both efficiency and waste management
                      concerns. This work contributes valuableinsights into the
                      feasibility and optimization of 99Mo production through
                      accelerator-basedneutron sources, paving the way for future
                      advancements in medical radioisotope
                      productiontechnology.AcknowledgmentsThis work is supported
                      by the German Federal Ministry of Education and Research
                      (BMBF) underGrant No. 02NUK080B.References1. NEA (2019),
                      “The Supply of Medical Radioisotopes: 2019 Medical Isotope
                      Demand and CapacityProjection for the 2019–2024 Period”,
                      OECD Publishing, Paris.2. Jaroszewicz J, Marcinkowska Z,
                      Pytel K (2014) Production of fission product 99Mo using
                      highenricheduranium plates in Polish nuclear research
                      reactor MARIA: Technology and neutronicanalysis. Nukleonika
                      59(2):43–52.3. Brückel, T., $\&$ Gutberlet, T., et al.
                      (2023), Technical Design Report HBS Volume 2 – Target
                      stationsand moderators, Forschungszentrum Jülich GmbH4.
                      Deutscher Bundestag, Drucksache 17/3142, 2010.},
      month         = {May},
      date          = {2024-05-05},
      organization  = {International Conference on Modern
                       Trends in Activation Analysis, MERCURE
                       BUDA CASTLE HILL BUDAPEST (Hungary), 5
                       May 2024 - 10 May 2024},
      subtyp        = {Invited},
      cin          = {JCNS-2 / JCNS-HBS / JARA-FIT},
      cid          = {I:(DE-Juel1)JCNS-2-20110106 / I:(DE-Juel1)JCNS-HBS-20180709
                      / $I:(DE-82)080009_20140620$},
      pnm          = {632 - Materials – Quantum, Complex and Functional
                      Materials (POF4-632) / 6G4 - Jülich Centre for Neutron
                      Research (JCNS) (FZJ) (POF4-6G4)},
      pid          = {G:(DE-HGF)POF4-632 / G:(DE-HGF)POF4-6G4},
      typ          = {PUB:(DE-HGF)6},
      url          = {https://juser.fz-juelich.de/record/1027077},
}