Development of a high temperature treatment device for spent nuclear fuel

  • Niko Kivel
  • Natalia Shcherbina
  • Ines Günther-Leopold


Novel reprocessing schemes and techniques are the focus of the Euratom FP7 project “Actinide Recycling for Separation and Transmutation” (ACSEPT), where the Paul Scherrer Institute (PSI) is represented in the pyrochemical domain. The subject of investigation is the selective separation of fission products (FPs) from spent nuclear fuel as a head-end step to either classical hydro based or pyro processes which are not yet applied on a large scale. The selective removal of FPs that are major contributors to the overall radiation dose or bear great potentials in terms of radiotoxicity (i.e. cesium or iodine), is advantageous for further processes. At PSI a device was developed to release volatile FPs by means of inductive heating. The heating up to 2,300 °C promotes the release of material that is further transported by a carrier gas stream into an inductively coupled plasma mass spectrometer for online detection. The carrier gas can be either inert (Ar) or can contain reducing or oxidizing components like hydrogen or oxygen, respectively. The development of the device by computer aided engineering approaches, the commissioning and evaluation of the device and data from first release experiments on a simulated fuel matrix are discussed.


Inductively coupled plasma mass spectrometry Reprocessing Inductive heating 



This research project has received funding from the European Atomic Energy Communities 7th Framework Programme under grant agreement no. FP7-CP-2007-211267, the ACSEPT project. The effort of the workshop personnel, especially Marcus Keller and Andreas Spahr, is greatly appreciated.


  1. 1.
    Del Cul GD, Spencer BB, Collins ED (2005) Hybrid processing of spent fuel. Proceedings of Global conferenceGoogle Scholar
  2. 2.
    Del Cul GD, Hunt R, Spencer BB (2004) Advanced head-end processing of spent fuel. American Nuclear Society Winter MeetingGoogle Scholar
  3. 3.
    Ozawa M, Koma Y, Nomura K, Tanaka Y (1998) Separation of actinides and fission products in high-level liquid wastes by the improved TRUEX process. J Alloy Compd. doi: 10.1016/S0925-8388(98)00147-9 Google Scholar
  4. 4.
    Nuclear fuel reprocessing (2010) Idaho National Laboratory (INL) Accessed 17 July 2012
  5. 5.
    Brand GE, Murbach EW (1965) Pyrochemical reprocessing of UO2 by AIROX. Atomics International, Canoga ParkGoogle Scholar
  6. 6.
    Laidler JJ, Battles JE, Miller WE, Ackerman JP, Carls EL (1997) Development of pyroprocessing technology. Prog Nucl Energy. doi: 10.1016/0149-1970(96)00007-8 Google Scholar
  7. 7.
    Malmbeck R, Nourry C, Ougier M, Souček P, Glatz JP, Kato T, Koyama T (2011) Advanced fuel cycle options. Energy Procedia. doi: 10.1016/j.egypro.2011.06.013 Google Scholar
  8. 8.
    Lucuta PG, Verrall RA, Matzke Hj, Palmer BJ (1991) Microstructural features of SIMFUEL–Simulated High-Burnup UO2–based nuclear fuel. J Nucl Mater. doi: 10.1016/0022-3115(91)90455-G Google Scholar
  9. 9.
    Lucuta PG, Verrall RA, Matzke Hj, Hastings IL (1992) Characterization and thermal properties of hyperstoichiometric SIMFUEL. Proceedings of 3rd International Conference on CANDU FuelGoogle Scholar

Copyright information

© Akadémiai Kiadó, Budapest, Hungary 2012

Authors and Affiliations

  • Niko Kivel
    • 1
  • Natalia Shcherbina
    • 1
  • Ines Günther-Leopold
    • 1
  1. 1.Department of Nuclear Energy and SafetyPaul Scherrer InstituteVilligen PSISwitzerland

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