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Extraction of Fission Products from Irradiated Fuel

#0279


Studies on Extraction of Fission Products from Fast Reactor Irradiated Fuel with Minor-Actinide Additives.

Tech Area / Field

  • FIR-FUC/Fuel Cycle/Fission Reactors

Status
8 Project completed

Registration date
25.10.1994

Completion date
05.12.2002

Senior Project Manager
Tocheny L V

Leading Institute
NIIAR (Atomic Reactors), Russia, Ulianovsk reg., Dimitrovgrad

Collaborators

  • European Commission / Joint Research Center / Institute for Transuranium Elements, Germany, Karlsruhe\nCEA / DRN / DER / CEN Cadarache, France, Cadarache\nBritish Nuclear Fuels Ltd (BNFL), UK, Chesire, Risley Warrington\nForschungszentrum Jülich, Germany, Jülich

Project summary

Project involves experimental estimations of the dry repro-cessing technologies for oxide fuel containing minor actinides in frames of the actinide burner reactor closed fuel cycle. This project is aimed at the solution of the problem of minor actinides (Np, Am, Cm) transmutation in the special nuclear power fa-cilities with oxide fuel.

The project objects are the theoretical and experimental es-timation of decontamination factors for irradiated oxide fuel contained MA under application of two "dry" technologies - pyroelectrochemical and partial vacuum-thermal reprocessing.

EXPECTED RESULTS

(1) The calculated data on decontamination levels of oxide fu-el, contained minor actinides, and irradiated in the special re-actor-burner, from fission products under pyroelectrochemlcal reprocessing;

(2) The experimental data on the irradiated oxide fuel decon-tamination factors from some fission products during partial thermal treatment of the real irradiated fuel of the BOR-60 reactor before repeated irradiation for additional actinide burning;

(3) The experimental data on the fission products distribution under pyroelectrochemlcal reprocessing of the simulators of irradiated oxide fuel, contained minor-actinides;

(4) The generalized flow-sheet for irradiated oxide fuel, con-tained minor-actinides, reprocessing and the estimation of fis-sion products distribution.


Results of this work can be used for experimental develop-ments of the closed fuel cycle for nuclear power facilitie
operating under the conditions of burning out most hazardaous radi-oactive waste components and using of oxide fuel.


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