Gateway for:

Member Countries

Extraction of Fission Products from Irradiated Fuel


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

Tech Area / Field

  • FIR-FUC/Fuel Cycle/Fission Reactors

8 Project completed

Registration date

Completion date

Senior Project Manager
Tocheny L V

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


  • 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.


(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.


The International Science and Technology Center (ISTC) is an intergovernmental organization connecting scientists from Kazakhstan, Armenia, Tajikistan, Kyrgyzstan, and Georgia with their peers and research organizations in the EU, Japan, Republic of Korea, Norway and the United States.


ISTC facilitates international science projects and assists the global scientific and business community to source and engage with CIS and Georgian institutes that develop or possess an excellence of scientific know-how.

Promotional Material

Значимы проект

See ISTC's new Promotional video view