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First steps of an identification procedure for fuel pellets of unknown origin by means of a relational database are demonstrated. Basic structure as well as main relations in the fresh-fuel sector of the database system are outlined. The database contains only parameters of nuclear fuel supposed to be used in power reactors. In the case studies presented the analysis results are systematically compared with the entries stored in the database. Apart from the macroscopic parameters, the analytical data cover uranium and plutonium element content, enrichment, as well as abundances of impurities and trace elements.

Additional information

Authors: DOLGOV Y ET AL, All-Russia Research Institute for Inorganic Materials, Moscow (RU);KOCH L ET AL, JRC Karlsruhe (DE)
Bibliographic Reference: Paper presented: Russian International Conference on Nuclear Material Protection, Control and Accounting, Obninsk (RU), March 9-14, 1997
Availability: Available from (1) as Paper EN 40457 ORA
Record Number: 199810040 / Last updated on: 1998-02-03
Original language: en
Available languages: en