Community Research and Development Information Service - CORDIS


Fuel studies have included the development of a "pure" optimised FBR nitride fuel for an He-bonding pin concept, the construction and testing of a laser autoclave technique for specific heat and density measurements, post-irradiation analysis of a commercial PWR fuel, and analysis of lattice damage in UO and its interaction with the kinetics of fission product precipitation and release. The codes FUTURE and MITRA were used in development of detailed physical models and further models were introduced into the code TRANSURANUS. The characteristics of the minor-actinide fuel for the SUPERFACT irradiation in Phenix are reported. The analysis of the off-gas from nitride dissolutions has been continued. Longterm applications of actinide research include the bonding properties of actinides in nuclear waste and the use of Th and U compounds as permanent magnets or catalytic materials. High purity samples have been prepared, often in the form of single crystals, and new materials such as thin films of amorphous actinide compounds.

Additional information

Authors: JRC KARLSRUHE, JRC, Karlsruhe (DE)
Bibliographic Reference: EUR 12233 EN (1990) 142 pp., ECU 8
Availability: (2)
Record Number: 199010171 / Last updated on: 1994-12-01
Original language: en
Available languages: en