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Abstract

In the frame of the CAPRA programme an experiment is prepared to irradiate three pins in a TRIO capsule in the HFR reactor. Two of these pins were designed and fabricated with two different fuel materials: (i) mixed (U,Pu,Np)O(2) with 40 wt% Pu and 5 wt% Np; (ii) mixed (Pu,Ce)O(2) with 41 wt% Pu and 59 wt% Ce, with the latter as a prototype uranium-free fuel type. Due to the unusual composition and the radiation level of the Np, it was necessary to develop special fabrication procedures and, in order to assure the formation of solid solutions, a sol-gel technique was used. Pellets were produced by cold-pressing and sintering and filled into tubes, made out of austenitic 1.4970 cladding material.

Additional information

Authors: GEUGNON J F, JRC Karlsruhe (DE);RICHTER K, JRC Karlsruhe (DE);MÜHLUNG G, Forschungszentrum Karlsruhe GmbH (DE);PLITZ H, Forschungszentrum Karlsruhe GmbH (DE)
Bibliographic Reference: Paper presented: ANS International Conference on Evaluation of Emerging Nuclear Cycle : Global '95, Versailles (FR), September 11-14, 1995
Availability: Available from (1) as Paper EN 38859 ORA
Record Number: 199510302 / Last updated on: 1995-03-08
Category: PUBLICATION
Original language: en
Available languages: en