Community Research and Development Information Service - CORDIS


TUBRNP (TRANSURANUS burnup) is a new model which predicts the radial power density distribution as a function of burnup (and hence the radial burnup profile as a function of time) together with the radial profile of plutonium. Comparisons between measurements and the predictions of the TUBRNP model have been made for MOX fuels. MOX fuels consist of uranium oxide with (U,Pu)O(2) agglomerates typically of the order of 100 microns in diameter. The factors considered in this report are further resonance effects and the MOX thermal neutron spectrum. SIMS and EPMA analyses provide detailed results for the total and radial dependent values for burnup and isotopic composition. The model, even in its present form, is a valuable tool for the analysis of mixed oxide fuel data.

Additional information

Authors: O'CARROLL C, JRC Karlsruhe (DE);VAN DE LAAR J, JRC Karlsruhe (DE);WALKER C T, JRC Karlsruhe (DE);OTT C, Paul Scherrer Institute, Villigen (CH);RESTANI R, Paul Scherrer Institute, Villigen (CH)
Bibliographic Reference: Paper presented: IAEA Technical Committee Meeting on Water Reactor Fuel Element, Windermere (GB), September 19-23, 1994
Availability: Available from (1) as Paper EN 38680 ORA
Record Number: 199411425 / Last updated on: 1994-12-06
Original language: en
Available languages: en