Published September 1999 | Version v1
Book

Fuel performance modelling of nitride fuels

Description

Nitrides have been identified as a candidate fuel for fast reactors due to the better thermal conductivity, compatibility with sodium and, in the case of aqueous fuel reprocessing, higher solubility in nitric acid compared to conventional oxide fuels. The physical properties and vaporisation behaviour of actinide nitrides and (Zr,Pu)N fuels are reviewed. The extent of transport of gaseous nitride species are predicted from kinetic calculations using the FAC SIMILE code and an appropriate model for the fuel pellet system. The assessed thermophysical data recommendations are incorporated into the oxide fuel performance code TRAFIC and a nitride version developed, NITRAF. Results from fuel pin calculations are presented; these include temperature profiles and the evolution of fuel-clad mechanical interaction

Additional details

Publishing Information

Publisher
American Nuclear Society - ANS
Imprint Place
Jackson Hole, Wyoming (United States)
Imprint Pagination
7 p.

Conference

Title
International Conference on Future Nuclear Systems - Nuclear Technology - Bridging the Millennia
Acronym
Global'99
Dates
29 Aug - 3 Sep 1999
Place
Las Vegas, NV (United States)

Optional Information

Notes
9 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)