Published February 1991 | Version v1
Journal article

Preparation, characterisation and out-of-pile property evaluation of (U,Pu)N fuel pellets

  • 1. Bhabha Atomic Research Centre, Bombay (India). Radiometallurgy Div.

Description

(U0.45Pu0.55)N and (U0.8Pu0.2)N are being considered in India as advanced alternative fuels for the operating fast breeder test reactor (FBTR) and the forthcoming prototype fast breeder reactor (PFBR). Mixed nitride fuel pellets containing <0.1 wt% each of oxygen and carbon impurities were fabricated by the conventional 'powder-pellet' (POP) and the advanced 'sol-gel microsphere pelletisation' (SGMP) processes, involving two major steps. First, carbothermic reduction of an oxide-graphite powder mixture (in the form of tablets) or gel-microspheres at 1773 - 1823 K in N2 followed by N2+H2 and Ar+H2 atmospheres. The nitride microspheres could be directly pelletised and sintered to pellets of relatively low density (≤ 85% TD) with an 'open' pore structure desirable for LMFBR application. Thermal conductivity and hot hardness of nitride pellets were evaluated up to 1800 and 1500 respectively. The out-of-pile chemical compatibility experiments of mixed nitride fuel pellets for FBTR with SS 316 cladding at 973 K for 1000 h did not reveal any significant fuel-cladding chemical interaction. (orig.)

Additional details

Publishing Information

Journal Title
Journal of Nuclear Materials
Journal Volume
178
Journal Issue
2/3
Series
J. Nucl. Mater.
Journal Page Range
234-241
ISSN
0022-3115
CODEN
JNUMA

Conference

Title
4. international conference on characterization and quality control of nuclear fuels.
Dates
19-21 Jun 1990.
Place
Karlsruhe (Germany, F.R.).