Preparation, characterisation and out-of-pile property evaluation of (U,Pu)N fuel pellets
Creators
- 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.).
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 22081219
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPATIBILITY; FABRICATION; FBR TYPE REACTORS; FUEL PELLETS; FUEL-CLADDING INTERACTIONS; HARDNESS; KALPAKKAM LMFBR REACTOR; PERFORMANCE TESTING; PLUTONIUM NITRIDES; THERMAL CONDUCTIVITY; URANIUM NITRIDES
- Descriptors DEC
- ACTINIDE COMPOUNDS; BREEDER REACTORS; EPITHERMAL REACTORS; FAST REACTORS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; MECHANICAL PROPERTIES; NITRIDES; NITROGEN COMPOUNDS; PHYSICAL PROPERTIES; PLUTONIUM COMPOUNDS; PNICTIDES; REACTORS; RESEARCH AND TEST REACTORS; TEST FACILITIES; TEST REACTORS; TESTING; THERMODYNAMIC PROPERTIES; TRANSURANIUM COMPOUNDS; URANIUM COMPOUNDS