Fabrication of (U,Pu)N fuel pellets
- 1. Japan Atomic Energy Research Inst., Oarai, Ibaraki
Description
Uranium-plutonium mixed nitride, (U,Pu)N, was fabricated by the carbothermic reduction in a N2-8% H2 mixed gas stream from UO2 and PuO2. The influence of the sintering conditions, such as milling time, compacting pressure, sintering temperature, sintering atmosphere and pore former content, on the characteristics of (U,Pn)N pellets was systematically investigated. High density (≅ 95% TD) pellets were obtained by sintering at 2023 K in an Ar-8% H2 or Ar stream without loss of plutonium using the highly activated powder. On the other hand, low density (≅ 85% TD) pellets with excellent thermal stability were fabricated by sintering with pore former particles. The difference in the microsctructure or composition was discussed in connection with the sintering conditions. Certain increase in the lattice parameter of (U,Pu)N was observed during sintering stage. (orig.)
Additional details
Publishing Information
- Journal Title
- Journal of Nuclear Materials
- Journal Volume
- 168
- Journal Issue
- 3
- Series
- J. Nucl. Mater.
- Journal Page Range
- 280-289
- ISSN
- 0022-3115
- CODEN
- JNUMA
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 21020440
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CONTROLLED ATMOSPHERES; DENSITY; FABRICATION; FLOWSHEETS; FUEL PELLETS; LATTICE PARAMETERS; MICROSTRUCTURE; MIXED NITRIDE FUELS; PLUTONIUM NITRIDES; SINTERED MATERIALS; URANIUM NITRIDES; X-RAY DIFFRACTION
- Descriptors DEC
- ACTINIDE COMPOUNDS; COHERENT SCATTERING; CRYSTAL STRUCTURE; DIAGRAMS; DIFFRACTION; ENERGY SOURCES; FUELS; INFORMATION; MATERIALS; NITRIDES; NITROGEN COMPOUNDS; NUCLEAR FUELS; PHYSICAL PROPERTIES; PLUTONIUM COMPOUNDS; PNICTIDES; REACTOR MATERIALS; SCATTERING; SOLID FUELS; TRANSURANIUM COMPOUNDS; URANIUM COMPOUNDS