Published September 2016 | Version v1
Journal article Metadata-only

Simfuel - near unirradiated analogue of high burn-up nuclear fuel

Creators

  • 1. Radiometallurgy Division, Bhabha Atomic Research Centre, Mumbai (India)
  • 2. Product Development Division, Bhabha Atomic Research Centre, Mumbai (India)
  • 3. Post Irradiation Examination Division, Bhabha Atomic Research Centre, Mumbai (India)

Description

Simulated fuel based on ThO2-3.5% UO2 corresponding to 28000 and 43000 MWd/t burn-up and simulated fuel based on UO2 corresponding to 7000 MWd/t burn-up were fabricated by powder metallurgical route by adding high purity oxides such as SrO, Y2O3, ZrO2, MoO3, BaCO3, La2O3, CeO2, Nd2O3, RuO2, Rh2O3, Pd, Cs2CO3, Pr6O11 and Sm2O3 to ThO2 and UO2 powders in desired quantities which simulate the fission products. Thermophysical properties e.g. thermal diffusivity/conductivity, thermal expansion and specific heat of fabricated samples were studied. (author)

Additional details

Publishing Information

Journal Title
BARC Newsletter
Journal Issue
no.353
Journal Page Range
p. 24-29
ISSN
0976-2108

INIS

Country of Publication
India
Country of Input or Organization
India
INIS RN
48043341
Subject category
S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
Descriptors DEI
BURNUP; MIXED OXIDE FUELS; SPECIFIC HEAT; THERMAL CONDUCTIVITY; THERMAL DIFFUSIVITY; THERMAL EXPANSION; THORIUM OXIDES; URANIUM OXIDES
Descriptors DEC
ACTINIDE COMPOUNDS; CHALCOGENIDES; ENERGY SOURCES; EXPANSION; FUELS; MATERIALS; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; PHYSICAL PROPERTIES; REACTOR MATERIALS; SOLID FUELS; THERMODYNAMIC PROPERTIES; THORIUM COMPOUNDS; URANIUM COMPOUNDS

Optional Information

Notes
9 refs., 8 figs., 2 tabs.