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http://www.scirp.org/journal/PaperInformation.aspx?PaperID=52978#.VK8wFMnQrzE
ABSTRACT
Thorium
based nuclear fuel is of immense interest to India by virtue of the
abundance of Thorium and relative shortage of Uranium. Thorium metal
tubes were being cold drawn using copper as cladding to prevent die
seizure. After cold drawing, the copper was removed by dissolution in
nitric acid. Thorium does not dissolve being passivated by nitric acid.
Initially the copper cladding was carried out by inserting copper tubes
inside and outside the thorium metal tube. In an innovative development,
the mechanical cladding with copper was replaced by electroplated
copper with a remarkable improvement in thorium tube acceptance rates.
Oxalate derived thoria powder was found to require lower compaction
pressures compared to ammonium diuranate derived urania powders to
attain the same green compact density. However, the green pellets of
thoria were fragile and chipped during handling. The strength improved
after introducing a ball milling step before compaction and maintaining
the green density above the specified value. Alternatively, binders were
used later for greater handling strength. Magnesia was conventionally
being used as dopant to enhance the sinterability of thoria. The normal
sintering temperature for magnesia doped thoria was 1600℃ - 1700℃, which
was achieved in electrically heated molybdenum element sintering
furnaces with reducing atmosphere. 0.25 mole percent addition of niobia
to the thoria was found to bring down the sintering temperature to
1150℃. Sintering could be done in ordinary furnaces in air atmosphere
using silicon carbide or Kanthal heating elements. Electrical
conductivity was measured for both magnesia and niobia doped sintered
thoria and used in interpreting differences in sintering behavior.
KEYWORDS
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