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Page Title: Uranium
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FUEL MATERIALS
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Material Science Volume 2 of 2
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Thorium

FUEL MATERIALS DOE-HDBK-1017/2-93 Plant Materials Plutonium dioxide  (PuO2) is  the  most common  form used  as  a  reactor fuel.   PuO2  is  not  used alone  as  a  reactor  fuel;  it  is  mixed  with  uranium  dioxide.    This  mixture  ranges  from  20% plutonium dioxide for fast reactor fuel to 3% to 5% for thermal reactors. Plutonium-239  can  serve  as  the  fissile  material  in  both  thermal  and  fast  reactors.    In  thermal reactors,  the plutonium-239 produced  from uranium-238  can provide  a partial  replacement for uranium-235.    The  use  of  plutonium-239  in  fast  reactors  is  much  more  economical,  because breeding takes place, which results in the production of more plutonium-239 than is consumed by fission. Uranium The  basic  nuclear  reactor  fuel  materials  used  today  are  the  elements  uranium  and  thorium. Uranium has played the major role for reasons of both availability and usability.   It can be used in the form of pure metal, as a constituent of an alloy, or as an oxide, carbide, or other suitable compound.   Although metallic uranium was used as a fuel in early reactors, its poor mechanical properties  and  great  susceptibility  to  radiation  damage  excludes  its  use  for  commercial  power reactors   today. The   source   material   for   uranium   is   uranium   ore,   which   after   mining   is concentrated in a "mill" and shipped as an impure form of the oxide U3O8 (yellow cake).   The material is then shipped to a materials plant where it is converted to uranium dioxide (UO2), a ceramic, which is the most common fuel material used in commercial power reactors.   The UO2 is  formed  into  pellets  and  clad  with  zircaloy  (water-cooled  reactors)  or  stainless  steel  (fast sodium-cooled reactors) to form fuel elements.  The cladding protects the fuel from attack by the coolant, prevents the escape of fission products, and provides geometrical integrity. Oxide  fuels  have  demonstrated  very  satisfactory  high-temperature,  dimensional,  and  radiation stability  and  chemical  compatibility  with  cladding  metals  and  coolant  in  light-water  reactor service.    Under  the  much  more  severe  conditions  in  a  fast  reactor,  however,  even  inert  UO2 begins to respond to its environment in a manner that is often detrimental to fuel performance. Uranium  dioxide  is  almost exclusively  used  in  light-water-moderated  reactors  (LWR).   Mixed oxides of uranium and plutonium are used in liquid-metal fast breeder reactors (LMFBR). The  major  disadvantages  of  oxide  fuels  that  have  prompted  the  investigation  of  other  fuel materials  are  their  low  uranium  density  and  low  thermal  conductivity  that  decreases  with increasing temperatures.   The low density of uranium atoms in UO2 requires a larger core for a given amount of fissile species than if a fuel of higher uranium density were used.   The increase in  reactor  size  with  no  increase  in  power  raises  the  capital  cost  of  the  reactor.    Poor  thermal conductivity  means  that  the  centerline  temperature  of  the  fuel  and  the  temperature  difference between the center and the surface of the fuel rod must be very large for sufficient fission heat be  extracted  from  a unit  of  fuel to  make  electric power  production  economical.   On  the other hand,  central  fuel  temperatures  close  to  the  melting  point  have  a  beneficial  fission  product scouring effect on the fuel. MS-05 Page 6 Rev. 0

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