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An accident probability analysis and design evaluation of the gas-cooled fast breeder reactor demonstration plant

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Academic year: 2021

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Figure

FIGURE  1.1  Cutaway View showing the  Principal  Components of  the Nuclear  Steam Supply System within the PCRV.
FIGURE  1.2  A  Simplified  Event  Tree  for a Loss  of  Coolant  Accident  in a Light  Water Reactor  (taken  from reference 5)
FIGURE  1.3  A  Simplified  Fault  Tree  for  the Loss of  Electrical Power  (taken from reference 5)
FIGURE  2.1  Cutaway  View of  300 MW(e) Gas-Cooled Fast  Breeder Reactor  Demonstration  Plant
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