Induced nuclear reactions: processes – systems – and elements – Reactor protection or damage prevention – Pressure suppression and relief
Reexamination Certificate
2007-06-04
2011-10-11
Palabrica, Ricardo (Department: 3663)
Induced nuclear reactions: processes, systems, and elements
Reactor protection or damage prevention
Pressure suppression and relief
C376S287000, C376S277000, C376S289000
Reexamination Certificate
active
08036335
ABSTRACT:
In a reactor vessel thermal load reducing system near the surface level of a coolant, the present invention is characterized in that a heat conductive member is installed not contacting the reactor vessel wall in an area above and below the coolant liquid surface, and the heat conducting member is attached to a guard vessel, the heat conducting member being made of material of good heat conductivity.
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Ando Masanori
Kasahara Naoto
Japan Nuclear Cycle Development Institute
Palabrica Ricardo
Westerman Hattori Daniels & Adrian LLP
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