Thermal load reducing system for nuclear reactor vessel

Induced nuclear reactions: processes – systems – and elements – Reactor protection or damage prevention – Pressure suppression and relief

Reexamination Certificate

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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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