Thermal load reducing system for nuclear reactor vessel
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United States of America Patent
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Jul 15, 2003
Grant Date -
May 22, 2003
app pub date -
Apr 5, 2002
filing date -
Nov 16, 2001
priority date (Note) -
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Abstract
The present invention is used to reduce thermal load itself, being the cause to generate stress, which develops near liquid surface in a nuclear reactor wall and to contribute to further improvement of safety. A partition member (5) is arranged above a coolant liquid surface (9) in an annulus space (3) between a reactor vessel (1) and a guard vessel (2), a low-temperature gas is circulated through the annulus space above the partition member to cool down, the gas is circulated through the annulus space from under the coolant liquid surface to the partition member, and the high-temperature gas heated under the coolant liquid surface is used to raise the temperature above the coolant liquid surface.
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