Concrete reactor pressure vessel for a gas cooled nuclear reactor of low capacity
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United States of America Patent
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-
Nov 29, 1988
Issued Date -
N/A
app pub date -
Jan 30, 1987
filing date -
Feb 1, 1986
priority date (Note) -
Expired
status (Latency Note)
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Abstract
A concrete reactor pressure vessel for a low capacity, gas cooled nuclear reactor is provided. To assure the safe containment of the cooling gas in an economical manner and to remove the heat generated in the reactor core, the pressure vessel is equipped with reinforcing or prestressing elements. Cooling gas transfers its heat to a heat exchanger means consisting of the liner of the pressure vessel and cooling pipes mounted on the concrete side of the liner with water flowing through the cooling pipes. The heat exchanger comprises on the secondary side at least two mutually independent systems, each provided with collector pipe means located outside the reactor pressrue vessel for the forerunnings and afterrunnings of the cooling water. Each cooling pipe is connected by means of an inlet and a drain line with the corressponding collector pipe means.
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