Method of retarding irradiated nuclear vessel crack initiation a

Induced nuclear reactions: processes – systems – and elements – Reactor protection or damage prevention – Shield or barrier between radiation or heat source and...

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376249, 220592, 522232, G21C 1300

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active

055639275

ABSTRACT:
An irradiated steel pressurized nuclear reactor pressure vessel 10 is provided with a crack initiation retarding and crack extension retarding reactor vessel integrity girdle 20 or 120 made up of shoes or links 22, with mechanical take up joints (26 to 34a or 126 to 134a). Instead of pivoted shoe links 22, the girdle 120 may be made using constricting roller chain links 122. In any event, crack initiation and crack extension which may result from pressure loading or vessel material embrittled in the beltline region by neutron bombardment is retarded by maintenance of a prestress under the nozzles during all periods of operation of the reactor.

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"A Guide To Nuclear Power Technology", John Wiley and Sons, Inc., New York, N.Y., Reprint Edition 1992, (Chapter 10, pp. 403-449).

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