Inhibiting stress corrosion cracking in the primary coolant circ

Details Inhibiting stress corrosion cracking in the primary coolant circ Inhibiting stress corrosion cracking in the primary coolant circ

1990-10-19

1992-04-28

Walsh, Donald P.

Induced nuclear reactions: processes, systems, and elements

Reactor protection or damage prevention

Corrosion or damage prevention

376305, 376312, 376310, G21C 900

Patent

active

051086972

ABSTRACT:
A primary coolant circuit for cooling a nuclear reactor has wetted mechanically stressed nickel base alloy components such as Alloy 600 tubes in steam generators having oxidized surfaces comprising 1-10 w/o zinc, which tubes are inhibited against primary water stress corrosion cracking. The crack initiation times may be delayed by a factor of two in pressurized water nuclear reactors.

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patent: 4756874 (1988-07-01), Ruiz et al.
patent: 4759900 (1988-07-01), Peterson et al.
patent: 4828790 (1989-05-01), Honda et al.
patent: 4877465 (1989-10-01), Donati et al.
patent: 4950449 (1990-08-01), Petersen et al.
patent: 5014760 (1991-05-01), Bombeke et al.
Electric Power Research Institute Report 6168, Jan. 1989.
Electric Power Research Institute Report 4447, Mar. 1986.

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