Method for testing the soluble contents of nuclear reactor coolant water
AssigneeGeneral Electric Company
InventorsRobert J. Law, Michel N. Robles, Dane T. Snyder
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Abstract
Water testing means for monitoring circulating water coolant in service within a water cooled nuclear reactor system is disclosed. The invention is an improvement in such water testing means and comprises a preconditioning of selected sample specimens of water with a pH adjustment for inhibiting unbalancing an equilibrium in solution of water coolant with ion solutes.
Claims15
An improved method of testing for soluble contents of coolant circulating through a water cooled and moderate nuclear fission reactor cooling system which inhibits unbalancing of an equilibrium in solutions of the coolant with metal ion solutes derived from fluid carrying metal conduits, consisting essentially of the combinations of steps of:
- alternately withdrawing samples of coolant water circulating through a nuclear reactor cooling system from several different locations within the system for analysis:
- conveying the alternately withdrawn coolant water samples through a network of fluid carrying metal conduits to an analytical testing apparatus for ascertaining any ion composition and concentration of each of the alternately withdrawn water coolant samples;
- adjusting the pH of each withdrawn water coolant sample to an acidic state prior to passing each withdrawn water coolant sample through the analytical testing apparatus by introducing an acidifying agent into each coolant water sample;
- and determining the soluble contents of each coolant water sample in the analytical testing apparatus.
An improved method of testing for soluble contents of coolant circulating through a water cooled and moderated nuclear fission reactor cooling system which inhibits unbalancing of an equilibrium in solutions of the coolant with metal ion solutes derived from fluid carrying metal conduits, consisting essentially of the combination of steps of:
- alternately withdrawing samples of coolant water circulating through a nuclear reactor cooling system from several different locations for individual analysis;
- conveying the alternately withdrawn coolant water samples through a network of fluid carrying metal conduits to an analytical testing apparatus for ascertaining any ion composition and concentration of each alternately withdrawn water coolant sample;
- adjusting the pH of each withdrawn water coolant sample to an acidic state prior to passing each withdrawn water coolant sample through the analytical testing apparatus by introducing carbon dioxide gas as an acidifying agent into each withdrawn water coolant sample;
- and determining the soluble contents of each withdrawn water coolant sample in the analytical testing apparatus.
An improved method of testing for soluble contents of coolant circulating through a water cooled and moderated nuclear fission reactor cooling system which inhibits unbalancing of an equilibrium in solutions of the coolant with metal ion solutes derived from fluid carrying metal conduits, consisting essentially of the combination of steps of:
- alternately withdrawing samples of coolant water circulating through a nuclear reactor cooling system from several different locations for individual analysis;
- conveying the alternately withdrawn coolant water samples through a network of fluid carrying metal conduits to an analytical testing apparatus for ascertaining any ion composition and concentration of each alternately withdrawn water coolant sample;
- adjusting the pH of each withdrawn water coolant sample to an acidic pH in the range of about 3.0 to about 5.5 prior to passing a sample of each withdrawn water coolant sample through the analytical testing apparatus by introducing an acidifying agent into each withdrawn water coolant sample;
- and determining the soluble contents of each withdrawn water coolant sample in the analytical testing apparatus.
An improved method of testing for soluble contents of coolant circulating through a water cooled and moderated nuclear fission reactor cooling system which inhibits unbalancing of an equilibrium in solutions of the coolant with metal ion solutes derived from fluid carrying metal conduits, consisting essentially of the combination of steps of:
- alternately withdrawing samples of coolant water circulating through a nuclear reactor cooling system from several different locations for individual analysis;
- conveying the alternately withdrawn coolant samples through a network of fluid carrying metal conduits to an analytical testing apparatus for ascertaining any ion composition and concentration of each alternately withdrawn water coolant sample;
- adjusting the pH of each withdrawn water coolant sample to an acidic pH in the range of about 4.0 to about 4.5 prior to passing each withdrawn water coolant sample through the analytical testing apparatus by introducing carbon dioxide gas as an acidifying agent into each withdrawn water coolant sample;
- and determining the soluble contents of each withdrawn coolant sample in the analytical testing apparatus.
Dependencies are inferred from the claim text.