Method of stress corrosion cracking mitigation for nuclear power plant structural materials

Abstract

The object of this invention is to provide a method for mitigating a stress corrosion cracking of reactor structural material which makes it possible to suppress the rise in the main steam line dose rate without secondary effects such as a rise in the concentration of radioactive cobalt-60, etc. in the reactor water. Hydrogen and a reductive nitrogen compound containing nitrogen having a negative oxidation number (for example, hydrazine) are injected into the core water of boiling water nuclear power plant. By injecting the reductive nitrogen compound containing nitrogen having a negative oxidation number into the core water, the stress corrosion cracking of structural material of reactor can be mitigated without side reactions such as a rise in the concentration of cobalt-60, etc.

1 . A method for mitigating a stress corrosion cracking of structural material in a nuclear power plant, comprising the step of injecting hydrogen and a reductive nitrogen compound containing nitrogen having a negative oxidation number into a reactor water of a boiling water nuclear power plant.  
   
   
       2 . The method for mitigating a stress corrosion cracking of structural material in a nuclear power plant according to  claim 1 , wherein the injection of said reductive nitrogen compound is controlled by using an oxygen concentration and an ammonia concentration in a cooling water as indications.  
   
   
       3 . The method for mitigating a stress corrosion cracking of structural material in a nuclear power plant according to  claim 1 , wherein the injection of said reductive nitrogen compound is stopped when the oxygen concentration in the cooling water has become a prescribed value or less or when the ammonia concentration in the cooling water becomes a prescribed value or more.  
   
   
       4 . The method for mitigating a stress corrosion cracking of structural material in a nuclear power plant according to  claim 1 , wherein the injection of said reductive nitrogen compound is controlled so that the concentration of said reductive nitrogen compound in the cooling water comes to 9.4×10 −6  mol/liter or less.  
   
   
       5 . The method for mitigating a stress corrosion cracking of structural material in a nuclear power plant according to  claim 1 , wherein said reductive nitrogen compound is injected into the cooling water from at least any one system line selected from the group consisting of a reactor water clean up system, a primary loop re-circulation system, an emergency core cooling system and a control rod drive hydraulic system, at the time of start up operation or shut down operation of the reactor.  
   
   
       6 . The method for mitigating a stress corrosion cracking of structural material in a nuclear power plant according to  claim 1 , wherein said reductive nitrogen compound is injected into the cooling water at the time of normal operation of the reactor, from at least one system line selected from the group consisting of a feed water system, a reactor water clean up system, a primary loop re-circulation system, an emergency core cooling system and a control rod drive hydraulic system.  
   
   
       7 . The method for mitigating a stress corrosion cracking of structural material in a nuclear power plant according to  claim 5 , wherein a site of the injection of said reductive nitrogen compound from the reactor water clean up system line is at least one injection connection selected from the group consisting of an injection connection provided on a line connecting the down stream of the filter demineralizer and the reactor pressure vessel and an injection connection provided on the line connecting the down stream of the connection part in the reactor water clean up system line of the sampling line provided for the purpose of measuring water quality at the outlet of filter demineralizer and the reactor pressure vessel.  
   
   
       8 . The method for mitigating a stress corrosion cracking of structural material in a nuclear power plant according to  claim 5 , wherein a site of the injection of said reductive nitrogen compound from the primary loop re-circulation system line is at least one connection selected from the group consisting of a connection provided on the primary loop re-circulation system main line and a sampling line provided for the purpose of measuring the water quality of primary loop re-circulation system.  
   
   
       9 . The method for mitigating a stress corrosion cracking of structural material in a nuclear power plant according to  claim 5 , wherein a site of the injection of said reductive nitrogen compound from the said control rod drive hydraulic system line is an injection connection provided on the upstream of a pump provided on the line connecting the outlet of condensate demineralizer and the control rod drive hydraulic system line.  
   
   
       10 . The method for mitigating a stress corrosion cracking of structural material in a nuclear power plant according to  claim 6 , wherein a site of the injection of the reductive nitrogen compound from said reactor water clean up system line is at least one injection connection selected from the group consisting of an injection connection provided on the line connecting the down stream of filter demineralizer and the reactor pressure vessel and an injection connection provided on the line connecting the down stream of the connection part, on the reactor water clean up system, of the sampling line provided for the purpose of measuring the water quality at the outlet of filter demineralizer and the reactor pressure vessel.  
   
   
       11 . The method for mitigating a stress corrosion cracking of structural material in a nuclear power plant according to  claim 6 , wherein a site of the injection of the reductive nitrogen compound from the primary loop re-circulation system line is at least one connection selected from the group consisting of a connection provided on the Primary Loop re-circulation system main line and a sampling line provided for the purpose of measuring the water quality of primary loop re-circulation system.  
   
   
       12 . The method for mitigating a stress corrosion cracking of structural material in a nuclear power plant according to  claim 6 , wherein a site of the injection of the reductive nitrogen compound from the control rod drive hydraulic system line is an injection connection provided on the up stream of a pump provided on a line connecting the outlet of condensate demineralizer and the reactor control rod drive hydraulic system line.  
   
   
       13 . The method for mitigating a stress corrosion cracking of structural material in a nuclear power plant according to  claim 6 , wherein a site of the injection of the reductive nitrogen compound from the feed water system line is at least any one injection connection selected from the group consisting of an injection connection provided on the line connecting the down stream of feed water heater and reactor pressure vessel and an injection connection provided on a line connecting the down stream of the connection part between the sampling line provided for the purpose of measuring water quality of water feed system and the mother line of feed water system line and the reactor pressure vessel.  
   
   
       14 . The method for mitigating a stress corrosion cracking of structural material in a nuclear power plant according to  claim 1 , wherein said reductive nitrogen compound is at least any one compound selected from the group consisting of hydroxylamine, carbohydrazide, hydrazine, ammonia and diazine.  
   
   
       15 . The method for mitigating a stress corrosion cracking of structural material in a nuclear power plant according to  claim 1 , further including the step of injecting hydrogen into the reactor water until a main steam line dose rate comes to a prescribed value and thereafter injecting said reductive nitrogen compound into the reactor water.  
   
   
       16 . The method for mitigating a stress corrosion cracking of structural material in a nuclear power plant according to  claim 1 , further including the step of injecting an alcohol into the reactor water together with said reductive nitrogen compound.  
   
   
       17 . The method for mitigating a stress corrosion cracking of structural material in a nuclear power plant according to  claim 16 , wherein the injection of said alcohol is controlled by using the electric conductivity of cooling water as an indication.  
   
   
       18 . The method for mitigating a stress corrosion cracking of structural material in a nuclear power plant according to  claim 16 , wherein said alcohol is methyl alcohol.