Patent Number: 
Section: claims

1. A method of early sensing of water leakage, through chemical concentration monitoring, in a nuclear reactor system using a liquid metal and molten salt, the method, implemented by a computer, comprising:measuring an electrical conductivity of a first channel and a second channel of a steam generator or a heat exchanger, the first channel including an outlet 1 and an outlet 2 and the second channel including an inlet;performing at least one of a dilution correction and a temperature compensation with respect to the measured electrical conductivity;calculating a first difference value between a corrected electrical conductivity of the outlet 1 and a corrected electrical conductivity of the inlet based on a method using a Wheatstone Bridge circuit;calculating a second difference value between a corrected electrical conductivity of the outlet 2 and the electrical conductivity of the inlet based on the method using the Wheatstone Bridge circuit;calculating an identification value associated with the water leakage in the steam generator or the heat exchanger by summing a first comparison value and a second comparison value, the first comparison value being outputted by comparing a predetermined threshold value with the calculated first difference value and the second comparison value being outputted by comparing the predetermined threshold value with the calculated second difference value;attempting to sense water leakage by comparing the calculated identification value and a reference value; anddetermining that the water leakage is sensed when the identification value is greater than the reference value, in which case a leakage alarm is raised; anddetermining that no water leakage is sensed when the identification value is less than or equal to the reference value,wherein the first comparison value is one of 0, 1 and the first difference value, and the second comparison value is one of 0, 1 and the second difference value. 2. The method of claim 1, wherein:the first channel comprises an m (m being a natural number) number of outlets,the second channel comprises an n (n being a natural number) number of inlets, andthe measuring of the electrical conductivity comprises measuring an electrical conductivity of each of the m number of outlets and the n number of inlets. 3. The method of claim 2, wherein the calculating of the difference value comprises:computing a difference value between an electrical conductivity of a single random outlet of the m number of outlets and an electrical conductivity of a single random inlet of the n number of inlet. 4. The method of claim 1:wherein the performing of the dilution correction or the temperature compensation comprises:correcting the measured electrical conductivity to be consistent with a standard temperature or a standard dilution which are used for determining when water has leaked. 5. The method of claim 1, wherein the steam generator or the heat exchanger included in the nuclear reactor system using the liquid metal and the molten salt which is any one of a liquid metal reactor, a sodium cooled fast reactor, a nuclear transmutation, a pressurized water reactor, and a heavy water reactor.