Abstract: Disclosed is a method for preparing a deNOx catalyst for removing nitrogen oxides (NOx) included in exhaust gas and the like. One embodiment of the present invention discloses a V2O5(vanadium pentoxide)-TiO2(titanium dioxide)-based deNOx catalyst for removing nitrogen oxides through selective catalytic reduction by dry-ball-milling crystalline titanium dioxide (TiO2) powder and crystalline vanadium pentoxide (V2O5) powder.

Abstract: A cooling unit cooling a coil assembly that generates electromagnetic force for driving a nuclear reactor control rod, and including a coil surrounding a driving shaft of the nuclear reactor control rod so as to generate the electromagnetic force; a coil housing surrounding the coil so as to enclose the coil; a cooling shroud-shell forming a cooling flow path between the cooling shroud-shell and the coil housing, whereby a cooling fluid for cooling heat that is generated in the coil passes through the cooling flow path; and a plurality of cooling fins disposed on the cooling flow path in a radial direction so as to allow heat to be effectively exchanged between the coil and the cooling fluid that flows through the cooling flow path.

Abstract: An apparatus for measuring load acting on pipe supports, the apparatus including a load cell which includes a contact portion contacting a pipe, and a measuring portion for measuring load acting from the pipe; and a gap sensor which measures a gap between the pipe support and the pipe, which is generated by a movement of the contact portion, wherein the load acting on the pipe support is measured based on the load measured by the load cell and the gap measured by the gap sensor.

Abstract: A method of reducing errors when calculating a shape annealing function (SAF) of an ex-core detector of a nuclear power plant is provided. The method comprises 3-dimensionally modeling elements of the nuclear power plant comprising a nuclear reactor core, an ex-core detector disposed in a nuclear reactor cavity, and nuclear reactor structures arranged between the nuclear reactor core and the ex-core detector; predicting an arrival position for emitted neutrons, by using a Monte Carlo method when a neutron source arranged at the ex-core detector and neutrons emitted towards the nuclear reactor core, the predicted arrival position indicating where the emitted neutron will arrive at the nuclear reactor core; and producing an SAF based on a correlation between the neutron source arranged at the ex-core detector and the predicted arrival position of the neutrons.

Abstract: An apparatus for controlling an output of a pressure setting signal to automatically control a steam bypass control system includes a pressure setting signal output unit for outputting a pressure setting signal according to a cold leg temperature of a reactor coolant; a first logic value output unit for outputting a first logic value that is changed according to reactor power; a second logic value output unit for outputting a second logic value that is changed according to a temperature difference between an average temperature of the reactor coolant and a reference temperature; a NAND gate circuit unit for outputting an inverse logic value according to the first and second logic values; and a first output control unit for controlling whether to output the pressure setting signal according to the inverse logic value of the NAND gate circuit unit.

Abstract: A system and a method of transforming a gain and an integral time constant of a proportional-integral (PI) controller according to a timer lapse time to relieve an excessive phenomenon of a steam generator level caused by rapid changes in open degrees of a downcomer feed-water valve and an economizer feed-water valve when reactor power transfers between low and high power sections. Accordingly, an excessive phenomenon of a steam generator level is relieved at a transfer time when reactor power transfers between low and high power sections. Therefore, a possibility of a stop of a reactor caused by the excessive phenomenon of the steam generator level is reduced to relieve burden on an operator and improve an operation rate and economic feasibility of a nuclear power plant.

Abstract: A cooling unit cooling a coil assembly that generates electromagnetic force for driving a nuclear reactor control rod, and including a coil surrounding a driving shaft of the nuclear reactor control rod so as to generate the electromagnetic force; a coil housing surrounding the coil so as to enclose the coil; a cooling shroud-shell forming a cooling flow path between the cooling shroud-shell and the coil housing, whereby a cooling fluid for cooling heat that is generated in the coil passes through the cooling flow path; and a plurality of cooling fins disposed on the cooling flow path in a radial direction so as to allow heat to be effectively exchanged between the coil and the cooling fluid that flows through the cooling flow path.

Abstract: Provided is a plant protection system, which determines initiation of protective actions for the plant, and more particularly to the plant protection system including four channels which controls systems that shut down the plant or mitigate consequences of abnormal conditions of the plant by detecting non-permissible plant conditions with the result of bistable logic comparing process parameters with their setpoints assigned to each channel. Accordingly, common mode failure and cyber security vulnerability caused by software are removed since the system is composed of FPGA and other types of hardware without central processing units and software in determining the initiation of plant protective actions.

Abstract: An apparatus for measuring load acting on pipe supports, the apparatus including a load cell which includes a contact portion contacting a pipe, and a measuring portion for measuring load acting from the pipe; and a gap sensor which measures a gap between the pipe support and the pipe, which is generated by a movement of the contact portion, wherein the load acting on the pipe support is measured based on the load measured by the load cell and the gap measured by the gap sensor.