Abstract: The present invention relates to a passive molten core cooling device comprising: a reactor vessel; a core catcher positioned at the lower part of the reactor vessel; a flow path structure positioned at the lower part of the core catcher, and having a coolant flow path filled with a coolant; and a coolant tank communicating with the flow path structure through a first pipe and supplying coolant to the coolant flow path through the first pipe, wherein the coolant flow path is divided into a first flow path adjacent to the core catcher and a second flow path spaced from the core catcher, and the first flow path and the second flow path are connected to each other

Abstract: The present invention relates to a Marinelli beaker correction container for stable radionuclide analysis, the Marinelli beaker correction container including: a container body having a diameter corresponding to a detector mounting part provided at a lower part of the Marinelli beaker, and being insertedly mounted to the detector mounting part; a detector coupling groove being formed at a lower part of the container body with an inner diameter corresponding to a diameter of the spectroscopy system detector, and allowing the Marinelli beaker to be mounted on the spectroscopy system detector by insertedly mounting the spectroscopy system detector to the detector coupling groove; and a ventilation hole being vertically formed through a center of a top surface of the container body, and allowing the container body to be smoothly mounted or dismounted due to air ventilation when the container body is mounted to or dismounted from the detector mounting part.

Abstract: The present invention relates to an apparatus and method for monitoring the water level within a pipe. The present specification discloses a method for monitoring the water level in a pipe, comprising the steps of: transmitting ultrasonic waves generated at a plurality of ultrasonic transducers, which are spaced apart from each other in the outside of the pipe, to the inside of the pipe via a solid contact medium; checking whether echoes corresponding to respective ultrasonic waves are present; and determining the water level on the basis of the presence of the echoes corresponding to the respective ultrasonic waves. The present invention can simply and conveniently install water level monitoring equipment within a pipe on a long term basis using a nondestructive method.

Abstract: In order to provide a coolant tank for preventing a containment from being recompressed and reheated during the cooling of the containment upon occurrence of a design basis accident and a severe accident and a passive containment cooling system comprising the same, the present invention comprises: a storage tank for storing a coolant; a division part which is arranged within the storage tank and divides the inside of the storage tank into a first storage tank and a second storage tank to separate the coolant; a first heat exchanger which is extended from the storage tank to the containment and cools the containment on the basis of the coolant; and a unidirectional valve which is provided on the division part and allows the coolant of the second storage tank to be introduced into the first storage tank when the water level of the first storage tank is reduced.

Abstract: Disclosed is a detection method for DNA repair-related genes which respond to low-level radiation. This invention provides a detection method for a DNA repair-related gene which responds to low-level radiation, including the steps of (1) breeding AKR/J mice, as a thymus cancer model, and normal ICR mice in a low-dose radiation environment; (2) collecting thymuses from the AKR/J thymus cancer mouse model and the normal ICR mice which have been bred at the step (1); (3) analyzing genes in the thymuses collected at the step (2); (4) detecting, among the genes analyzed at the step (3), a DNA repair-associated gene expressed commonly or differentially in the AKR/J thymus cancer mouse model and the normal ICR mice; and (5) amplifying the gene detected at the step (4) and measuring the expression level thereof.

Abstract: The present invention relates to a passive nitrogen injecting device for a nuclear reactor coolant pump, the device comprising: a nitrogen supply unit for supplying nitrogen; a pressure control valve for controlling the supply of nitrogen from the nitrogen supply unit according to pressure; an accumulator for filling the nitrogen supplied through the pressure control valve at a set pressure, and supplying the filled nitrogen in the event that an accident involving coolant loss occurs; and an isolation valve for controlling the supply of the nitrogen from the accumulator into a seal housing of a nuclear reactor coolant pump. The present invention uses an accumulator so as to be able to supply nitrogen by using the pressure in the accumulator without the supply of external power in the event of an accident involving coolant loss, and therefore has the effect of being able to improve safety.

Abstract: A method for detecting genes sensitive to low-level ionizing radiation and genes detected by the method. More specifically, genes sensitive to low-level ionizing radiation and related to suppressing thymic cancer, discovered in a carcinogenic entity and verified in a normal entity are detected by subjecting a cancerous AKR/J mouse and a normal ICR mouse to low-level radiation. Thymus is collected therefrom, immunogenic and apoptotic genes are classified via microarray processing of the thymus. The genes are amplified and the levels of gene expression are measured. Thus, a gene having a specific reaction to radiation can be accurately detected by preventing the interference of confounding variables.

Abstract: Disclosed is a correction container of a Marinelli, wherein a first groove is formed in the lower portion of the container body formed with a diameter corresponding to the inner diameter of the lower surface of the Marinelli beaker, to be attached to a detector of a detecting system for nuclide analysis, a second groove having a diameter smaller than that of the first groove is formed on the upper portion, and an intake and exhaust hole is formed through the first groove to the second groove. According to the present invention, a Marinelli beaker covers a upper portion of a container body to wrap around it, and a detector of a nuclide detecting device is inserted into a first groove formed in a lower portion of the container body. By means of the correction container according to the present invention, the distance between the position of radionuclides in the sample in a Marinelli beaker and the detector is maintained constant.

Abstract: The present invention is related to an apparatus and a method for producing fibrous debris of test for a nuclear plant. More particularly, producing fibrous debris of test having the uniform length distribution equal to the fibrous debris collected by a plurality of strainer bags while passing through a strainer in length distribution degree, and conducting a test for evaluating the influence of debris in the core due to a loss of coolant accident based on the produced fibrous debris for testing, thereby ensuring reproducibility of a test by the fibrous debris of test having a uniform length distribution and, thereby producing conservative experimental data.

Abstract: A nuclear fuel simulation method is provided that includes: step (a) for receiving an input of data on the order in which nuclear fuels are moved; step (b) for extracting, from the data, information on nuclear fuels, the coordinates of locations from which nuclear fuels are unloaded, and the coordinates of locations into which nuclear fuels are loaded; and step (c) for simulating the information extracted in step (b) according to a flowchart of the data. The present invention has an advantage in that it is possible to accurately and quickly verify all fuel movement works requiring the unloading and loading of nuclear fuels by receiving an input of a huge amount of data on the order in which nuclear fuels are moved and systematically verify an error that may occur during a simulation according to a flowchart, which enables the workload of about three man-days, required per cycle for each reactor, to be done in three man-hours, thereby achieving a significant reduction in working time.

Abstract: An apparatus for measuring the temperature of a glass melting furnace includes a glass window part which has a transparent glass window and is mounted to a temperature measurement hole of the glass melting furnace and extended outward from the glass melting furnace, and a camera part which has a thermographic camera to capture image of an inside of the glass melting furnace through the glass window part. The measuring apparatus supplies cooling gas into the through hole in upper and lower directions, thereby preventing the surface of the glass window from being covered with fumes, and confines heated gases and fumes to the glass melting furnace.

Abstract: A method for managing the movements of nuclear fuels is provided that includes: (a) loading a storage status map in which storage racks of an SFPR where spent fuels are stored and an NFS where new fuels are stored are mapped; (b) assigning the storage locations of nuclear fuels and the colors thereof in the storage status map; (c) receiving a pattern type input of tasks for designating the order in which nuclear fuels are moved and the locations to which the nuclear fuels are moved, and generating a movement flowchart; and (d) updating the storage status map according to the level at which the movement flowchart has progressed. The present invention has an advantage in that it is possible to quickly create a nuclear fuel movement flowchart by automating all fuel movement works requiring the unloading and loading of nuclear fuels, which enables the workload of about 30 man-days, required per cycle for each reactor, to be done in three man-hours, thereby achieving a significant reduction in working time.

Abstract: A uranium dioxide nuclear fuel pellet has about 50 to about 400 ?M (with respect to a 3-dimentional size) microcells formed of a ceramic material having a chemical attraction with fission products generated in the nuclear fuel pellet to absorb and trap the fission products, such that the extraction of the fission product may be retrained in a normal operation condition and that the performance of the nuclear fuel may be enhanced by mitigating PCI. In addition, highly radioactive fission products including Cs and I having a large generation amount or a long half-life enough to affect the environments can be trapped in the pellet in an accident condition, without being released outside.

Abstract: The present invention relates to an ultrasonic inspection device for small bore pipes comprising: a first arc-shaped frame part and a second arc-shaped frame part which surround the circumference of a pipe when combined with the pipe, and which have one side thereof rotationally connected to each other by means of a rotary connecting pin; an adjustment part that connects the other side of the first arc-shaped frame part and the other side of the second arc-shaped frame part to each other and is capable of adjusting the diameter of the bore formed by the first arc-shaped frame part and the second arc-shaped frame part according to the diameter of the pipe; a probe fixing part for fixing a probe to the first arc-shaped frame part such that the probe comes into contact with the surface of the pipe; an encoder part which is provided to the second arc-shaped frame part and maintains an encoder at a predetermined distance from the pipe; and a plurality of roller parts which are provided to the first arc-shaped fram

Abstract: Disclosed is a correction container of a Marinelli, wherein a first groove is formed in the lower portion of the container body formed with a diameter corresponding to the inner diameter of the lower surface of the Marinelli beaker, to be attached to a detector of a detecting system for nuclide analysis, a second groove having a diameter smaller than that of the first groove is formed on the upper portion, and an intake and exhaust hole is formed through the first groove to the second groove. According to the present invention, a Marinelli beaker covers a upper portion of a container body to wrap around it, and a detector of a nuclide detecting device is inserted into a first groove formed in a lower portion of the container body. By means of the correction container according to the present invention, the distance between the position of radionuclides in the sample in a Marinelli beaker and the detector is maintained constant.

Abstract: This invention relates to the vitrification of radioactive waste products. According to this invention, a glass composition that is suitable for mixed waste products, which include flammable waste products, such as gloves, working clothes, plastic waste, and rubber, and low-level radioactive waste products, and a method of vitrifying the mixed waste products using the same are provided to significantly reduce the volume of radioactive waste products and to vitrify the mixed waste products using the glass composition, which is suitable for vitrifying the mixed waste products, thereby maximally delaying or completely preventing the leakage of radioactive materials from a glass solidified body.

Abstract: This invention relates to the vitrification of radioactive waste products. According to this invention, a glass composition, which is suitable for flammable waste products, such as gloves, working clothes, plastic waste, and rubber, and a method of vitrifying the flammable waste products using the same are provided to significantly reduce the volume of radioactive waste products and to vitrify the flammable waste products using the glass composition, which is suitable for vitrifying the flammable waste products, thereby maximally delaying or completely preventing the leakage of radioactive materials from a molten solidified body.

Abstract: A remote attaching and detaching device which includes a camera module to substitute a worker's vision in such an environment where the worker's direct access to the in-cell is extremely limited or impossible. In a remote attaching and detaching device including a camera module for monitoring operating environment of a slave arm of a remote robot working in hazardous environment, the remote attaching and detaching device includes a fixing module fixed to a proximity of a gripper provided on the slave arm, and the camera module is attachable to and detachable from the fixing module, and provides visual in-cell information or situation about surroundings of the gripper.

Abstract: A nuclear power plant includes a nuclear reactor containment structure housing a nuclear reactor, a pressure vessel containing condensed water therein and having a receiving space located lower than a bottom of the containment structure, a release pipe connecting the containment structure to the pressure vessel such that water vapor and fission products generated in the containment structure in the event of an accident is capable of flowing into the pressure vessel, and a recovery pipe connecting the pressure vessel to the containment structure such that the condensed water received in the pressure vessel is capable of flowing into the containment structure. When a level of the condensed water received in the pressure vessel is higher than a water level in the containment structure, the condensed water flows from the pressure vessel toward the containment structure by a water head difference.