Abstract: The present disclosure relates to a radioactive material reduction facility, including a containment, a boundary section provided inside the compartment to partition an inner space of the containment into a first space for accommodating a reactor coolant system and a second space formed between the first space and the containment, and surround the reactor coolant system to prevent radioactive material discharged from the reactor coolant system or a line connected to the reactor coolant system inside the first space from being directly discharged into the second space during an accident, an in-containment refueling water storage tank (IRWST) installed between the first space and the second space and formed to accommodate refueling water, and a first discharge line formed to guide the flow of steam and radioactive material formed in the first space inside the boundary section into the in-containment refueling water storage tank.

Abstract: The present invention relates to a method for preparing an herbal composition with increased fat-soluble polyphenols, an herbal composition prepared by the method, and a use of the composition. The herbal composition with increased fat-soluble polyphenols of the present invention is characterized by the significantly increased content of fat-soluble polyphenols including decursin, compared with the herbal composition of comparative example, and also demonstrates a significant anti-oxidative activity, immune cell activating effect, and cancer cell growth inhibitory effect, significantly reduces renal toxicity and liver toxicity induced by the anticancer agent cisplatin back so as to be almost normal condition, and significantly inhibits the intestinal crypt loss caused by irradiation, compared with the herbal composition of comparative example.

Abstract: A coolant recirculation system of a nuclear power plant is provided that may include: a reactor vessel configured to accommodate a reactor core and a reactor coolant therein; a steam generator configured to transfer a gas, converted from a liquid phase to a gaseous phase by exchanging heat with the reactor coolant, to a turbine system; a pressurizer configured to control pressure of the reactor coolant in the reactor vessel; a primary system pressure reducing valve located above the pressurizer and configured to open at a predetermined pressure to discharge the reactor coolant into a containment building for rapid depressurization; and a moisture separator connected to the primary system pressure reducing valve to separate moisture. The moisture separator may separate the reactor coolant into a gaseous phase and a liquid phase. Then, the liquid phase reactor coolant may be returned to the reactor vessel to be recirculated.

Abstract: Provided are a system and method for reducing the atmospheric release of radioactive materials caused by a severe accident. The system includes a steam generator disposed in a containment building, configured to generate steam by using heat of a coolant heated in a nuclear reactor, and connected to a turbine through a main steam line, a decontamination tank connected to the main steam line through a connection line and containing decontamination water for decontaminating the steam delivered from the steam generator and reducing atmospheric release of radioactive materials when a severe accident occurs, and a depressurizing power generation unit disposed on the connection line and configured to generate emergency power while depressurizing the steam delivered from the steam generator toward the decontamination tank when the severe accident occurs.

Abstract: Disclosed is a nondestructive inspection system includes: a radiation source system generating different types of radiations and irradiating the generated different types of radiations toward an inspection object; a detector system detecting each of the radiations transmitted through the inspection object; a transfer system varying a position of the inspection object such that the radiations generated by the radiation source system are irradiated to the inspection object; and an image system generating an image regarding the inspection object on the basis of a detection result from the detector system, wherein the radiation source system comprises: an electron gun generating an electron beam; an electron accelerator accelerating the electron beam generated by the electron gun; and a target system selectively generating at least one of various types of radiations according to variables when the electron beam accelerated by the electron accelerator is irradiated thereto.

Abstract: The present invention discloses a passive cooling system of a containment building, to which a plate-type heat exchanger is applied. A passive cooling system of a containment building comprises: a containment building; a plate-type heat exchanger provided to at least one of the inside and the outside of the containment building and comprising channels respectively provided to the both sides of a plate so as to be arranged dividedly from each other such that the plate-type heat exchanger carries out mutual heat exchange between the internal atmosphere of the containment building and a heat exchange fluid while maintaining a pressure boundary; and a pipe connected to the plate-type heat exchanger by penetrating the containment building so as to form the path of the internal atmosphere of the containment building or the heat exchange fluid.

Abstract: The present invention relates to a composition for controlling plant diseases containing a limonene derivative as an active ingredient. In the present invention, the limonene derivatives have an effect of inhibiting the growth of Xanthomonas oryzae pv. Oryzae (Xoo), which is a pathogen mediating bacterial leaf blight, and Magnaporthe oryzae, which is a pathogen mediating rice blast, and it was confirmed in an experiment with respect to inhibition using volatility (i.e., in a state not being in direct contact with Xoo or M. oryzae) that the limonene derivatives have a growth inhibitory effect. Accordingly, the limonene derivatives have an inhibitory effect against the growth of Xoo and thus they can be effectively used as a composition for controlling plant diseases.

Abstract: The present invention relates to a method for manufacturing Alloy 690 ordered alloy to be used in a steam generator tube serving as a heat exchanger in a nuclear power plant (hereinafter, referred to as NPP), and Alloy 690 ordered alloy manufactured thereby, and provides a method for manufacturing Alloy 690 ordered alloy with improved thermal conductivity, and Alloy 690 ordered alloy manufactured thereby, the method comprising the steps of: solution-annealing Alloy 690; cooling the solution-annealed Alloy 690 to a first temperature of 200° C./min or less; and ordering the cooled Alloy 690 in the temperature range of 410-520° C.

Abstract: The present invention relates to a curcumin derivative, a method for producing same, and a photo-acoustic imaging agent comprising the curcumin derivative for detecting beta-amyloid plaque. The curcumin derivative, expressed by chemical formula 1, according to the present invention exhibits superb selective bonding with beta-amyloid, thereby allowing beta-amyloid to be detected by means of an optical or photo-acoustic imaging methods, and, particularly, the curcumin derivative can highly effectively detect photo-acoustic signals with almost no noise by reacting to irradiation of light having a particular wavelength range, and thus can be useful as a composition for detecting beta-amyloid and for diagnosing diseases caused by excessive production of beta-amyloid.

Abstract: Disclosed is a nuclear power plant which drives a Stirling engine by means of heat generated in nuclear power plant safety systems during an accident, uses the resulting power directly or generates electric power so as to supply the power to the safety systems, and thus can improve economic efficiency as well as the reliability of safety systems, such as a passive safety system, by operating the safety systems without an emergency diesel generator or external electric power.

Abstract: A radioactive waste container, for storing and transporting a radioactive waste, includes a container body, a cover and a water drain unit. The cover is fastened to the container body. The water drain unit is provided at the container body without protruding to an outside of the container body and configured to selectively drain water in the container body.

Abstract: An in-vessel cooling and power generation system according to the present disclosure may include a small scale reactor vessel, a heat exchange section provided inside the reactor vessel, and formed to supply supercritical fluid to receive heat from a reactor coolant system in the reactor vessel, an electric power production section comprising a supercritical turbine formed to produce electric energy using the energy of the supercritical fluid whose temperature has increased while receiving heat from the reactor coolant system, a cooling section configured to exchange heat with the supercritical fluid discharged after driving the supercritical turbine to shrink a volume of the supercritical fluid, wherein the supercritical fluid that has received heat from the reactor coolant system in the heat exchange section is formed to circulate through the electric power production section, and the cooling section.

Abstract: The present invention relates to a technology for treating radioactive liquid waste containing a hardly degradable compound, and more specifically, to a technology for treating radioactive liquid waste containing a material such as an organic decontamination agent, an inorganic decontamination agent, liquid scintillation counter liquid waste, and the like generated at nuclear power plants, nuclear facilities, facilities at which radiation (radioactivity) is used, and the like. The method for treating radioactive liquid waste of the present invention includes adding two or more selected from the group consisting of a metal ion, an oxidizing agent, air, oxygen, or nitrous oxide, and a semiconductor to radioactive liquid waste to prepare a pre-treatment solution, and irradiating the pre-treatment solution with radiation.

Abstract: A reactor cooling and power generation system according to the present disclosure may include a reactor vessel, a heat exchange section formed to receive heat generated from a core inside the reactor vessel through a fluid, and an electric power production section including a Sterling engine formed to produce electric energy using the energy of the fluid whose temperature has increased while receiving the heat of the reactor, wherein the system is formed to circulate the fluid that has received heat from the core in the heat exchange section through the electric power production section, and operate even during a normal operation and during an accident of the nuclear power plant to produce electric power. Furthermore, the reactor cooling and power generation system according to the present disclosure may be continuously operated not only during a normal operation but also during an accident to perform reactor cooling, and produce emergency power, thereby improving the system reliability.

Abstract: A volume reduction treatment method able to reduce the volume of the final disposal waste of a spent uranium catalyst. As a result, the disposal cost of the spent uranium catalyst is able to be reduced and the utilization of waste repositories are able to be improved.

Abstract: An apparatus for detecting leakage of a pipe by using a distance difference-frequency analysis includes: vibration detecting sensors, which are mounted at a predetermined distance in a longitudinal direction of a pipe and are configured to measure vibration signals of the pipe; and a control unit, which is configured to calculate a cross-correlation function by using the vibration signals, to reveal time delay information in the frequency domain by calculating time-delay frequency analysis diagram for the cross-correlation function, to calculate a distance difference-frequency analysis diagram by applying compensation conversion using frequency-dependent propagation speed information to the time-delay frequency analysis diagram, and to detect a leakage component of the pipe in the distance difference-frequency analysis diagram.

Abstract: A reactor cooling and power generation system according to the present invention includes a reactor vessel, a heat exchange section to receive heat generated from a core inside the reactor vessel through a fluid, and a power production section having a thermoelectric element configured to produce electric energy using energy of the fluid whose temperature has increased while receiving the heat of the reactor, wherein the system is configured to allow the fluid that has received the heat from the core to circulate through the power production section, and to operate even during an accident as well as during a normal operation of a nuclear power plant to produce electric power. Also, the reactor cooling and power generation system according to the present invention may continuously operate during an accident as well as a normal operation so as to cool the reactor and produce emergency power, thereby improving system reliability.

Abstract: Disclosed herein is a different radiation measuring sensor and a manufacturing method thereof. The different radiation measuring sensor includes a semiconductor substrate, at least one bottom electrode formed on a bottom surface of the semiconductor, a plurality of top electrodes formed on a top surface of the semiconductor and electrically connected to the bottom electrode, and sensing films formed on the plurality of top electrodes and reacting with different materials.

Abstract: The present invention relates to an apparatus for treating a spent ion exchange resin, the apparatus including: a graphite reactor for receiving a spent ion exchange resin including a radionuclide-containing ion exchange group therein; a graphite heater for heating the spent ion exchange resin; an inert gas injection tube for injecting an inert gas into the graphite reactor for drying and carbonizing the spent ion exchange resin; and a halogenation gas injection tube for injecting a halogen-containing gas or a halogenation compound gas into the graphite reactor for halogenation of a compound derived from the radionuclide-containing ion exchange group, and to a method for treating a spent ion exchange resin, the method including steps of (A) drying a spent ion exchange resin including a radionuclide-containing ion exchange group; (B) producing a compound derived from the radionuclide-containing ion exchange group by separating the radionuclide-containing ion exchange group from the dried spent ion exchange res

Abstract: An apparatus for detecting leakage of a pipe by using a distance difference-frequency analysis includes: vibration detecting sensors, which are mounted at a predetermined distance in a longitudinal direction of a pipe and are configured to measure vibration signals of the pipe; and a control unit, which is configured to calculate a cross-correlation function by using the vibration signals, to reveal time delay information in the frequency domain by calculating time-delay frequency analysis diagram for the cross-correlation function, to calculate a distance difference-frequency analysis diagram by applying compensation conversion using frequency-dependent propagation speed information to the time-delay frequency analysis diagram, and to detect a leakage component of the pipe in the distance difference-frequency analysis diagram.