Korea Atomic Energy Research Institute

www.kaeri.re.kr
Daejeon, South Korea

The Korea Atomic Energy Research Institute in Daejeon, South Korea was established in 1959 as the sole professional research-oriented institute for nuclear power in South Korea, and has rapidly built a reputation for research and development in various fields. In 1995 KAERI designed and constructed the nation's first multipurpose research reactor, HANARO based on the Canadian MAPLE design. KAERI is dedicated to finding a wide range of uses for atomic energy. As examples, KAERI developed the world's first radiopharmaceutical "Milican injection" for treating liver cancer. KAERI has made significant contributions to the nation's nuclear technology development. After Korea achieved self-reliance in nuclear core technologies, KAERI have transferred highly developed technologies to local industries for practical applications. The Korea Institute of Nuclear Safety , responsible for supporting the government in regulatory and licensing works, and the Nuclear Environment Technology Institute, responsible for low and medium level radioactive waste management, are also originally spin-offs from KAERI. KAERI established the present KEPCO E&C , responsible for not only the architect engineering works of nuclear power plants, but also for designing nuclear steam supply systems. KAERI also established the present Korea Nuclear Fuel Co., Ltd., responsible for designing and manufacturing PWR as well as PHWR fuels. Wikipedia.

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Patent
Korea Atomic Energy Research Institute, Korea Hydro and Nuclear Power Co. | Date: 2017-01-23

Provided are a nuclear fuel rod for fast reactors that includes a metallic fuel slug coated with a protective coating layer and a fabrication method thereof. The nuclear fuel rod for fast reactors that includes a surface treated metallic fuel slug and a cladding tube according to the present invention has an excellent effect of stabilizing components of the metallic fuel slug and fission products or impurities, because the interdiffusion between the metallic fuel slug and the cladding tube does not occur. Also, since the uniform coating on the surface of the metallic fuel slug may be facilitated and fabrication costs may be significantly reduced in comparison to a typical technique of using a functional material for preventing the interdiffusion at an inner surface of the cladding tube, it may be suitable for fabricating the nuclear fuel rod for fast reactors.


Patent
Korea Atomic Energy Research Institute | Date: 2016-11-11

Disclosed are a system and method for preventing and monitoring a leakage of water from a tank liner at a storage tank having: a concrete reservoir; the tank liner made up of a wall liner that is formed by coupling a plurality of first panels and is attached to an inner wall of the concrete reservoir, and a floor liner that is formed by coupling a plurality of second panels, is attached to a floor of the concrete reservoir, and is coupled to the wall liner by welding; a leaking water collecting plate formed by welding a plurality of third panels and inserted between the floor liner and the floor of the concrete reservoir; and an edge leaking water collecting channel buried in an edge of the storage tank and configured to collect leaking water discharged between the floor liner and the leaking water collecting plate.


Patent
Korea Atomic Energy Research Institute, Korea Hydro and Nuclear Power Co. | Date: 2017-01-23

Provided are a nuclear fuel rod for fast reactors that includes a metallic fuel slug coated with a protective coating layer and a fabrication method thereof. The nuclear fuel rod for fast reactors that includes a surface treated metallic fuel slug and a cladding tube according to the present invention has an excellent effect of stabilizing components of the metallic fuel slug and fission products or impurities, because the interdiffusion between the metallic fuel slug and the cladding tube does not occur. Also, since the uniform coating on the surface of the metallic fuel slug may be facilitated and fabrication costs may be significantly reduced in comparison to a typical technique of using a functional material for preventing the interdiffusion at an inner surface of the cladding tube, it may be suitable for fabricating the nuclear fuel rod for fast reactors.


Patent
Korea Atomic Energy Research Institute | Date: 2017-02-22

The present invention relates to a cutting process simulation method and a system thereof which can efficiently optimize the decommissioning process of a nuclear facility, thereby saving costs and time and ensuring safety in the decommissioning process. The cutting process simulation system, according to one embodiment of the present invention, may comprise: a display unit: and a control unit which cuts a cutting target in a nuclear facility by using a design program, displays the cut shape on the display unit, and predicts the amount of secondary waste generated in the process of cutting the cutting target.


Patent
Korea Atomic Energy Research Institute | Date: 2015-07-22

The present invention relates to a passive heat removal system which circulates cooling fluid via a main water supply line, connected to the lower inlet of a steam generator, and a main steam pipe, connected to the top outlet of the steam generator, to the steam generator, in order to remove sensible heat of a reactor coolant system and residual heat of a core, the passive heat removal system comprising: supplementary equipment for receiving surplus cooling fluid or supplying supplementary cooling fluid in order to maintain the flow rate of the cooling fluid within a predetermined range, wherein the supplementary equipment comprises: a supplementary tank, installed at a predetermined height between the lower inlet and the top outlet of the steam generator, for receiving the surplus cooling fluid or supplying the supplementary cooling fluid, passively, depending on the flow rate of the cooling fluid; a first connection pipe, connected to the main steam pipe and the supplementary tank, for forming a flow path to allow the cooling fluid, exhausted to the main steam pipe from the steam generator, to flow to the supplementary tank; and a second connection pipe connected to the supplementary tank and the main water supply pipe for forming a supply flow path of the supplementary cooling fluid supplied from the supplementary tank.


Patent
Korea Atomic Energy Research Institute | Date: 2016-11-22

A method and an apparatus for the treatment of waste ion exchange resins containing radionuclides, and the present invention relates to a method for the treatment of waste ion exchange resins containing radionuclides by the stepwise heat treatment and an apparatus to accomplish the said method.


The present invention provides an ionic polymer membrane prepared by irradiating the compound represented by formula 1 and an ionic polymer. The ionic polymer membrane of the present invention has the advantage of excellent processability, low production costs, high ion exchange capacity and high durability. Also, the method for preparing the ionic polymer membrane of the invention not only facilitates the production of the ionic polymer membrane in a 3-dimensional network structure which has high ion exchange capacity and high dimensional stability but also makes it easy to produce membranes in various forms and sizes by using the composition itself as a coating solution with using the commercialized inexpensive ionic polymer without additional high-risk multi-step introduction process of ionic exchange group. In the aspect of preparation process, the simplicity of the process and suitable for the mass-production, and the production cost is reduced by saving the processing time as much as minimum 1/15 (56 min.) in comparison to the processing time of the conventional thermal-crosslinking (1 hour).


Patent
Korea Atomic Energy Research Institute | Date: 2014-10-21

The present invention relates to a cutting process simulation method and a system thereof which can efficiently optimize the decommissioning process of a nuclear facility, thereby saving costs and time and ensuring safety in the decommissioning process. The cutting process simulation system, according to one embodiment of the present invention, may comprise: a display unit: and a control unit which cuts a cutting target in a nuclear facility by using a design program, displays the cut shape on the display unit, and predicts the amount of secondary waste generated in the process of cutting the cutting target.


Patent
Korea Atomic Energy Research Institute | Date: 2016-08-29

A smart bed for a radiation therapy includes a rest to which radiation is applied, a support structure having one end fixed to the ground and having four columns disposed to be spaced apart from one another, centered around the rest, four connection parts extending from one side of each of the columns and connected to each vertex of the rest, and lengthened or shortened through a linear actuator provided on one side thereof, and a controller independently controlling each of the linear actuators to implement movement of the rest, wherein rotational and translational movement of the rest is implemented such that radiation is applied to each position of an upper surface and a lower surface of the rest.


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 200C/min or less; and ordering the cooled Alloy 690 in the temperature range of 410-520C.

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