KR-102963081-B1 - Waste resin drying device for nuclear power plant waste
Abstract
The present invention relates to a waste resin drying device for nuclear waste, comprising: a movable part consisting of a chassis equipped with wheels and a housing mounted on the upper part of the chassis and having an internal space formed therein; a drying container having an internal space formed therein and an opening formed on the upper part, in which waste resin of nuclear waste is stored; a drying head part housed within the housing and drawn out to the outside to be coupled with the drying container; and a fluid circulation part provided within the housing and connected to the drying head part to supply high-temperature air, comprising an air heater that supplies high-temperature air, a filter box that purifies the high-temperature air recovered from the drying head part, a wastewater suction pump that absorbs moisture from the drying container, and a wastewater storage tank that stores the absorbed moisture.
Inventors
- 이운장
Assignees
- 주식회사 오리온이엔씨
Dates
- Publication Date
- 20260511
- Application Date
- 20240723
Claims (5)
- A movable part comprising a chassis equipped with wheels and a housing mounted on the upper part of the chassis and having a space formed inside; A drying container in which waste resin of nuclear waste is stored, with a space formed inside and an opening formed at the top; A drying head portion that is housed within the above-mentioned housing and drawn out to the outside to be coupled with the above-mentioned drying container; and A fluid circulation unit comprising an air heater provided within the above-mentioned housing and connected to the drying head unit to supply high-temperature air, a filter box for purifying the high-temperature air recovered from the drying head unit, a wastewater suction pump for absorbing moisture from the drying tank, and a wastewater storage tank for storing the absorbed moisture; Includes, The above drying head A cover coupled to the upper opening of the above drying container; A stirrer having a driving source formed on the upper part of the above cover, a blower tube connected to the driving source and vertically mounted on the lower part of the above cover, and stirring blades formed on the outer surface of the blower tube; A suction tube connected to the lower part of the above cover and sucking up moisture from the drying tank; A plug mounting portion formed with a water suction plug mounted on the upper part of the above cover, communicating with the suction tube and having a water suction pipe connected to absorb moisture within the drying tank, a water discharge plug that discharges moisture within the drying tank, a hot air inlet that supplies high-temperature air into the blower tube to heat the inside of the drying tank, and a hot air outlet that sucks in and discharges air inside the drying tank; and A waste resin inlet tube formed to penetrate the above cover and be exposed at the bottom, and connected to communicate with a waste resin injection inlet provided in the plug mounting part; A waste resin drying device for nuclear waste characterized by including
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- In Article 1, A passage is formed inside the blower tube, and a plurality of nozzle holes are formed on the outer surface, and A waste resin drying device for nuclear waste, characterized by including a blower motor mounted on the upper part of the above cover to inject air into the passage of the above blower tube.
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Description
Waste resin drying device for nuclear power plant waste The present invention relates to a waste resin drying device for nuclear power plant waste. In general, light water or heavy water reactors used in nuclear power plants utilize light water or heavy water as a moderator and coolant, respectively. In nuclear power generation using a light water reactor, the primary coolant heated by energy generated from the nuclear fuel is sent to a steam generator connected to the cooling system to heat the secondary coolant, and the resulting steam is used to operate a turbine to produce electricity. The primary and secondary coolants circulate through their respective systems and are reinjected into the reactor or steam generator. However, since they are contaminated by fission products or fine impurities generated as the nuclear fuel undergoes fission, they need to be filtered before being reinjected into the reactor or steam generator. The primary coolant, which passes directly through the inside of the reactor, is highly exposed to radiation generated as the nuclear fuel undergoes fission, whereas the secondary coolant cools the primary coolant injected into the steam generator, so it is not as severely exposed to radiation compared to the primary coolant. Therefore, the waste resin used to filter the primary coolant is classified as high-level waste when it reaches the end of its lifespan due to severe radioactive contamination, and is dried using the SRDS (Spent Resin Drying System), sealed in an HIC (High Integrity Container), and stored in a radioactive waste storage facility. The waste resin used to filter the secondary coolant is also treated in the same or similar manner as the waste resin used to filter the primary coolant. Waste resin refers to ion exchange resin used to remove radionuclides during the process of treating liquids such as heavy water. It contains the radioisotope carbon-14. As it was intermediate-level radioactive waste with high radioactivity concentration and large volume, it was impossible to dispose of it at the Gyeongju Radioactive Waste Disposal Facility. Currently, it is being stored separately in storage tanks within the power plant for an extended period. There was a problem in that piling up waste resin and allowing it to air dry took too much time, and the waste resin located deep inside did not dry properly. Korean Registered Utility Model Publication No. 20-0411349 discloses a "radioactive sludge and waste resin drying device." A schematic overview of the prior art invention comprises: a drying chamber equipped with a hopper into which radioactive sludge and waste resin are injected, and an exhaust port through which gas generated upon heating is discharged; a first geared motor having a first gear and a second geared motor having a second gear, each provided on one side and the other side of the drying chamber, respectively; a stirring means that is driven by obtaining rotational force from the first and second geared motors and stirs and conveys the radioactive sludge and waste resin; a semi-circular heater bucket located below the stirring means and equipped with an outlet on one side through which the dried sludge and waste resin are discharged; and a heater wire installed inside the heater bucket to generate heat. Meanwhile, conventional technology had the disadvantage of requiring high transportation costs and time because it had to be fixedly installed in a designated location and used, and the waste resin collected at the site had to be transported to the waste resin drying device. FIG. 1 is a perspective view of a waste resin drying device for nuclear waste according to the present invention. FIG. 2 is a perspective view from another direction of a waste resin drying device for nuclear waste according to the present invention. FIG. 3 is a perspective view of the ‘drying head section’ of the waste resin drying device for nuclear waste according to the present invention. FIG. 4 is a cross-sectional perspective view showing the ‘drying tank and drying head section’ of a waste resin drying device for nuclear waste according to the present invention. FIG. 5 is a perspective view showing the combination process of the ‘drying tank and drying head part’ of the waste resin drying device for nuclear waste according to the present invention. Preferred embodiments are described in detail below based on the attached drawings. The embodiments described below are intended to provide a detailed description sufficient for a person skilled in the art to easily practice the invention, and do not imply that the technical scope and concept of the invention are limited thereby. In addition, the size or shape of the components shown in the drawings may be exaggerated for clarity and convenience of explanation, and terms specifically defined in consideration of the configuration and operation of the present invention may vary according to the intent or convention of the user or operator, an