Abstract

The present disclosure relates to a tunnel excavation apparatus to which a spectroscopic analysis method is applied. The tunnel excavation apparatus to which a spectroscopic analysis method is applied may include a ground component measurement unit to measure the properties of the ground which is excavated, and control a first driving unit and a second driving unit to be operated on the basis of the measured information on the ground, thereby preventing cracks from occurring on the ground during a ground excavation process.

IPC Classes  ?

• E21D 9/00 - Tunnels or galleries, with or without liningsMethods or apparatus for making thereofLayout of tunnels or galleries
• E21D 9/11 - Making by using boring or cutting machines with a rotary drilling-head cutting simultaneously the whole cross-section, i.e. full-face machines
• G01N 21/71 - Systems in which the material investigated is excited whereby it emits light or causes a change in wavelength of the incident light thermally excited
• G01N 33/24 - Earth materials

Abstract

The present invention relates to a dry storage container for spent nuclear fuel with improved heat dissipation efficiency of decay heat. The dry storage container for spent nuclear fuel with improved heat dissipation efficiency of decay heat has a plurality of protrusions formed on the outer surface thereof and can thus transfer heat with high efficiency to a buffer material installed on the outer surface thereof.

IPC Classes  ?

• G21F 5/10 - Heat-removal systems, e.g. using circulating fluid or cooling fins
• G21F 5/008 - Containers for fuel elements

Abstract

The present invention relates to a spent nuclear fuel disposal container for recovering decay heat by applying a thermoelectric element. The spent nuclear fuel disposal container for recovering decay heat by applying a thermoelectric element has a power generation module, including the thermoelectric element, installed inside a lid, and thus can generate electrical energy with high efficiency by using heat generated from spent nuclear fuel.

IPC Classes  ?

• G21F 5/10 - Heat-removal systems, e.g. using circulating fluid or cooling fins
• G21C 3/40 - Structural combination of fuel element with thermoelectric element for direct production of electric energy from fission heat
• G21F 5/008 - Containers for fuel elements
• G21F 5/12 - Closures for containersSealing arrangements
• H10N 10/10 - Thermoelectric devices comprising a junction of dissimilar materials, i.e. devices exhibiting Seebeck or Peltier effects operating with only the Peltier or Seebeck effects

Abstract

The present invention relates to a spent nuclear fuel dry container having internal oxygen and moisture removal functions. The spent nuclear fuel dry container having internal oxygen and moisture removal functions comprises an oxygen and moisture removal apparatus including: an oxygen removal unit capable of removing oxygen contained in the internal space; and a moisture removal unit capable of removing moisture contained in the internal space.

IPC Classes  ?

• G21F 5/06 - Details of, or accessories to, the containers
• G21F 5/008 - Containers for fuel elements
• B01D 53/00 - Separation of gases or vapoursRecovering vapours of volatile solvents from gasesChemical or biological purification of waste gases, e.g. engine exhaust gases, smoke, fumes, flue gases or aerosols
• B01D 53/26 - Drying gases or vapours

Abstract

The present invention relates to a tunnel excavation apparatus to which a spectroscopic analysis method is applied. The tunnel excavation apparatus to which a spectroscopic analysis method is applied may comprise a ground component measurement unit to measure the properties of the ground which is excavated, and control a first driving unit and a second driving unit to be operated on the basis of the measured information about the ground, thereby preventing cracks from occurring on the ground during a ground excavation process.

IPC Classes  ?

• E21D 9/093 - Control of the driving shield
• E21D 9/00 - Tunnels or galleries, with or without liningsMethods or apparatus for making thereofLayout of tunnels or galleries
• E21D 9/11 - Making by using boring or cutting machines with a rotary drilling-head cutting simultaneously the whole cross-section, i.e. full-face machines
• G01N 21/71 - Systems in which the material investigated is excited whereby it emits light or causes a change in wavelength of the incident light thermally excited

Abstract

The present invention relates to a constructing method for delaying corrosion of radioactive waste disposal container in concrete disposal vault and, more specifically, to a constructing method for delaying corrosion of radioactive waste disposal container in concrete disposal vault in which backfill, placed to the top, combines pH control capsules, thereby dissolving the pH control capsules in rainwater, and a pH controller, inside, is discharged, thereby preventing decrease of pH of the backfill below 8.5 and delaying corrosion in the disposal containers, upon filling in backfill after placing radioactive waste disposal containers in the concrete vault.

IPC Classes  ?

• G21F 9/30 - Processing

Abstract

The present invention relates to a system for monitoring electrical properties of materials of deep bedrock samples for estimating nuclide movement in disposal site of spent fuel and, more specifically, to a system for monitoring electrical properties of materials of deep bedrock samples for estimating nuclide movement in disposal site of spent fuel which installs a tube wherein ring-shaped potential electrode is formed in multi layers inside a column; adheres the potential electrode to deep bedrock samples by pressing on the external side of the tube while filling the deep bedrock samples inside of the tube; and reproduces real condition of deep bedrock and monitors precisely by measuring electrical resistivity for each location of the deep bedrock samples while injecting nuclide and underground water to the inside the tube.

IPC Classes  ?

• G01N 33/24 - Earth materials
• G01N 27/04 - Investigating or analysing materials by the use of electric, electrochemical, or magnetic means by investigating impedance by investigating resistance
• G01T 1/167 - Measuring radioactive content of objects, e.g. contamination

Abstract

In a spent nuclear fuel canister according to the present invention, an alloy with a specific composition is used, and a mixed filler having fillers, which fill the inside of the canister and have different compositions and shapes, can be applied in a multi-layer structure, so that the spent nuclear fuel can maintain high durability even in a highly corrosive environment resulting from the generation of decay heat of spent nuclear fuel and an environment to which external impact may be applied, and thus has excellent chemical resistance and corrosion resistance. Furthermore, the spent nuclear fuel canister has an effect of facilitating the release of decay heat generated from the spent nuclear fuel located inside the canister and an effect of having a self-sealing function of preventing the radiation emitted from the spent nuclear fuel located inside the canister from being exposed to the outside when the canister is damaged by external impact, corrosion, or the like.

IPC Classes  ?

• G21F 5/008 - Containers for fuel elements
• G21F 5/10 - Heat-removal systems, e.g. using circulating fluid or cooling fins
• G21F 1/08 - MetalsAlloysCermets, i.e. sintered mixtures of ceramics and metals
• G21F 5/12 - Closures for containersSealing arrangements
• C22C 9/04 - Alloys based on copper with zinc as the next major constituent
• C22C 1/00 - Making non-ferrous alloys
• C22C 45/02 - Amorphous alloys with iron as the major constituent

Abstract

According to the present invention, a spent nuclear fuel canister has a composition of a filler filled inside the canister and a mixed filler different in its shape applied in a multilayer structure, such that decay heat generated from spent nuclear fuel inside the canister can easily be dissipated, and the canister has a self-sealing function to keep radiation emitted from the spent nuclear fuel located inside from being released to the outside when the canister suffers damage from external impact, corrosion, etc.

IPC Classes  ?

• G21F 5/008 - Containers for fuel elements
• G21F 5/10 - Heat-removal systems, e.g. using circulating fluid or cooling fins
• G21F 1/08 - MetalsAlloysCermets, i.e. sintered mixtures of ceramics and metals
• G21F 5/12 - Closures for containersSealing arrangements
• C22C 1/00 - Making non-ferrous alloys
• C22C 45/02 - Amorphous alloys with iron as the major constituent

Abstract

Disclosed are a system for three-dimensionally monitoring a multi-layer structure on the basis of various types of sensors, and a method therefor, the system being capable of providing state information in a three-dimensional spatial region to a user by measuring, in real time, anomalies, deformation and the like of a cover layer of a multi-layer structure. The system for three-dimensionally monitoring a multi-layer structure on the basis of various types of sensors comprises the various types of sensors, a data collection-transmission module, a relational DB management system (RDBMS) and a central management module, and provides state information about a cover layer in a three-dimensional spatial region by measuring, in real time, anomalies, deformation and the like of the cover layer formed in a multi-layer structure. The various types of sensors are arranged in the layers of the cover layer, respectively, to detect measurement values in order to measure, in real-time, anomalies and deformation of the cover layer. The data collection-transmission module collects and transmits the measurement values. The RDBMS stores and manages the measurement values transmitted from the data collection-transmission module. The central management module performs the function of calculating the presence/absence of anomalies and current status information about the cover layer through the RDBMS and processing an alarm.

IPC Classes  ?

• G06Q 50/10 - Services
• G06Q 50/26 - Government or public services
• G21F 9/00 - Treating radioactively contaminated materialDecontamination arrangements therefor
• G06F 9/451 - Execution arrangements for user interfaces
• G01D 21/02 - Measuring two or more variables by means not covered by a single other subclass
• G06F 16/28 - Databases characterised by their database models, e.g. relational or object models

Abstract

A three-dimensional distributed monitoring system and method of the present invention have an effect of performing simultaneous monitoring by three-dimensionally distributing sensors, and connecting different types of sensors to each other via one cable so as to receive information of each of the sensors without disturbance and perform monitoring, by comprising: sensor cables to which sensor bundles each including a plurality of different types of sensor objects are connected in a form sharing a power line and a communication line; monitoring system units that control the sensor cables; and a communication unit that receives and transmits sensor information.

IPC Classes  ?

• E21B 47/13 - Means for transmitting measuring-signals or control signals from the well to the surface, or from the surface to the well, e.g. for logging while drilling by electromagnetic energy, e.g. of radio frequency range
• G01V 3/34 - Transmitting data to recording or processing apparatusRecording data

Abstract

The present invention relates to a disposal container and a storage system for high-level radioactive waste and, more specifically, to a disposal container for high-level radioactive waste using multiple barriers and a barrier system using thereof, the disposal container having the multiple barriers consisting of an inner wall made of carbon steel for excellent corrosion resistance and ease of manufacture, a middle wall made of Inconel, which is bonded to a lateral surface of the inner wall, and an outer wall made of copper, which is bonded to a lateral surface of the middle wall.

IPC Classes  ?

• G21F 9/34 - Disposal of solid waste
• G21F 1/08 - MetalsAlloysCermets, i.e. sintered mixtures of ceramics and metals
• G21F 1/12 - Laminated shielding materials
• G21F 5/10 - Heat-removal systems, e.g. using circulating fluid or cooling fins

Abstract

A method for preventing corrosion of a spent nuclear fuel canister by using electrolytic corrosion protection, according to the present invention, has an effect of enabling a semi-permanent operation and, particularly, has effects of preventing oxidation and corrosion problems of a canister made of a metal material, in consideration of various environmental variables that may cause corrosion, and ensuring the structural stability of the canister so as to enable a semi-permanent operation.

IPC Classes  ?

• C23F 13/14 - Material for sacrificial anodes
• C23F 13/22 - Monitoring arrangements therefor
• G21F 5/008 - Containers for fuel elements

Abstract

The present invention relates to a spent nuclear fuel canister, and the spent nuclear fuel canister according to the present invention comprises: a main body having one end that is opened and an internal space in which the spent nuclear fuel is mounted; a cover mounted on the opened one end of the main body and fixed to the main body; a first screw ridge formed on the inner surface at one end of the main body; and a second screw ridge located on the outer side surface of the cover and configured to be fastened with the first screw ridge due to the rotation of the cover.

IPC Classes  ?

• G21F 5/12 - Closures for containersSealing arrangements
• F16B 5/02 - Joining sheets or plates to one another or to strips or bars parallel to them by means of fastening members using screw-thread

Abstract

A spent nuclear fuel canister according to the present invention, although manufactured through 3D printing, has the effect of exhibiting excellent mechanical properties, such as strength, impact resistance, and tensile strength, and minimizing variations in the mechanical properties along the stacking direction. Moreover, the spent nuclear fuel canister, although containing enough neutron shielding material to completely prevent exposure to radioactive nuclides, has the effect of minimizing deterioration of mechanical properties such as toughness and strength. Furthermore, the spent nuclear fuel canister according to the present invention has the effect of having excellent corrosion resistance and durability and high structural stability, as well as exhibiting excellent sealing properties while being free from welding and not requiring external fastening parts such as bolts and nuts. In addition, the spent nuclear fuel canister according to the present invention has a more advantageous effect of securing space by minimizing the thickness of the canister while having sufficient neutron shielding performance.

IPC Classes  ?

• G21F 1/06 - CeramicsGlassesRefractories
• G21F 1/08 - MetalsAlloysCermets, i.e. sintered mixtures of ceramics and metals
• B29C 64/153 - Processes of additive manufacturing using only solid materials using layers of powder being selectively joined, e.g. by selective laser sintering or melting
• B29C 64/268 - Arrangements for irradiation using laser beamsArrangements for irradiation using electron beams [EB]
• B29C 64/106 - Processes of additive manufacturing using only liquids or viscous materials, e.g. depositing a continuous bead of viscous material
• B33Y 10/00 - Processes of additive manufacturing
• B33Y 30/00 - Apparatus for additive manufacturingDetails thereof or accessories therefor
• B33Y 80/00 - Products made by additive manufacturing

Abstract

The present invention provides a disposal container for spent nuclear fuel. The disposal container includes: a metal container (11) in which spent nuclear fuel can be loaded; a ceramic member (20) disposed on the outer surface of the metal container (11); and a polymer member (30) disposed on the outer surface of the ceramic member (20). The present invention provides a disposal container for spent nuclear fuel, which has excellent corrosion resistance and durability, and excellent adhesion between dissimilar materials of metal, ceramic, and polymer, and can improve ease of handling and workability of the container.

IPC Classes  ?

• G21F 5/06 - Details of, or accessories to, the containers
• C23C 4/06 - Metallic material
• C23C 4/129 - Flame spraying
• C08L 69/00 - Compositions of polycarbonatesCompositions of derivatives of polycarbonates
• C08L 23/12 - Polypropene
• C08L 25/06 - Polystyrene

Abstract

A method for preventing corrosion of a spent nuclear fuel canister by using electrolytic corrosion protection, according to the present invention, has an effect of enabling a semi-permanent operation and, particularly, has effects of preventing oxidation and corrosion problems of a canister made of a metal material, in consideration of various environmental variables that can cause corrosion, and ensuring the structural stability of the canister so as to enable a semi-permanent operation.

IPC Classes  ?

• C23F 13/00 - Inhibiting corrosion of metals by anodic or cathodic protection
• G21F 5/008 - Containers for fuel elements
• C23F 13/14 - Material for sacrificial anodes
• C23F 13/22 - Monitoring arrangements therefor

Abstract

The present invention relates to a disposal container and a storage system for high-level radioactive waste and, more specifically, to a disposal container for high-level radioactive waste using multiple barriers and a barrier system using same, the disposal container having the multiple barriers consisting of an inner wall made of carbon steel for excellent corrosion resistance and ease of manufacture, a middle wall made of Inconel, which is bonded to an outer surface of the inner wall, and an outer wall made of copper, which is bonded to an outer surface of the middle wall.

IPC Classes  ?

• G21F 5/10 - Heat-removal systems, e.g. using circulating fluid or cooling fins
• G21F 5/008 - Containers for fuel elements

Abstract

The present invention relates to a guiding device for positioning a radioactive waste drum in a near-surface disposal facility. In detail, a guiding device for positioning a radioactive waste drum at a proper position on a vault bottom or grout bottom in a near-surface disposal facility is installed to provide stowage convenience when radioactive waste drums are stacked, and designates an accurate position in advance so that a radioactive waste drum damaged during an institutional control period is easily dealt with to prevent the effects of the damage from spreading to surrounding drums, so as to improve positional stability of the radioactive waste drum and structural stability thereof after being positioned.

IPC Classes  ?

• G21F 5/005 - Containers for solid radioactive wastes, e.g. for ultimate disposal