13 results about "Containment building" patented technology

Device and Method for Maintaining a Pressure Reactor Containment The present invention relates to a maintenance device (10) for a pressure reactor containment, comprising a connecting fitting (120) on a wall (20) of the containment, said connecting fitting (120) extending in a longitudinal direction (X) between an internal base (55) and an external base (60) and comprising: a) an insertion portion (65) intended to be positioned in a receiving recess (90) machined in the wall (20) of the containment, b) an external portion (70) intended to be positioned outside (30) of the containment and comprising a support element (105) intended to be placed opposite the wall (20) of the containment on a periphery (P) of the receiving recess (90), a fluid conduit (75) extending through the connecting fitting (120), a groove (88) of reception of a compression seal (100) being provided in the insertion portion,the maintenance device (10) comprising means for fixing said connecting branch (120) to the wall (20). Figure for the abbreviation: 4,

Disclosed is a method for dismantling a D2O tank of a heavy water reactor installed on an inner wall of a containment building and surrounded by a concrete structure, the method including cutting and opening a front surface of the concrete structure so as to dismantle the D2O tank, descending the D2O Tank by using an dedicated dismantling apparatus, and taking the D2O tank out of the containment building by using a crane, and a dismantling apparatus.

The utility model provides a kind of safety shell ring corridor's ventilation system, the safety shell ring corridor's ventilation system includes the first exhaust system, second exhaust system and third exhaust system for gas flow of safety shell ring corridor and safety shell outside. Among them, first exhaust system is set in first fire compartment, second exhaust system is set in second fire compartment, and first fire compartment and second fire compartment are physically separated. By designing two independent and mutually redundant first exhaust system and second exhaust system, for accident condition, collect the gas leakage from inner layer safety shell to safety shell ring corridor and the gas flow in safety shell ring corridor from outer layer safety shell, to reduce the radioactive gas leakage amount in safety shell ring corridor as far as possible, ensure the working stability of entire ventilation system. While third exhaust system maintains the negative pressure in safety shell ring corridor not less than design reference under normal condition.

Disclosed is a method for dismantling metal equipment of a heat transport system in a containment building at a nuclear power plant, the metal equipment including a heat transport pump, a steam generator, a pressurizer, a condenser, and a D2O tank, including: a first dismantling step of dismantling the heat transport pump; a second dismantling step of dismantling the steam generator after the first dismantling step; a third dismantling step of dismantling the pressurizer after the second dismantling step; and a fourth dismantling step of dismantling the condenser and the D2O tank after the third dismantling step.

The rainproof system of the nuclear island containment building integration platform and the construction method of the rainproof system aim at solving the problem that no rainproof equipment exists in a top discharging area of an existing integration platform, and safety risks exist. The plate turnover device comprises a plurality of plate turnover devices which are arranged on the top of a blanking area of the integrated platform in the radial direction of the axis, each plate turnover device comprises at least one pair of main plate turnover mechanism and auxiliary plate turnover mechanism which are oppositely arranged and arranged in the radial direction, and the main plate turnover mechanism and the auxiliary plate turnover mechanism are hinged to two adjacent radial steel beams respectively. And the opening and closing of the main turning plate mechanism and the auxiliary turning plate mechanism are respectively controlled by the telescopic rod. The method comprises the steps that after the main turning plate mechanism is closed, the supporting beams can be erected on the adjacent radial steel beams, and after the auxiliary turning plate mechanism is closed, the auxiliary turning plate mechanism is supported on the supporting beams to form a closed rainproof operation space; when horizontal steel bars or large materials need to be transported, the main turnover plate mechanism and the auxiliary turnover plate mechanism of the turnover plate device can be integrally and synchronously opened; the turning plate device can partially open the first turning plate, and the grating plate is exposed to serve as a transfer channel of the vertical steel bars.

The invention relates to an in-containment out-of-core detector system. A device for amplifying a low level signal within a containment building of a nuclear power plant from an off-core nuclear instrumentation system. The system employs a vacuum microelectronic device instead of a conventional preamplifier assembly to position the preamplifier assembly closer to and near the out-of-core detector output.

Method for quantification by Raman spectrometry. This method comprises: - the measurement (TON), in the presence of an excitation beam, of values ​​S3(λ) and S4(λ), at a wavelength λ, respectively, of optical signals S3 and S4 measured with polarization directions, respectively, parallel and perpendicular to a predetermined direction; - the measurement (TOFF), in the absence of the excitation beam, of values ​​S1(λ) and S2(λ), at a wavelength λ, respectively, of optical signals S1 and S2 measured with polarization directions, respectively, parallel and perpendicular to the predetermined direction; and - the determination (230) of a quantity of a gaseous component present inside a containment building of a nuclear reactor, from a difference [(S3(λ) / t3 – S1(λ) / t1] and a difference [S4(λ) / t4 – S2(λ) / t2], where t1, t2, t3 and t4 are the durations of time windows during which the signals S1, S2, S3 and S4 are measured. Fig. 5

Disclosed is a method of testing a leak rate of a reactor containment building, the method including: a division step of dividing the reactor containment building into an upper containment area and a lower containment area by a spectacle flange; a measurement step of measuring the leak rate of the containment building after pressurizing the inside of the containment building at a maximum pressure; and an identification step of identifying whether the leak rate measured in the measurement step satisfies an allowable standard for the leak rate of the containment building.

The embodiment of the invention provides a containment building material testing method and device, electronic equipment and a storage medium, and belongs to the technical field of nuclear power containment. The method comprises the following steps: generating a batch of containment building materials based on preset building material specification information; wherein the containment building material comprises a prestressed steel beam and a concrete test piece; carrying out a drawing pressure test on each containment building material, and continuously increasing the drawing force on the containment building materials until a preset bearing failure condition is reached, so as to obtain drawing experiment data of the containment building materials; constructing a constitutive model of the containment building materials based on the drawing experiment data of the multiple containment building materials; and performing finite element analysis based on the constitutive model of the containment building material to obtain performance evaluation information of the containment building material. According to the embodiment of the invention, the structural behavior of the prestressed containment after the prestressed steel beam is broken can be simulated, and the key parameters of the building materials of the containment can be obtained more accurately.

Underground nuclear installation (10), comprising: - a vertical shaft (12) having, at a lower end, a bottom (12c) and, at an upper end, an opening (12b), - at least one reactor building (26) housed in the shaft, - and which contains at least one nuclear reactor containment building (30) enclosed within said at least one reactor building (26), and / or at least one spent nuclear fuel pool housed in the shaft, - at least one protective slab (20) against external hazards which seals the opening (12b) of the shaft, extending in particular above said at least one reactor building, - one or more pieces of equipment or buildings (b1-b4) arranged on said at least one protective slab (20). Figure for the abbreviation: Fig. 3.

This invention relates to an auxiliary pressure relief device for venting gases within the containment building of a nuclear power plant. The device includes a diversion pipeline and a pressure relief assembly. The diversion pipeline includes an installation end and a connection end. The installation end is detachably connected to and communicates with the containment's exhaust pipe. The inlet end of the pressure relief assembly is connected to and communicates with the connection end, and the exhaust end of the pressure relief assembly is connected to the external environment. At least a portion of the gas flowing through the exhaust pipe can flow along the diversion pipeline to the pressure relief assembly for discharge. When the containment undergoes a pressure test and the test gas within it is discharged, the gas can be discharged simultaneously through the containment's own pressure relief system and this auxiliary pressure relief device, increasing the pressure relief rate, saving time required for the pressure relief process, and thus enabling a more rapid reduction in pressure inside the containment, shortening the containment pressure test period.

An embodiment of the present invention relates to an air treatment device, wherein the air treatment device installed in a containment building includes a body, an inlet for guiding the inflow of air into the body, an adsorber supported on the body, a catalyst spaced apart from the adsorber in the body, and an outlet for guiding the discharge of air from the body.

The present invention relates to a spent fuel storage system for reusing a decommissioned nuclear power plant, the spent fuel storage system comprising: a refueling pool which is located inside a containment building of the decommissioned nuclear power plant and has a storage space filled with cooling water; a storage rack which is installed inside the refueling pool and stores spent fuel; and a residual heat removal unit for cooling the cooling water heated by the spent fuel.