TRANSPORT BASKET FOR DEFECTIVE SPENT NUCLEAR FUEL OF HEAVY-WATER REACTOR

    公开(公告)号:EP4235699A1

    公开(公告)日:2023-08-30

    申请号:EP21883290.5

    申请日:2021-10-21

    IPC分类号: G21F5/008 G21F5/12 F16B5/02

    摘要: The present invention relates to a transport basket for defective spent nuclear fuel of a heavy water reactor and, more particularly, to a transport basket for defective spent nuclear fuel of a heavy water reactor that can reduce the burden of a personnel when handling spent nuclear fuel in a test facility by minimizing a storage space and maximizing a thickness such that only a predetermined amount of spent nuclear fuel for soundness evaluation in the test facility can be transported. To this end, provided is a transport basket for defective spent nuclear fuel of a heavy water reactor, comprising: a basket body having a storage space and an internal support that partitions the storage space; a fuel pocket that is installed on one side of each storage space partitioned through the internal support and is installed so as to be rotatable toward the other side of the storage space, and has a detachable groove open in an upward direction such that a fuel case containing the spent nuclear fuel can be detached therefrom; and a cover that opens and closes the storage space of the basket body and is screwed to the basket body.

    REACTOR COOLING SYSTEM FOR DISASTER ACCIDENT, AND REACTOR COOLING METHOD USING SAME

    公开(公告)号:EP4187554A1

    公开(公告)日:2023-05-31

    申请号:EP21847083.9

    申请日:2021-07-12

    摘要: The present invention relates to a reactor cooling system for a disaster accident, and a reactor cooling method using same, and, more specifically, to a reactor cooling system and a reactor cooling method using same, the system performing heat exchange on high-temperature contaminated water generated at a nuclear power generation facility when a serious accident occurs, so as to use same as a coolant, and thus can maximally suppress the discharge of contaminated water to the sea. To this end, provided is the reactor cooling system for a disaster accident, comprising: the nuclear power generation facility; a seawater storage tank for providing a water storage space so that seawater can be stored therein; a seawater inflow path and a seawater discharge path provided on one side and the other side, respectively, of the seawater storage tank, the seawater inflow path providing a pipeline that enables the seawater to flow into the seawater storage tank, and the seawater discharge path providing a pipeline that enables the seawater to be discharged from the seawater storage tank to the sea; a heat exchanger provided in an accommodation space of the seawater storage tank; a contaminated water supply path providing a pipeline that enables the contaminated water generated at the nuclear power generation facility to be transferred to the heat exchanger when a serious accident occurs; and a contaminated water discharge path which is provided between the heat exchanger and the nuclear power generation facility, and which provides a pipeline that enables the contaminated water having been heat exchanged with the seawater of the seawater storage tank through the heat exchanger to be discharged to the nuclear power generation facility.

    EXPOSURE DOSE MEASUREMENT SIMULATION APPARATUS AND METHOD

    公开(公告)号:EP4141757A1

    公开(公告)日:2023-03-01

    申请号:EP21792882.9

    申请日:2021-03-10

    IPC分类号: G06Q10/04 G21C23/00

    摘要: An exposure dose measurement simulation device according to an embodiment of the present invention includes: a virtual work area generating portion that generates a virtual work area corresponding to a work area of a radiation facility; and an exposure dose prediction portion that predicts an exposure dose of a worker positioned in the virtual work area, wherein the exposure dose prediction portion includes a database portion that includes first data on a spatial dose rate of the radiation facility and second data on a position of a radiation source in the radiation facility, and a first exposure dose calculation portion that calculates the exposure dose of the worker positioned in the virtual work area using the first data and second data.

    METHOD AND SYSTEM FOR INTELLIGENT MONITORING OF STATE OF NUCLEAR POWER PLANT

    公开(公告)号:EP4113539A1

    公开(公告)日:2023-01-04

    申请号:EP20922024.3

    申请日:2020-12-18

    IPC分类号: G21C17/00 G21D3/04

    摘要: In order to provide a method and a system for monitoring a state of a nuclear power plant capable of reducing a state prediction error of a sensor during startup, full power, shut down operation of a nuclear power plant, and of providing an early warning, without an error alarm by remotely and automatically diagnosing the state of a sensor, device, system and power plant, the present invention comprises: a first layer that compares a sensor measurement value and a device measurement value with predicted values so as to detect anomalies of the sensor and the device; a second layer that classifies a type of the sensor and diagnoses the presence or absence of an anomaly of the sensor on the basis of an anomaly value of the sensor provided from the first layer; and a third layer that diagnoses a state of the nuclear power plant on the basis of detection and diagnosis results for the sensor provided from the first and second layers and an anomaly result for the device provided from the first layer.

    LOAD-FOLLOWING OPERATION SYSTEM INCLUDING BORON CONCENTRATION ADJUSTMENT AND LOAD-FOLLOWING OPERATION METHOD USING SAME

    公开(公告)号:EP3848942A1

    公开(公告)日:2021-07-14

    申请号:EP19857722.3

    申请日:2019-09-03

    发明人: YU, Keuk Jong

    IPC分类号: G21C7/06

    摘要: The present invention relates to a load-following operation system and operation method for a nuclear reactor load-following operation including boron concentration adjustment. The operation system according to the present disclosure comprises: a boron concentration control unit for adjusting a boron concentration, the boron concentration control unit comprising a boron concentration determination unit for determining a boron concentration on the basis of input first operation information and a boron concentration adjustment for adjusting a boron concentration according to the determination of the boron concentration determination unit; a control rod control unit for controlling a control rod, the control rod control unit comprising a control rod determination for determining a control of the control rod on the basis of input second operation information and a control rod driving unit for controlling the control rod according to the determination of the control rod determination unit.