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KR-20260066701-A - DEPRESSURIZATION SYSTEM FOR NUCLEAR REACTOR

KR20260066701AKR 20260066701 AKR20260066701 AKR 20260066701AKR-20260066701-A

Abstract

To provide a nuclear power plant depressurization system that ensures operability when performing depressurization even in a high-temperature environment inside a nuclear power plant, the nuclear power plant depressurization system according to the present invention comprises: a receiving portion connected to a nuclear power plant facility, into which high-pressure steam is introduced from the nuclear power plant facility and a steam outlet passage is formed through which the high-pressure steam is discharged; a first opening/closing member having one end disposed inside the receiving portion to open and close the steam outlet passage; a pressure providing portion having a pressure discharge passage formed through which a high-pressure fluid is discharged and filled inside so that the first opening/closing member closes the steam outlet passage when the nuclear power plant facility is in a normal pressure state; a second opening/closing member having one end disposed inside the pressure providing portion to close the pressure discharge passage when the nuclear power plant facility is in a normal pressure state; and a fluid supply portion that supplies an operating fluid to which the second opening/closing member opens the pressure discharge passage so that the first opening/closing member opens the steam outlet passage and the nuclear power plant facility is depressurized when the nuclear power plant facility is in an overpressure state. Accordingly, the present invention includes the effect of improving the stability of nuclear power plant operation by ensuring operability for performing pressure reduction of the nuclear power plant system when the nuclear power plant system is in an abnormal operating state.

Inventors

  • 하희운
  • 이석호
  • 윤석종
  • 한승주

Assignees

  • 한국수력원자력 주식회사

Dates

Publication Date
20260512
Application Date
20260506

Claims (1)

  1. A receiving section connected to a nuclear power plant facility, through which high-pressure steam flows in from the nuclear power plant facility and a steam outlet is formed through which the high-pressure steam flows out; A first opening/closing member having one end disposed inside the above-mentioned receiving portion to open/close the above-mentioned steam outlet; A pressure providing part in which a pressure discharge path is formed through which the first opening/closing member closes the steam discharge path when the above nuclear power plant facility is in a normal pressure state, and the pressure discharge path is formed through which the high-pressure fluid is discharged; A second opening/closing member having one end disposed inside the pressure providing part and closing the pressure release path when the nuclear power plant facility is in a normal pressure state; A fluid supply unit that supplies an operating fluid such that when the above nuclear power plant facility is in an overpressure state, the first opening/closing member opens the steam outlet so that the nuclear power plant facility is depressurized, and the second opening/closing member opens the pressure release path; and It includes a pilot operating unit configured to transmit the high-pressure steam to the second opening/closing member according to the pressure change of the high-pressure steam transmitted from the receiving member, so that when the nuclear power plant facility is in an overpressure state, the second opening/closing member opens the pressure release passage by the high-pressure steam. The above second opening/closing member is A first rod positioned inside the pressure supply unit at one end to close the above pressure release path, and A portion provided at the other end of the first rod and transmitted from the pilot operating part It includes a rod support that is configured to open the pressure release path of the first rod by means of high-pressure steam, and The above pilot operating unit is, A pilot frame that forms a pilot space for receiving the high-pressure steam transmitted from the receiving portion, and forms a pressure transmission path for transmitting the high-pressure steam from the pilot space to the load support, It includes a pilot opening/closing member provided inside the pilot frame to close the pressure transmission path and to open the pressure transmission path according to a pressure change of the high-pressure steam accommodated in the pilot space. The above-mentioned pilot opening/closing member is, An opening/closing body for opening and closing the above pressure transmission path, and A housing provided inside the pilot frame to form the pilot space inside the pilot frame, connected to the opening/closing body to move together inside the pilot frame, and configured such that the opening/closing body opens the pressure transmission path by a pressure change of high-pressure steam contained in the pilot space, and A nuclear power plant depressurization system comprising an elastic member that provides pressure to the housing to pressurize the opening/closing body, thereby causing the opening/closing body to close the pressure transmission path.

Description

Depressurization System for Nuclear Reactor The present invention relates to a nuclear power plant pressure reduction system, and more specifically, to a nuclear power plant pressure reduction system that reduces the pressure of a nuclear power plant system when overpressure occurs in the nuclear power plant system. Generally, it is important to maintain the pressure of the nuclear power plant system in a nuclear power plant. The pressure of the nuclear power plant system can change depending on the operating conditions, and in certain cases, an overpressure condition may occur. Accordingly, nuclear power plants are equipped with pressure reduction facilities to reduce the pressure of the nuclear power plant system in order to prevent accidents caused by overpressure. Prior art regarding such pressure reduction equipment is disclosed in Korean Registered Patent Publication No. 10-1535479 (Reactor coolant system pressure reduction system and nuclear power plant equipped with the same, July 3, 2015). The above-described invention can perform pressure reduction by opening an outlet so that a portion of the high-pressure steam of the nuclear power plant facility is discharged when overpressure occurs in the nuclear power plant facility. The depressurization equipment performs depressurization by classifying the nuclear power plant system into normal or abnormal operating states. In the case of an abnormal operating state, depressurization is carried out by an operator assessing the status of the nuclear power plant system and directly controlling the depressurization equipment. Conventional depressurization equipment was placed inside a containment vessel and performed depressurization using a fluid. However, there was a problem in that the fluid could change due to the high-temperature atmosphere inside the containment vessel, which could lead to reduced operability and consequently lower the reliability of the depressurization equipment. FIG. 1 is a conceptual diagram showing a depressurization system of a nuclear power plant facility according to the present embodiment. Figure 2 is an enlarged perspective view of A in Figure 1. Figure 3 is an enlarged perspective view of B in Figure 1. FIG. 4 is a conceptual diagram showing that the nuclear power plant depressurization system according to the present embodiment performs depressurization of the nuclear power plant system when the nuclear power plant system is in a normal operating state. FIG. 5 is a conceptual diagram showing that the nuclear power plant depressurization system according to the present embodiment performs depressurization of the nuclear power plant system when the nuclear power plant system is in an abnormal operating state. FIG. 6 is a conceptual diagram showing the recovery of the working fluid supplied by the fluid supply unit of the nuclear power plant depressurization system according to the present embodiment to the operating unit. Embodiments of the present invention will be described in detail below with reference to the attached drawings. However, the embodiments disclosed below are not limited to those disclosed below and may be implemented in various forms; the embodiments provided are merely intended to ensure that the disclosure of the present invention is complete and to fully inform those skilled in the art of the scope of the invention. The shapes of elements in the drawings may be exaggerated for clearer explanation, and elements indicated by the same reference numeral in the drawings represent the same element. FIG. 1 is a conceptual diagram showing a depressurization system of a nuclear power plant facility according to the present embodiment. As illustrated in FIG. 1, the nuclear power plant depressurization system (100) according to the present embodiment is connected to the nuclear power plant facility (10) and performs depressurization when the pressure of the nuclear power plant system exceeds the reference pressure. Here, the nuclear power plant depressurization system (100) can perform depressurization when overpressure occurs in the nuclear power plant system in either a normal operating state or an abnormal operating state. In a normal operating state, overpressure may occur when an operator controls the nuclear power plant facility of the nuclear power plant system. In an abnormal operating state, overpressure may occur due to damage to a specific nuclear power plant facility or abnormal operation in the nuclear power plant system. The nuclear power plant pressure reduction system (100) can detect pressure changes in the nuclear power plant system when the nuclear power plant system is in a normal operating state and automatically perform pressure reduction when the pressure exceeds the reference pressure. Additionally, the nuclear power plant pressure reduction system (100) can perform pressure reduction under the control of an operator when the nuclear power plant system is in an abnormal operating state. This n