JP2016145726A5

JP2016145726A5 -

Info

Publication number: JP2016145726A5
Application number: JP2015022207A
Authority: JP
Filing date: 2015-02-06
Publication date: 2017-03-23
Anticipated expiration: 2035-02-06

Claims

The emergency core cooling system has at least three sections, and the first section of the emergency core cooling system has a low pressure having a reactor isolation cooling system having a turbine-driven high-pressure water injection pump and an electrically driven low-pressure water injection pump. Consists of a water injection system and an emergency power supply, water is supplied into the reactor pressure vessel via the first piping and first water supply piping by the reactor isolation cooling system, and the second piping is supplied by the low pressure water injection system. An emergency core cooling system of a nuclear power plant that supplies water into a reactor pressure vessel via a second water supply pipe and has an automatic pressure reducing system shared by the three divided emergency core cooling systems. And
A break detection device for detecting breakage of the first water supply pipe or the second water supply pipe, a first valve provided in a second pipe of the low-pressure water injection system, and an upstream side of the first valve; A tie line pipe connecting the first pipe and the second pipe via a second valve;
The rupture detection device detects a rupture of the second water supply pipe, operates the first valve and the second valve, and connects the tie line pipe and the first water supply pipe from the low pressure water injection system. An emergency core cooling system for a nuclear power plant characterized in that water is supplied into the reactor pressure vessel via

An emergency core cooling system for a nuclear power plant according to claim 1,
The first-section emergency core cooling system supplies the water into the reactor pressure vessel via the first piping and the first feed water piping by the reactor isolation cooling system, and the three-section emergency core cooling system. An automatic depressurization system shared by the core cooling system is operated, and after depressurization in the reactor pressure vessel, water is supplied into the reactor pressure vessel from the low-pressure water injection system via the tie line piping and the first water supply piping. An emergency core cooling system for nuclear power plants.

An emergency core cooling system for a nuclear power plant according to claim 1 or 2,
Among the three-sectioned emergency core cooling systems, the emergency core cooling systems other than the first section include a high-pressure core injection system that can inject reactor coolant even when the inside of the reactor pressure vessel is at a high pressure, It consists of a low-pressure water injection system that injects reactor coolant when the pressure inside the reactor pressure vessel is low,
The low pressure water injection pump of the first section can be used even when it is difficult to cool by the emergency core cooling system other than the first section and the second water supply pipe is broken. An emergency core cooling system for nuclear power plants.

An emergency core cooling system for a nuclear power plant according to any one of claims 1 to 3,
An emergency core of a nuclear power plant comprising any one of a motor-driven valve, a compressed air-driven valve, a nitrogen-driven valve, a manual valve, and the like that can be opened and closed as the operable first valve and the second valve Cooling system.

An emergency core cooling system for a nuclear power plant according to any one of claims 1 to 4,
A breakage detection device for detecting breakage of the first water supply pipe or the second water supply pipe is provided between the first water supply pipe and the second water supply pipe and measures a state quantity in the water supply pipe. An emergency core cooling system for a nuclear power plant using a signal from a measuring instrument, and comprising any one of a differential pressure gauge, a differential flow meter, a thermometer, a radiation concentration meter, and the like as the instrument.

An emergency core cooling system for a nuclear power plant according to claim 5,
The differential pressure gauge is formed so that the reactor isolation cooling system side is a high pressure side and the low pressure water injection system side is a low pressure side, and when the second water supply pipe is broken, water injection of the low pressure water injection system is performed by downscaling. An emergency core cooling system for nuclear power plants, characterized in that the route does not change.

An emergency core cooling system for a nuclear power plant according to claim 5 or claim 6,
The differential pressure gauge is located in the reactor containment vessel, and is installed closer to the reactor containment vessel than the rising portions of the first water supply pipe and the second water supply pipe. Emergency core cooling system for nuclear power plants.

An emergency core cooling system for a nuclear power plant according to any one of claims 5 to 7,
The differential pressure gauge sets the set value of the water injection route switching differential pressure to be equal to or higher than the pressure difference between the first water supply pipe and the second water supply pipe during normal operation, and the water injection route is not switched during normal operation. An emergency core cooling system for nuclear power plants.

An emergency core cooling system for a nuclear power plant according to claim 8,
The differential pressure gauge, the reactor pressure near vessel of the second water supply pipe, and even assuming a pipe rupture in the second reactor pressure vessel side of the rising portion of the water supply pipe, the difference pressure detection An emergency core cooling system for nuclear power plants, which is possible.

An emergency core cooling system for a nuclear power plant according to any one of claims 1 to 9,
The break detecting device, so as not to cause the first water supply pipe or the second fracture operation the wrong the breakage detection device is also in consideration of shock waves which may occur immediately after the water supply pipe, breakage after quiet talk time An emergency core cooling system for a nuclear power plant comprising a timer set to operate after a while.

An emergency core cooling system for a nuclear power plant according to any one of claims 1 to 10,
The differential pressure gauge employs a 2 out of 4 theory to prevent erroneous measurement, and an emergency core cooling system for a nuclear power plant.