Emergency reactor core cooling system, and boiling-ater nuclear power plant

A technology of accident cooling and atomic energy, applied in cooling devices, auxiliary equipment of nuclear power plants, reactors, etc., to avoid system loss of function and minimize the number of systems

Inactive Publication Date: 2013-07-24
KK TOSHIBA
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

), the high-pressure core cooling system 1 and the low-pressure core cooling system 2 in the same safety zone will also lose their function due to the loss of function of the cooling system of the auxiliary equipment of the reactor. Non-reliability-determined problems of cooling systems for reactor auxiliary equipment in three zones

Method used

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  • Emergency reactor core cooling system, and boiling-ater nuclear power plant
  • Emergency reactor core cooling system, and boiling-ater nuclear power plant
  • Emergency reactor core cooling system, and boiling-ater nuclear power plant

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no. 1 approach

[0047] use figure 1 A first embodiment of the core emergency cooling system according to the present invention will be described.

[0048] figure 1 It is a figure which shows the structure of the core emergency cooling system which concerns on the 1st Embodiment of this invention. The core accident cooling system in this embodiment is composed of the first, second, third and fourth safety partitions dedicated to the dynamic core accident cooling system and the fifth safety partition including the static core accident cooling system, a total of five safety partitions . In the first, second, third, and fourth safety zones dedicated to the dynamic core accident cooling system, a low-pressure core cooling system (LPFL) 2 is provided as an electric-driven low-pressure core cooling system, as a A residual heat removal system (RHR) that shares a part of the pump and piping of the system 2 is provided with a residual heat removal system 3 , and a backup diesel generator (EDG) 4 i...

no. 2 approach

[0069] Secondly, figure 2 It is a diagram showing the configuration of a core emergency cooling system according to a second embodiment of the present invention. In this embodiment, only one gas turbine generator 6 is provided as an auxiliary power supply, which is shared in all the safety zones dedicated to the dynamic core emergency cooling system, and can be switched to any of the safety zones dedicated to the dynamic core emergency cooling system. One for power supply. Since it is possible to switch to each dynamic safety zone and supply power from the gas turbine generator 6 , it is possible to switch and supply power from the gas turbine generator 6 to the power supply bus of each dynamic safety zone via the disconnector 7 .

[0070] In the present embodiment configured as described above, the safety against the loss of all AC power sources during the operation of the facility is improved. In addition, the diversity of power sources can be secured even when only four ...

no. 3 approach

[0072] Secondly, image 3 It is a diagram showing the configuration of a core emergency cooling system according to a third embodiment of the present invention. In this embodiment, a turbine-driven Reactor Isolation Cooling System (RCIC) 10 as an auxiliary water supply system is installed in the common system partition. The reactor isolation cooling system 10 works with the main steam of the reactor as the power source, so the standby diesel generator 4 is not needed during operation. In addition, since cooling by the reactor auxiliary equipment cooling system is not required, it can be separately installed in the above-mentioned common system partition.

[0073] In the present embodiment, since the reactor isolation cooling system 10 is present, even if the overflow safety valve is stuck, the water level of the reactor can be safely maintained. Moreover, even if a small fracture cooling material loss accident occurs, the reactor will not be decompressed, and the reactor wat...

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Abstract

An emergency reactor core cooling system is provided with at least four dynamic safety sections each equipped with an electrically-driven dynamic safety system, and at least one static safety section equipped with a static safety system that does not require to be electrically driven. The number of dynamic safety sections is equal to or greater than the number of dynamic safety sections needed during a design basis accident by two and each dynamic safety section is provided with one electrically-driven dynamic safety system. The static safety system is capable of cooling the reactor core without being re-supplied with cooling water from the outside during the time needed for the dynamic safety system subjected to online maintenance to recover when supposing that an accident occurred during online maintenance of one dynamic safety system. An emergency reactor core cooling system for a boiling-water nuclear power plant, wherein it is possible to reduce the size of an emergency power source and the number of electrically-driven systems, and to prevent a plurality of systems from losing the function thereof caused by an auxiliary cooling system losing the function thereof.

Description

technical field [0001] The invention relates to a reactor core accident cooling system and a boiling water type atomic energy equipment equipped with the reactor core accident cooling system. Background technique [0002] [N+1 Security Benchmark and N+2 Security Benchmark] [0003] As the most common safety criterion applied in the design of the emergency core cooling system (ECCS) of the boiling water reactor in the past, there is a single failure criterion. This standard is a safety standard that, when performing a safety assessment of a loss of cooling material accident (LOCA), which is a design basis accident (DBA), even if a failure occurs in one part of the core accident cooling system, at least one system of the reactor Even in a state where the core accident cooling system cannot function, it is required that the required cooling of the core can be sufficiently performed. This is referred to as the N+1 reference in the following description. [0004] Moreover, the...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C15/18
CPCG21D1/02G21C15/18G21D3/06Y02E30/40Y02E30/00Y02E30/30
Inventor 佐藤崇
Owner KK TOSHIBA
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