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Auxiliary steam device

A technology of auxiliary steam and auxiliary steam header, applied in the field of nuclear power, can solve problems such as inability to provide steam in time, avoid dynamic and static friction and the risk of large shaft bending, and ensure the gas supply demand.

Pending Publication Date: 2021-12-24
HUANENG SHANDONG SHIDAO BAY NUCLEAR POWER CO LTD
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0004] Therefore, the technical problem to be solved by the present invention lies in the defect that in the prior art, the high-temperature reactor cannot provide steam in time due to the emergency shutdown of the single reactor operation or the simultaneous stack jump operation of the dual reactor operation.

Method used

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  • Auxiliary steam device

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Embodiment 1

[0042] This embodiment provides an auxiliary steam device, such as figure 1 As shown, it includes: an auxiliary steam mechanism 1 , a heating mechanism 2 , a shaft sealing system 3 , a first isolation device 4 and a second isolation device 5 . Wherein, the auxiliary steam mechanism 1 is connected to the heating mechanism 2 through a pipeline; the first isolation device 4 is arranged between the auxiliary steam mechanism 1 and the heating mechanism 2, and is used to isolate the auxiliary steam mechanism 1 from the heating mechanism 2 , forming different spaces; the heating mechanism 2 is connected to the shaft sealing system 3 through pipes; the second isolation device 5 is arranged between the heating mechanism 2 and the shaft sealing system 3, and is used to connect the heating mechanism 2 and the shaft sealing The system 3 is isolated to form different spaces; the auxiliary steam mechanism 1, the heating mechanism 2, the shaft sealing system 3, the first isolation device 4 a...

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Abstract

The invention discloses an auxiliary steam device. The device comprises an auxiliary steam mechanism suitable for generating steam, a heating mechanism, a shaft seal system, a first isolation device and a second isolation device. The heating mechanism is connected with the auxiliary steam mechanism through a pipeline and is suitable for heating steam generated by the auxiliary steam mechanism; the shaft seal system is connected with the heating mechanism through a pipeline; the first isolation device is arranged between the auxiliary steam mechanism and the heating mechanism; and the second isolation device is arranged between the heating mechanism and the shaft seal system. The steam mechanism, the heating mechanism, the first isolation device and the second isolation device are arranged and connected with the shaft seal system in series, so that high-temperature steam can be provided for a steam turbine in time through the shaft seal system after single-reactor operation emergency shutdown or double-reactor operation simultaneous tripping, and the steam turbine can continue to operate; and the risks of dynamic and static friction and large shaft bending caused by lack of high-temperature steam of the steam turbine are avoided.

Description

technical field [0001] The invention relates to the technical field of nuclear power, in particular to an auxiliary steam device. Background technique [0002] my country is a big electricity consumer in the world, and it is also a big power generation country. At present, nuclear power generation is one of the main power generation methods in our country. Among them, the pebble bed high-temperature gas-cooled reactor is an advanced nuclear reactor with good inherent safety, wide range of uses, and high power generation efficiency. It is also the fourth-generation nuclear energy reactor technology in the international nuclear energy field. [0003] Although the pebble bed high temperature gas-cooled reactor is a new type of energy reactor technology, its technology is not yet perfect. For example, when a high-temperature gas-cooled reactor is shut down in a single-reactor operation or a dual-reactor reactor is operated at the same time, the main steam isolation valve on the...

Claims

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Application Information

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IPC IPC(8): F01D11/04F01D25/00F01D25/10
CPCF01D11/04F01D25/00F01D25/10
Inventor 于爱军王宏国李杰刘军强
Owner HUANENG SHANDONG SHIDAO BAY NUCLEAR POWER CO LTD
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