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Test system and method for heat transfer performance of diversified hot-well system in nuclear power plant

A technology of heat transfer performance and test system, applied in the field of nuclear power, can solve problems such as inability to meet MHSS, and achieve the effect of controllable risk and simple operation.

Active Publication Date: 2017-09-19
中广核工程有限公司 +1
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0005] The present invention aims at the problem existing in the prior art that cannot meet the requirement of MHSS performance test, and provides a heat transfer performance test system and method of a nuclear power plant diversification heat sink system, and finally realizes that without adding additional equipment, in a nuclear power plant Realize the performance test of the MHSS system before loading nuclear fuel, the operation is simple and easy, and the risk is controllable

Method used

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  • Test system and method for heat transfer performance of diversified hot-well system in nuclear power plant

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Embodiment 1

[0045] Please refer to figure 2 , Embodiment 1 of the present invention provides a heat transfer performance test system for a diversified heat sink system in a nuclear power plant, including a reactor coolant circulation loop 1 and a heat export circulation loop 2. The solid line in the figure shows the reactor coolant circulation loop 1, The dotted line shows the heat export circulation loop 2, the reactor coolant circulation loop 1 and the heat export circulation loop 2 both use water as the heat transfer medium, and the reactor coolant circulation loop 1 includes: the reactor coolant that communicates with the reactor coolant circulation loop 1 The main pump 11 is used to provide heat for the reactor coolant circulation loop 1 through the heat generated by the reactor coolant main pump 11's own mechanical power; the hot side of the waste heat removal system 12 communicating with the reactor coolant circulation loop 1, It is used to receive and adjust part of the heat prov...

Embodiment 2

[0056] Such as Figure 4 As shown, Embodiment 2 of the present invention provides a test method for heat transfer performance of a diversified heat sink system in a nuclear power plant, which includes the following steps:

[0057] S1, start the reactor coolant main pump 11, the reactor coolant main pump 11 provides heat for the reactor coolant circulation loop 1 through its own mechanical power heating, specifically, the reactor coolant circulation loop 1 through the volume control pump 15 The injection pressure is medium, and at the same time, the regulating valve assembly 122 of the waste heat removal system 12 is adjusted, so that the reactor coolant circulation loop 1 maintains a preset pressure so that the reactor coolant main pump 11 operates normally.

[0058]S2. The reactor coolant main pump 11 directly transfers part of the heat provided to the conventional cold chain heat sink system 13 of the heat export circulation loop 2, while the waste heat removal system 12 rec...

Embodiment 3

[0062] Such as Figure 5 As shown, step S2 specifically includes the following simultaneous steps:

[0063] S21. The reactor coolant main pump 11 directly transfers part of the heat provided to the conventional cold-chain heat sink system 13 of the heat derivation loop 2;

[0064] S22. The first heat exchanger 1211 of the waste heat removal system 12 receives part of the heat provided by the reactor coolant main pump 11 and transfers it to the conventional cold chain heat sink system 13 for cooling;

[0065] S23. The second heat exchanger 1212 of the waste heat removal system 12 receives part of the heat provided by the reactor coolant main pump 11 and transfers it to the diversified heat sink system 14 for cooling.

[0066] When the diversified heat sink system 14 breaks down, adjust the regulating valve assembly 122 of the waste heat removal system 12 so that the second heat exchanger 1212 cannot receive heat, and all the heat generated by the reactor coolant main pump 11 i...

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Abstract

The invention discloses a test system for heat transfer performance of a diversified hot-well system in a nuclear power plant. The test system for heat the transfer performance of the diversified hot-well system in the nuclear power plant comprises a reactor coolant circulation loop and a heat derived circulation loop, the reactor coolant circulation loop comprises: a reactor coolant main pump communicating with the reactor coolant circulation loop and a hot side of a waste heat discharge system communicating with the reactor coolant recirculation loop; the heat derived circulation loop comprises a cooler of the reactor coolant main pump, a cold side of the waste heat discharge system, a conventional cold chain hot-well system, and a diversified hot-well system, wherein the conventional cold chain hot-well system is communicated with the cooler of the reactor coolant main pump and the cold side of the waste heat discharge system, and the diversified hot-well system communicates with the cold side of the waste heat discharge system. The test system for heat transfer performance of the diversified hot-well system in the nuclear power plant realizes the performance test of the diversified hot-well system without adding additional equipment, the operation method is simple and the risk is controllable. In addition, the invention also discloses a test method for heat transfer performance of the diversified hot-well system in the nuclear power plant.

Description

technical field [0001] The invention relates to the technical field of nuclear power, in particular to a heat transfer performance test system and method for a diversified heat sink system of a nuclear power plant. Background technique [0002] Before the nuclear power plant is loaded with nuclear fuel, there is no heating nuclear fuel in the core and the spent fuel pool, the containment spray system (PCSS) heat exchanger and the spent fuel pool cooling system (SFPC) heat exchanger cannot provide heat, the PCSS pump and low pressure safety The heat provided by the injection (LPSI) pump is about 2% of the design heat transfer capacity of the Multi-Heat Sink System (MHSS), which cannot meet the needs of the MHSS for performance tests. [0003] The existing technical scheme uses an external heat source to heat the spent fuel pool, and then uses the spent fuel pool as a heat source to transfer the heat to the MHSS through the SFPC heat exchanger. Such as figure 1 As shown, the...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C17/00
CPCG21C17/00Y02E30/30
Inventor 杨廷马超李增芬廖金远魏颖娣李世光曾建丽
Owner 中广核工程有限公司
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