Backwashing device and backwashing method for nuclear power plant closed cycle system
A circulation system and backwashing technology, applied in nuclear power plants, chemical instruments and methods, separation methods, etc., can solve the problems of equipment damage, system safety operation risk, insufficient water filling and exhausting of pump inlets and outlets, prolongation of nuclear power plant commissioning cycle, etc. , achieve the effect of reducing the risk of pump damage in the closed circulation system of nuclear power plants, solving the problem of water leakage, and reducing safety and quality risks
Active Publication Date: 2022-01-18
中广核工程有限公司 +2
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Problems solved by technology
[0012] After the filter is cleaned, it is necessary to fill and exhaust the inlet and outlet of the pump, and the operation of filling and exhausting water needs to be repeated many times, so there is a risk of insufficient water filling and exhaust at the inlet and outlet of the pump, resulting in the risk of cavitation damage to the pump
[0013] The most direct results of the above three defects are: increased investment in manpower and material resources for washing work, increased risk of equipment damage and safe operation of the system; the indirect results are the prolongation of the commissioning cycle of nuclear power plants, which ultimately leads to increased construction costs of nuclear power plants
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[0038] In order to make the object, technical solution and technical effect of the present invention clearer, the present invention will be further described in detail below in conjunction with the accompanying drawings and specific implementation methods. It should be understood that the specific implementations described in this specification are only for explaining the present invention, not for limiting the present invention.
[0039] Please refer to figure 1 and figure 2 As shown, the nuclear power plant closed circulation system backwashing device of the present invention includes:
[0040] The first short pipe 10 is equipped with a filter screen 30 with a front end and a rear end, and at least one first opening (not marked) is provided along the periphery of the first short pipe 10, and a flushing valve is installed at the first opening. The inlet pipe 100 of 102; and
[0041] The second short pipe 20 is connected with the first short pipe 10 , and the second short ...
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The invention discloses a backwashing device for a closed circulation system of a nuclear power plant. The first opening is equipped with a water inlet pipe with a flushing valve; and the second short pipe is connected to the first short pipe. The second short pipe is provided with a second opening, and the second opening is installed with a drain with an isolation valve. Tube. Compared with the prior art, the backwashing device of the nuclear power plant closed circulation system of the present invention can connect the pressurized backwashing water source to the closed circulation system, and the flushing water backwashes the filter screen from the back end of the filter screen to the front end, and the inside of the filter screen The sediment flows out of the filter screen with the flushing water and is discharged through the drain pipe at the front of the filter screen, so that online backwashing without disassembling the filter screen can be realized.
Description
technical field [0001] The invention belongs to the field of nuclear power plant debugging, and more specifically, the invention relates to a backwashing device and a backwashing method for a closed circulation system of a nuclear power plant. Background technique [0002] As a unique system for nuclear power plants, the containment and spent fuel pool medium and long-term waste heat removal system (SEU) belongs to the mitigation measures for beyond-design-basis accidents under the condition of losing the final heat sink. The SEU system does not perform operating functions during the normal operation of the nuclear power unit, does not directly participate in the realization of reactivity control, and does not directly participate in the realization of radioactive material containment. The residual heat of the core and the spent fuel pool is discharged under the condition of small loop loss of water accident (small LOCA), and the waste heat of the spent fuel pool is exported...
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IPC IPC(8): B01D29/66G21D1/00
CPCB01D29/668G21D1/00Y02E30/00
Inventor 周亮亮范博仁王志明
Owner 中广核工程有限公司