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Method for calculating containment leakage rate under special working conditions

A calculation method and containment technology, applied in the direction of calculation, computer-aided design, special data processing applications, etc., can solve problems such as timely processing of delays and abnormal problems, judgments affecting the integrity of containment, and risks of unit safe and stable operation, etc., to achieve Realize the effect of timeliness

Active Publication Date: 2021-01-15
CNNC FUJIAN FUQING NUCLEAR POWER
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Problems solved by technology

[0018] In the actual monitoring process, it is found that when the monitoring system is restarted in the initial stage and the unit is in special working conditions such as the state change of the primary circuit before and after the overhaul, the calculation of Ql60 by the monitoring system has a problem of insufficient timeliness
[0019] From the two conditions for calculating Ql60, it can be seen that after the monitoring system is restarted and the unit is overhauled, the △P-Qld leakage rate curve needs to be re-fitted. Monitoring of containment integrity is inactive
[0020] At the same time, if there is a real abnormality in the integrity of the containment, the range of △P cannot meet the condition of greater than 1.5kPa, and the monitoring system will always be unable to calculate Ql60, which will affect the judgment of the technicians on the integrity of the containment, and delay the inspection of the completeness of the containment. The timely handling of abnormal problems brings risks to the safe and stable operation of the unit, and also loses the significance of monitoring the integrity of the containment

Method used

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  • Method for calculating containment leakage rate under special working conditions
  • Method for calculating containment leakage rate under special working conditions
  • Method for calculating containment leakage rate under special working conditions

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Embodiment Construction

[0046] The present invention will be described in further detail below in conjunction with the accompanying drawings and specific embodiments.

[0047] Such as Figure 2-3 As shown, a method for calculating the containment leakage rate under special working conditions includes the following steps;

[0048] Step 1: Draw the limit curve of the new containment leakage rate △P-Qleak.

[0049] According to the regulations on the limit value of Ql60 in the operation technical specification: when the pressure difference is +6kPa, its absolute value cannot exceed 5Nm 3 / h, that is, two (△P, Qleak) coordinate points (+6, 5) and (+6, -5) are known; according to the physical principle of gas flow, when the pressure difference △P inside and outside the shell is 0kPa, Gas leakage rate through mechanical penetrations is 0Nm 3 / h, that is, the third coordinate point (0,0) is known.

[0050]According to the principle of determining a straight line at two points, a positive limit curve of ...

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Abstract

The invention belongs to the technical field of nuclear leakage rate calculation, and particularly relates to a method for calculating a containment leakage rate under special working conditions, themethod comprises seven steps. The method is characterized by comprising the following steps: step 1, drawing a limit value curve of the leakage rate deltaP-Qleak of a new containment; step 2, queryingQp historical data of a unit needing to be monitored, and selecting a relatively large value; 3, comparing the calculated value with a limit value; step 4, performing result judgment; step 5, performing pressure change analysis; step 6, performing temperature change analysis; and step 7, ending the reverse calculation. The method has strong executability, can accurately calculate the leakage rateof the containment under special working conditions, and can realize timely and effective monitoring of the integrity of the containment every day, i.e., the effective monitoring of the integrity ofthe containment is shortened from 5 days to 1 day, and the timeliness is realized.

Description

technical field [0001] The invention belongs to the technical field of nuclear leakage rate calculation, and in particular relates to a method for calculating the leakage rate of containment under special working conditions. Background technique [0002] 1) Brief introduction of containment leakage rate [0003] The containment vessel is the third safety barrier of a nuclear power plant and is a prestressed concrete structure with a steel liner that limits the release of radioactive gases to the environment. During the normal operation of the unit, the containment vessel was in a closed state, but the leakage of the containment vessel was caused due to the incorrect online status of the penetrating parts. In order to protect the radiation safety of the public, the power plant has set up an online monitoring system for the containment leakage rate (hereinafter referred to as the "monitoring system") to monitor the containment leakage rate during the operation of the unit on-...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G06F30/20G06F17/18G21C17/00G06F111/10G06F119/08G06F119/14
CPCG06F30/20G06F17/18G21C17/002G06F2119/08G06F2119/14G06F2111/10Y02E30/30
Inventor 王志永李晓庚金凯李振饶建民
Owner CNNC FUJIAN FUQING NUCLEAR POWER
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