CN111028962A - Method for evaluating tightness test of high-low pressure safety injection penetration piece of nuclear power station - Google Patents

Method for evaluating tightness test of high-low pressure safety injection penetration piece of nuclear power station Download PDF

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Publication number
CN111028962A
CN111028962A CN201911396782.4A CN201911396782A CN111028962A CN 111028962 A CN111028962 A CN 111028962A CN 201911396782 A CN201911396782 A CN 201911396782A CN 111028962 A CN111028962 A CN 111028962A
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test
valve
leakage rate
pressure
containment
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李晓庚
金凯
王志永
王洪凯
高原
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CNNC Fujian Nuclear Power Co Ltd
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CNNC Fujian Nuclear Power Co Ltd
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/003—Remote inspection of vessels, e.g. pressure vessels
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C13/00—Pressure vessels; Containment vessels; Containment in general
    • G21C13/02—Details
    • G21C13/028—Seals, e.g. for pressure vessels or containment vessels
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

The invention belongs to the technical field of test result evaluation, and particularly relates to a method for evaluating the sealing performance of a high-low pressure safety injection penetration piece of a nuclear power station. Measuring the total leakage rate of the valve in the containment vessel under the actual test pressure and recording as QInner part(ii) a Measuring the total leakage rate of the valve outside the containment vessel under the test design test pressure of 0.42MPa.g, and recording the total leakage rate as QOuter cover(ii) a When the test pressure of the valve in the containment is greater than the test design test pressure of 0.42MPa.g, the evaluation method in the fourth step and the fifth step is used; when the test pressure of the valve in the containment is equal to the test design test pressure of 0.42MPa.g, the evaluation methods in the fourth step and the fifth step can be used, and a general evaluation method can also be used; directly selecting total leakage rate Q of valve outside containmentOuter coverAs the final leak rate of the penetration; and (3) comparing the final leakage rate of the penetration piece with an acceptance standard, and evaluating the penetration piece test result: if the test result is not greater than the testIf the standard is accepted, the test result is qualified; and if the test result is greater than the acceptance standard, the test result is unqualified.

Description

Method for evaluating tightness test of high-low pressure safety injection penetration piece of nuclear power station
Technical Field
The invention belongs to the technical field of test result evaluation, and particularly relates to a method for evaluating the sealing performance of a high-low pressure safety injection penetration piece of a nuclear power station.
Background
According to the license document of the nuclear power station, namely the requirement of regular test supervision of safety-related systems and equipment, the mechanical penetration piece arranged in the nuclear power station is verified to be sealed through tests (the design test pressure is 0.42MPa.g) during shutdown, refueling and overhaul so as to evaluate the leakage quantity of the penetration piece under the accident condition. High and low pressure safety injection penetrations (8 total) are one type of mechanical penetrations for which a leak tightness test is performed during each refurbishment overhaul. Currently, the general evaluation method for the sealing test results of mechanical penetration pieces is as follows:
firstly, the leakage rate (Q) of all valves of the mechanical penetration piece positioned at the inner side and the outer side of the containment vessel is respectively measuredInner partAnd QOuter cover) And then, obtaining the leakage rate of the mechanical penetration piece according to a leakage rate value-taking principle of the mechanical penetration piece, and evaluating the sealing performance test result of the mechanical penetration piece according to an acceptance standard (a fixed value given by a design file). If the sealing performance test result of the mechanical penetration piece is not greater than the acceptance standard, the result is qualified; and if the sealing performance test result of the mechanical penetration piece is greater than the acceptance standard, the result is unqualified.
The test result obtained by the principle of the leakage rate value of the mechanical penetration piece directly reflects the leakage amount of the containment from the inside of the containment to the outside of the containment through the penetration piece under the accident condition. According to the test guide (design file), the value of the mechanical penetration piece sealing test is divided into three principles:
Figure BDA0002346540130000011
Figure BDA0002346540130000021
according to the design file, the valve driving signal of the high-pressure and low-pressure safety injection penetration piece is driven in a remote manual driving or safety injection signal mode, and a containment isolation signal is not received, so that the value-taking principle of the mechanical penetration piece adopts the type III in the value-taking principle, namely the total leakage rate of the valve inside and outside the containment is respectively calculated, and the smaller of the two values is taken as the leakage rate of the mechanical penetration piece.
According to the design of a nuclear power station process system, a test isolation boundary of a valve in a containment vessel of a high-pressure and low-pressure safety injection penetration piece is a primary loop boundary check valve, and the check valve cannot be used as a normal boundary valve for isolation, so that a mode of isolating the primary loop boundary check valve by providing back pressure through a primary loop in an NS/RRA mode of 2.5MPa. Because of the sealing characteristic of the check valve, the pressure in the test boundary can be far higher than the design test pressure (0.42MPa.g) required by the mechanical penetration piece sealing performance test, and the test method adopted in the industry at present is to convert a formula Q by a linear pressure-leakage raten＝Qt×Pn/Pt，(Qn: calculating the leakage rate of the test valve under the design test pressure; qt: testing the leakage rate of the valve under actual test pressure; pn: the design test pressure of the test valve is 0.42 MPa.g; pt: actual test pressure of the test valve) the leakage rate measurements of the test valve at high pressure are converted to a calculated leakage rate at the design test pressure. The conversion method is lack of upstream design demonstration and test of engineering practice on result conformity, the converted test result may have a certain deviation from the true value, the test result of the valve in the containment is assumed to be converted by a pressure-leakage rate conversion formula, and the leakage rate (Q) of the valve in the containment is assumed to beInner part) Lower than the leakage rate (Q) of the valve outside the containmentOuter cover) According to the class III value-taking principle, the leakage rate value of the penetration piece can adopt measurement data of a valve in a containment, the leakage rate of the penetration piece obtained under the condition can be lower than a true value, and the accuracy of the leakage rate of the penetration piece passing through the penetration piece under the accident condition is influenced.
Disclosure of Invention
The invention aims to provide a method for evaluating the tightness test of a high-low pressure safety injection penetration piece of a nuclear power station, which effectively solves the problem that the leakage rate result of a valve in a containment is inaccurate due to overhigh test pressure, so that the accuracy of the leakage rate of the penetration piece is influenced under the condition of evaluating accidents, the leakage rate test result of the penetration piece is not lower than the true value under various conditions, the safety margin of the value of the leakage rate of the corresponding penetration piece is improved, and the nuclear power station is ensured to be safely controlled.
In order to achieve the purpose, the technical scheme adopted by the invention is as follows:
a method for evaluating the tightness test of a high-low pressure safety injection penetration piece of a nuclear power station,
the method comprises the following steps: measuring the total leakage rate of the valve in the containment vessel under the actual test pressure and recording as QInner part；
Step two: measuring the total leakage rate of the valve outside the containment vessel under the test design test pressure of 0.42MPa.g, and recording the total leakage rate as QOuter cover；
Step three: when the test pressure of the valve in the containment is greater than the test design test pressure of 0.42MPa.g, the evaluation method in the fourth step and the fifth step is used; when the test pressure of the valve in the containment is equal to the test design test pressure of 0.42MPa.g, the evaluation methods in the fourth step and the fifth step can be used, and a general evaluation method can also be used;
step four: directly selecting total leakage rate Q of valve outside containmentOuter coverAs the final leak rate of the penetration;
step five: and (3) comparing the final leakage rate of the penetration piece with an acceptance standard, and evaluating the penetration piece test result: if the test result is not greater than the acceptance standard, the test result is qualified; and if the test result is greater than the acceptance standard, the test result is unqualified.
The general evaluation method comprises the following steps: first using the conversion formula QInner part’＝QInner part×Pn/PtCalculate to get Q'Inner part，Q’Inner part: calculating the leakage rate of the valve in the containment under the design test pressure; qInner part: the leakage rate of the valve in the containment vessel is measured under the actual test pressure; pn: the design test pressure of the valve in the containment vessel is 0.42 MPa.g; pt: actual test pressure of the valve in the containment vessel; then, Q 'is taken from the III class according to a penetration piece value principle'Inner part、QOuter coverThe smaller of the two values is taken as the leak rate of the penetration.
The beneficial effects obtained by the invention are as follows:
the leakage rate value of the high-low pressure safety injection penetration piece of the nuclear power station is not lower than the true value under various conditions, the safety margin of the leakage rate value of the penetration piece is improved, the leakage quantity of the penetration piece is not lower than the true value under the accident condition, and the nuclear safety is controlled.
The comparison between the evaluation method of the present invention and the general evaluation method is as follows:
Figure BDA0002346540130000041
during the pre-critical inspection period of Fuqing nuclear power 302 overhaul unit, the evaluation method is successfully applied to evaluate the test result of the high-low pressure safety injection penetration piece, and the approval of the national nuclear safety supervision department is obtained.
Detailed Description
The present invention will be described in detail with reference to specific examples.
A method for evaluating the tightness test of a high-low pressure safety injection penetration piece of a nuclear power station comprises the following steps:
the method comprises the following steps: measuring the total leakage rate of the valve in the containment vessel under the actual test pressure and recording as QInner part；
Step two: measuring the total leakage rate of the valve outside the containment vessel under the test design test pressure of 0.42MPa.g, and recording the total leakage rate as QOuter cover；
Step three: when the test pressure of the valve in the containment is greater than the test design test pressure of 0.42MPa.g, the evaluation method in the fourth step and the fifth step is used; when the test pressure of the valve in the containment is equal to the test design test pressure of 0.42MPa.g, the evaluation methods described in the fourth step and the fifth step can be used, and a general evaluation method can also be used, wherein the general evaluation method comprises the following steps:
first using the conversion formula QInner part’＝QInner part×Pn/Pt，(Q’Inner part: calculating the leakage rate of the valve in the containment under the design test pressure; qInner part: the leakage rate of the valve in the containment vessel is measured under the actual test pressure; pn: design test pressure of the valve in the containment: 0.42 MPa.g; pt: valve in containmentActual test pressure) to calculate Q'Inner partThen, a penetration piece value principle is applied to obtain Q 'from the III class'Inner part、QOuter coverThe smaller of the two values is taken as the leakage rate of the penetration;
step four: directly selecting total leakage rate Q of valve outside containmentOuter coverAs the final leak rate of the penetration;
step five: and (3) comparing the final leakage rate of the penetration piece with an acceptance standard, and evaluating the penetration piece test result: if the test result is not greater than the acceptance standard, the test result is qualified; and if the test result is greater than the acceptance standard, the test result is unqualified.
The present invention is described in further detail below with reference to a specific example (evaluation of No.261 penetration by Fuqing Nuclear Power 302 overhaul).
The method comprises the following steps: the backpressure of a valve RIS048VP in the containment vessel is measured to be 2.1161MPa.g by using a pressure gauge, the backpressure of the valve RIS049VP in the containment vessel is 2.4080MPa.g, and the backpressure is both greater than the test pressure of the test design 0.42MPa.g, and the evaluation method is used;
step two: measuring total leakage rate Q of valve RIS048VP + RIS049VP + RIS405VP in containment vesselInner part＝8892.00ml/h；
Step three: under the test pressure of 0.42MPa.g, the total leakage rate Q of an outside-containment valve RIS023VP is measuredOuter cover＝12996.00ml/h；
Step four: and selecting the total leakage rate of the out-of-containment valve as the final leakage rate of the penetration piece, wherein the final leakage rate of the penetration piece is 12996.00 ml/h.
Step five: and comparing the final leakage rate of the penetration piece with the acceptance standard, evaluating the test result of the penetration piece, wherein the final leakage rate (12996.00ml/h) of the penetration piece is less than the acceptance standard (55200.00ml/h), and the test result of the penetration piece is qualified.
The evaluation method provided by the invention is applied to the test evaluation of the sealing performance of the high-low pressure safety injection penetration piece, and can effectively solve the problem that the valve leakage rate result in the containment vessel is inaccurate due to overhigh test pressure, so that the final penetration piece leakage rate value influences the acceptance check effect, the penetration piece leakage rate value is not lower than the true value under various conditions, the safety margin of the corresponding penetration piece leakage rate value is improved, and the nuclear safety control is ensured.
Figure BDA0002346540130000061

Claims (2)

1. A method for evaluating the tightness test of a high-low pressure safety injection penetration piece of a nuclear power station is characterized by comprising the following steps:
the method comprises the following steps: measuring the total leakage rate of the valve in the containment vessel under the actual test pressure and recording as QInner part；
Step two: measuring the total leakage rate of the valve outside the containment vessel under the test design test pressure of 0.42MPa.g, and recording the total leakage rate as QOuter cover；
Step three: when the test pressure of the valve in the containment is greater than the test design test pressure of 0.42MPa.g, the evaluation method in the fourth step and the fifth step is used; when the test pressure of the valve in the containment is equal to the test design test pressure of 0.42MPa.g, the evaluation methods in the fourth step and the fifth step can be used, and a general evaluation method can also be used;
step four: directly selecting total leakage rate Q of valve outside containmentOuter coverAs the final leak rate of the penetration;
step five: and (3) comparing the final leakage rate of the penetration piece with an acceptance standard, and evaluating the penetration piece test result: if the test result is not greater than the acceptance standard, the test result is qualified; and if the test result is greater than the acceptance standard, the test result is unqualified.
2. The method for evaluating the tightness test of the high-low pressure safety injection penetration piece of the nuclear power station according to claim 1, is characterized in that: the general evaluation method comprises the following steps: first using the conversion formula QInner part’＝QInner part×Pn/PtCalculate to get Q'Inner part，Q’Inner part: calculating the leakage rate of the valve in the containment under the design test pressure; qInner part: the leakage rate of the valve in the containment vessel is measured under the actual test pressure; pn: design of valve in containmentThe test pressure is 0.42 MPa.g; pt: actual test pressure of the valve in the containment vessel; then, Q 'is taken from the III class according to a penetration piece value principle'Inner part、QOuter coverThe smaller of the two values is taken as the leak rate of the penetration.
CN201911396782.4A 2019-12-30 2019-12-30 Method for evaluating tightness test of high-low pressure safety injection penetration piece of nuclear power station Pending CN111028962A (en)

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Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN114235307A (en) * 2021-12-06 2022-03-25 中广核工程有限公司 System and method for testing tightness of isolation valve of mechanical penetration piece of containment vessel of nuclear power station

Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2002039905A (en) * 2000-07-24 2002-02-06 Pentafu Kk Apparatus and method for testing leakage resistance of piping
CN105157923A (en) * 2015-07-16 2015-12-16 中国核电工程有限公司 Method for testing airtightness of containment vessel inlet and outlet isolating valve group

Patent Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2002039905A (en) * 2000-07-24 2002-02-06 Pentafu Kk Apparatus and method for testing leakage resistance of piping
CN105157923A (en) * 2015-07-16 2015-12-16 中国核电工程有限公司 Method for testing airtightness of containment vessel inlet and outlet isolating valve group

Non-Patent Citations (2)

* Cited by examiner, † Cited by third party
Title
张勇等: "高低压安注系统机械贯穿件密封性定期试验优化研究", 《核科学与工程》 *
高忠勇等: "秦山核电厂安全壳系统B、C类密封性试验", 《核科学与工程》 *

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN114235307A (en) * 2021-12-06 2022-03-25 中广核工程有限公司 System and method for testing tightness of isolation valve of mechanical penetration piece of containment vessel of nuclear power station

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Application publication date: 20200417