CN103870615A - Periodic demonstration method of longer-period material-changing renovation equipment from nuclear power station - Google Patents
Periodic demonstration method of longer-period material-changing renovation equipment from nuclear power station Download PDFInfo
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- CN103870615A CN103870615A CN201210529342.3A CN201210529342A CN103870615A CN 103870615 A CN103870615 A CN 103870615A CN 201210529342 A CN201210529342 A CN 201210529342A CN 103870615 A CN103870615 A CN 103870615A
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Abstract
The invention discloses a periodic demonstration method of longer-period material-changing renovation equipment from a nuclear power station, and the method comprises the following steps of: screening out systems and equipment affected by prolonging a material-changing period, acquiring related information of the equipment, analyzing fault modes and fault influence of the equipment with an RCM technology, acquiring the main fault mode and fault consequence of the equipment, in turn judging whether the fault consequence of the equipment is serious, the fault mode thereof is related to time, and time developed to the equipment fault is less than the material-changing period after renovation, gaining positive or negative feedback, when three feedback is positive, the equipment does not conform to requirements of prolonging the material-changing period, otherwise the equipment conform to the requirements of prolonging the material-changing period. The method has the beneficial effects that an important technology is provided for the longer-period material-changing renovation in the nuclear power station when operation and maintenance data of the nuclear power station is insufficient, operation and maintenance coost is reduced and the method is easily popularized.
Description
Technical field
The present invention relates to the Demonstration Method of nuclear power generating equipment time between overhauls(TBO), the newly-built nuclear power station that particularly relates to operating maintenance data deficiencies is implemented the long period periodically method of demonstration of reforming equipment of reloading.
Background technology
In the world, pressurized-water reactor nuclear power plant is generally implemented the fuel management mode reloading for 18 months.Use for reference this advanced experience, domestic operation and will carry out the transformation of reloading for 18 months at the second generation PWR nuclear power plant of founding a capital, extended to 18 months by the refulling cycle of fuel by 12 months that design.But, because can only be in the time of reactor shutdown could repair apparatus, such transformation certainly will cause the time between overhauls(TBO) of equipment to extend, and feasibility analysis demonstration is carried out in the behave that power plant must extend equipment overhaul cycle.
The domestic and international nuclear power station long period using reloads at present, and transformation periodicity Demonstration Method mainly contains Experience Feedback method and producer's maintenance is advised.Experience Feedback method is the operating maintenance experience based on nuclear power plant equipment self, by statistics equipment maintenance record during one's term of military service, the reliability situation of qualitative or quantitative analysis and evaluation equipment, finally provide the conclusion whether time between overhauls(TBO) of equipment can extend, the method is mainly used in moving nuclear power station long period and reloads reforming equipment periodically in demonstration.But, for newly-built nuclear power station, because equipment lacks operating maintenance experience, not possessing enough related data accumulation, traditional Experience Feedback method is difficult to be suitable for.
Producer's maintenance suggestion is the technical information providing by searching equipment supply business, the technical requirement with reference to producer to equipment Maintenance Policy, and whether the time between overhauls(TBO) of carrying out judgment device can meet the requirement that long period reloads.But the method is directly advised as foundation the maintenance of equipment taking producer, often lacks the adequacy demonstration being consistent with the current actual conditions of nuclear power plant equipment, therefore the method is difficult for applying.
Classical RCM(Reliability Centered Maintenance, the maintenance centered by reliability) technology, be a kind of analytical approach of widespread use, but can not be directly used for instructing the periodically demonstration of reforming equipment of reloading of nuclear power station long period.
Summary of the invention
Can not be applicable to the defect of the newly-built nuclear power station of operating maintenance data deficiencies for the above-mentioned Experience Feedback method of prior art, and producer's maintenance suggestion lacks adequacy demonstration, and be difficult for the defect of promoting, the invention provides a kind of nuclear power station long period that has merged RCM technology periodically Demonstration Method of reforming equipment that reloads, for the nuclear power station long period problem of equipment O&M data deficiencies in transformation of reloading, for reloading to transform, nuclear power station enforcement long period provides great technical support, can reduce O&M cost, and be easy to promote.
The technical solution adopted for the present invention to solve the technical problems is: a kind of nuclear power station long period periodically Demonstration Method of reforming equipment that reloads, it is characterized in that, and it comprises the steps:
S1, all systems in definite kernel power station, filter out and be subject to the refulling cycle to extend the system affecting;
S2, for the system filtering out in step S1, filter out and be subject to the refulling cycle to extend the equipment affecting;
S3, for the equipment filtering out in step S2, obtain the relevant information of equipment;
S4, utilization RCM technology, fault mode and fault effects to equipment are analyzed, and obtain chife failure models and the failure effect of equipment;
S5, successively judgment device failure effect whether serious, fault mode whether whether be less than the improved refulling cycle with time correlation, time of being developed to equipment failure, and obtain the feedback of positive or negative, when above-mentioned three feedbacks are when sure, judgment device does not meet the requirement that the refulling cycle extends, otherwise judgment device meets the requirement that the refulling cycle extends.
Further, in step S3, the relevant information of described equipment comprises unit type, designing requirement, functional requirement, operating condition, working environment, self structure, self material.
Further, in step S4, the fault mode to equipment and fault effects analysis comprise functions of the equipments analysis, functional fault analysis, failure mode analysis (FMA), failure effect analysis (FEA), failure effect analysis.
Further, in step S5, whether equipment failure consequence seriously judges according to equipment failure consequences analysis platform.
Further, in step S5, whether whether fault mode be less than the improved refulling cycle with time correlation, time of being developed to equipment failure, all judges by fault mode temporal evolution relational database platform.
Implement the nuclear power station long period of the present invention periodically Demonstration Method of reforming equipment that reloads, there is following beneficial effect: for the nuclear power station long period problem of equipment O&M data deficiencies in transformation of reloading, for reloading to transform, nuclear power station enforcement long period provides great technical support, can effectively instruct the periodically demonstration of reforming equipment of reloading of nuclear power station long period, avoid the dependence to equipment operating maintenance data.The present invention is easy to promote, except equipment periodic demonstration that newly-built nuclear power station long period is reloaded has good applicability, the present invention can also promote the use of in fortune nuclear power station long period reload equipment periodic demonstration, the optimization of nuclear power plant equipment maintenance policy and equipment periodic nargin research field.Can greatly reduce nuclear power generating equipment operating maintenance cost, bring economic benefit to nuclear power plant.
Brief description of the drawings
Below in conjunction with drawings and Examples, the invention will be further described, in accompanying drawing:
Fig. 1 is the nuclear power station long period provided by the invention periodically process flow diagram of the preferred embodiment of Demonstration Method of reforming equipment that reloads;
Fig. 2 is the particular flow sheet of " analyzing judgment device and whether meet the requirement that long period reloads " this step in Fig. 1
Embodiment
Within 18 months, reload and transform example explanation as with newly-built pressurized-water reactor nuclear power plant enforcement below.
For traditional pressurized-water reactor nuclear power plant of implementing to reload for 18 months and transform, refulling cycle by fuel extended to 18 months by 12 months that originally designed, because some equipment can only just can overhaul in reactor shutdown, this certainly will cause the time between overhauls(TBO) of equipment component to extend (becoming 18 months by 12 months).Power station must extend and carry out feasibility analysis demonstration equipment overhaul cycle, i.e. equipment periodic demonstration.
Shown in Fig. 1 is the nuclear power station long period provided by the invention periodically process flow diagram of a preferred embodiment of Demonstration Method of reforming equipment that reloads.In the present embodiment, the method comprises the following steps:
Step S1, the system that first definite kernel power station is all,, filters out and is subject to the refulling cycle to extend the system affecting because the refulling cycle extends the impact that is subject to and the degree of correlation of nuclear safety and availability according to each system.
Step S2, to the above-mentioned system screening, extend the impact that is subject to and the degree of correlation of nuclear safety and availability according to each equipment in this system because of the refulling cycle, filter out and be subject to the refulling cycle to extend the equipment affecting, and this part equipment is carried out to periodicity demonstration, to guarantee that whether equipment overhaul cycle extends reasonable.
Step S3, carries out the periodically equipment of demonstration for the definite needs of above-mentioned steps, obtains the relevant information of equipment, comprises unit type, designing requirement, functional requirement, operating condition, working environment, self structure, self material.These information are bases that the technical program is analyzed judgement.
Step S4, use RCM technology, fault mode and the fault effects of the equipment that step S3 is screened are analyzed, and obtain chife failure models and the failure effect of equipment, comprise functions of the equipments analysis, functional fault analysis, failure mode analysis (FMA), failure effect analysis (FEA).Although this link has been applied RCM technology, but be not to apply classical RCM technology completely, but the means of reference RCM technology, and extend to the situation such as new requirement to equipment overhaul cycle after 18 months in conjunction with the refulling cycle, after proposition relevant issues, analyze step by step chife failure models and the failure effect of the equipment that obtains, this is analyzed mainly in conjunction with 18 months periodically objects of demonstration of reforming equipment of reloading, more targeted and emphasis.
Step S5, analyzes by above-mentioned steps, just learns chife failure models and the failure effect of the equipment that step S3 screens.Extend the feature that causes equipment overhaul cycle to extend in conjunction with the refulling cycle, the seriousness of analysis of failure consequence, the relation of analysis of failure and time, and whether judgment device meets the requirement that long period reloads.Fig. 2 is the particular flow sheet of " analyzing judgment device and whether meet the requirement that long period reloads " this step in Fig. 1, need to make following three judgements in this stage:
Step S51, whether the failure effect of the equipment that determining step S3 screens is serious, be whether syncaryon power station can be accepted the consequence that judgment device fault may cause that requires of nuclear safety, unit availability, system reliability etc., if equipment failure consequence is not serious, and power plant can effectively manage the consequence of equipment failure, can enter step S55, judgment device is the requirement that can meet the transformation of reloading for 18 months; On the contrary, if equipment failure consequence is serious, need further analysis of failure pattern relation over time, enter step S52.In this judgement, whether seriously carry out judgment device failure effect with equipment failure consequences analysis platform, this platform is a database platform, has wherein stored the fault effects possible according to most nuclear power plant equipments of history collection and failure effect information.User, according to analysis result above, selects corresponding fault effects in platform, and software can be automatically associated with failure effect by fault effects, carries out correlation analysis, finally the judged result of output " failure effect is serious " or " failure effect is not serious ".
Step S52, the equipment failure mode that determining step S3 screens whether with time correlation, if the fault mode of this equipment is equal and time-independent, the equipment overhaul cycle that the transformation of reloading for 18 months causes extends does not make the reliability of equipment reduce, can enter step S55, judge that this equipment meets the requirement of the transformation of reloading for 18 months; On the contrary, if equipment failure mode is relevant with the time, need the time range of further analytical equipment fault progression, enter step S53.
Step S53, if the issuable fault of the equipment that determining step S3 screens in step S52 is relevant with the time, need the time that judges this equipment failure whether to be less than 18 months, if certain fault mode causes that the development time of equipment failure is longer, as be greater than 18 months, this cycle that shows overhaul of the equipments can be greater than 18 months, can enter step S55, and judgment device meets the requirement of the transformation of reloading for 18 months; Be less than 18 months if be developed to the time of equipment failure, enter step S54, judgment device does not meet the requirement of the transformation of reloading for 18 months.Whether whether above equipment failure mode be less than the improved refulling cycle with time correlation, time of being developed to equipment failure, analyze by fault mode temporal evolution relational database platform, this platform is a database platform, wherein store according to the fault mode of the nuclear power station overwhelming majority equipment of history collection, and fault mode relation over time.The information such as material, fault mode of user by selecting device type, critical piece, just can obtain fault mode relation over time, and time range or the trend of fault mode development.
In above S51-S53 step, need judgment device failure effect successively whether serious, fault mode whether whether be less than the improved refulling cycle with time correlation, time of being developed to equipment failure, and obtain affirming or negative feedback, only have and be when sure when above-mentioned three feedbacks, just judgment device does not meet the requirement that the refulling cycle extends, otherwise judgment device meets the requirement that the refulling cycle extends.
Below taking certain nuclear power plant within 18 months, reload reforming equipment periodically in demonstration in auxiliary feedwater system the analytic demonstration of valve as example, the technical program is further illustrated.
Whether step S1, filters out and is subject to the refulling cycle to extend the system affecting, relevant to nuclear safety and availability on the impact of system according to refulling cycle prolongation, filters out auxiliary feedwater system (ASG system), and ASG system is the transformation related system that reloads for 18 months;
Step S2, for ASG system, in this system, to give on steam turbine steam supply pipe and have three reverse stop valves, the refulling cycle extends relevant to nuclear safety and availability on the impact of valve, therefore filtering out these three valves is the relevant equipment that reloads for 18 months, need to carry out equipment periodic demonstration;
Step S3, obtain the relevant information of this valve: this valve is that main steam system (VVP system) is to the check valve on ASG system pneumatic pump steam supply pipeline, valve is swing check valve, by Dalian, factory produces, equipment RIN code is NATSSB00100, valve body material is alloy steel, 900 pounds of levels of design pressure grade, sealing pair material is that cobalt irons tungsten, be connected with pipeline welding, manufacturing grade is RCC-M2 level, the steam that this valve running environment is High Temperature High Pressure, the whole steam feed line of unit normal operation period is not moved, and this valve seldom moves.
Step S4, uses RCM analytical approach, carries out fault mode and failure effect analysis (FEA).For the fault mode of valve leakage out of steam system, because valve and pipeline welding, the possibility leaking is extremely low, does not therefore consider herein; Damage for sealing surface, because this valve working environment is steam, the possibility of chemical erosion electrochemical reaction is extremely low, causes that the main cause that sealing surface damages is the mechanical wear between flap and valve seat in medium erosion and valve switch process.Therefore this valve chife failure models is: 1. valve corrosion causes refusing out; 2. medium erosion and mechanical wear cause that packing surface damage causes valves leakage.To the fault effects of the chife failure models analysis result that sees the following form.
Step S5, in conjunction with the seriousness of software platform analysis of failure consequence, the relation of analysis of failure and time, judges whether to meet the requirement of reloading for 18 months.
Step S51, uses equipment failure consequences analysis platform failure judgement severity of consequence.1. the fault mode that valve is refused out, three reverse stop valve simultaneous faults possibilities are extremely low, and this situation is not considered, and only selects " may cause system reliability to decline " in fault effects list, and result is " failure effect is not serious " by analysis.2. the fault mode of valves leakage is selected " producing first group of I0 ", " causing system reliability to decline ", " affecting Unit Economic type " in fault effects list, and result is " failure effect is serious " by analysis.
Step S52, whether the further analysis of failure consequence of relational database platform is relevant with the time over time to use common failure pattern.After failure effect is analyzed, sealing surface wear causes the failure effect of valves leakage serious, needs a step to analyze the relation of this fault mode and time.In database, choose corresponding device type, material properties and fault mode, result demonstration, the fault mode of this valve is relevant with the time.
Step S53, whether the time that uses the common failure pattern further analysis of relational database platform to be over time developed to fault mode is less than the improved refulling cycle, database analysis result shows, this valve sealing face material is that cobalt irons tungsten wimet, there is good corrosion-resistant and polishing machine, if valve is not frequent movement, the time that causes sealing surface to damage is longer, is generally greater than 5 years.
Analyze through above, the failure effect that valve is refused out is not serious, and the failure effect of valves leakage is serious, but sealing surface damage causes the time of valves leakage much larger than 18 months, therefore the step S55 entering, judges that this valve meets the requirement of the transformation of reloading for 18 months.
The present invention's application RCM technology, simultaneously fusion device fault mode and the relation of time, the long period factors such as transforming requirement to the overhaul of the equipments time of reloading, instructs the nuclear power station long period reforming equipment cycle Demonstration Method that reloads.
By reference to the accompanying drawings embodiments of the invention are described above; but the present invention is not limited to above-mentioned embodiment; above-mentioned embodiment is only schematic; instead of restrictive; those of ordinary skill in the art is under enlightenment of the present invention; not departing from the scope situation that aim of the present invention and claim protect, also can make a lot of forms, within these all belong to protection of the present invention.
Claims (5)
1. the nuclear power station long period periodically Demonstration Method of reforming equipment that reloads, is characterized in that, it comprises the steps:
S1, all systems in definite kernel power station, filter out and be subject to the refulling cycle to extend the system affecting;
S2, for the system filtering out in step S1, filter out and be subject to the refulling cycle to extend the equipment affecting;
S3, for the equipment filtering out in step S2, obtain the relevant information of equipment;
S4, utilization RCM technology, fault mode and fault effects to equipment are analyzed, and obtain chife failure models and the failure effect of equipment;
S5, successively judgment device failure effect whether serious, fault mode whether whether be less than the improved refulling cycle with time correlation, time of being developed to equipment failure, and obtain the feedback of positive or negative, when above-mentioned three feedbacks are when sure, judgment device does not meet the requirement that the refulling cycle extends, otherwise judgment device meets the requirement that the refulling cycle extends.
2. the nuclear power station long period according to claim 1 periodically Demonstration Method of reforming equipment that reloads, it is characterized in that, in step S3, the relevant information of described equipment comprises unit type, designing requirement, functional requirement, operating condition, working environment, self structure, self material.
3. the nuclear power station long period according to claim 1 periodically Demonstration Method of reforming equipment that reloads, it is characterized in that, in step S4, the fault mode to equipment and fault effects analysis comprise functions of the equipments analysis, functional fault analysis, failure mode analysis (FMA), failure effect analysis (FEA), failure effect analysis.
4. the nuclear power station long period according to claim 1 periodically Demonstration Method of reforming equipment that reloads, is characterized in that, in step S5, whether equipment failure consequence seriously judges by equipment failure consequences analysis platform.
5. the nuclear power station long period according to claim 1 periodically Demonstration Method of reforming equipment that reloads, it is characterized in that, in step S5, whether whether fault mode be less than the improved refulling cycle with time correlation, time of being developed to equipment failure, all judges by fault mode temporal evolution relational database platform.
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Cited By (3)
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| CN105260947A (en) * | 2015-10-13 | 2016-01-20 | 苏州热工研究院有限公司 | Available rate evaluation method for design period of nuclear power station |
| CN107705018A (en) * | 2017-10-10 | 2018-02-16 | 苏州热工研究院有限公司 | A kind of Demonstration Method for nuclear power plant's routine test cycle stretch-out |
| CN110909982A (en) * | 2019-10-24 | 2020-03-24 | 广东核电合营有限公司 | Delay demonstration method for long-term temporary-halt short-period maintenance project of nuclear power unit |
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Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105260947A (en) * | 2015-10-13 | 2016-01-20 | 苏州热工研究院有限公司 | Available rate evaluation method for design period of nuclear power station |
| CN105260947B (en) * | 2015-10-13 | 2019-06-25 | 苏州热工研究院有限公司 | Availability evaluation method for the nuclear power station design phase |
| CN107705018A (en) * | 2017-10-10 | 2018-02-16 | 苏州热工研究院有限公司 | A kind of Demonstration Method for nuclear power plant's routine test cycle stretch-out |
| CN110909982A (en) * | 2019-10-24 | 2020-03-24 | 广东核电合营有限公司 | Delay demonstration method for long-term temporary-halt short-period maintenance project of nuclear power unit |
| CN110909982B (en) * | 2019-10-24 | 2023-10-24 | 广东核电合营有限公司 | Delay demonstration method for short-period maintenance project in long-term temporary stop of nuclear power unit |
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