CN111834025B - Evaluation method for prolonging cycle of check type supervision project of safety related instrument of nuclear power plant - Google Patents
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Abstract
一种核电厂安全相关仪表校验类监督项目周期延长的评价方法，包括以下步骤：获取安全相关仪表的名义触发整定值NTSP和分析限值AL；根据安全相关仪表的历史校验数据，计算安全相关仪表校验类监督项目在周期延长后的漂移量ADC1；根据所述漂移量ADC1计算安全相关仪表校验类监督项目在周期延长后的通道不确定度CUC1；计算安全相关仪表的安全裕度，其中，安全相关仪表的安全裕度＝AL－CUC1－NTSP；然后判断安全相关仪表的安全裕度是否大于0，若是，则不调整安全相关仪表的名义触发整定值NTSP。本发明的核电厂安全相关仪表校验类监督项目周期延长的评价方法设计新颖，实用性强。
A method for evaluating the period extension of a safety-related instrument verification type supervision project in a nuclear power plant, comprising the following steps: obtaining a nominal trigger setting value NTSP and an analysis limit AL of a safety-related instrument; calculating the safety value according to historical verification data of the safety-related instrument The drift amount AD C1 of the relevant instrument calibration supervision item after the period is extended; calculate the channel uncertainty CU C1 of the safety-related instrument calibration supervision item after the period is extended according to the drift amount AD C1 ; calculate the safety-related instrument Safety margin, among which, the safety margin of safety-related instruments = AL-CU C1 -NTSP; then judge whether the safety margin of safety-related instruments is greater than 0, if so, do not adjust the nominal trigger setting value NTSP of safety-related instruments. The evaluation method for prolonging the cycle of a nuclear power plant safety-related instrument calibration type supervision project has a novel design and strong practicability.
Description
技术领域technical field
本发明涉及核电厂定期试验领域，是一种核电厂安全相关仪表校验类监督项目周期延长的评价方法。The invention relates to the field of periodic tests of nuclear power plants, and is an evaluation method for prolonging the period of a safety-related instrument calibration supervision project of a nuclear power plant.
背景技术Background technique
随着近年经济的下滑，机组可利用率有所下降，在核电领域表现为机组时常临停甚至处于中长期备用状态。通常核电厂实施的是18个月换料的燃料管理策略，单循环的核安全相关定期试验最长执行周期不超过20个月。为提高核电机组能力因子、大修安排灵活性和电厂经济效益，核电厂希望在目前长期低功率运行的制约下，增加单循环运行时间(延长至24个月)，因此需要评价定期试验周期延长的影响，试验周期可以延长的前提是试验周期延长后核安全相关设备可用性依然能够得到保障，对于非仪表类监督项目主要采用经验反馈法进行评价，而对于安全相关仪表校验类监督项目，由于仪表漂移与时间相关，而且有分析限值的约束，不宜使用经验反馈法，而应该考虑试验周期延长对仪表漂移和触发整定值的影响，而目前还没有相关的评价方法。With the economic downturn in recent years, the availability of units has declined, and in the field of nuclear power, units are often temporarily shut down or even in medium and long-term standby. Usually nuclear power plants implement a fuel management strategy of 18-month refueling, and the longest execution period of a single-cycle nuclear safety-related periodic test does not exceed 20 months. In order to improve the capacity factor of nuclear power units, the flexibility of overhaul scheduling and the economic benefits of the power plant, the nuclear power plant hopes to increase the single-cycle operation time (extended to 24 months) under the current constraints of long-term low-power operation, so it is necessary to evaluate the extension of the periodic test period. Influence, the premise that the test period can be extended is that the availability of nuclear safety-related equipment can still be guaranteed after the test period is extended. For non-instrument supervision projects, the experience feedback method is mainly used for evaluation. Drift is related to time, and is constrained by the analysis limit. It is not appropriate to use the empirical feedback method. Instead, the influence of the extension of the test period on the instrument drift and trigger setting value should be considered, and there is no relevant evaluation method at present.
发明内容SUMMARY OF THE INVENTION
本发明针对上述技术问题，提出一种核电厂安全相关仪表校验类监督项目周期延长的评价方法。Aiming at the above-mentioned technical problems, the present invention proposes an evaluation method for prolonging the period of a nuclear power plant safety-related instrument verification type supervision project.
本发明所提出的技术方案如下：The technical scheme proposed by the present invention is as follows:
本发明提出了一种核电厂安全相关仪表校验类监督项目周期延长的评价方法，包括以下步骤：The present invention proposes an evaluation method for prolonging the cycle of a nuclear power plant safety-related instrument calibration supervision project, comprising the following steps:
步骤S1、获取安全相关仪表的名义触发整定值NTSP和分析限值AL；Step S1, obtaining the nominal trigger setting value NTSP and the analysis limit AL of the safety-related instrument;
步骤S2、根据安全相关仪表的历史校验数据，计算安全相关仪表校验类监督项目在周期延长后的漂移量ADC1；根据所述漂移量ADC1计算安全相关仪表校验类监督项目在周期延长后的通道不确定度CUC1；Step S2, according to the historical calibration data of the safety-related instruments, calculate the drift amount AD C1 of the safety-related instrument calibration supervision items after the period is extended; Calculate the safety-related instrument calibration supervision items in the cycle according to the drift amount AD C1 . The extended channel uncertainty CU C1 ;
步骤S3、计算安全相关仪表的安全裕度，其中，Step S3, calculating the safety margin of the safety-related instrument, wherein,
安全相关仪表的安全裕度＝AL－CUC1－NTSP；Safety margin of safety-related instruments = AL-CU C1 -NTSP;
然后判断安全相关仪表的安全裕度是否大于0，若是，则不调整安全相关仪表的名义触发整定值NTSP，若否，则调整安全相关仪表的名义触发整定值NTSP。Then judge whether the safety margin of the safety-related instrument is greater than 0, if so, do not adjust the nominal trigger setting value NTSP of the safety-related instrument, if not, adjust the nominal trigger setting value NTSP of the safety-related instrument.
本发明上述的核电厂安全相关仪表校验类监督项目周期延长的评价方法中，在步骤S1和步骤S2之间，还包括：根据安全相关仪表的历史校验数据，确定安全相关仪表在C0周期的可接受限值ALC0；In the above-mentioned method for evaluating the period extension of the safety-related instrument verification type supervision project of the nuclear power plant of the present invention, between step S1 and step S2, the method further includes: according to the historical verification data of the safety-related instrument, determining that the safety-related instrument is in the C0 period. The acceptable limit of AL C0 ;
判断安全相关仪表的历史校验数据是否存在大于可接受限值ALC0的数据，并计算大于可接受限值ALC0的AFAL数据的数量，若AFAL数据的占比小于或等于5％，则进入步骤S2。Determine whether the historical verification data of safety-related instruments has data greater than the acceptable limit AL C0 , and calculate the number of AFAL data greater than the acceptable limit AL C0 , if the proportion of AFAL data is less than or equal to 5%, enter Step S2.
本发明上述的核电厂安全相关仪表校验类监督项目周期延长的评价方法中，所述根据安全相关仪表的历史校验数据，确定安全相关仪表在C0周期的可接受限值ALC0的步骤包括：In the above-mentioned method for evaluating the period extension of a safety-related instrument verification type supervision project in a nuclear power plant according to the present invention, the step of determining the acceptable limit value AL C0 of the safety-related instrument in the C0 period according to the historical verification data of the safety-related instrument includes the following steps: :
根据安全相关仪表的在C0期间的历史校验数据，获取安全相关仪表的精确度、C0期间的漂移量ADC0以及M&TE误差，确定安全相关仪表在C0周期的可接受限值ALC0。According to the historical calibration data of the safety-related instruments during the C0 period, the accuracy of the safety-related instruments, the drift amount AD C0 and the M&TE error during the C0 period are obtained, and the acceptable limit AL C0 of the safety-related instruments in the C0 period is determined.
本发明上述的核电厂安全相关仪表校验类监督项目周期延长的评价方法中，所述根据安全相关仪表的历史校验数据，计算安全相关仪表校验类监督项目在周期延长后的漂移量ADC1的步骤包括：In the above-mentioned method for evaluating the period extension of the safety-related instrument verification supervision items of the nuclear power plant according to the present invention, the drift amount AD of the safety-related instrument verification supervision items after the period extension is calculated according to the historical verification data of the safety-related instruments The steps for C1 include:
对安全相关仪表的AFAL数据进行正态分布验证，若通过验证，则分析安全相关仪表的在C0期间的漂移量ADC0与时间的相关性，得到分析结果；然后根据该分析结果将漂移量ADC0进行外推计算出安全相关仪表在校验类监督项目周期延长后的漂移量ADC1。Verify the normal distribution of the AFAL data of the safety-related instruments. If the verification is passed, analyze the correlation between the drift amount AD C0 of the safety-related instrument during the C0 period and time, and obtain the analysis result; then according to the analysis result, the drift amount AD is calculated. C0 is extrapolated to calculate the drift amount AD C1 of the safety-related instrument after the period of the calibration supervision project is extended.
本发明上述的核电厂安全相关仪表校验类监督项目周期延长的评价方法中，所述根据所述漂移量ADC1计算安全相关仪表校验类监督项目在周期延长后的通道不确定度CUC1的步骤根据ISA RP67.04.02标准计算得到。In the above-mentioned evaluation method for the period extension of the safety-related instrument calibration supervision items of the nuclear power plant according to the present invention, the channel uncertainty CU C1 of the safety-related instrument calibration supervision items after the period extension is calculated according to the drift amount AD C1 The steps are calculated according to the ISA RP67.04.02 standard.
本发明的核电厂安全相关仪表校验类监督项目周期延长的评价方法是整套分析评价流程和以机组安全裕度为判断依据的思路，应用该流程可以全面分析周期延长后安全相关仪表通道不确定度(包括漂移)，仪表漂移分析和不确定度计算可以采用通用的方法，将分析评价的焦点集中在电厂和监管方最关注的安全裕度上，正面分析评价周期延长后对安全相关仪表校验类监督项目的影响。本发明的核电厂安全相关仪表校验类监督项目周期延长的评价方法设计新颖，实用性强。The method for evaluating the period extension of the nuclear power plant safety-related instrument verification type supervision project of the present invention is a complete set of analysis and evaluation procedures and the idea of taking the unit safety margin as the judgment basis. The application of this procedure can comprehensively analyze the uncertainty of the safety-related instrument channel after the period is extended. A general method can be used for instrument drift analysis and uncertainty calculation, focusing on the safety margin of the power plant and the regulator, which is the most concerned by the power plant and the regulator. The impact of inspection-type supervision projects. The evaluation method for prolonging the cycle of a nuclear power plant safety-related instrument calibration type supervision project has a novel design and strong practicability.
附图说明Description of drawings
下面将结合附图及实施例对本发明作进一步说明，附图中：The present invention will be further described below in conjunction with the accompanying drawings and embodiments, in which:
图1示出了本发明优选实施例的核电厂安全相关仪表校验类监督项目周期延长的评价方法的流程图；Fig. 1 shows a flowchart of a method for evaluating the period extension of a nuclear power plant safety-related instrument verification type supervision project according to a preferred embodiment of the present invention;
图2示出了安全限值SL、分析限值AL、安全系统整定值LTSP、名义触发整定值NTSP与正常运行限值OL之间的关系示意图。Figure 2 shows a schematic diagram of the relationship between the safety limit SL, the analysis limit AL, the safety system setting LTSP, the nominal trigger setting NTSP and the normal operating limit OL.
具体实施方式Detailed ways
本发明所要解决的技术问题是：单循环的核安全相关定期试验周期可以延长的前提是试验周期延长后核安全相关设备可用性依然能够得到保障，对于非仪表类监督项目主要采用经验反馈法进行评价，而对于安全相关仪表校验类监督项目，由于仪表漂移与时间相关，而且有分析限值的约束，不宜使用经验反馈法，而应该考虑试验周期延长对仪表漂移和触发整定值的影响，而目前还没有相关的评价方法。本发明就该技术问题而提出的技术思路是：结合仪表漂移分析、不确定度计算以及仪表通道触发整定值的确定方法，开发出一套适用于安全相关仪表校验类监督项目周期延长的分析评价方法，合理评价核电厂安全相关仪表校验类监督项目周期延长对核电厂安全裕度的影响，进而合理延长试验周期，在确保核安全水平的前提下，提高核电机组能力因子和大修安排的灵活性，改善核电厂经济效益。The technical problem to be solved by the present invention is: the premise that the single-cycle nuclear safety-related periodic test period can be extended is that the availability of nuclear safety-related equipment can still be guaranteed after the test period is extended. For non-instrument supervision projects, the experience feedback method is mainly used for evaluation , and for safety-related instrument calibration supervision projects, because the instrument drift is time-related and is constrained by the analysis limit, the empirical feedback method should not be used, but the influence of the extension of the test period on the instrument drift and trigger setting value should be considered, while There is currently no relevant evaluation method. The technical idea proposed by the present invention for this technical problem is: combining the instrument drift analysis, uncertainty calculation and the determination method of the trigger setting value of the instrument channel, a set of analysis methods suitable for the period extension of the safety-related instrument calibration supervision project are developed. Evaluation method, reasonably evaluate the influence of the extension of the cycle of nuclear power plant safety-related instrument verification supervision projects on the safety margin of the nuclear power plant, and then reasonably extend the test cycle, and on the premise of ensuring the nuclear safety level, improve the nuclear power unit capability factor and overhaul arrangements. Flexibility to improve the economics of nuclear power plants.
为了使本发明的技术目的、技术方案以及技术效果更为清楚，以便于本领域技术人员理解和实施本发明，下面将结合附图及具体实施例对本发明做进一步详细的说明。In order to make the technical purpose, technical solutions and technical effects of the present invention clearer and facilitate those skilled in the art to understand and implement the present invention, the present invention will be further described in detail below with reference to the accompanying drawings and specific embodiments.
如图1所示，图1示出了本发明优选实施例的核电厂安全相关仪表校验类监督项目周期延长的评价方法的流程图。本实施例提出了一种核电厂安全相关仪表校验类监督项目周期延长的评价方法，包括以下步骤：As shown in FIG. 1 , FIG. 1 shows a flowchart of a method for evaluating the period extension of a nuclear power plant safety-related instrument verification type supervision project according to a preferred embodiment of the present invention. This embodiment proposes an evaluation method for prolonging the cycle of a nuclear power plant safety-related instrument verification type supervision project, which includes the following steps:
步骤S1、获取安全相关仪表的名义触发整定值NTSP和分析限值AL；Step S1, obtaining the nominal trigger setting value NTSP and the analysis limit AL of the safety-related instrument;
如图2所示，图2示出了安全限值SL、分析限值AL、安全系统整定值LTSP、名义触发整定值NTSP与正常运行限值OL之间的关系示意图。安全限值SL用于保证实体屏障的完整性，防止不可控的放射性释放。分析限值AL用于保证不超过安全限值SL。分析限值SL由事故分析模型获得，并要考虑如过程延迟、控制棒插入时间、反应性变化和仪表响应时间等因素。安全系统整定值LTSP用于确保在工艺条件达到分析限值SL前启动保护动作，因此可将设计基准事件的后果限值在有安全分析确定的范围内。名义触发整定值NTSP是一个预先设置在定值器组件内的数值，当监测的变量达到预设值时，定值器输出就会发生状态改变。另外，在图2中，CU表示通道不确定度；Safety Margin表示安全裕度；Operating Margin表示运行裕度。As shown in FIG. 2, FIG. 2 shows a schematic diagram of the relationship between the safety limit SL, the analysis limit AL, the safety system setting value LTSP, the nominal trigger setting value NTSP and the normal operation limit OL. The safety limit SL is used to ensure the integrity of the physical barrier against uncontrolled release of radioactivity. The analysis limit AL is used to ensure that the safety limit SL is not exceeded. The analytical limit SL is derived from the accident analysis model and takes into account factors such as process delays, control rod insertion times, reactivity changes, and instrument response times. The safety system setting LTSP is used to ensure that the protective action is initiated before the process conditions reach the analysis limit SL, so that the consequences of the design basis event can be limited within the range determined by the safety analysis. The nominal trigger setting value NTSP is a value preset in the evaluator assembly, and when the monitored variable reaches the preset value, the evaluator output will change state. In addition, in Figure 2, CU represents channel uncertainty; Safety Margin represents safety margin; Operating Margin represents operating margin.
在本步骤中，名义触发整定值NTSP主要是用于保护实测过程参数在达到安全限值SL之前，能先行产生停堆或安全动作，它包含了仪表的不确定性，其大小是由技术规格书中的系统安全设定值来指定。In this step, the nominal trigger setting value NTSP is mainly used to protect the measured process parameters before reaching the safety limit SL, the shutdown or safety action can be generated first. It includes the uncertainty of the instrument, and its size is determined by the technical specifications. Specify the system security settings in the book.
步骤S2、根据安全相关仪表的历史校验数据，计算安全相关仪表校验类监督项目在周期延长后的漂移量ADC1；根据所述漂移量ADC1计算安全相关仪表校验类监督项目在周期延长后的通道不确定度CUC1；Step S2, according to the historical verification data of the safety-related instrument, calculate the drift amount AD C1 of the safety-related instrument verification class supervision item after the period is extended; Calculate the safety-related instrument verification class supervision item in the cycle according to the drift amount AD C1 . The extended channel uncertainty CU C1 ;
所述根据安全相关仪表的历史校验数据，计算安全相关仪表在校验类监督项目周期延长后的漂移量ADC1的步骤包括：The step of calculating the drift amount AD C1 of the safety-related instrument after the period of the calibration supervision project is extended according to the historical calibration data of the safety-related instrument includes:
采集预分析的安全相关仪表及同类仪表数据，将数据进行分组，分组好的数据按统一格式处理，然后进行异常数据分析，并对该类安全相关仪表的AFAL数据进行正态分布验证，接着计算安全相关仪表的在C0期间的漂移量ADC0并分析仪表漂移的时间的相关性，得到分析结果；然后根据该分析结果将ADC0进行适当的外推计算出安全相关仪表在校验类监督项目周期延长后的漂移量ADC1。Collect pre-analyzed safety-related instrument data and similar instrument data, group the data, and process the grouped data in a unified format, then analyze abnormal data, and verify the normal distribution of the AFAL data of this type of safety-related instrument, and then calculate The drift amount AD C0 of the safety-related instrument during C0 and the time correlation of the instrument drift are analyzed to obtain the analysis result; then according to the analysis result, the AD C0 is appropriately extrapolated to calculate the safety-related instrument in the calibration supervision project Drift AD C1 after period extension.
进一步地，核电厂安全相关仪表的通道不确定度，根据计算对象不同，一般可归纳为压力、温度、流量、液位测量通道等几种类型。仪表通道不确定度的方法主要依据ISARP67.04.02标准中给出的平方和的平方根法(SRSS)和代数和方法。在本实施例中，所述根据所述漂移量ADC1计算安全相关仪表在校验类监督项目周期延长后的通道不确定度CUC1的步骤根据ISA RP67.04.02标准计算得到。Further, the channel uncertainty of safety-related instruments in nuclear power plants can generally be classified into several types such as pressure, temperature, flow, and liquid level measurement channels according to different calculation objects. The method of instrument channel uncertainty is mainly based on the square root method of the sum of squares (SRSS) and the algebraic sum method given in the ISARP67.04.02 standard. In this embodiment, the step of calculating the channel uncertainty CU C1 of the safety-related instrument after the period of the calibration supervision project is extended according to the drift amount AD C1 is calculated according to the ISA RP67.04.02 standard.
步骤S3、计算安全相关仪表的安全裕度，其中，Step S3, calculating the safety margin of the safety-related instrument, wherein,
安全相关仪表的安全裕度＝AL－CUC1－NTSP；Safety margin of safety-related instruments = AL-CU C1 -NTSP;
然后判断安全相关仪表的裕度是否大于0，若是，则不调整安全相关仪表的名义触发整定值NTSP，若否，则调整调整安全相关仪表的名义触发整定值NTSP或采取其他措施。Then judge whether the margin of the safety-related instrument is greater than 0. If so, do not adjust the nominal trigger setting value NTSP of the safety-related instrument; if not, adjust the nominal trigger setting value NTSP of the safety-related instrument or take other measures.
核电厂安全相关仪表校验类监督项目周期延长的评价方法在步骤S1之前，还包括：Before step S1, the evaluation method for the period extension of the safety-related instrument calibration supervision project of the nuclear power plant further includes:
步骤S0、对安全相关仪表做出适用性甄别，判断该安全相关仪表是否适合使用漂移分析法，若是，则进入步骤S1，若否，则应考虑其他方法保守评价。In step S0, the applicability of the safety-related instrument is screened to determine whether the safety-related instrument is suitable for using the drift analysis method. If so, go to step S1. If not, consider other methods for conservative evaluation.
在这里，对于新安全相关仪表的历史校验数据不足，或该安全相关仪表不要求不确定度计算/分析限值，或者安全相关仪表的安全功能具有明显的裕度，则安全相关仪表不适合使用漂移分析法。Here, if there is insufficient historical verification data for a new safety-related instrument, or the safety-related instrument does not require uncertainty calculation/analysis limits, or the safety-related instrument has a significant margin for its safety function, the safety-related instrument is not suitable Use drift analysis.
进一步地，核电厂安全相关仪表校验类监督项目周期延长的评价方法，在步骤S1和步骤S2之间，还包括：根据安全相关仪表的历史校验数据，确定安全相关仪表在C0周期的可接受限值ALC0；Further, the evaluation method for prolonging the cycle of a safety-related instrument verification type supervision project of a nuclear power plant, between step S1 and step S2, further includes: according to the historical verification data of the safety-related instrument, determining the availability of the safety-related instrument in the C0 cycle. Acceptance limit AL C0 ;
判断安全相关仪表的历史校验数据是否存在大于可接受限值ALC0的数据，并计算大于可接受限值ALC0的AFAL数据的数量，若AFAL数据的占比小于或等于5％，则进入步骤S2；若AFAL数据的占比大于5％，则需要评估其他选项，包括但不限于修改设计基准、修改整定值、修改校验程序、替换仪表或保持当前周期的C0的监督要求。Determine whether the historical verification data of safety-related instruments has data greater than the acceptable limit AL C0 , and calculate the number of AFAL data greater than the acceptable limit AL C0 , if the proportion of AFAL data is less than or equal to 5%, enter Step S2: If the proportion of AFAL data is greater than 5%, other options need to be evaluated, including but not limited to modifying the design basis, modifying the setting value, modifying the calibration procedure, replacing the instrument or maintaining the supervision requirements of the current cycle C0.
其中，所述根据安全相关仪表的历史校验数据，确定安全相关仪表在C0周期的可接受限值ALC0的步骤包括：Wherein, the step of determining the acceptable limit value AL C0 of the safety-related instrument in the C0 cycle according to the historical verification data of the safety-related instrument includes:
根据安全相关仪表的在C0期间的历史校验数据，获取安全相关仪表的精确度、C0期间的漂移量ADC0以及M&TE(Material&Test Equipments)误差，确定安全相关仪表在C0周期的可接受限值ALC0。According to the historical verification data of the safety-related instruments during the C0 period, the accuracy of the safety-related instruments, the drift AD C0 during the C0 period, and the M&TE (Material&Test Equipments) error are obtained, and the acceptable limit AL of the safety-related instruments in the C0 period is determined. C0 .
在这里，该安全相关仪表C0期间的可接受限值ALC0的最终确定是由相关技术人员基于安全相关仪表的精确度、C0期间的漂移量以及M&TE误差根据经验确定。Here, the final determination of the acceptable limit AL CO during the safety-related instrumentation C0 is empirically determined by the relevant skilled person based on the accuracy of the safety-related instrumentation, the amount of drift during the CO period, and the M&TE error.
本发明的核电厂安全相关仪表校验类监督项目周期延长的评价方法是整套分析评价流程和以机组安全裕度为判断依据的思路，应用该流程可以全面分析周期延长后安全相关仪表通道不确定度(包括漂移)，仪表漂移分析和不确定度计算可以采用通用的方法，将分析评价的焦点集中在电厂和监管方最关注的安全裕度上，正面分析评价周期延长后对安全相关仪表校验类监督项目的影响。本发明的核电厂安全相关仪表校验类监督项目周期延长的评价方法设计新颖，实用性强。The method for evaluating the period extension of the nuclear power plant safety-related instrument verification type supervision project of the present invention is a complete set of analysis and evaluation procedures and the idea of taking the unit safety margin as the judgment basis. The application of this procedure can comprehensively analyze the uncertainty of the safety-related instrument channel after the period is extended. A general method can be used for instrument drift analysis and uncertainty calculation, focusing on the safety margin of the power plant and the regulator, which is the most concerned by the power plant and the regulator. The impact of inspection-type supervision projects. The evaluation method for prolonging the cycle of a nuclear power plant safety-related instrument calibration type supervision project has a novel design and strong practicability.
上面结合附图对本发明的实施例进行了描述，但是本发明并不局限于上述的具体实施方式，上述的具体实施方式仅仅是示意性的，而不是限制性的，本领域的普通技术人员在本发明的启示下，在不脱离本发明宗旨和权利要求所保护的范围情况下，还可做出很多形式，这些均属于本发明的保护之内。The embodiments of the present invention have been described above in conjunction with the accompanying drawings, but the present invention is not limited to the above-mentioned specific embodiments, which are merely illustrative rather than restrictive. Under the inspiration of the present invention, without departing from the scope of protection of the present invention and the claims, many forms can be made, which all belong to the protection of the present invention.
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