WO2023087529A1 - 在线保护方法及系统 - Google Patents

在线保护方法及系统 Download PDF

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Publication number
WO2023087529A1
WO2023087529A1 PCT/CN2022/071875 CN2022071875W WO2023087529A1 WO 2023087529 A1 WO2023087529 A1 WO 2023087529A1 CN 2022071875 W CN2022071875 W CN 2022071875W WO 2023087529 A1 WO2023087529 A1 WO 2023087529A1
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Prior art keywords
lpd
dnbr
power distribution
control rod
distribution data
Prior art date
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PCT/CN2022/071875
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English (en)
French (fr)
Inventor
卢向晖
胡艺嵩
冯英杰
张一骏
王炜如
胡友森
李可嘉
何明涛
黄禹
吴宇婷
陈天铭
毛玉龙
张薇
彭思涛
程艳花
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
China General Nuclear Power Corp
China Nuclear Power Technology Research Institute Co Ltd
China Nuclear Power Engineering Co Ltd
CGN Power Co Ltd
Original Assignee
China General Nuclear Power Corp
China Nuclear Power Technology Research Institute Co Ltd
China Nuclear Power Engineering Co Ltd
CGN Power Co Ltd
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Application filed by China General Nuclear Power Corp, China Nuclear Power Technology Research Institute Co Ltd, China Nuclear Power Engineering Co Ltd, CGN Power Co Ltd filed Critical China General Nuclear Power Corp
Priority to EP22894078.9A priority Critical patent/EP4432302A4/en
Publication of WO2023087529A1 publication Critical patent/WO2023087529A1/zh
Anticipated expiration legal-status Critical
Ceased legal-status Critical Current

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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
    • G21C17/108—Measuring reactor flux
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C7/00—Control of nuclear reaction
    • G21C7/36—Control circuits
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D3/00—Control of nuclear power plant
    • G21D3/001—Computer implemented control
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
    • G21C17/12—Sensitive element forming part of control element
    • 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

Definitions

  • the invention relates to the field of nuclear power design, in particular to an online protection method and system.
  • the maximum heat flux on the surface of the fuel assembly is required to be less than the critical heat flux in the design, thus introducing DNBR (Departure from Nucleate Boiling Ratio, deviating from nucleate boiling ratio) protection.
  • DNBR Departure from Nucleate Boiling Ratio, deviating from nucleate boiling ratio
  • LPD Linear Power Density, line power density
  • DNBR and LPD are not only related to the main pump speed, cold section temperature and coolant pressure, but also related to the core power distribution data, and the core power distribution monitoring is very important to the safe operation of the reactor.
  • PWR generally detects the neutron flux in the core through neutron detectors, and then calculates the power distribution of the core regularly in combination with the monitoring data of external nuclear instruments, but the calculation accuracy of this method is not high enough, and the response time is too short. Slow, so that LPD and DNBR protection functions cannot be well realized.
  • the technical problem to be solved by the present invention lies in the defects of low calculation accuracy and slow response time in the prior art.
  • the technical solution adopted by the present invention to solve the technical problems is: construct a kind of online protection method for reactor LPD and DNBR protection, comprising:
  • Step S10 Obtain regularly updated calibration state data, wherein the calibration state data includes multiple sets of calibration state core parameter data corresponding to a plurality of different control rod positions;
  • Step S20 According to the calibrated state core parameter data corresponding to each control rod position, reconstruct and calculate the core power distribution data corresponding to each control rod position;
  • Step S30 Obtain the current control rod position in real time, and select a set of core power distribution data from multiple sets of core power distribution data as the current core power distribution data according to the current control rod position;
  • Step S40 According to the current core power distribution data, calculate the maximum value of LPD and the minimum value of DNBR corresponding to the current control rod position;
  • Step S50 According to the calculated maximum value of LPD and minimum value of DNBR, as well as the preset setting value of LPD and setting value of DNBR, it is judged whether to trigger the shutdown signal.
  • the current core power distribution data according to the following method:
  • the step S50 includes:
  • the calibration state data is obtained in the following manner:
  • Calibration state data is obtained according to a pre-established 3D model.
  • the calibration state data is obtained in the following manner:
  • the calibration state data is obtained through experiments.
  • the calibration state data is obtained in the following manner:
  • the neutron flux in the core is detected by multiple neutron detectors arranged in the reactor.
  • the present invention also constructs an online protection system for reactor LPD and DNBR protection, including:
  • An acquisition module configured to acquire regularly updated calibration state data, wherein the calibration state data includes multiple sets of calibration state core parameter data corresponding to a plurality of different control rod positions;
  • the power reconstruction module is used to reconstruct and calculate the core power distribution data corresponding to each control rod position according to the calibrated state core parameter data corresponding to each control rod position;
  • the determining module is used to obtain the current control rod position in real time, and select a set of core power distribution data from multiple sets of core power distribution data as the current core power distribution data according to the current control rod position ;
  • a calculation module configured to calculate the maximum value of LPD and the minimum value of DNBR corresponding to the current control rod position according to the current core power distribution data
  • the judging module is used to judge whether to trigger the shutdown signal according to the calculated maximum value of LPD and minimum value of DNBR, as well as the preset setting value of LPD and setting value of DNBR.
  • the determination module is configured to subtract the total rod positions of the plurality of control rods in the calibration state data from the current control rod positions respectively, and the control rod positions corresponding to the smallest positive number with the difference value A set of core power distribution data of is used as the current core power distribution data.
  • the judging module includes:
  • the first judging subunit is used to judge whether the calculated maximum value of LPD is greater than a preset LPD setting value
  • the second judging subunit is used to judge whether the calculated minimum value of DNBR is less than a preset DNBR setting value
  • the shutdown trigger unit is configured to trigger a shutdown signal when the maximum value of LPD is greater than the set value of LPD, or the minimum value of DNBR is smaller than the set value of DNBR.
  • the acquiring module is used to acquire calibration state data by periodically performing three-dimensional simulation or experiment on the operation of the reactor in each calibration state.
  • Fig. 1 is a flow chart of Embodiment 1 of the online protection method of the present invention
  • Fig. 2 is a logical structure diagram of Embodiment 1 of the online protection system of the present invention.
  • the control rods as a tool for rapid control of reactivity, can adjust the power of the reactor during normal operation, and quickly introduce negative reactivity under accident conditions to shut down the reactor quickly. Tests have proved that the total rod position of the control rods also affects the power distribution of the reactor. Based on this, in the technical solution of this application, first, according to the total number of control rod insertion steps, different full-core power distributions are reconstructed in sections, and then a section of the reconstructed full-core power is selected according to the total rod position on site. distribution, and then determine the values of LPD and DNBR in real time on site. This method can reduce the calculation uncertainty, improve the response speed of protection, and obtain more safety margins.
  • Fig. 1 is the flowchart of embodiment one of online protection method of the present invention, and the online protection method of this embodiment is used for reactor LPD and DNBR protection, and comprises the following steps:
  • Step S10 Obtain regularly updated calibration state data, wherein the calibration state data includes multiple sets of calibration state core parameter data corresponding to a plurality of different control rod positions;
  • the core parameter data refers to the derivation coefficient matrix for power reconstruction calculation, and, using the derivation coefficient matrix, the current moment can be reconstructed according to the detection signals of multiple detectors (SPND) obtained in real time.
  • SPND multiple detectors
  • the power of each fuel assembly in the whole core for example, in the 177 core, the number of detectors is 42, and each detector has a total of 7 measurement points in the axial direction, then, the corresponding derivation can be used
  • the coefficient matrix reconstructs the three-dimensional power distribution of the 177 core according to 42*7 detection signals.
  • the calibration state core parameter data when the master rod position is R1; the calibration state core parameter data when the master rod position is R2; Core parameter data in calibration state when the position is R3; core parameter data in calibration state when the master rod is in position R4.
  • R1 the calibration state core parameter data when the master rod position is R1
  • R2 the calibration state core parameter data when the master rod position is R2
  • Core parameter data in calibration state when the position is R3 core parameter data in calibration state when the master rod is in position R4.
  • a trade-off is generally made in engineering, for example, to obtain the three groups corresponding to the three total rod positions Calibration state core parameter data.
  • the calibration state data is obtained according to the pre-established 3D model. Specifically, the theoretical physics library of the core is calculated by using 3D physics software to obtain the calibration state data. Core theoretical state data, that is, the calibration state data calculated according to the three-dimensional theory.
  • the calibration state data is obtained through experiments, and when the reactor is running in each calibration state, the neutron flux in the core is detected by a plurality of neutron detectors arranged in the reactor. , and calculate the core flux map based on the neutron flux in the core. Specifically, during the reactor start-up test, the state of the control rods of the reactor core is adjusted to the rod position state of the calibration state, and the test data obtained at this time is the data of the calibration state of the test.
  • the calibration state data can be generated or updated by the host computer (non-safety level equipment), and periodically sent to the lower computer (safety level equipment), that is, the lower computer obtains the regularly updated calibration data from the upper computer. The moment data, and then execute step S20 to step S50.
  • Step S20 According to the calibrated state core parameter data corresponding to each control rod position, reconstruct and calculate the core power distribution data corresponding to each control rod position;
  • the weight coefficient method, coupling coefficient method or harmonic synthesis method can be used to reconstruct the core power distribution data, and, according to the calibration state core parameters corresponding to different master rod positions
  • Data reconstruction of different full-core power distribution data for example, according to the calibration state core parameter data at the master rod position R1 to reconstruct the whole core power distribution corresponding to the master rod position R1, according to the total core power distribution at the master rod position R2 Reconstruct the power distribution of the whole core corresponding to the master rod position R2 from the calibration state core parameter data, and reconstruct the whole core power distribution corresponding to the master rod position R3 according to the calibration state core parameter data when the master rod position is R3 , according to the calibration state core parameter data at the master rod position R4, the power distribution of the whole core corresponding to the master rod position R4 is reconstructed.
  • Step S30 Obtain the current control rod position in real time, and select a set of core power distribution data from multiple sets of core power distribution data as the current core power distribution data according to the current control rod position;
  • the rod position measurement signal of each rod of the control rods can be obtained from the measurement mechanism, so as to obtain the current total rod position of the control rods.
  • a set of core power distribution data is selected from multiple sets of core power distribution data according to the current slave rod position, and used as the current core power distribution data.
  • Step S40 According to the current core power distribution data, calculate the maximum value of LPD and the minimum value of DNBR corresponding to the current control rod position;
  • the current core power distribution data can be used to calculate the LPD value and DNBR value of each occurrence point of each fuel assembly under the current master rod position. It should be understood that LPD and The calculation methods of DNBR are all existing methods, and will not be repeated here. Then, determine the maximum LPD value from the calculated LPD values, and determine the DNBR minimum value from the calculated DNBR values. For example, if a core has 177 fuel assemblies, and each assembly There are 44 occurrence points, then 177*44 LPD values and 177*44 DNBR values will be generated.
  • Step S50 According to the calculated maximum value of LPD and minimum value of DNBR, as well as the preset setting value of LPD and setting value of DNBR, it is judged whether to trigger the shutdown signal.
  • both the LPD setting value and the DNBR setting value are set in advance according to the accident analysis results.
  • the current core power distribution data can be obtained according to the following method: subtracting a plurality of control rod positions in the calibration state data from the current control rod positions respectively, A set of core power distribution data corresponding to the total rod positions of the control rods whose difference is the smallest positive number is taken as the current core power distribution data.
  • the current master rod position of the core control rod is R
  • R if 0 ⁇ R ⁇ R1, select the core power distribution data corresponding to the master rod position R1 to calculate the minimum value of DNBR and the maximum value of LPD
  • R3 ⁇ R ⁇ R4 select the core power distribution data corresponding to the master rod position R4 to calculate the minimum value of DNBR and the maximum value of LPD.
  • step S50 includes:
  • FIG. 2 is a logical structure diagram of Embodiment 1 of the online protection system of the present invention, the online protection system is used for reactor LPD and DNBR protection, and includes: an acquisition module 10, a power reconfiguration module 20, a determination module 30, a calculation module 40 and a judgment Module 50, wherein the acquisition module 10 is used to acquire regularly updated calibration state data, wherein the calibration state data includes multiple sets of calibration state core parameter data corresponding to a plurality of different control rod positions
  • the power reconstruction module 20 is used to reconstruct and calculate the core power distribution data corresponding to each control rod total rod position respectively according to the calibration state core parameter data corresponding to each control rod total rod position;
  • the determination module 30 is used to obtain the current control rod position in real time, and select a set of core power distribution data from multiple sets of core power distribution data as the current core power distribution data according to the current control rod position; calculate
  • the module 40 is used to calculate the maximum value of LPD and the minimum value of DNBR corresponding to the current control rod position according to the current core power distribution data
  • the acquiring module 10 is used to acquire calibration state data by regularly performing three-dimensional simulation or experiment on the operation of the reactor in each calibration state.
  • the determination module 30 is used to subtract the total rod positions of the plurality of control rods in the calibration state data from the current control rod total rod positions respectively, and the difference value is the one corresponding to the control rod total rod positions with the smallest positive number.
  • the group core power distribution data is used as the current core power distribution data.
  • the judging module 40 includes a first judging subunit, a second judging subunit and a shutdown triggering unit, wherein the first judging subunit is used to judge whether the calculated maximum value of LPD is greater than a preset LPD setting value; The second judging subunit is used to judge whether the calculated minimum value of DNBR is less than the preset DNBR setting value; the shutdown trigger unit is used to determine whether the maximum value of LPD is greater than the setting value of LPD, or the minimum value of DNBR is less than the preset value When the above DNBR setting value is exceeded, the shutdown signal is triggered.

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Abstract

一种在线保护方法及系统，该在线保护方法包括：获取定期更新的校刻态数据（S10）；对各个控制棒总棒位分别所对应的堆芯功率分布数据进行重构计算（S20）；实时获取当前的控制棒总棒位，并从多组堆芯功率分布数据中选择出一组堆芯功率分布数据作为当前堆芯功率分布数据（S30）；计算当前的控制棒总棒位所对应的LPD最大值和DNBR最小值（S40）；根据所计算的LPD最大值和DNBR最小值，以及预设的LPD整定值和DNBR整定值，判断是否触发停堆信号（S50）。

Description

在线保护方法及系统 技术领域
本发明涉及核电设计领域，尤其涉及一种在线保护方法及系统。
 背景技术
为保证反应堆安全，在设计中要求燃料组件表面的最大热流密度小于临界热流密度，从而引入了DNBR（Departure from Nucleate Boiling Ratio，偏离泡核沸腾比）保护。同时，为了避免堆芯线功率密度过高，引入了LPD（Linear Power Density，线功率密度）保护。
DNBR及LPD计算除了与主泵转速、冷段温度、冷却剂压力有关外，还与堆芯功率分布数据有关，而且，堆芯功率分布监测对反应堆安全运行至关重要。目前，压水堆一般通过中子探测器对堆芯中子通量进行探测，再结合堆外核仪表监测数据来定期计算堆芯功率分布，但这种方式计算精度不够高，且响应时间也较慢，从而无法很好地实现LPD和DNBR保护功能。
 技术问题
本发明要解决的技术问题在于，现有技术存在的计算精度不高且响应时间较慢的缺陷。
 技术解决方案
本发明解决其技术问题所采用的技术方案是：构造一种在线保护方法，用于反应堆LPD和DNBR保护，包括：
步骤S10.获取定期更新的校刻态数据，其中，所述校刻态数据包括多个不同的控制棒总棒位分别所对应的多组校刻态堆芯参数数据；
步骤S20.根据各个控制棒总棒位分别所对应的校刻态堆芯参数数据，对各个控制棒总棒位分别所对应的堆芯功率分布数据进行重构计算；
步骤S30.实时获取当前的控制棒总棒位，并根据当前的控制棒总棒位，从多组堆芯功率分布数据中选择出一组堆芯功率分布数据作为当前堆芯功率分布数据；
步骤S40.根据所述当前堆芯功率分布数据，计算当前的控制棒总棒位所对应的LPD最大值和DNBR最小值；
步骤S50.根据所计算的LPD最大值和DNBR最小值，以及预设的LPD整定值和DNBR整定值，判断是否触发停堆信号。
优选地，在所述步骤S30中，根据以下方式当前堆芯功率分布数据：
将校刻态数据中的多个控制棒总棒位分别与当前的控制棒总棒位相减，将差值为最小的正数的控制棒总棒位所对应的一组堆芯功率分布数据作为当前堆芯功率分布数据。
优选地，所述步骤S50包括：
判断所计算的LPD最大值是否大于预设的LPD整定值；
判断所计算的DNBR最小值是否小于预设的DNBR整定值；
若所述LPD最大值大于所述LPD整定值，或者，所述DNBR最小值小于所述DNBR整定值，则触发停堆信号。
优选地，在所述步骤S10中，根据以下方式获取校刻态数据：
根据预先建立的三维模型来获取校刻态数据。
优选地，在所述步骤S10中，根据以下方式获取校刻态数据：
通过试验的方式来获取校刻态数据。
优选地，在所述步骤S10中，根据以下方式获取校刻态数据：
反应堆在各个校刻态下运行时，通过设置在堆内的多个中子探测器来探测堆芯中子通量。
本发明还构造一种在线保护系统，用于反应堆LPD和DNBR保护，包括：
获取模块，用于获取定期更新的校刻态数据，其中，所述校刻态数据包括多个不同的控制棒总棒位分别所对应的多组校刻态堆芯参数数据；
功率重构模块，用于根据各个控制棒总棒位分别所对应的校刻态堆芯参数数据，对各个控制棒总棒位分别所对应的堆芯功率分布数据进行重构计算；
确定模块，用于实时获取当前的控制棒总棒位，并根据当前的控制棒总棒位，从多组堆芯功率分布数据中选择出一组堆芯功率分布数据作为当前堆芯功率分布数据；
计算模块，用于根据所述当前堆芯功率分布数据，计算当前的控制棒总棒位所对应的LPD最大值和DNBR最小值；
判断模块，用于根据所计算的LPD最大值和DNBR最小值，以及预设的LPD整定值和DNBR整定值，判断是否触发停堆信号。
优选地，所述确定模块，用于将校刻态数据中的多个控制棒总棒位分别与当前的控制棒总棒位相减，将差值为最小的正数的控制棒总棒位所对应的一组堆芯功率分布数据作为当前堆芯功率分布数据。
优选地，所述判断模块包括：
第一判断子单元，用于判断所计算的LPD最大值是否大于预设的LPD整定值；
第二判断子单元，用于判断所计算的DNBR最小值是否小于预设的DNBR整定值；
停堆触发单元，用于在所述LPD最大值大于所述LPD整定值，或者，所述DNBR最小值小于所述DNBR整定值时，触发停堆信号。
优选地，所述获取模块，用于通过定期对反应堆在各个校刻态下的运行进行三维模拟或试验来获取校刻态数据。
 有益效果
在本发明所提供的技术方案中，在获取到定期更新的校刻态数据（多个不同的控制棒总棒位分别所对应的多组校刻态堆芯参数数据）后，按照不同的控制棒总棒位分段重构不同的全堆芯功率分布，然后再根据现场的实时总棒位来从多组全堆芯功率分布数据中选择出一组全堆芯功率分布数据，进而实时确定实时的LPD最大值和DNBR最小值，这种方法不但能够降低计算不确定度，而且可提高保护的响应速度。
 附图说明
图1是本发明在线保护方法实施例一的流程图；
图2是本发明在线保护系统实施例一的逻辑结构图。
 本发明的实施方式
下面将结合本发明实施例中的附图，对本发明实施例中的技术方案进行清楚、完整地描述，显然，所描述的实施例仅仅是本发明一部分实施例，而不是全部的实施例。基于本发明中的实施例，本领域普通技术人员在没有做出创造性劳动前提下所获得的所有其他实施例，都属于本发明保护的范围。
首先说明的是，控制棒作为一种快速控制反应性的工具，可在正常运行时调节反应堆的功率，在事故工况下快速引入负反应性，使反应堆快速停堆。试验证明，控制棒的总棒位也影响反应堆的功率分布。基于此，在本申请的技术方案中，首先按照不同的控制棒插入总步数，分段重构不同的全堆芯功率分布，然后再根据现场的总棒位选择一段重构后的全堆芯功率分布，进而现场实时确定LPD与DNBR取值，这种方法能够降低计算不确定度，而且可提高保护的响应速度，获得更多的安全裕量。
图1是本发明在线保护方法实施例一的流程图，该实施例的在线保护方法用于反应堆LPD和DNBR保护，且包括以下步骤：
步骤S10.获取定期更新的校刻态数据，其中，所述校刻态数据包括多个不同的控制棒总棒位分别所对应的多组校刻态堆芯参数数据；
在该步骤中，堆芯参数数据是指进行功率重构计算的推衍系数矩阵，而且，利用该推衍系数矩阵，可根据实时得到的多个探测器（SPND）的探测信号重构出此刻全堆芯每个燃料组件的功率，例如，在177堆芯中，探测器的数量为42个，且每个探测器在轴向上共有7个测量点，那么，便可利用相应的推衍系数矩阵，根据42*7个探测信号重构出该177堆芯的三维功率分布。另外，校刻态数据有多组，分别对应不同的总棒位，例如，总棒位R1时的校刻态堆芯参数数据；总棒位R2时的校刻态堆芯参数数据；总棒位R3时的校刻态堆芯参数数据；总棒位R4时的校刻态堆芯参数数据。应理解，堆芯参数数据分的组数越多，计算的越精准，但同时也增加了计算量，因此，工程上一般会做权衡，比如，获取3个总棒位分别所对应的三组校刻态堆芯参数数据。
关于校刻态数据的获取方式，在一个具体例子中，根据预先建立的三维模型来获取校刻态数据，具体地，采用三维物理软件计算堆芯的理论物理库，获得校刻态情况下的堆芯理论状态数据，即，根据三维理论计算的校刻态数据。在另一个具体例子中，通过试验的方式来获取校刻态数据，而且，在反应堆在各个校刻态下运行时，通过设置在堆内的多个中子探测器来探测堆芯中子通量，并根据堆芯中子通量来计算堆芯通量图。具体地，在反应堆启堆试验时，将堆芯的控制棒等状态调整到校刻态的棒位状态，此时得到的试验数据就是试验的校刻态数据。
另外，需说明的是，校刻态数据可由上位机（非安全级设备）生成或更新，并定期将其传送至下位机（安全级设备），即，下位机从上位机获取定期更新的校刻态数据，然后执行步骤S20至步骤S50。
步骤S20.根据各个控制棒总棒位分别所对应的校刻态堆芯参数数据，对各个控制棒总棒位分别所对应的堆芯功率分布数据进行重构计算；
在该步骤中，在进行堆芯功率分布数据的重构计算时，可采用权重系数法、耦合系数法或谐波综合法，而且，分别根据不同总棒位所对应的校刻态堆芯参数数据重构不同的全堆芯功率分布数据，例如，根据总棒位R1时的校刻态堆芯参数数据重构出对应总棒位R1的全堆芯功率分布，根据总棒位R2时的校刻态堆芯参数数据重构出对应总棒位R2的全堆芯功率分布，根据总棒位R3时的校刻态堆芯参数数据重构出对应总棒位R3的全堆芯功率分布，根据总棒位R4时的校刻态堆芯参数数据重构出对应总棒位R4的全堆芯功率分布。
步骤S30.实时获取当前的控制棒总棒位，并根据当前的控制棒总棒位，从多组堆芯功率分布数据中选择出一组堆芯功率分布数据作为当前堆芯功率分布数据；
在该步骤中，需说明的是，可从测量机构获取控制棒的各个棒的棒位测量信号，从而获取控制棒的当前总棒位。在获取到当前的控制棒总棒位后，再根据当前的从棒位从多组堆芯功率分布数据中选择出一组堆芯功率分布数据，并将其作为当前堆芯功率分布数据。
步骤S40.根据所述当前堆芯功率分布数据，计算当前的控制棒总棒位所对应的LPD最大值和DNBR最小值；
在该步骤中，在确定出当前堆芯功率分布数据后，可利用该当前堆芯功率分布数据计算当前总棒位下各燃料组件的各发生点的LPD值和DNBR值，应理解，LPD及DNBR的计算方法均为现有方法，在此不做赘述。然后，从计算出的多个LPD值中确定出LPD最大值，以及，从计算出的多个DNBR值中确定出DNBR最小值，例如，假如某堆芯有177个燃料组件，且每个组件有44个发生点，那么将产生177*44个LPD值及177*44个DNBR值。
步骤S50.根据所计算的LPD最大值和DNBR最小值，以及预设的LPD整定值和DNBR整定值，判断是否触发停堆信号。
在该步骤中，需说明的是，LPD整定值和DNBR整定值均是根据事故分析结果提前设定的。
进一步地，在一个具体实施例中，在步骤S30中，可根据以下方式当前堆芯功率分布数据：将校刻态数据中的多个控制棒总棒位分别与当前的控制棒总棒位相减，将差值为最小的正数的控制棒总棒位所对应的一组堆芯功率分布数据作为当前堆芯功率分布数据。例如，假设某一时刻，堆芯控制棒的当前总棒位为R，若0≤R≤R1时，选用对应总棒位R1的堆芯功率分布数据计算DNBR最小值和LPD最大值；若R1<R≤R2时，选用对应总棒位R2的堆芯功率分布数据计算DNBR最小值和LPD最大值；若R2<R≤R3时，选用对应总棒位R3的堆芯功率分布数据计算DNBR最小值和LPD最大值；若R3<R≤R4时，选用对应总棒位R4的堆芯功率分布数据计算DNBR最小值和LPD最大值。
进一步地，在一个具体实施例中，步骤S50包括：
判断所计算的LPD最大值是否大于预设的LPD整定值；
判断所计算的DNBR最小值是否小于预设的DNBR整定值；
若所述LPD最大值大于所述LPD整定值，或者，所述DNBR最小值小于所述DNBR整定值，则触发停堆信号。
图2是本发明在线保护系统实施例一的逻辑结构图，该在线保护系统用于反应堆LPD和DNBR保护，且包括：获取模块10、功率重构模块20、确定模块30、计算模块40和判断模块50，其中，获取模块10用于获取定期更新的校刻态数据，其中，所述校刻态数据包括多个不同的控制棒总棒位分别所对应的多组校刻态堆芯参数数据；功率重构模块20用于根据各个控制棒总棒位分别所对应的校刻态堆芯参数数据，对各个控制棒总棒位分别所对应的堆芯功率分布数据进行重构计算；确定模块30用于实时获取当前的控制棒总棒位，并根据当前的控制棒总棒位，从多组堆芯功率分布数据中选择出一组堆芯功率分布数据作为当前堆芯功率分布数据；计算模块40用于根据所述当前堆芯功率分布数据，计算当前的控制棒总棒位所对应的LPD最大值和DNBR最小值；判断模块50用于根据所计算的LPD最大值和DNBR最小值，以及预设的LPD整定值和DNBR整定值，判断是否触发停堆信号。
进一步地，获取模块10用于通过定期对反应堆在各个校刻态下的运行进行三维模拟或试验来获取校刻态数据。
进一步地，确定模块30用于将校刻态数据中的多个控制棒总棒位分别与当前的控制棒总棒位相减，将差值为最小的正数的控制棒总棒位所对应的一组堆芯功率分布数据作为当前堆芯功率分布数据。
进一步地，判断模块40包括第一判断子单元、第二判断子单元和停堆触发单元，其中，第一判断子单元用于判断所计算的LPD最大值是否大于预设的LPD整定值；第二判断子单元用于判断所计算的DNBR最小值是否小于预设的DNBR整定值；停堆触发单元用于在所述LPD最大值大于所述LPD整定值，或者，所述DNBR最小值小于所述DNBR整定值时，触发停堆信号。
以上所述仅为本发明的优选实施例而已，并不用于限制本发明，对于本领域的技术人员来说，本发明可以有各种更改和变化。凡在本发明的精神和原则之内，所作的任何纂改、等同替换、改进等，均应包含在本发明的权利要求范围之内。

Claims (10)

  1. 一种在线保护方法，用于反应堆LPD和DNBR保护，其特征在于，包括：
    步骤S10.获取定期更新的校刻态数据，其中，所述校刻态数据包括多个不同的控制棒总棒位分别所对应的多组校刻态堆芯参数数据；
    步骤S20.根据各个控制棒总棒位分别所对应的校刻态堆芯参数数据，对各个控制棒总棒位分别所对应的堆芯功率分布数据进行重构计算；
    步骤S30.实时获取当前的控制棒总棒位，并根据当前的控制棒总棒位，从多组堆芯功率分布数据中选择出一组堆芯功率分布数据作为当前堆芯功率分布数据；
    步骤S40.根据所述当前堆芯功率分布数据，计算当前的控制棒总棒位所对应的LPD最大值和DNBR最小值；
    步骤S50.根据所计算的LPD最大值和DNBR最小值，以及预设的LPD整定值和DNBR整定值，判断是否触发停堆信号。
  2. 根据权利要求1所述的在线保护方法，其特征在于，在所述步骤S30中，根据以下方式当前堆芯功率分布数据：
    将校刻态数据中的多个控制棒总棒位分别与当前的控制棒总棒位相减，将差值为最小的正数的控制棒总棒位所对应的一组堆芯功率分布数据作为当前堆芯功率分布数据。
  3. 根据权利要求1所述的在线保护方法，其特征在于，所述步骤S50包括：
    判断所计算的LPD最大值是否大于预设的LPD整定值；
    判断所计算的DNBR最小值是否小于预设的DNBR整定值；
    若所述LPD最大值大于所述LPD整定值，或者，所述DNBR最小值小于所述DNBR整定值，则触发停堆信号。
  4. 根据权利要求1所述的在线保护方法，其特征在于，在所述步骤S10中，根据以下方式获取校刻态数据：
    根据预先建立的三维模型来获取校刻态数据。
  5. 根据权利要求1所述的在线保护方法，其特征在于，在所述步骤S10中，根据以下方式获取校刻态数据：
    通过试验的方式来获取校刻态数据。
  6. 根据权利要求5所述的在线保护方法，其特征在于，在所述步骤S10中，根据以下方式获取校刻态数据：
    反应堆在各个校刻态下运行时，通过设置在堆内的多个中子探测器来探测堆芯中子通量。
  7. 一种在线保护系统，用于反应堆LPD和DNBR保护，其特征在于，包括：
    获取模块，用于获取定期更新的校刻态数据，其中，所述校刻态数据包括多个不同的控制棒总棒位分别所对应的多组校刻态堆芯参数数据；
    功率重构模块，用于根据各个控制棒总棒位分别所对应的校刻态堆芯参数数据，对各个控制棒总棒位分别所对应的堆芯功率分布数据进行重构计算；
    确定模块，用于实时获取当前的控制棒总棒位，并根据当前的控制棒总棒位，从多组堆芯功率分布数据中选择出一组堆芯功率分布数据作为当前堆芯功率分布数据；
    计算模块，用于根据所述当前堆芯功率分布数据，计算当前的控制棒总棒位所对应的LPD最大值和DNBR最小值；
    判断模块，用于根据所计算的LPD最大值和DNBR最小值，以及预设的LPD整定值和DNBR整定值，判断是否触发停堆信号。
  8. 根据权利要求7所述的在线保护系统，其特征在于，
    所述确定模块，用于将校刻态数据中的多个控制棒总棒位分别与当前的控制棒总棒位相减，将差值为最小的正数的控制棒总棒位所对应的一组堆芯功率分布数据作为当前堆芯功率分布数据。
  9. 根据权利要求7所述的在线保护系统，其特征在于，所述判断模块包括：
    第一判断子单元，用于判断所计算的LPD最大值是否大于预设的LPD整定值；
    第二判断子单元，用于判断所计算的DNBR最小值是否小于预设的DNBR整定值；
    停堆触发单元，用于在所述LPD最大值大于所述LPD整定值，或者，所述DNBR最小值小于所述DNBR整定值时，触发停堆信号。
  10. 根据权利要求7所述的在线保护系统，其特征在于，
    所述获取模块，用于通过定期对反应堆在各个校刻态下的运行进行三维模拟或试验来获取校刻态数据。
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