CN108962411B - Method for improving nuclear power generating unit output based on reactor core monitoring - Google Patents

Method for improving nuclear power generating unit output based on reactor core monitoring Download PDF

Info

Publication number
CN108962411B
CN108962411B CN201810802991.3A CN201810802991A CN108962411B CN 108962411 B CN108962411 B CN 108962411B CN 201810802991 A CN201810802991 A CN 201810802991A CN 108962411 B CN108962411 B CN 108962411B
Authority
CN
China
Prior art keywords
power
nuclear
value
reactor core
thermal power
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Active
Application number
CN201810802991.3A
Other languages
Chinese (zh)
Other versions
CN108962411A (en
Inventor
李国仁
曹广玉
丁兆建
李昕洁
李斌
裴征
袁潇
阳珍妮
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
Guangxi Fangchenggang Nuclear Power Co Ltd
Original Assignee
China General Nuclear Power Corp
Guangxi Fangchenggang Nuclear Power Co Ltd
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by China General Nuclear Power Corp, Guangxi Fangchenggang Nuclear Power Co Ltd filed Critical China General Nuclear Power Corp
Priority to CN201810802991.3A priority Critical patent/CN108962411B/en
Publication of CN108962411A publication Critical patent/CN108962411A/en
Application granted granted Critical
Publication of CN108962411B publication Critical patent/CN108962411B/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Images

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C17/00Monitoring; Testing ; Maintaining
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • 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 discloses a method for improving the output of a nuclear power generating unit based on reactor core monitoring, which comprises the following steps: the real-time information monitoring system records each reactor core parameter value of each second every day; step two: carrying out data processing on various reactor core parameter values recorded every second; step three: analyzing various reactor core parameters after data processing; step four: finding out various factors influencing the output of the unit; step five: making countermeasures aiming at various factors influencing the output of the unit; and step six: and transmitting the analysis result to relevant professional departments of the power plant in time every day, and simultaneously adjusting the core power of the reactor by an operator according to the curing treatment measures to improve the output of the unit. The method improves the generating efficiency of the nuclear generating set, increases the income of a power plant, ensures the safe operation of the generating set and establishes a complete operation flow for improving the output of the generating set.

Description

Method for improving nuclear power generating unit output based on reactor core monitoring
Technical Field
The invention relates to the field of nuclear power generation, in particular to a method for improving the output of a nuclear power generation unit based on reactor core monitoring.
Background
Nuclear reactor core monitoring is an important task for core physics technicians. The operation is mainly to monitor whether the reactor is operated safely and predict whether the reactor has potential risks by analyzing various parameters of the reactor core (power, temperature, pressure, water level, boron concentration, quadrant power inclination, axial power deviation, burnup and the like).
Reactor core thermal power control is one of the main reasons affecting the output of the unit. Under the condition that the efficiency of the unit generator is stable, the thermal power of the reactor core of the reactor is reasonably improved, and the electric power of the unit generator can be effectively improved (the thermal power of the reactor core of the reactor is improved by 3WM, which is equivalent to the electric power of the generator of the reactor core of the reactor of 1WM, and 1000-DEG electricity can be generated more in 1 hour).
Factors influencing the instability of the thermal power of the reactor core include fuel consumption, temperature, Gk parameters (nuclear power correction coefficient), power grid load limitation, large seawater temperature change and the like. In the actual operation process, technicians can not only evaluate the safety of the reactor core through daily core monitoring, but also estimate whether the output of the unit is improved or not every day through analyzing corresponding data of the core monitoring.
Reactor core monitoring is one way to assess whether the reactor is operating safely. The monitoring contents mainly record the reactor core thermal power, the primary circuit average temperature, the primary circuit reference temperature and other parameters. And processing data of each parameter to obtain the nuclear heat power deviation of the reactor, the average value of the heat power of a loop, the average value of the average temperature of the loop and the average value of the reference temperature of the loop. And then evaluating the reactor core, and giving the deviation of the current reactor core power and the actual core power and the safety operation degree of the reactor core.
By detecting the power parameters of the reactor, the method not only can guide an operator to improve the thermal power of the reactor core of the reactor and enable the unit to generate electricity to the maximum, but also can prejudge the predegree of the thermal power available every day and the predegree of the available electric power. Meanwhile, the economic benefit of the power plant is guaranteed.
Therefore, it is imperative to develop a method for improving the output of a nuclear power generating unit based on reactor core monitoring.
The information disclosed in this background section is only for enhancement of understanding of the general background of the invention and should not be taken as an acknowledgement or any form of suggestion that this information forms the prior art already known to a person skilled in the art.
Disclosure of Invention
The invention aims to provide a method for improving the power of a nuclear power generating unit based on reactor core monitoring, which can be used for prejudging the predegree of thermal power available every day and the predegree of available electric power according to the change condition of thermal power of a reactor core monitored every day. According to the method, the thermal power budget available every day is judged in advance, and on the premise that the thermal power of the reactor core does not exceed 100% FP, an operator is guided to improve the thermal power of the reactor core of the reactor, so that the unit generates electricity to the maximum extent. And according to the predicted available electric power degree every day, giving out possible reasons that the available degree is larger than the limit value. And simultaneously, according to the analysis reason, giving influence factors influencing the output of the unit and corresponding treatment suggestions. The output of the unit is improved, the generated energy is increased, and the economic benefit of the power plant is improved.
In order to achieve the above object, the present invention provides a method for improving the output of a nuclear power generating unit based on reactor core monitoring, which comprises the following steps:
the method comprises the following steps: the real-time information monitoring system records each reactor core parameter value of each second every day;
step two: carrying out data processing on various reactor core parameter values recorded every second;
step three: analyzing various reactor core parameters after data processing;
step four: finding out various factors influencing the output of the unit;
step five: making countermeasures aiming at various factors influencing the output of the unit; and
step six: and transmitting the analysis result to relevant professional departments of the power plant in time every day, and simultaneously adjusting the core power of the reactor by an operator according to the curing treatment measures to improve the output of the unit.
In a preferred embodiment, step one is to record the reactor core thermal power, the primary circuit average temperature, the primary circuit reference temperature, the 8 hour wait moving average thermal power and the electrical power from 0 to 8 points per day.
In a preferred embodiment, the average value, the maximum value, the minimum value, the maximum average value, the minimum average value and the average floating value of each core parameter can be obtained through the second step.
In a preferred embodiment, the three steps can obtain daily available electric power pre-degree and available thermal power pre-degree, theoretical available electric power pre-degree and theoretical available thermal power pre-degree, 8-hour sliding average thermal power, single-channel nuclear thermal power maximum average deviation and peak value and maximum channel nuclear power average value.
In a preferred embodiment, the fourth step further comprises comparing the difference between the available electric power budget and the available thermal power budget and the rated power value, and the difference between the theoretically available electric power budget and the theoretically available thermal power budget and the full load power value is larger than a limit value, so as to analyze various factors influencing the output of the unit.
In a preferred embodiment, 5 cases and treatment measures including the following can be found out through the fourth step and the fifth step:
1) when the nuclear power peak value reaches 101.5 percent FP, the fluctuation of the nuclear power peak value is large or the average deviation is large, the processing measures at the moment are that fuel management technicians implement adjustment of the nuclear power correction coefficient and the deviation of the display value and the actual value of the core thermal power is reduced;
2) when the nuclear power is reduced due to the defects of the test or the equipment within 8 hours, the processing measures at the moment are to ask operating personnel to continuously pay attention to various works influencing the output of the unit, and the power is timely increased after the works are finished;
3) when the load of the power grid is limited, the processing measures at the moment are to ask operating personnel to communicate with the power grid in time, and the power is increased in time after the peak regulation is finished;
4) when the setting value of the electric power is adjusted and changed but not adjusted back in time, the current processing measure is to ask an operator to adjust the setting value in time; and
5) when the temperature change of the seawater is overlarge, in order to avoid frequent adjustment, the treatment measures at the moment are to ask operating personnel to continuously pay attention to the cold source so as to keep the power of the reactor core stable.
In a preferred embodiment, the nominal power value is 99.85% of the full load power value.
In a preferred embodiment, the limit is 3 MW.
In a preferred embodiment, the method further comprises analyzing and providing specific provisions for adjusting the nuclear power correction factor, which includes calculating the maximum average deviation of the reactor nuclear power from the reactor thermal power as the maximum average deviation value of the nuclear thermal power from the data derived from the nuclear power plant computer information and the control system, wherein:
when the maximum average deviation value of the nuclear thermal power is less than or equal to 1.0 percent, the nuclear thermal power is normal;
when the maximum average deviation value of the nuclear thermal power is larger than 1.5 percent;
when the maximum average deviation value of the nuclear thermal power is larger than 1.0% and the nuclear power peak value of the reactor is larger than or equal to 101.5% FP, starting the nuclear power correction coefficient to confirm work; and
when the nuclear fuel consumption of the reactor reaches the end of the service life of more than 80 percent EOL, the control standard of the maximum average deviation value of the nuclear thermal power needs to be modified, and the modification conditions are as follows:
1) when the maximum average deviation value of the nuclear thermal power is more than 0.6 percent and the nuclear power peak value is more than or equal to 101.5 percent FP; and
2) when the maximum average deviation value of the nuclear thermal power is more than 1.0 percent.
Compared with the prior art, the method for improving the nuclear power generating set output has the following beneficial effects:
1. the output of the set is promoted, the average daily calculation is carried out according to 1MW promotion, the generated energy can be increased by 500-600 ten thousand DEG electricity in 1 year, and the income can be increased by 300-350 ten thousand;
2. the power generation capacity of the power plant is improved to the maximum extent, and the heat transfer efficiency of the unit is optimized;
3. optimizing the monitoring of the reactor core of the reactor and keeping the unit to run safely;
4. according to the monitoring data of the reactor core, 5 factors influencing the output of the unit are solidified, and processing measures are given in time to improve the working efficiency;
5. establishing a set of system: and (3) processing the reactor core monitoring data by technicians to guide an operator to intervene in the specific implementation process of the output of the reactor lifting unit.
Drawings
Fig. 1 is a flow chart diagram of a method of boosting nuclear power generation plants in accordance with an embodiment of the present invention.
FIG. 2 is a block flow diagram prior to core monitoring of a method of boosting nuclear power generation stack capacity according to an embodiment of the present invention.
Description of the main reference numerals:
delta-maximum average deviation of nuclear thermal power.
Detailed Description
The following detailed description of the present invention is provided in conjunction with the accompanying drawings, but it should be understood that the scope of the present invention is not limited to the specific embodiments.
Throughout the specification and claims, unless explicitly stated otherwise, the word "comprise", or variations such as "comprises" or "comprising", will be understood to imply the inclusion of a stated element or component but not the exclusion of any other element or component.
As shown in fig. 1 to 2, fig. 1 is a flow chart of a method for improving the power of a nuclear power generating set according to an embodiment of the present invention. FIG. 2 is a block flow diagram prior to core monitoring of a method of boosting nuclear power generation stack capacity according to an embodiment of the present invention. A method for improving the output of a nuclear power generating unit based on reactor core monitoring in a preferred embodiment of the invention comprises recording core parameter values from 0 point to 8 points every day by a real-time information monitoring system (KNS), and recording the core parameter values 1 time per second. In some embodiments, the core parameter values include reactor core thermal power, primary loop average temperature, primary loop reference temperature, 8 hour wait moving average thermal power, and electrical power. The method for improving the output of the nuclear power generating set further comprises the step of carrying out data processing on the reactor core parameter values recorded for 1 time per second to obtain the average value, the maximum value, the minimum value, the maximum average value, the minimum average value and the average floating value of the reactor core parameters.
In some embodiments, the method for improving the nuclear power generating unit output further comprises analyzing the average value, the maximum value, the minimum value, the maximum average value, the minimum average value and the average floating value of each core parameter after data processing to obtain daily available electric power advance and available thermal power advance, theoretical available electric power advance and theoretically available thermal power advance, 8-hour sliding average thermal power, single-channel nuclear thermal power maximum average deviation and peak value and maximum channel nuclear power average value.
In some embodiments, the method for increasing the output of the nuclear power generating unit further comprises comparing the difference between the available electric power budget and the available thermal power budget and the rated power value, and the difference between the theoretically available electric power budget and the theoretically available thermal power budget and the full load power value to be greater than a limit value, so as to analyze various factors influencing the output of the unit.
In some embodiments, the various factors that influence the plant output of the method of boosting the plant output of a nuclear power plant include the following 5 conditions and measures:
1) when the nuclear power peak value reaches 101.5 percent FP, the fluctuation of the nuclear power peak value is large or the average deviation is large, the processing measures at the moment are that fuel management technicians carry out adjustment of a nuclear power correction coefficient (Gk) and the deviation between the display value and the actual value of the core thermal power is reduced;
2) when the nuclear power is reduced due to the defects of the test or the equipment within 8 hours, the processing measures at the moment are to ask operating personnel to continuously pay attention to various works influencing the output of the unit, and the power is timely increased after the works are finished;
3) when the load of the power grid is limited, the processing measures at the moment are to ask operating personnel to communicate with the power grid in time, and the power is increased in time after the peak regulation is finished.
4) When the setting value of the electric power is adjusted and changed but not adjusted back in time, the processing measures at the moment are to ask an operator to adjust the setting value in time.
5) When the temperature change of the seawater is overlarge, in order to avoid frequent adjustment, the treatment measures at the moment are to ask operating personnel to continuously pay attention to the cold source so as to keep the power of the reactor core stable.
In some embodiments, the nominal power value is 99.85% of the full load power value. The limit was 3 MW.
In some embodiments, the method of boosting nuclear power generating unit output further comprises analyzing and providing specific specifications for adjusting a nuclear power correction factor (Gk), which comprises calculating a maximum average deviation of reactor nuclear power from reactor thermal power as a nuclear thermal power maximum average deviation value Δ from data derived from the nuclear power plant computer information and control system (KIC);
wherein, the nuclear thermal power is normal when the maximum average deviation value delta of the nuclear thermal power is less than or equal to 1.0 percent;
when the maximum average deviation value delta of the nuclear thermal power is larger than 1.5 percent;
when the maximum average deviation value delta of the nuclear thermal power is larger than 1.0% and the nuclear power peak value of the reactor is larger than or equal to 101.5% FP, starting the nuclear power correction coefficient (Gk) to confirm work; and
when the nuclear fuel consumption of the reactor reaches the end of the service life of more than 80 percent EOL, the control standard of the maximum average deviation value delta of the nuclear thermal power needs to be modified, and the modification conditions are as follows:
1) when the maximum average deviation value delta of the nuclear thermal power is larger than 0.6 percent and the nuclear power peak value is larger than or equal to 101.5 percent FP; and
2) when the maximum average deviation value delta of the nuclear thermal power is larger than 1.0 percent.
In some embodiments, the method for improving the output of the nuclear power generating unit further comprises the step of transmitting the analysis result to relevant professional departments of the power plant in time at 8 am every day, and simultaneously adjusting the reactor core power of the reactor according to the curing treatment measures by an operator to improve the output of the unit. The transmission method of the present embodiment is Outlook transmission method, but the present invention is not limited to this.
In summary, compared with the prior art, the method for improving the output of the nuclear power generating set has the following advantages:
1. the output of the set is promoted, the average daily calculation is carried out according to 1MW promotion, the generated energy can be increased by 500-600 ten thousand DEG electricity in 1 year, and the income can be increased by 300-350 ten thousand;
2. the power generation capacity of the power plant is improved to the maximum extent, and the heat transfer efficiency of the unit is optimized;
3. optimizing the monitoring of the reactor core of the reactor and keeping the unit to run safely;
4. according to the monitoring data of the reactor core, 5 factors influencing the output of the unit are solidified, and processing measures are given in time to improve the working efficiency;
5. establishing a set of system: and (3) processing the reactor core monitoring data by technicians to guide an operator to intervene in the specific implementation process of the output of the reactor lifting unit.
The foregoing descriptions of specific exemplary embodiments of the present invention have been presented for purposes of illustration and description. It is not intended to limit the invention to the precise form disclosed, and obviously many modifications and variations are possible in light of the above teaching. The exemplary embodiments were chosen and described in order to explain certain principles of the invention and its practical application to enable one skilled in the art to make and use various exemplary embodiments of the invention and various alternatives and modifications as are suited to the particular use contemplated. It is intended that the scope of the invention be defined by the claims and their equivalents.

Claims (8)

1. A method of increasing nuclear power plant capacity based on reactor core monitoring, comprising the steps of:
the method comprises the following steps: the real-time information monitoring system records each reactor core parameter value of each second every day;
step two: carrying out data processing on the reactor core parameter values recorded every second;
step three: analyzing the reactor core parameters after data processing;
step four: finding out various factors influencing the output of the unit;
step five: making countermeasures aiming at various factors influencing the output of the unit;
step six: transmitting the analysis result to relevant professional departments of the power plant in time every day, and simultaneously adjusting the core power of the reactor by an operator according to the curing treatment measures to improve the output of the unit; and
analyzing and giving a specific regulation for adjusting the nuclear power correction coefficient, wherein the specific regulation comprises the following steps of calculating the maximum average deviation of the nuclear power of the reactor and the thermal power of the reactor as the maximum average deviation value of the thermal power of the reactor through the computer information of the nuclear power station and data derived by a control system, wherein:
when the maximum average deviation value of the nuclear thermal power is less than or equal to 1.0 percent, the nuclear thermal power is normal;
the maximum average deviation value of the nuclear thermal power is larger when the maximum average deviation value of the nuclear thermal power is larger than 1.5 percent;
when the maximum average deviation value of the nuclear thermal power is larger than 1.0% and the nuclear power peak value of the reactor is larger than or equal to 101.5% FP, starting the nuclear power correction coefficient to confirm work; and
when the nuclear fuel consumption of the reactor reaches the end of the service life of more than 80% EOL, the control standard of the maximum average deviation value of the nuclear thermal power needs to be modified, and the modification conditions are as follows:
1) when the maximum average deviation value of the nuclear thermal power is larger than 0.6%, and the nuclear power peak value is larger than or equal to 101.5% FP; and
2) when the maximum average deviation value of the nuclear thermal power is larger than 1.0%.
2. The method of improving the power of a nuclear power generation assembly based on reactor core monitoring of claim 1, wherein the first step is recording the reactor core thermal power from 0 to 8 points per day, a primary circuit thermal power, a primary circuit average temperature, a primary circuit reference temperature, an 8 hour sliding average thermal power, and electrical power.
3. The method for improving the power of a nuclear power generating unit based on reactor core monitoring of claim 1, wherein the second step is used to obtain the average value, the maximum value, the minimum value, the maximum average value, the minimum average value and the average floating value of each core parameter.
4. The reactor core monitoring based method for boosting nuclear power plant output according to claim 3, wherein the third step is performed to derive daily available electrical power budget and available thermal power budget, theoretical available electrical power budget and theoretical available thermal power budget, 8 hour moving average thermal power, single channel nuclear thermal power maximum average deviation and peak value, and maximum channel nuclear power average value.
5. The reactor core monitoring based method for boosting nuclear power plant output according to claim 4, wherein step four further comprises comparing the difference between the available electrical power budget and the available thermal power budget and the rated power value and the difference between the theoretically available electrical power budget and the theoretically available thermal power budget and the full load power value to a threshold value for analyzing various factors affecting the plant output.
6. The method for improving the power of a nuclear power generating unit based on reactor core monitoring of claim 5, wherein the following 5 conditions and measures can be found through the fourth step and the fifth step:
1) when the nuclear power peak value reaches 101.5 percent FP, the fluctuation of the nuclear power peak value is large or the average deviation is large, the processing measures at the moment are that fuel management technicians implement adjustment of a nuclear power correction coefficient, and the deviation between the display value and the actual value of the core thermal power is reduced;
2) when the nuclear power is reduced due to the defects of the test or the equipment within 8 hours, the processing measures at the moment are to ask operating personnel to continuously pay attention to various works influencing the output of the unit, and the power is timely increased after the works are finished;
3) when the load of the power grid is limited, the processing measures at the moment are to ask operators to communicate with power grid dispatching personnel in time, and the power is timely increased after the peak regulation is finished;
4) when the setting value of the electric power is adjusted and changed but not adjusted back in time, the current processing measure is to ask an operator to adjust the setting value in time; and
5) when the temperature change of the seawater is overlarge, in order to avoid frequent adjustment, the treatment measures at the moment are to ask operating personnel to continuously pay attention to the cold source so as to keep the power of the reactor core stable.
7. The method of boosting nuclear power generation assembly capacity based on reactor core monitoring of claim 6, wherein said rated power level is 99.85% of said full load power level.
8. The reactor core monitoring based method of boosting nuclear power plant output of claim 6, wherein the limit value is 3 MW.
CN201810802991.3A 2018-07-20 2018-07-20 Method for improving nuclear power generating unit output based on reactor core monitoring Active CN108962411B (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201810802991.3A CN108962411B (en) 2018-07-20 2018-07-20 Method for improving nuclear power generating unit output based on reactor core monitoring

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201810802991.3A CN108962411B (en) 2018-07-20 2018-07-20 Method for improving nuclear power generating unit output based on reactor core monitoring

Publications (2)

Publication Number Publication Date
CN108962411A CN108962411A (en) 2018-12-07
CN108962411B true CN108962411B (en) 2020-01-14

Family

ID=64482104

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201810802991.3A Active CN108962411B (en) 2018-07-20 2018-07-20 Method for improving nuclear power generating unit output based on reactor core monitoring

Country Status (1)

Country Link
CN (1) CN108962411B (en)

Families Citing this family (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN110580964B (en) * 2019-09-03 2021-05-04 中广核工程有限公司 Online monitoring method and system for thermal power improvement margin of nuclear power unit
CN110568357A (en) * 2019-09-10 2019-12-13 国网黑龙江省电力有限公司电力科学研究院 nuclear power unit electric output monitoring and diagnosing system
CN113192660B (en) * 2021-04-20 2024-06-07 广东核电合营有限公司 Nuclear power station reactor core measurement system parameter adjustment method, device, equipment and medium
CN115390126A (en) * 2022-08-29 2022-11-25 中国核动力研究设计院 Nuclear power automatic correction method and system based on single detector and single detector
CN115614112B (en) * 2022-10-11 2024-06-18 中广核工程有限公司 Nuclear power plant steam turbine generator electric power control method and system

Family Cites Families (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP2872814A4 (en) * 2012-07-13 2016-03-09 Mpr Associates Inc Internal mechanical stress improvement method for mitigating stress corrosion cracking in weld areas of nuclear power plant piping
US20140369456A1 (en) * 2013-06-18 2014-12-18 Analysis And Measurement Services Corporation Rod movement diagnostics for nuclear power plant using advanced data fitting
JP6382578B2 (en) * 2014-05-27 2018-08-29 株式会社東芝 Stability calculation monitoring device, reactor power stability monitoring system, and reactor power stability monitoring method
JP6523877B2 (en) * 2015-08-31 2019-06-05 株式会社日立製作所 Reactor instrumentation system and reactor
CN106128529B (en) * 2016-06-27 2018-02-16 中广核研究院有限公司 A kind of On-line Measuring Method of reactor core three-dimensional power distribution

Also Published As

Publication number Publication date
CN108962411A (en) 2018-12-07

Similar Documents

Publication Publication Date Title
CN108962411B (en) Method for improving nuclear power generating unit output based on reactor core monitoring
Dany Power reserve in interconnected systems with high wind power production
CN115102290A (en) Real-time safety early warning system of smart power grids
EP3188337A1 (en) Method and systems for managing power systems
CN109274131B (en) Probability statistics theory-based non-time sequence quantitative evaluation method for new energy consumption capability
CN109631007B (en) Fuel feedback signal optimization processing method for generator set boiler master control system
CN109459985A (en) A kind of method of power plant's primary frequency modulation real time monitoring
CN114498679A (en) Power system energy storage demand quantification method and system considering frequency modulation rate and capacity
CN109858125B (en) Thermal power unit power supply coal consumption calculation method based on radial basis function neural network
CN112531773B (en) New energy power generation system and energy regulation and control method and device thereof
CN110750760B (en) Abnormal theoretical line loss detection method based on situation awareness and control diagram
CN110033873B (en) Method for analyzing and judging breakage of nuclear fuel assembly
CN102509154B (en) Dynamic adjustment method for infrared temperature measuring period of transformer station equipment
CN108256663B (en) Real-time prediction method for nuclear power operation accident risk
Gjorgiev et al. Nuclear power plant load following: problem definition and application
CN105760985B (en) Low-frequency risk comprehensive evaluation method for nuclear power access power grid
CN113991647A (en) Frequency response capacity planning-oriented random production simulation method for power system
CN112800625A (en) Method and system for determining full-clean power supply operation boundary of regional power grid
CN117955110B (en) Auxiliary optimization method for innovative power system load regulation and control
CN115525041B (en) Fault diagnosis method, system, equipment and medium for evaluating performance indexes of power plant
CN105024379A (en) Fan overhaul management dispatching system
CN113935567B (en) Quantitative evaluation method for fuel economy loss of early shutdown refueling of nuclear power plant
CN115296338B (en) Wind power output extreme climbing risk assessment method based on multi-time scale analysis
CN111934328B (en) Energy storage self-adaptive control method for coping with wind power limit scene
CN108984875B (en) Method for calculating capacity of photo-thermal unit participating in power balance

Legal Events

Date Code Title Description
PB01 Publication
PB01 Publication
SE01 Entry into force of request for substantive examination
SE01 Entry into force of request for substantive examination
GR01 Patent grant
GR01 Patent grant