CN112133460A - Fast reactor core on-line supervision method and system - Google Patents
Fast reactor core on-line supervision method and system Download PDFInfo
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- CN112133460A CN112133460A CN202010871968.7A CN202010871968A CN112133460A CN 112133460 A CN112133460 A CN 112133460A CN 202010871968 A CN202010871968 A CN 202010871968A CN 112133460 A CN112133460 A CN 112133460A
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/14—Period meters
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- 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
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- 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
- G21C17/102—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain the sensitive element being part of a fuel element or a fuel assembly
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/04—Safety arrangements
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/08—Regulation of any parameters in the plant
- G21D3/10—Regulation of any parameters in the plant by a combination of a variable derived from neutron flux with other controlling variables, e.g. derived from temperature, cooling flow, pressure
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- 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
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Abstract
The invention relates to a fast reactor core on-line supervision method and a system, wherein the method comprises the steps of firstly, acquiring monitoring data of reactor nuclear power and control rod in-reactor position by using a fast reactor out-of-reactor nuclear measurement system and a control rod monitoring system; then, taking the real-time reactor power and in-reactor control rod position measurement data obtained in the previous step as real-time input parameters of a reactor core neutron calculation program in a selected time step, performing steady-state reactor core calculation to obtain in-reactor neutron flux density and power, further calculating to obtain component burnup data, and storing the data in a database; and extracting relevant data of the database as required to carry out graphical display. The invention can realize the on-line supervision of the reactor core of the fast reactor, provide detailed data support for the operation decision and fuel management of the fast reactor power plant, and improve the economic benefit and the safety level of the power plant.
Description
Technical Field
The invention belongs to the technical field of nuclear reactor design, and particularly relates to a fast reactor core online supervision method and system.
Background
In order to ensure safe use of nuclear fuel in a reactor of a nuclear power plant, certain parameters of the reactor and related parameters of a reactor core measuring system are monitored on line, and the operation trend of related contents is tracked and analyzed to guide operation and ensure that the reactor operation parameters meet design requirements. At present, reactor core supervision and management are arranged in mainstream pressurized water reactor nuclear power plants.
The fast neutron reactor (fast reactor) is a master reactor type of the fourth generation nuclear power system, in which the most mature technology level is the sodium-cooled fast reactor technology using liquid metal sodium as a coolant. To date, more than twenty fast reactors with different power scales are built by the American, Russian, Farad, English, Rid and German printing, most of which are sodium-cooled fast reactors including experimental fast reactors, prototype fast reactors and commercial validation reactors, and the operation experience of about 300 fast reactors per year is accumulated. China has built up a Chinese experimental fast reactor with 20MW of electric power at present, and design, research, development and construction of 60 ten thousand kilowatts Chinese demonstration fast reactors are in progress. The fast reactor can also use heavy metals such as liquid lead/lead bismuth alloy and He gas or CO2Etc. as a coolant.
In a pressurized water reactor, effective monitoring on neutron flux density is usually realized by arranging in-reactor and out-of-reactor neutron detectors, inversion calculation of the neutron flux density and power at different positions in the reactor is carried out based on measurement data and a mathematical method, and relevant monitoring data are obtained and used for tracking reactor operation parameters on line and guiding operation.
The design of fuel assemblies and reactor systems in fast reactors is very different from that of hot neutron reactors such as pressurized water reactors, for example: fuel assemblies typically use a tight grid and are typically designed with an assembly outer sleeve, high coolant operating temperatures, a primary system pool-type integrated design, etc., resulting in an inability to arrange in-core fuel assembly detectors in the fast reactor core for neutron flux density or power measurements per cartridge of fuel assemblies. The operating personnel can not directly monitor or obtain parameters such as the power, the neutron flux density, the power peak value, the fuel assembly burnup and the like of the fuel assembly on line through the in-reactor detector. In the fast reactor, the design calculation value, the reaction rate distribution measurement test data developed in the starting stage, the operating power history and other data are generally used for off-line analysis, so that the supervision and management of the reactor core assembly power and the fuel consumption are realized.
In the actual operation process of the fast reactor power plant, parameters such as neutron flux density, power, fuel burnup and the like are required to be monitored on line in consideration of the limitation of off-line analysis and the complexity of the operation history of the reactor. Therefore, it is necessary to develop an on-line monitoring method for the operation supervision and fuel management of the fast reactor core.
Disclosure of Invention
The invention aims to provide a method and a system for monitoring reactor core parameters of a fast reactor aiming at the defects of the prior art, so as to realize online reactor core supervision and provide detailed data support for operation supervision, operation decision, fuel management and the like of a fast reactor power plant.
In order to achieve the purpose, the technical scheme of the invention is as follows: a fast reactor core online supervision method comprises the following steps:
(1) acquiring monitoring data of the nuclear power of the reactor and the position in the control rod reactor by using a fast reactor external nuclear measurement system and a control rod monitoring system;
(2) taking the real-time reactor power and in-reactor control rod position measurement data obtained in the previous step as real-time input parameters of a reactor core neutron calculation program in a selected time step, performing steady-state reactor core calculation to obtain in-reactor neutron flux density and power, further calculating to obtain component burnup data, and storing the data in a database;
(3) and extracting relevant data of the database as required to carry out graphical display.
Further, according to the fast reactor core online monitoring method, in the step (1), the monitoring data can be obtained by reading an offline file or reading real-time data, the read data corresponds to the physical quantity one by one, and the data is processed into a form capable of being input into a calculation program and stored in a database.
Further, in the fast reactor core online monitoring method, in the step (2), a set of reactor core neutron calculation program input files aiming at the reactor core state is prepared in advance, the obtained real-time reactor power and the position measurement data of the in-reactor control rods are edited, and then calculation is carried out, so that the power distribution and the neutron flux density distribution of the current state of the reactor core are obtained.
Further, the fast reactor core online monitoring method as described above, wherein the database includes core loading data, operation monitoring data and calculation result data, the core loading data includes loading information of all components in the reactor, the operation monitoring data includes processed reactor nuclear power and control rod in-reactor position monitoring data, and the calculation result data includes power operation history of the core, operation history of the components, component burnup, and component nuclide quality data.
Further, in the fast reactor core online monitoring method, the core plan is graphically displayed in the step (3), and the graph is divided into values according to colors, and the values include a component power distribution diagram, a component power factor distribution diagram, a component axial/radial power peak factor distribution diagram, and a component burnup distribution diagram.
An on-line monitoring system for a fast reactor core, comprising:
the nuclear measurement system data acquisition module is used for acquiring the nuclear power of the reactor and the monitoring data of the position in the control rod reactor by using the fast reactor external nuclear measurement system and the control rod monitoring system;
the reactor core calculation program module is used for taking the real-time reactor power and the in-reactor control rod position measurement data obtained in the previous step as real-time input parameters at a selected time step, performing steady-state reactor core calculation to obtain in-reactor neutron flux density and power, further calculating to obtain component burnup data, and storing the data into a database;
the database module is used for storing reactor core loading data, operation monitoring data and calculation result data;
and the graphical display module is used for extracting relevant data of the database as required to carry out graphical display.
Further, in the fast reactor core online monitoring system, the core calculation program module performs the steady-state core calculation by using a nuclear design program NAS program of the fast reactor.
The invention has the following beneficial effects: the method can quickly calculate the parameters such as neutron flux density, power and fuel burnup of the reactor core at a selected time point according to the real-time monitoring data of a nuclear measurement system and a rod position monitoring system of a fast reactor nuclear power plant and by combining a neutron calculation program of the reactor core, and can simultaneously give the parameters such as power operation history and burnup history of components to realize the quasi-real-time monitoring of the related parameters. In addition, parameters such as power, burnup and neutron flux density can be displayed graphically as required. The reactor core supervision method can provide detailed data support for operation decision and fuel management of the fast reactor power plant, and improve the economic benefit and the safety level of the power plant.
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FIG. 1 is a schematic diagram of the general architecture of the fast reactor core online supervision method of the invention;
FIG. 2 is a schematic structural diagram of the fast reactor core online monitoring system of the invention.
Detailed Description
In order to make the objects, technical solutions and advantages of the present invention more apparent, the present invention is described in further detail below with reference to the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are merely illustrative of the invention and are not intended to limit the invention.
Because the fast reactor core is difficult to arrange in-reactor neutron detectors for realizing on-line core supervision, the existing fast reactors mostly use design calculation values, reaction rate distribution measurement test data developed in a starting stage, operating power history and other data for off-line analysis, and supervision and management of core assembly power and burnup are realized. The invention provides a new technical idea to realize the online monitoring function of a fast reactor core, and the overall architecture of the specific method is shown in figure 1 and comprises the following steps:
firstly, a fast reactor outer nuclear measurement system and a control rod monitoring system are utilized to obtain the nuclear power of a reactor and real-time monitoring data of the position in the control rod reactor.
Then, using a high-precision and rapid reactor core neutronics calculation program, taking the real-time reactor power and in-reactor control rod position measurement data obtained in the previous step as real-time input parameters of the reactor core neutronics calculation program on a selected time step, performing steady-state reactor core calculation to obtain in-reactor neutron flux density and power, further calculating to obtain component burnup data, and storing related data into a database; in general, the time step can be selected from 5 to 30 minutes as a step length, and the specific step length can be determined according to actual conditions.
And finally, extracting relevant data in the database according to the user requirement for graphical display.
Therefore, the system structure required for implementing the method is as follows: the nuclear measurement system comprises a nuclear measurement system data acquisition module, a reactor core calculation program module, a database module and a graphical display module. The system architecture is shown in fig. 2.
The database and the core computing program are core modules of the platform. The reactor core loading information, the operation and maintenance platform monitoring data and other parameters are entered into the database to be processed for being used by a neutron calculation program NAS and other auxiliary calculation programs, and the calculation result of the core calculation program is stored and processed in the database and can be used for the next calculation and the visual output of related data.
The core calculation program adopts a nuclear design program NAS program of a fast reactor, and an NAS program system is a multifunctional and high-precision fast reactor neutron physical design program system which is developed through digestion and absorption and a large amount of independent innovation on the basis of introduction in China and is widely used in the design of the fast reactor. The NAS program is a hexagonal coarse mesh nodal method program, which adopts a nodal expansion method, approximates neutron flux distribution in the nodal blocks by using a piecewise polynomial expansion formula, and establishes a coupling relation between the nodal blocks by using average bias current. The calculation precision of the method is equivalent to the difference calculation of a hexagonal grid cell containing 54 triangular mesh points. The program enables neutron flux calculations as well as neutron value calculations. It can provide the results of the effective multiplication factor, the power distribution of the segment, the neutron flux distribution, the control rod value, the reactivity effect, the dynamic parameters and the disturbance calculation of the reactor. Because the time required by the NAS program for core calculation is shorter than the interval of the selected calculation time points, the quasi-real-time monitoring data of parameters such as neutron flux density, power, burnup and the like can be obtained.
According to the above general design architecture, the fast reactor core online supervision method of the specific embodiment includes the following steps:
1. and acquiring relevant data of the nuclear testing system and converting the relevant data into the input of the calculation program.
The acquisition of the data of the nuclear measurement system can be implemented by reading an offline file or reading real-time data, and the read data corresponds to the physical quantity one by one and is stored in a database.
After the monitoring data are obtained, corresponding processing is needed, and the reactor power and control rod position data of the nuclear measurement system are converted into data required by a program and applied to the visualization output of the reactor core state and the input of a calculation program.
2. And calling a calculation program to calculate and simulate the state of the reactor core.
The core calculation program adopts a neutron calculation program NAS program of the fast reactor, the NAS program is a three-dimensional hexagonal section expansion method program, and calculation results of the NAS program comprise parameters such as keff, power distribution, burnup distribution and neutron flux density distribution.
In the method, a set of program input files for the core state needs to be prepared in advance, and parameters of the program input files comprise parameters such as core loading, nuclear density of each grid cell, multi-group cross sections of each grid cell and the like. Meanwhile, according to the acquired nuclear measurement system data, parameters of the power of the reactor core and the position of the control rod are edited, relevant data are converted into data required by program input, and then calculation is carried out, so that parameters such as power distribution, neutron flux density distribution and the like of the current state of the reactor core can be simulated.
The database comprises three types of reactor core loading data, operation monitoring data and calculation result data, and the three types of data integrally form a database of the platform and can be mutually called.
The loading data module is used for storing loading information of all components in the reactor, and when the data is inquired, the time + the core position + the component number can uniquely position the data of one component at a certain time, as shown in the table 1. The reactor core loading data module stores the first loading data in the database, and the reloading data module updates the loading data in the subsequent updating process to form the current loading data.
And storing the acquired monitoring data to form an operation monitoring data module.
And storing and processing the calculation result to form a calculation result data module, wherein the calculation result data module comprises parameters such as power operation history of the reactor core, operation history of the components, component burnup, component nuclide quality and the like.
TABLE 1 core Loading data schematic
| Serial number | Core position | Component numbering | Component type | Time of loading into heap | In-pile dwell period |
| 1 | 1-1 | 40000204 | I type stainless steel subassembly | 2008-02-28 | 0 |
| 2 | 2-1 | 10001504 | Type I fuel assembly | 2010-07-21 | 0 |
| 3 | 2-2 | 10001004 | Type I fuel assembly | 2010-07-21 | 0 |
| 4 | 2-3 | 10001104 | Type I fuel assembly | 2010-07-21 | 0 |
3. And storing the main calculation result into a database and displaying the related calculation result.
The visual output is mainly displayed on a plan view, and can output a component power distribution diagram, a component power factor distribution diagram, a component axial/radial power peak factor distribution diagram, a component fuel consumption distribution diagram and the like. The output graphics are colored to distinguish the magnitude of the values while the display values can be selected.
Other embodiments of the invention will be apparent to those skilled in the art from consideration of the specification and practice of the invention disclosed herein. This application is intended to cover any variations, uses, or adaptations of the invention following, in general, the principles of the invention and including such departures from the present disclosure as come within known or customary practice within the art to which the invention pertains. Thus, if such modifications and application-adaptive changes to the present invention are within the scope of the claims of the present invention and their equivalents, the present invention is also intended to include such modifications and application-adaptive changes.
The above-described embodiments are merely illustrative of the present invention, and the present invention may be embodied in other specific forms or other specific forms without departing from the spirit or essential characteristics thereof. The described embodiments are, therefore, to be considered in all respects as illustrative and not restrictive. The scope of the invention should be indicated by the appended claims, and any changes that are equivalent to the intent and scope of the claims should be construed to be included therein.
Claims (7)
1. A fast reactor core online supervision method comprises the following steps:
(1) acquiring monitoring data of the nuclear power of the reactor and the position in the control rod reactor by using a fast reactor external nuclear measurement system and a control rod monitoring system;
(2) taking the real-time reactor power and in-reactor control rod position measurement data obtained in the previous step as real-time input parameters of a reactor core neutron calculation program in a selected time step, performing steady-state reactor core calculation to obtain in-reactor neutron flux density and power, further calculating to obtain component burnup data, and storing the data in a database;
(3) and extracting relevant data of the database as required to carry out graphical display.
2. The on-line monitoring method for the reactor core of the fast reactor as claimed in claim 1, wherein in the step (1), the monitoring data can be obtained by reading off-line files or real-time data, and the read data is in one-to-one correspondence with the physical quantities, processed into a form capable of being input into a calculation program and stored in a database.
3. The on-line monitoring method for the reactor core of the fast reactor as claimed in claim 1, wherein in the step (2), a set of nuclear neutron calculation program input files for the reactor core state is prepared in advance, the obtained real-time reactor power and the position measurement data of the in-reactor control rods are edited, and then calculation is carried out, so that the power distribution and the neutron flux density distribution of the current state of the reactor core are obtained.
4. The on-line monitoring method for the fast reactor core according to any one of claims 1 to 3, wherein the database comprises core loading data, operation monitoring data and calculation result data, the core loading data comprises loading information of all components in the reactor, the operation monitoring data comprises processed reactor nuclear power and control rod in-reactor position monitoring data, and the calculation result data comprises power operation history of the core, operation history of the components, component burnup and component nuclide quality data.
5. The on-line monitoring method for the reactor core of the fast reactor as claimed in claim 1, wherein the core plan is graphically displayed in the step (3), and the graph is divided into values by colors, and the values comprise a component power distribution diagram, a component power factor distribution diagram, a component axial/radial power peak factor distribution diagram and a component burnup distribution diagram.
6. An on-line monitoring system for a fast reactor core, comprising:
the nuclear measurement system data acquisition module is used for acquiring the nuclear power of the reactor and the monitoring data of the position in the control rod reactor by using the fast reactor external nuclear measurement system and the control rod monitoring system;
the reactor core calculation program module is used for taking the real-time reactor power and the in-reactor control rod position measurement data obtained in the previous step as real-time input parameters at a selected time step, performing steady-state reactor core calculation to obtain in-reactor neutron flux density and power, further calculating to obtain component burnup data, and storing the data into a database;
the database module is used for storing reactor core loading data, operation monitoring data and calculation result data;
and the graphical display module is used for extracting relevant data of the database as required to carry out graphical display.
7. The on-line core supervision system of the fast reactor according to claim 6, wherein the core calculation program module adopts the core design program NAS program of the fast reactor to perform steady-state core calculation.
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| CN113205896A (en) * | 2021-03-26 | 2021-08-03 | 中广核研究院有限公司 | Nuclear reactor core monitoring method, device, computer equipment and storage medium |
| CN113409971A (en) * | 2021-05-28 | 2021-09-17 | 中国原子能科学研究院 | Method, device, medium, and electronic apparatus for monitoring damage to core of nuclear reactor |
| WO2023184956A1 (en) * | 2022-04-02 | 2023-10-05 | 中广核工程有限公司 | Power distribution measurement method, apparatus and system for nuclear power plant |
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