CN112885492B - Zero-power reactor experiment simulation device and method for simulating critical experiment - Google Patents
Zero-power reactor experiment simulation device and method for simulating critical experiment Download PDFInfo
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- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
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Abstract
The embodiment of the invention provides a zero-power reactor experiment simulation device, which comprises: the simulation reactor is used for simulating a zero-power reactor to perform a critical experiment, and the console is used for controlling the simulation reactor to perform the simulation experiment; the simulation reactor comprises a reactor core container, a reactor core and a loop system; the reactor core is arranged in the reactor core container and comprises a fuel assembly and a control rod assembly, wherein the fuel assembly is used for simulating the reactor core active area, and the control rod assembly is used for simulating the operation of a protection reactor and regulating the reactor power; the recirculation system is connected to the core vessel for providing moderator and reflector layers to the core. According to the zero-power reactor experiment simulation device provided by the embodiment of the invention, the simulated fuel rods are adopted to replace real nuclear fuel rods, and the simulated signals are used to replace the reactor core detector measuring signals and the conversion signals thereof, so that a visual operation practice platform which is closer to the actual condition can be conveniently provided for operators, and the optimization of training or teaching effect is facilitated.
Description
Technical Field
The invention relates to the technical field of critical experiment device simulation, in particular to a zero-power reactor experiment simulation device and a method for simulating a critical experiment.
Background
Critical experiments are carried out on a zero-power reactor (or called a zero-power device), the physical performance of the reactor is simulated, scientific research personnel can obtain critical data, and meanwhile, the method is also a way for nuclear power station operator training and university experiment teaching.
For training of operators of nuclear power plants and experiment teaching of universities, two methods can be generally adopted: the first one is to develop a critical experiment on a zero-power device, so that operators can practically experience the operation processes of core loading, control rod driving and the like; the second is to simulate the critical experiment process by operating computer software by using an analogue simulation method.
The above methods all have the following disadvantages: the first method adopts a real zero-power device, the device construction cost is high, the period is long, and the performance and the service life of the zero-power device are not good when the zero-power device is operated at high frequency for critical experiments; the second method adopts software simulation, takes off entity operation, and is difficult to obtain real experience, thereby influencing training or teaching effect.
Disclosure of Invention
The invention aims to provide a zero-power reactor experiment simulation device and a method for simulating a critical experiment, thereby providing an intuitive and economic experiment simulation device and method for training or teaching.
According to an aspect of the present invention, there is provided a zero power reactor experiment simulation apparatus, comprising: the simulation reactor is used for simulating the zero-power reactor to perform a critical experiment, and the control console is used for controlling the simulation reactor to perform a simulation experiment; wherein the simulated reactor comprises a reactor core container, a reactor core and a loop system; the core is arranged in the core container and comprises fuel assemblies and control rod assemblies, wherein the fuel assemblies are used for simulating core active areas, and the control rod assemblies are used for simulating the operation of a protection reactor and regulating the power of the reactor; the loop system is connected to the core vessel for providing moderator and reflector layers to the core.
Optionally, the fuel assembly comprises simulated fuel rods and a grid plate for positioning a plurality of the simulated fuel rods.
Optionally, the control rod assembly comprises a safety rod for achieving a protected reactor operation and a regulating rod for compensating reactivity fluctuations.
Optionally, the simulated reactor further comprises a control rod drive mechanism disposed above the core vessel for driving the control rod assemblies into or out of the core.
Optionally, the control rod driving mechanism includes a motor, a sliding seat and a lead screw, the motor drives the lead screw to rotate, so that the lead screw drives the sliding seat to move up and down, and the sliding seat drives the control rod assembly to insert into or lift out of the reactor core.
Optionally, the circuit system comprises a vessel that forms a circuit with the core vessel through the conduit, a pipe through which the vessel is used to store the moderator, a pump, and a valve; the pump is used to control the moderator entering the core vessel and the valve is used to control the moderator exiting the core vessel.
Optionally, when the simulated reactor is started for critical experiments, the reactor core is provided with a neutron source which is used for providing exogenous neutrons for starting of the simulated reactor.
Optionally, an inductor is disposed at the bottom of the core for inducing the insertion of the simulation fuel rod into the core.
Optionally, the console comprises: the device comprises an operation module, a signal generation module and a display module; the operation module is used for controlling the simulation reactor to start the reactor, adjust the reactor power and stop the reactor; the signal generating module is used for generating a signal according to the operation state of the simulation reactor; the display module is used for displaying the operation state of the simulation reactor and the signal.
Optionally, the operation module includes an operation switch and a button, and the operation switch includes: the silencing optical switch is used for silencing the photon plate and the lamp whistle; the neutron source operating switch is used for controlling the neutron source to enter and exit the reactor core; a control rod drive mechanism operating switch for controlling the insertion or withdrawal of the safety rod and the regulating rod into or out of the core; a moderator operating switch for controlling the volume of moderator within the core vessel; the button includes: the shutdown button is used for realizing shutdown of the simulated reactor; and a temperature control button for adjusting the temperature of the moderator.
Optionally, the signal generation module includes a reactor core state data acquisition sub-module, a source database sub-module, and a detector response calculation sub-module; the reactor core state data acquisition submodule is used for acquiring reactor core loading parameters, moderator liquid level parameters, control rod position parameters and neutron source position parameters; the source database submodule comprises an effective value-added coefficient group, and the effective value-added coefficient group stores corresponding relations between the safety rod of the zero-power reactor and the reactor core loading capacity, the moderator liquid level and the effective value-added coefficient when the regulating rod is in a proposed state; the source database submodule also comprises a safety rod differential value curve group, and the safety rod differential value curve group stores the corresponding relation between the reactor core loading capacity, the moderator liquid level and the material parameters of the safety rod and the safety rod differential value curve; the source database submodule also comprises a regulating rod differential value curve group, and the regulating rod differential value curve group stores the corresponding relation between the reactor core loading capacity, the moderator liquid level and the material parameters of the regulating rod and the regulating rod differential value curve; the source database submodule also comprises an external source response meter array, and the external source response meter array stores the corresponding relation between the position of a neutron source, the liquid level of a moderator and external source response counting when the simulation reactor is in a non-value-added state; and the detector response calculation submodule is used for calculating according to the reactor core state data and the source database so as to generate a signal.
Optionally, the display module includes an instrument display screen, a reactor core state display screen, a reactor core three-dimensional display screen and an experiment result display screen; the instrument display screen is used for starting monitoring, power protection, periodic protection and alarm providing of the simulation reactor; the reactor core state display screen is used for displaying neutron source signals, control rod position signals, reactor core loading signals, moderator liquid level signals and the states of the pump and the valve; the reactor core three-dimensional display screen is used for displaying the processes of entering and exiting the reactor core by the neutron source, adding or discharging the moderator by the reactor core container, inserting and pulling the simulated fuel rods in the reactor core, inserting and pulling the control rods in the reactor core and measuring the liquid level of the moderator; the experimental result display screen is used for displaying different experimental results.
According to another aspect of the present invention, there is also provided a simulation method of a zero-power reactor critical experiment, including: controlling and simulating the action of the reactor; acquiring reactor core state information of the simulated reactor; calculating a reactor core response signal of the simulated reactor; and monitoring the critical experiment of the simulated reactor through the signal.
The zero-power reactor experiment simulation device disclosed by the invention integrates the advantages of a real critical experiment device and a simulation machine, is convenient for providing an operation practice platform which is closer to the actual condition and visual for operators, is beneficial to optimizing the training or teaching effect, and is low in construction cost and simple to operate.
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Other objects and advantages of the present invention will become apparent from the following description of the invention which refers to the accompanying drawings, and may assist in a comprehensive understanding of the invention.
The accompanying drawings, which are incorporated in and constitute a part of this application, illustrate embodiments of the invention and, together with the description, serve to explain the invention and not to limit the invention. In the drawings:
FIG. 1 is a schematic structural diagram of a zero-power reactor experimental simulation apparatus according to an embodiment of the present invention;
FIG. 2 is a schematic diagram of a simulated reactor according to an embodiment of the invention;
fig. 3 is a schematic structural diagram of a console according to an embodiment of the invention.
It is noted that the drawings are not necessarily to scale and are merely illustrative in nature and not intended to obscure the reader.
Detailed Description
In order to make the technical solutions of the present invention better understood, the technical solutions in the embodiments of the present invention will be clearly and completely described below with reference to the drawings in the embodiments of the present invention, and it is obvious that the described embodiments are only a part of the embodiments of the present invention, and not all of the embodiments. All other embodiments, which can be obtained by a person skilled in the art without making any creative effort based on the embodiments in the present invention, shall fall within the protection scope of the present invention.
Unless defined otherwise, technical or scientific terms used herein shall have the ordinary meaning as understood by one of ordinary skill in the art to which this invention belongs.
Referring to fig. 1-3, the invention is a schematic structural diagram of a zero power reactor experimental simulation apparatus and components thereof according to an embodiment of the invention. The simulation reactor provides the entity simulation of the critical experimental device, the console realizes the operation control of the simulation reactor, and simultaneously, the signal transmission and processing are carried out, so that the experimental data are obtained. Therefore, critical experiments are carried out based on the experiment simulation device, so that operators can obtain more real and visual experiences, and training or teaching effects are optimized.
Referring to fig. 1-2, a zero power reactor experimental simulation apparatus 100 according to an embodiment of the present invention includes: the simulation reactor 10 is used for simulating a zero-power reactor to perform a critical experiment, and the console 20 is used for controlling the simulation reactor 10 to perform the simulation experiment; the simulation reactor 10 includes a reactor core vessel 11, a reactor core 12, and a loop system 13; the core 12 is arranged in the core container 11, the core 12 comprises a fuel assembly 121 and a control rod assembly 122, the fuel assembly 121 is used for simulating core active area, and the control rod assembly 122 is used for simulating the operation of protecting a reactor and regulating the power of the reactor; a recirculation system 13 is connected to the core vessel 11 for providing moderator and reflector layers to the core 12.
Specifically, the simulation reactor 10 is determined according to a reactor type actually required for training or research, such as a simulation apparatus for a light water reactor or a heavy water reactor. In one embodiment, the simulated reactor 10 corresponds to a uranium rod grid zero power water reactor.
The core 12 is used to simulate the active area of an actual reactor, which together with the moderator disposed thereabout constitutes the conditions for the core to meet critical requirements. The core 12 includes fuel assemblies 121, and the appropriate fuel is selected based on the type of core to be simulated, and the amount and manner of fuel loading of the core is determined as desired. In one embodiment, the fuel assembly 121 includes simulated fuel rods 1211 and a grid plate 1212, the grid plate 1212 being used to position a plurality of simulated fuel rods 1211. For the convenience of fuel transportation and core loading, the plurality of dummy fuel rods 1211 are assembled and fixed, for example, the upper grid and the lower grid are used to position both ends of the dummy fuel rods 1211, respectively, for example, the plurality of dummy fuel rods 1211 are assembled in a cylindrical shape. The simulated fuel rods 1211 are made of stainless steel, for example, to replace real fuel, so that the experiment cost is reduced.
The bottom of the core 12 is provided with, for example, an inductor 15 for inducing the insertion of the dummy fuel rod 1211 into the core 12. The inductor 15 thus helps to determine the loading of the core when it is loaded with fuel assemblies.
Further, the core 12 includes a control rod assembly 122 to control the reactivity of the core, to ensure safe and reliable continuous reactor operation, or to effect a shutdown of the reactor. Control rods are classified into different types based on the difference in function. In one embodiment, the control rod assembly 122 includes a safety rod 1221 for achieving reactor operation protection and a tuning rod 1222 for compensating for reactivity fluctuations. Referring to fig. 2, the core 12 is provided with, for example, two sets of safety rods 1221 and two sets of adjusting rods 1222, respectively, which are symmetrically arranged. The safety rods 1221 play a safety protection role on the simulated reactor 10, and particularly can quickly fall into a reactor core to realize emergency shutdown when an accident occurs; the tuning rod 1222 is mainly used to compensate for fast reactivity changes, such as power ramping, which is fast acting and responsive.
To provide controllable reactivity regulation, the control rod drive mechanisms 14 are employed to drive the control rod assemblies 122, for example, to vary the depth of insertion of the regulating rods 1222 into the core using the control rod drive mechanisms 14 when the reactor needs to vary its operating power, or to insert the safety rods 1221 and the regulating rods 1222 into the core 12 using the control rod drive mechanisms 14 when the reactor needs to be shut down; the control rod drive mechanisms 14 are disposed, for example, above the core vessel 11 to provide for easy adjustment of the position of the rod control assemblies.
The crdm is classified into, for example, an electromagnetic drive, a hydraulic drive, and the like based on a driving principle, and in one embodiment, the crdm is controlled by the electromagnetic drive, and the crdm 14 includes, for example, a motor, a slider, and a screw, and the motor drives the screw to rotate, so that the screw drives the slider to move up and down, so that the slider (on which an electromagnet acting with a control rod is disposed) drives the control rod assembly 122 to insert or extract the core 12.
The control rod drive mechanisms for controlling the safety rods 1221 and the adjusting rods 1222 may be of the same or different construction, may be driven by the same or different driving principles, or may be combined in a plurality of driving manners to improve the reactive control or shutdown effect.
Moderator is one of the factors that affects the core to critical conditions, and serves to reduce fission neutron energy, thereby increasing the likelihood that the core will sustain a nuclear fission reaction. The circuit system 13 is used, for example, to control the amount of moderator around the core. For example, a pump 133 is used to introduce a desired volume of moderator from the storage vessel 131 into the core vessel 11, or a valve 134, such as a solenoid valve, is used to allow excess moderator in the core vessel 11 to drain when moderating capacity needs to be weakened. In the uranium rod grid zero-power water reactor, light water is used as a moderator and a reflecting layer.
Further, a critical test is performed using the above-described test simulation apparatus 100, such as providing a neutron source to the core 12 when the critical test is initiated, and removing the neutron source when the reactor power is stabilized to be critical.
The experiment simulation apparatus 100 can simulate a series of processes of a critical experiment, such as fuel rod addition to a reactor core, moderator addition to or removal from a reactor core, lifting or insertion of a control rod assembly, critical extrapolation, critical interpolation, and the like, thereby providing a rich operation experience for training personnel.
The console has both software and hardware functions, for example, computer software is used for simulating the signal change in the critical experiment process, the signals are processed at the same time, and the processed data or results are displayed by figures or numbers, so that operators can obtain visual experience effects.
Referring to fig. 3, the console 20 includes, for example: an operation module 21, a signal generation module 22 and a display module 23; the operation module 21 is used for controlling the simulation reactor 10 to perform reactor startup, reactor power regulation and reactor shutdown operation; the signal generating module 22 is used for generating signals according to the operation state of the simulated reactor 10; the display module 23 is used for displaying the operation state and signals of the simulated reactor 10.
Specifically, the operation module 21 may implement the motion control of the simulated reactor 10, that is, implement the process control of the critical reactor experiment, by manually adjusting its components, which is helpful for operators to obtain a more real operation experience.
In one embodiment, the operating module 21, for example provided with mechanical components for facilitating the adjustment, comprises an operating switch 211, the operating switch 211 for example comprising a neutron source operating switch for controlling the neutron source to enter the core 12, for example when the neutron source operating switch is in the "1" gear, indicating that the neutron source is controlled to enter the core to provide the startup neutrons for the core, and when the neutron source operating switch is in the "2" gear, indicating that the neutron source is controlled to move out of the core; control rod drive mechanism operating switches for controlling the insertion or withdrawal of the safety rods and the regulating rods into or out of the core 12, for example, an "up" gear and a "down" gear being set for each set of safety rods or regulating rods; the moderator operation switches are used for controlling the volume of moderator in the core vessel 11, and are classified into, for example, a pump operation switch, a valve operation switch, a level gauge (for measuring the level of moderator in the core vessel 11), and the like, which respectively perform their corresponding functions.
The operation module 21 further includes, for example, a function button 212, when the simulation reactor 10 starts a critical test, for example, when the protection input button is pressed, the critical test starts; when the simulated reactor 10 normally operates and a normal shutdown button is pressed, the safety rod 1221 and the adjusting rod 1222 are inserted into the reactor core 12 along with the driving mechanism, and the drain valve 134 is opened, so that normal shutdown is realized; when the scram button is pressed down, the control rod driving mechanism electromagnet is powered off, the safety rod 1221 and the adjusting rod 1222 are quickly inserted into the reactor core 12, and the drain valve 134 is opened, so that scram is realized; or a temperature control button is further included for adjusting the moderator temperature (virtual temperature) so as to carry out the moderator temperature effect experiment.
Further, the signal generating module 22 obtains the position information of the fuel assemblies and the control rod assemblies of the reactor core, the neutron source information, the water level information of the moderator, and the like according to the above actions performed by the simulation reactor 10, and performs calculation according to the database information by querying a preset database, so as to generate physical parameters such as neutron count, reactivity, period, reactor power, and the like representing the state of the reactor core, so that an operator can know the operating condition of the reactor and perform appropriate regulation and control. The signal generation module 22 is, for example, a signal simulator for generating virtual signals representing the operating states of the core, such as neutron count, reactivity, period, reactor power, etc.
In one embodiment, the signal generation module 22 includes a core status data acquisition submodule 221, a source database submodule 222, a detector response calculation submodule 223; the reactor core state data acquisition submodule 221 is used for acquiring reactor core loading parameters, moderator liquid level parameters, control rod position parameters and neutron source position parameters; the source database sub-module 222 includes an effective value-added coefficient group, which stores the corresponding relationship between the safety rod of the zero-power reactor and the reactor core loading, moderator liquid level and effective value-added coefficient when the regulating rod is in the proposed state; the source database submodule 222 further includes a safety rod differential value curve group, where the safety rod differential value curve group stores the corresponding relationship between the reactor core loading capacity, the moderator liquid level, and the material parameters of the safety rod and the safety rod differential value curve; the source database submodule 222 further includes a regulating rod differential value curve group, where the regulating rod differential value curve group stores the corresponding relationship between the reactor core loading capacity, the moderator liquid level, and the material parameters of the regulating rod and the regulating rod differential value curve; the source database submodule 222 further includes an external source response meter group, which stores the corresponding relationship between the position of the neutron source, the moderator liquid level and the external source response count when the simulation reactor is in a non-value-added state; the detector response calculating submodule 223 calculates a virtual signal to which the detector can respond according to the reactor core state data and the source database.
Furthermore, the operating state of the reactor core and signals thereof can be fed back to an operator by the display module, so that the operator can master the state of the reactor core in real time, and favorable measures can be taken according to different conditions. The display module 23 includes, for example, an instrument display screen 231, a core state display screen 232, a core three-dimensional display screen 233, and an experiment result display screen 234; the instrument display screen 231 is used for simulating the startup monitoring, power protection, periodic protection of the reactor and providing an alarm; the core state display screen 232 is used for displaying a neutron source signal, a control rod position signal, a core loading signal, a moderator liquid level signal and states of a pump and a valve; the reactor core three-dimensional display screen 233 is used for displaying the processes of neutron source entering and exiting the reactor core, adding or discharging moderator to or from the reactor core container, inserting and pulling the reactor core into or out of the simulated fuel rod, inserting and pulling the reactor core into or out of the control rod, and measuring the liquid level of the moderator; the experimental results display 234 is used to display various experimental results.
The simulation reactor 10 of the present invention uses a simulation fuel rod instead of a real nuclear fuel rod, and uses a reactor core simulation signal instead of a real reactor core probe measurement signal and its conversion signal, thereby simulating the state of a real reactor core, and simultaneously uses the console 20 to provide a platform for conveniently operating the reactor core. The parameters of the simulated fuel rod are set according to the nuclear fuel type to be simulated and the requirement of the reactor core on meeting critical conditions, so that the simulation closer to the actual condition is provided. In order to provide an optimized simulation effect, the composition and functions of the console 20 can be set correspondingly to the structure of the simulation reactor 10, so that the operation is more vivid and lifelike, the display and feedback are more intuitive and accurate, and the quality for training or teaching is improved.
A simulation method of a zero power reactor criticality experiment according to an embodiment of the present invention is described below.
In this embodiment, the zero-power reactor experiment simulation apparatus is used to perform a critical experiment simulation; the zero-power reactor experiment simulation device is constructed according to the critical condition of the simulated reactor.
The simulation method for the zero-power reactor critical experiment comprises the following steps:
controlling components such as a neutron source, a safety rod, an adjusting rod, a moderator, a simulation fuel rod and the like to perform corresponding actions or adjustments through a control console;
obtaining reactor core state information of the simulated reactor through the reactor core state data obtaining submodule;
extracting data to be calculated corresponding to the reactor core state information in a pre-stored source database;
calculating a virtual signal simulating the reactor core detector response of the reactor according to the reactor core state information and the data to be calculated, such as neutron count, reactivity, period, reactor power and other parameters representing the reactor core state;
and monitoring the simulation device through the virtual signal responded by the detector so as to complete the simulation critical experiment process.
Therefore, the zero-power reactor experiment simulation device is used for carrying out simulation critical experiments, is convenient to operate, is beneficial to training personnel to obtain visual experience, and provides a beneficial way for training and experiment teaching of nuclear professionals.
It should also be noted that, in case of conflict, the embodiments and features of the embodiments of the present invention may be combined with each other to obtain new embodiments.
The above description is only an embodiment of the present invention, but the scope of the present invention is not limited thereto, and the scope of the present invention is subject to the scope of the claims.
Claims (10)
1. A zero-power reactor experimental simulation apparatus (100), comprising: the system comprises a simulation reactor (10) and a control console (20), wherein the simulation reactor (10) is used for simulating the zero-power reactor to perform a critical experiment, and the control console (20) is used for controlling the simulation reactor (10) to perform a simulation experiment; wherein,
the console (20) comprises: an operation module (21), a signal generation module (22) and a display module (23);
the operation module (21) is used for controlling the simulation reactor (10) to start up, adjust the power of the reactor and stop the reactor;
the operation module (21) comprises an operation switch (211) and a button (212),
the operation switch includes:
the silencing optical switch is used for silencing the photon plate and the lamp whistle;
a neutron source operating switch for controlling the neutron source to enter and exit the core (12);
a control rod drive mechanism operating switch for controlling the insertion or withdrawal of the safety and conditioning rods into or out of the core (12);
a moderator operating switch for controlling the volume of moderator within the core vessel (11);
the button includes:
a shutdown button for effecting shutdown of the simulated reactor (10); and
the temperature control button is used for adjusting the temperature of the moderator;
the signal generating module (22) is used for generating a signal according to the operation state of the simulation reactor (10);
the signal generation module (22) comprises a reactor core state data acquisition sub-module (221), a source database sub-module (222) and a detector response calculation sub-module (223);
the reactor core state data acquisition submodule (221) is used for acquiring reactor core loading parameters, moderator liquid level parameters, control rod position parameters and neutron source position parameters;
the source database submodule (222) comprises an effective value-added coefficient group, and the effective value-added coefficient group stores the corresponding relation between the reactor core loading capacity, the moderator liquid level and the effective value-added coefficient of the safety rod and the regulating rod of the zero-power reactor in the proposed state;
the source database submodule (222) also comprises a safety rod differential value curve group, and the safety rod differential value curve group stores the corresponding relation between the reactor core loading capacity, the moderator liquid level and the material parameters of the safety rod and the safety rod differential value curve;
the source database submodule (222) also comprises a regulating rod differential value curve group, and the regulating rod differential value curve group stores the corresponding relation between the reactor core loading capacity, the moderator liquid level and the material parameters of the regulating rod and the regulating rod differential value curve;
the source database submodule (222) also comprises an external source response meter array, and the external source response meter array stores the corresponding relation between the position of a neutron source, the moderator liquid level and the external source response count when the simulation reactor is in a non-value-added state;
a detector response calculation submodule (223) calculates and generates a signal according to the reactor core state data and the source database;
the display module (23) is used for displaying the operation state of the simulation reactor (10) and the signal;
the simulated reactor (10) comprises a reactor core container (11), a reactor core (12) and a loop system (13);
the core (12) is arranged in the core vessel (11), the core (12) comprises a fuel assembly (121) and a control rod assembly (122), the fuel assembly (121) is used for simulating a core active area, and the control rod assembly (122) is used for simulating the operation of a protection reactor and regulating the power of the reactor;
the circuit system (13) is connected to the core vessel (11) for providing moderator and reflector layers to the core (12).
2. The zero-power reactor experimental simulation device (100) of claim 1,
the fuel assembly (121) comprises simulated fuel rods (1211) and a grid plate (1212), the grid plate (1212) being for positioning a plurality of the simulated fuel rods (1211).
3. The zero-power reactor experimental simulation device (100) of claim 1,
the control rod assembly (122) comprises a safety rod (1221) and a regulating rod (1222), the safety rod (1221) is used for realizing the operation of a protection reactor, and the regulating rod (1222) is used for compensating reactivity fluctuation.
4. The zero-power reactor experimental simulation device (100) of claim 3,
the simulated reactor (10) further includes a control rod drive mechanism (14) disposed above the core vessel (11) for driving the control rod assemblies (122) to insert into or withdraw from the core (12).
5. The zero-power reactor experimental simulation device (100) of claim 4,
the control rod driving mechanism comprises a motor, a sliding seat and a lead screw, the motor drives the lead screw to rotate, so that the lead screw drives the sliding seat to move up and down, and the sliding seat drives the control rod assembly to insert or lift out the reactor core.
6. The zero-power reactor experimental simulation apparatus (100) of claim 1,
the circuit system (13) comprising a vessel (131), a pipe (132), a pump (133) and a valve (134), the vessel (131) being in circuit with the core vessel (11) through the pipe (132), the vessel (131) being for storing the moderator;
the pump (133) is used to control the moderator entering the core vessel (11), and the valve (134) is used to control the moderator exiting the core vessel (11).
7. The zero-power reactor experimental simulation apparatus (100) of claim 1,
when the simulation reactor (10) is started for critical experiments, the reactor core (12) is provided with a neutron source which is used for providing exogenous neutrons for the starting of the simulation reactor (10).
8. The zero-power reactor experimental simulation device (100) of claim 1,
an inductor (15) is arranged at the bottom of the core (12) and used for inducing the simulation fuel rod (1211) to be inserted into the core (12).
9. The zero-power reactor experimental simulation device (100) of claim 1,
the display module (23) comprises an instrument display screen (231), a reactor core state display screen (232), a reactor core three-dimensional display screen (233) and an experiment result display screen (234);
the instrument display screen (231) is used for starting monitoring, power monitoring, periodic protection, power protection and alarm providing of the simulation reactor;
the core state display screen (232) is used for displaying neutron source signals, control rod position signals, core loading signals, moderator liquid level signals and the states of the pump and the valves;
the reactor core three-dimensional display screen (233) is used for displaying the passing in and out of the reactor core of the neutron source, the adding or discharging of the moderator from the reactor core container, the plugging of the simulated fuel rods in the reactor core, the plugging of the control rods in the reactor core, and the measuring process of the liquid level of the moderator;
the experiment result display screen (234) is used for displaying different experiment results.
10. A simulation method for a zero-power reactor critical experiment comprises the following steps:
controlling the simulated reactor action of the zero-power reactor experimental simulation device (100) of any one of claims 1 to 9;
obtaining the reactor core state information of the simulated reactor;
calculating a core response signal of the simulated reactor;
and monitoring the critical experiment of the simulated reactor through the signal.
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| CN113921156B (en) * | 2021-11-22 | 2023-12-12 | 中国原子能科学研究院 | Critical experimental device and method for spent fuel |
| CN114171220B (en) * | 2021-12-03 | 2024-02-20 | 中国原子能科学研究院 | Control rod and/or control drum integral value measuring method and device |
| CN114171214B (en) * | 2021-12-03 | 2024-02-20 | 中国原子能科学研究院 | Control rod system for critical device |
| CN114188051B (en) * | 2021-12-03 | 2024-02-20 | 中国原子能科学研究院 | Method and device for monitoring position of safety bar |
| CN114188046B (en) * | 2021-12-03 | 2023-12-12 | 中国原子能科学研究院 | Zero-power reactor start control method and device |
| CN115171926A (en) * | 2022-06-20 | 2022-10-11 | 中核核电运行管理有限公司 | Method for establishing reactor shutdown state based on control rod for heavy water reactor |
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