CN111508620A - Reactor maneuverability self-adjusting method - Google Patents
Reactor maneuverability self-adjusting method Download PDFInfo
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- G21C7/02—Control of nuclear reaction by using self-regulating properties of reactor materials, e.g. Doppler effect
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Abstract
The invention discloses a reactor maneuverability self-adjusting method, which is used for power adjustment of a reactor core, the implementation of the method is based on the reactor core with negative feedback characteristic, and the method is used for realizing dynamic response of two-loop load and one-loop power: the load change of the secondary circuit is realized by adjusting the power of the steam generator, and the power of the reactor core is increased or decreased by utilizing the temperature change of the primary circuit coolant and the negative temperature coefficient of the reactor caused by the power change of the steam generator. The method is adopted to realize the power regulation of the nuclear reactor, not only can reduce the dependence of the nuclear reactor on a control rod system or avoid the adoption of the control rod system, reduce or avoid the nuclear reactor accidents caused by the failure of a control rod driving mechanism, but also can effectively flatten the power distribution of the nuclear reactor core.
Description
Technical Field
The invention relates to the technical field of nuclear reactor control, in particular to a reactor maneuverability self-adjusting method.
Background
In order to meet the load change mobility requirement of a nuclear power plant, the power of a nuclear reactor needs to be regulated: the nuclear reactor power regulating system has the advantages that parameters such as reactor power, coolant temperature, coolant flow, steam pressure and the like can fluctuate greatly in the normal operation transient state and the working condition conversion process of the reactor, and the nuclear reactor power regulating system has the function of ensuring that the parameters such as the reactor power, the temperature, the pressure, the flow and the like meet safe operation conditions under various operation working conditions of the reactor and can enable a nuclear power device to have good maneuverability. Generally, a reactor power regulating system realizes the control of reactor power through a rod control system, namely, the reactor core reactivity is changed through a regulating rod, so that the purpose of power regulation is achieved.
The traditional nuclear power device is designed to carry out load tracking in a rod control mode of a nuclear reactor power regulating rod group, and has the advantages of fast response, good following performance and the like.
Further research on nuclear reactor power regulation schemes to further promote nuclear operation development is an important direction for technical innovation research of technicians in the field.
Disclosure of Invention
Aiming at the technical problems that the proposal for further researching the power regulation scheme of the nuclear reactor is provided to further promote the application and development of the nuclear reactor and is an important direction for technical innovation research of technicians in the field, the invention provides the power regulation method of the nuclear reactor.
The technical means of the scheme is as follows, a reactor maneuverability self-regulating method is used for power regulation of a reactor core, the implementation of the method is based on the reactor core with negative feedback characteristic, and the method is used for realizing dynamic response of two-loop load and one-loop power: the load change of the secondary circuit is realized by adjusting the power of the steam generator, and the power of the reactor core is increased or decreased by utilizing the temperature change of the primary circuit coolant and the negative temperature coefficient of the reactor caused by the power change of the steam generator.
As described above, although the conventional nuclear power plant has advantages such as fast response and good follow-up performance, in the actual operation process, there are also: the stroke of the control rod driving mechanism of the power regulating rod group reaches the design limit value earlier, more control rod driving mechanisms need to be arranged, the number of control rods driven by a single control rod driving mechanism is small, and the like, so that the improvement of the design performance and the overall integration performance of the reactor core is hindered. The reactor mobility self-adjusting scheme provided by the scheme is used for reactors with reactive temperature negative feedback capacity, particularly reactors with strong reactive temperature negative feedback capacity, such as pressurized water reactors, provides a control idea different from the existing reactor power control mode, can cancel a power regulating rod group of a loop reactor core conventional design through the dynamic response of two-loop load and a loop power, does not depend on the action of a reactor power regulating rod, and realizes the purpose of controlling the reactor power by depending on the negative feedback characteristic of the reactor core through the adjustment of the reactor core design. By adopting the scheme, on one hand, compared with the power regulation mode of the existing control rod of the reactor tracking machine, the cancellation of the regulation rods or the reduction of the quantity of the regulation rods can reduce the risk of reactivity accidents of the reactor, such as rod clamping, rod bouncing, rod dropping and the like, and improve the inherent safety of the reactor; on the other hand, the problem that the stroke life of the control rod driving mechanism is too long is solved fundamentally, the design of the reactor core can be simplified, the power distribution of the reactor core can be flattened, the power design capability is improved, the aim of improving the overall integration and simplification of the reactor system is fulfilled, and the realization of a series of advanced indexes such as miniaturization of the reactor system design and long service life is facilitated; on the other hand, the weakening of the dependence of the adjusting rods or the avoidance of the adjusting rods can release the design constraint of the adjusting rods which need to be considered in the core design, and release larger lifting space for the core design.
When the reactor is specifically used, if the reactor is used for a pressurized water reactor, the setting of the reactor core power regulating rod group is cancelled, and the advantage of strong negative feedback capability of the reactive temperature of the pressurized water reactor is fully utilized without relying on the action of the reactor power regulating rod in the process of the mobility change of the reactor.
The further technical scheme is as follows:
as an implementation of the steam generator power regulation, it is provided that: and the adjustment of the power of the steam generator is realized by adjusting the opening of a steam adjusting valve at the steam outlet end of the steam generator.
As an implementation of the steam generator power regulation, it is provided that: the power of the steam generator is adjusted by adjusting the water supply flow of the steam generator.
In the above two modes, the temperature changes of the reactor and the primary loop system are caused by the flow change of the steam and the feed water of the secondary loop, and the reactor power is increased or decreased because the reactor has negative temperature coefficient and the reactivity is introduced. When the steam load increases the power-up, the reactor core coolant temperature is reduced to introduce positive reactivity so that the reactor core power-up matches the steam load, and similarly, when the steam load decreases the power-down, the reactor core coolant temperature is increased to introduce negative reactivity so that the reactor core power-down matches the steam load.
Preferably, the above manner of synchronously adjusting the opening of the steam regulating valve and the flow rate of the feed water is adopted.
In order to maintain the normal operation of a loop, the method comprises the following steps: and in the process of the power rise or the power fall of the reactor core, the pressure control system and the water supply system are used for realizing the pressure regulation of the primary circuit and the water level regulation of the pressure stabilizer.
As a specific implementation manner capable of fast responding, the following steps are set: the pressure regulation is realized by a voltage stabilizer: controlling saturation parameters of steam and water in a voltage stabilizer through electric heating or spray condensation to realize pressure regulation of a primary loop of the reactor;
the water level adjustment is realized through a primary circuit water supplementing system.
In order to match with a compact system design concept, the quick-action response capability of the reactor is improved, and the response time to load change is shortened, wherein the length of a pipeline between a main pump in a loop and a pressure container in the reactor is less than 1000 mm.
In order to match with a compact system design concept, the fast dynamic response capability of the reactor is improved, and the response time to load change is shortened, wherein the steam generator is a direct-current steam generator.
In order to reduce the height of the reactor, the aim of reducing the circulation flow path and time of the primary coolant is achieved, so that the temperature change of the primary coolant caused by the load change of the secondary circuit can be transferred to the core in the shortest time, and the matching of the primary and secondary circuits is realized quickly, and the steam generator is arranged inside the pressure vessel.
In order to be able to compensate for the variations in the volume of the coolant in the primary circuit more quickly, in the nuclear reactor, the volume of the pressurizer is: 25-35% of the volume of the primary loop water.
In order to realize the integral automatic operation of the reactor, the method is set as follows: the method is realized based on a control system: the control system receives a load demand signal, judges the deviation from the current power of the reactor core based on the load demand, and adjusts the power of the steam generator according to the deviation; meanwhile, the linkage of the reactor core power change and the working state change of a primary circuit auxiliary system is realized through a control system.
The invention has the following beneficial effects:
although the existing nuclear power device has the advantages of fast response, good following performance and the like, in the actual application process, the following advantages are also provided: the stroke of the control rod driving mechanism of the power regulating rod group reaches the design limit value earlier, more control rod driving mechanisms need to be arranged, the number of control rods driven by a single control rod driving mechanism is small, and the like, so that the improvement of the design performance and the overall integration performance of the reactor core is hindered. The reactor mobility self-adjusting scheme provided by the scheme is used for reactors with reactive temperature negative feedback capacity, particularly reactors with strong reactive temperature negative feedback capacity, such as pressurized water reactors, provides a control idea different from the existing reactor power control mode, can cancel a power regulating rod group of a loop reactor core conventional design through the dynamic response of two-loop load and a loop power, does not depend on the action of a reactor power regulating rod, and realizes the purpose of controlling the reactor power by depending on the negative feedback characteristic of the reactor core through the adjustment of the reactor core design. By adopting the scheme, on one hand, compared with the power regulation mode of the existing control rod of the reactor tracking machine, the cancellation of the regulation rods or the reduction of the quantity of the regulation rods can reduce the risk of reactivity accidents of the reactor, such as rod clamping, rod bouncing, rod dropping and the like, and improve the inherent safety of the reactor; on the other hand, the problem that the stroke life of the control rod driving mechanism is too long is solved fundamentally, the design of the reactor core can be simplified, the power distribution of the reactor core can be flattened, the power design capability is improved, the aim of improving the overall integration and simplification of the reactor system is fulfilled, and the realization of a series of advanced indexes such as miniaturization of the reactor system design and long service life is facilitated; on the other hand, the weakening of the dependence of the adjusting rods or the avoidance of the adjusting rods can release the design constraint of the adjusting rods which need to be considered in the core design, and release larger lifting space for the core design.
Drawings
FIG. 1 is a process flow diagram of an embodiment of a method for reactor maneuverability self-tuning in accordance with the present invention;
FIG. 2 is a static reactor operating curve based on the present method for reflecting the average coolant temperature as a function of power after a self-regulating power control scheme.
Detailed Description
The present invention will be described in further detail with reference to examples, but the structure of the present invention is not limited to the following examples.
Example 1:
a reactor maneuverability self-tuning method for reactor core power regulation, the method being implemented based on a reactor core with negative feedback characteristics, the method being used to achieve dynamic response of two-loop load to one-loop power: the load change of the secondary circuit is realized by adjusting the power of the steam generator, and the power of the reactor core is increased or decreased by utilizing the temperature change of the primary circuit coolant and the negative temperature coefficient of the reactor caused by the power change of the steam generator.
As described above, although the conventional nuclear power plant has advantages such as fast response and good follow-up performance, in the actual operation process, there are also: the stroke of the control rod driving mechanism of the power regulating rod group reaches the design limit value earlier, more control rod driving mechanisms need to be arranged, the number of control rods driven by a single control rod driving mechanism is small, and the like, so that the improvement of the design performance and the overall integration performance of the reactor core is hindered. The reactor mobility self-adjusting scheme provided by the scheme is used for reactors with reactive temperature negative feedback capacity, particularly reactors with strong reactive temperature negative feedback capacity, such as pressurized water reactors, provides a control idea different from the existing reactor power control mode, can cancel a power regulating rod group of a loop reactor core conventional design through the dynamic response of two-loop load and a loop power, does not depend on the action of a reactor power regulating rod, and realizes the purpose of controlling the reactor power by depending on the negative feedback characteristic of the reactor core through the adjustment of the reactor core design. By adopting the scheme, on one hand, compared with the power regulation mode of the existing control rod of the reactor tracking machine, the cancellation of the regulation rods or the reduction of the quantity of the regulation rods can reduce the risk of reactivity accidents of the reactor, such as rod clamping, rod bouncing, rod dropping and the like, and improve the inherent safety of the reactor; on the other hand, the problem that the stroke life of the control rod driving mechanism is too long is solved fundamentally, the design of the reactor core can be simplified, the power distribution of the reactor core can be flattened, the power design capability is improved, the aim of improving the overall integration and simplification of the reactor system is fulfilled, and the realization of a series of advanced indexes such as miniaturization of the reactor system design and long service life is facilitated; on the other hand, the weakening of the dependence of the adjusting rods or the avoidance of the adjusting rods can release the design constraint of the adjusting rods which need to be considered in the core design, and release larger lifting space for the core design.
When the reactor is specifically used, if the reactor is used for a pressurized water reactor, the setting of the reactor core power regulating rod group is cancelled, and the advantage of strong negative feedback capability of the reactive temperature of the pressurized water reactor is fully utilized without relying on the action of the reactor power regulating rod in the process of the mobility change of the reactor.
Example 2:
this example is further defined on the basis of example 1:
as an implementation of the steam generator power regulation, it is provided that: and the adjustment of the power of the steam generator is realized by adjusting the opening of a steam adjusting valve at the steam outlet end of the steam generator.
As an implementation of the steam generator power regulation, it is provided that: the power of the steam generator is adjusted by adjusting the water supply flow of the steam generator.
In the above two modes, the temperature changes of the reactor and the primary loop system are caused by the flow change of the steam and the feed water of the secondary loop, and the reactor power is increased or decreased because the reactor has negative temperature coefficient and the reactivity is introduced. When the steam load increases the power-up, the reactor core coolant temperature is reduced to introduce positive reactivity so that the reactor core power-up matches the steam load, and similarly, when the steam load decreases the power-down, the reactor core coolant temperature is increased to introduce negative reactivity so that the reactor core power-down matches the steam load.
Preferably, the above manner of synchronously adjusting the opening of the steam regulating valve and the flow rate of the feed water is adopted.
In order to maintain the normal operation of a loop, the method comprises the following steps: and in the process of the power rise or the power fall of the reactor core, the pressure control system and the water supply system are used for realizing the pressure regulation of the primary circuit and the water level regulation of the pressure stabilizer.
As a specific implementation manner capable of fast responding, the following steps are set: the pressure regulation is realized by a voltage stabilizer: controlling saturation parameters of steam and water in a voltage stabilizer through electric heating or spray condensation to realize pressure regulation of a primary loop of the reactor;
the water level adjustment is realized through a primary circuit water supplementing system.
In order to match with a compact system design concept, the quick-action response capability of the reactor is improved, and the response time to load change is shortened, wherein the length of a pipeline between a main pump in a loop and a pressure container in the reactor is less than 1000 mm.
In order to match with a compact system design concept, the fast dynamic response capability of the reactor is improved, and the response time to load change is shortened, wherein the steam generator is a direct-current steam generator.
In order to reduce the height of the reactor, the aim of reducing the circulation flow path and time of the primary coolant is achieved, so that the temperature change of the primary coolant caused by the load change of the secondary circuit can be transferred to the core in the shortest time, and the matching of the primary and secondary circuits is realized quickly, and the steam generator is arranged inside the pressure vessel.
In order to be able to compensate for the variations in the volume of the coolant in the primary circuit more quickly, in the nuclear reactor, the volume of the pressurizer is: 25-35% of the volume of the primary loop water.
In order to realize the integral automatic operation of the reactor, the method is set as follows: the method is realized based on a control system: the control system receives a load demand signal, judges the deviation from the current power of the reactor core based on the load demand, and adjusts the power of the steam generator according to the deviation; meanwhile, the linkage of the reactor core power change and the working state change of a primary circuit auxiliary system is realized through a control system.
Example 3:
the embodiment is further defined on the basis of the corresponding technical solutions provided by the above embodiments, and the present solution is further explained with reference to fig. 1 and fig. 2:
FIG. 2 shows the average temperature of the coolant as a function of power after a self-regulated power control scheme has been employed. When the load demand of the two loops is reduced, the average temperature Tref1 of the reactor coolant gradually rises to Tref', and larger negative reactivity is introduced, so that the power of the reactor core is reduced and finally the reactor core is stabilized. To realize a self-regulating power control scheme with a large power range, a large negative feedback coefficient of the coolant temperature must be ensured in design; meanwhile, in order to control the average core coolant temperature within the stable operation band, as shown by the dotted line, it is necessary to set corresponding design requirements for the stable operation of the apparatus.
The specific operation flow of the self-regulating power control scheme is as follows, as shown in fig. 1:
in the process of converting the lifting load working condition of the nuclear power plant, the steam flow of the steam generator is adjusted by adjusting the opening of steam adjusting valves (M01 and M02) according to the mobility requirement and a certain change rate.
The steam generator feedwater flow is varied by steam generator feedwater valves (F01 and F02) to follow the steam flow variation. The temperature change of the reactor and the primary loop system is caused by the flow change of the steam and the feed water of the secondary loop, and the reactor power is increased or decreased because the reactor has negative temperature coefficient and the reactivity is introduced. When the steam load increases the power-up, the reactor core coolant temperature is reduced to introduce positive reactivity so that the reactor core power-up matches the steam load, and similarly, when the steam load decreases the power-down, the reactor core coolant temperature is increased to introduce negative reactivity so that the reactor core power-down matches the steam load.
The pressure regulator pressure control system controls the saturation parameters of steam and water in the pressure regulator by electric heating to realize pressure regulation of a reactor coolant system; when the instantaneous power changes, the pressure fluctuation amplitude is limited within an allowable range by the compressibility of steam and spray condensation or heating by an electric heater. And in the working condition conversion process of the primary circuit water replenishing system, the contraction or expansion of the water volume of the primary circuit system is compensated (through W01-W04 and the like), and the water level of the voltage stabilizer is maintained within a normal range.
By the conversion mode and the operation of each system, normal conversion among working conditions can be realized, parameters such as reactor power, coolant temperature, steam pressure and the like fluctuate within an allowable range in the conversion process, protection actions are not triggered, steam discharge is not triggered, and on the premise of ensuring the safety of the reactor, a loop system of the reactor has good load tracking capacity in the transition process, and the requirement of the maneuverability of a nuclear power device is met.
The foregoing is a more detailed description of the present invention in connection with specific preferred embodiments thereof, and it is not intended that the specific embodiments of the present invention be limited to these descriptions. For those skilled in the art to which the invention pertains, other embodiments that do not depart from the scope of the invention are intended to be encompassed by the scope of the invention.
Claims (10)
1. A reactor maneuverability self-tuning method for reactor core power regulation, the method being implemented based on a reactor core with negative feedback characteristics, characterized in that the method is used to achieve dynamic response of two-loop load to one-loop power: the load change of the secondary circuit is realized by adjusting the power of the steam generator, and the power of the reactor core is increased or decreased by utilizing the temperature change of the primary circuit coolant and the negative temperature coefficient of the reactor caused by the power change of the steam generator.
2. The method of claim 1, wherein the adjusting the power of the steam generator is performed by adjusting the opening of a steam control valve at a steam outlet of the steam generator.
3. The method of claim 1, wherein the adjusting the steam generator power is performed by adjusting steam generator feedwater flow.
4. The method of claim 1, wherein primary pressure regulation and pressurizer level regulation are achieved by the pressure control system and the makeup system during core power ramp up or ramp down.
5. The method of claim 4, wherein the pressure regulation is performed by a potentiostat: controlling saturation parameters of steam and water in a voltage stabilizer through electric heating or spray condensation to realize pressure regulation of a primary loop of the reactor;
the water level adjustment is realized through a primary circuit water supplementing system.
6. A method of reactor maneuverability self-tuning as claimed in claim 1 wherein the length of the piping between the main pump and the pressure vessel in a primary circuit in the reactor is less than 1000 mm.
7. The method of claim 1, wherein the steam generator is a once-through steam generator.
8. The method of claim 8, wherein the steam generator is disposed within the pressure vessel.
9. The method of claim 1, wherein the nuclear reactor comprises a pressurizer volume of 25% to 35% of a primary loop water volume.
10. A method for self-regulation of reactor maneuverability according to any of claims 1 to 9 characterized in that it is based on a control system implementing: the control system receives a load demand signal, judges the deviation from the current power of the reactor core based on the load demand, and adjusts the power of the steam generator according to the deviation; meanwhile, the linkage of the reactor core power change and the working state change of a primary circuit auxiliary system is realized through a control system.
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| CN113539527A (en) * | 2021-06-16 | 2021-10-22 | 西安交通大学 | Method and system for adjusting startup of space heat pipe cooling reactor |
| CN113871037A (en) * | 2021-09-14 | 2021-12-31 | 中广核研究院有限公司 | Reactor operation control method, reactor operation control device, computer equipment and storage medium |
| WO2022262225A1 (en) * | 2021-06-18 | 2022-12-22 | 中广核研究院有限公司 | Reactor starting method and system |
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