CN114038595A - Flow and power two-subarea control method for pressurized water reactor core - Google Patents
Flow and power two-subarea control method for pressurized water reactor core Download PDFInfo
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- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title claims abstract description 70
- 238000000034 method Methods 0.000 title claims abstract description 29
- 239000002826 coolant Substances 0.000 claims abstract description 55
- 238000013461 design Methods 0.000 abstract description 37
- 238000005516 engineering process Methods 0.000 abstract description 11
- 230000008569 process Effects 0.000 abstract description 6
- 238000005192 partition Methods 0.000 description 25
- 239000002574 poison Substances 0.000 description 17
- 231100000614 poison Toxicity 0.000 description 17
- 230000009257 reactivity Effects 0.000 description 13
- 238000013316 zoning Methods 0.000 description 7
- 238000012360 testing method Methods 0.000 description 6
- 239000000446 fuel Substances 0.000 description 5
- 238000011160 research Methods 0.000 description 5
- 238000005457 optimization Methods 0.000 description 4
- XLYOFNOQVPJJNP-ZSJDYOACSA-N Heavy water Chemical compound [2H]O[2H] XLYOFNOQVPJJNP-ZSJDYOACSA-N 0.000 description 2
- 230000009286 beneficial effect Effects 0.000 description 2
- 239000006185 dispersion Substances 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 230000006872 improvement Effects 0.000 description 2
- 230000000712 assembly Effects 0.000 description 1
- 238000000429 assembly Methods 0.000 description 1
- 238000009835 boiling Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000004907 flux Effects 0.000 description 1
- 230000007246 mechanism Effects 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 230000002093 peripheral effect Effects 0.000 description 1
- 238000006467 substitution reaction Methods 0.000 description 1
- 230000001052 transient effect Effects 0.000 description 1
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- G—PHYSICS
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- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/02—Details of handling arrangements
- G21C19/04—Means for controlling flow of coolant over objects being handled; Means for controlling flow of coolant through channel being serviced, e.g. for preventing "blow-out"
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
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- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
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Abstract
The invention discloses a flow and power two-subarea control method for a pressurized water reactor core, which relates to the technical field of the reactor core of a nuclear reactor and has the technical scheme that: the cross section of the pressurized water reactor core is sequentially provided with a first flow area and a second flow area in an outward expansion mode along the radial direction, and the first flow area wraps the second flow area; the flow rate of the coolant introduced into the first flow rate area is larger than that of the coolant introduced into the second flow rate area. Compared with the existing three-region control technology, the invention effectively reduces the complexity of the reactor core design and has higher flexibility of the flow and power cooperative control of the pressurized water reactor in the practical application process, and simultaneously reduces the practical use cost.
Description
Technical Field
The invention relates to the technical field of nuclear reactor cores, in particular to a flow and power two-subarea control method for a pressurized water reactor core.
Background
At present, non-pressurized water reactors such as fast reactors, boiling water reactors, supercritical water reactors, heavy water reactors and the like all adopt power partition and flow partition technologies in the world, so that the efficient utilization of reactor core coolant is realized. Under the same core power level, through the design of power partition and flow partition, the coolant flow required by the core can be reduced, or the thermal safety margin of the core can be improved, and the core outlet coolant temperature can be improved, so that the overall parameters and the overall performance of the core can be improved. For example, the flow of the reactor core of the Indian prototype fast reactor is divided into 15 areas, and the flow of the Chinese experimental fast reactor is divided into 4 areas; in addition, the supercritical water reactor design in Japan also adopts a flow partition concept, and the reactor core flow is finely matched according to the power of each box assembly.
For the pressurized water reactor core partition design, less engineering application is realized at home and abroad, the applicant applies a patent in the prior art to realize the pressurized water reactor core flow partition design, the publication number is CN104882183B, the requirement of the system coolant flow is reduced by 15-19 percent on the premise that the thermal safety margin of the reactor core is not reduced, and the temperature of the coolant at the outlet of the reactor core is improved by at least 3-6 ℃.
However, the flow control difficulty of the existing pressurized water reactor core flow dividing and dividing design is high, the core design complexity is high, the flexibility of the pressurized water reactor core flow and power cooperative control in the practical application process is poor, and the practical use cost is high. Therefore, it is important to further study the flow and power distribution of the pressurized water reactor core.
Disclosure of Invention
Aiming at the design of the pressurized water reactor core, the invention adopts the design of dividing the core power and the flow into two regions under the condition of realizing the performance of reducing the flow of the pressurized water reactor core and the performance of improving the core outlet temperature, thereby effectively reducing the complexity of the core design, having stronger flexibility of the cooperative control of the flow and the power of the pressurized water reactor core in the practical application process and simultaneously reducing the practical use cost.
The technical purpose of the invention is realized by the following technical scheme: a flow and power two-subarea control method for a pressurized water reactor core comprises the following steps:
the cross section of the pressurized water reactor core is sequentially provided with a first flow area and a second flow area in an outward expansion mode along the radial direction, and the first flow area wraps the second flow area;
the flow rate of the coolant introduced into the first flow rate area is larger than that of the coolant introduced into the second flow rate area.
Further, the first flow area is communicated with the coolant with the average mass flow rate of 122-132% of the whole pressurized water reactor core, and the second flow area is communicated with the coolant with the average mass flow rate of 65-75% of the whole pressurized water reactor core.
Furthermore, the first flow area is filled with the coolant with the average mass flow rate of 122-127% of the whole pressurized water reactor core, and the second flow area is filled with the coolant with the average mass flow rate of 67-72% of the whole pressurized water reactor core.
Furthermore, the first flow area is filled with coolant with the average mass flow rate of 123.9% of the total mass flow rate of the pressurized water reactor core, and the second flow area is filled with coolant with the average mass flow rate of 70.3% of the total mass flow rate of the pressurized water reactor core.
Furthermore, the distribution centers of the first flow area and the second flow area are both arranged concentrically with the axis of the reactor core.
Further, the outer contour line of the first flow area is any one of a circle, an ellipse, a prism and a regular polygon.
Further, the inner contour line of the second flow area is any one of a circle, an ellipse, a prism and a regular polygon.
Further, the outer contour line of the second flow rate region may be any one of a circle and a regular polygon.
Further, the regular polygon is a regular quadrangle, a regular hexagon or a regular octagon.
Further, the outer contour of the first flow region coincides with the inner contour of the second flow region.
Compared with the prior art, the invention has the following beneficial effects:
1. compared with the existing three-region control technology, the method has the advantages that the complexity of the core design is effectively reduced under the condition that the performance of reducing the flow of the pressurized water reactor core coolant and the performance of improving the core outlet temperature are not weakened, the flexibility of the cooperative control of the flow and the power of the pressurized water reactor core in the practical application process is stronger, and the practical use cost is reduced at the same time;
2. the invention can reduce the coolant flow demand of the system by 15-16 ℃ and improve the coolant temperature at the reactor core outlet by 3-5 ℃ on the premise of not reducing the thermal safety allowance of the reactor core.
Drawings
The accompanying drawings, which are included to provide a further understanding of the embodiments of the invention and are incorporated in and constitute a part of this application, illustrate embodiment(s) of the invention and together with the description serve to explain the principles of the invention. In the drawings:
FIG. 1 is a schematic illustration of core flow zoning in an embodiment of the invention;
FIG. 2 is a schematic diagram of the power division of the core in the whole life cycle in the embodiment of the invention, wherein a is the beginning of the life cycle, b is the life cycle, and c is the end of the life cycle.
Reference numbers and corresponding part names in the drawings:
1. a first flow rate zone; 2. a second flow field.
Detailed Description
In order to make the objects, technical solutions and advantages of the present invention more apparent, the present invention is further described in detail below with reference to examples and accompanying drawings, and the exemplary embodiments and descriptions thereof are only used for explaining the present invention and are not meant to limit the present invention.
It will be understood that when an element is referred to as being "secured to" or "disposed on" another element, it can be directly on the other element or be indirectly on the other element. When an element is referred to as being "connected to" another element, it can be directly or indirectly connected to the other element.
It will be understood that the terms "length," "width," "upper," "lower," "front," "rear," "left," "right," "vertical," "horizontal," "top," "bottom," "inner," "outer," and the like, as used herein, refer to an orientation or positional relationship indicated in the drawings that is solely for the purpose of facilitating the description and simplifying the description, and do not indicate or imply that the device or element being referred to must have a particular orientation, be constructed and operated in a particular orientation, and is therefore not to be construed as limiting the invention.
Furthermore, the terms "first", "second" and "first" are used for descriptive purposes only and are not to be construed as indicating or implying relative importance or implicitly indicating the number of technical features indicated. Thus, a feature defined as "first" or "second" may explicitly or implicitly include one or more of that feature. In the description of the present invention, "a plurality" means two or more unless specifically defined otherwise.
Example 1
A flow and power two-zone control method for a pressurized water reactor core is disclosed, as shown in figure 1, a first flow zone 1 and a second flow zone 2 are sequentially arranged on a cross section of the pressurized water reactor core in an outward extending mode along a radial direction, and the first flow zone 1 wraps the second flow zone 2. The first flow area 1 is filled with coolant with the average mass flow rate of 122% of the whole pressurized water reactor core, and the second flow area 2 is filled with coolant with the average mass flow rate of 65% of the whole pressurized water reactor core. The distribution centers of the first flow area 1 and the second flow area 2 are both arranged concentrically with the axis of the reactor core. The outer contour of the first flow field 1 coincides with the inner contour of the second flow field 2, and in this embodiment, the outer contour of the first flow field 1 and the inner and outer contours of the second flow field 2 are both circular.
Through the test: in the embodiment, by adopting the design technology of dividing the power of the reactor core into two areas and dividing the flow into two areas, the flow demand of the coolant of the system can be reduced by more than 15 percent on the premise that the thermal safety allowance of the reactor core is not reduced, and the temperature of the coolant at the outlet of the reactor core can be improved by more than 4 ℃.
Example 2
A flow and power two-zone control method for a pressurized water reactor core is characterized in that a first flow zone 1 and a second flow zone 2 are sequentially arranged on a cross section of the pressurized water reactor core in an outward extending mode along the radial direction, and the first flow zone 1 wraps the second flow zone 2. The first flow area 1 is filled with coolant with an average mass flow rate of 132% of the total mass flow rate of the pressurized water reactor core, and the second flow area 2 is filled with coolant with an average mass flow rate of 75% of the total mass flow rate of the pressurized water reactor core. The distribution centers of the first flow area 1 and the second flow area 2 are both arranged concentrically with the axis of the reactor core. The outer contour of the first flow field 1 coincides with the inner contour of the second flow field 2, and in this embodiment, the outer contour of the first flow field 1 and the inner and outer contours of the second flow field 2 are both circular.
Through the test: in the embodiment, by adopting the design technology of dividing the power of the reactor core into two areas and dividing the flow into two areas, the flow demand of the coolant of the system can be reduced by more than 16% on the premise that the thermal safety allowance of the reactor core is not reduced, and the temperature of the coolant at the outlet of the reactor core can be improved by more than 3 ℃.
Example 3
A flow and power two-zone control method for a pressurized water reactor core is characterized in that a first flow zone 1 and a second flow zone 2 are sequentially arranged on a cross section of the pressurized water reactor core in an outward extending mode along the radial direction, and the first flow zone 1 wraps the second flow zone 2. The first flow area 1 is filled with coolant with the average mass flow rate of 122% of the whole pressurized water reactor core, and the second flow area 2 is filled with coolant with the average mass flow rate of 67% of the whole pressurized water reactor core. The distribution centers of the first flow area 1 and the second flow area 2 are both arranged concentrically with the axis of the reactor core. The outer contour of the first flow field 1 coincides with the inner contour of the second flow field 2, and in this embodiment, the outer contour of the first flow field 1 and the inner and outer contours of the second flow field 2 are both circular.
Through the test: in the embodiment, by adopting the design technology of dividing the power of the reactor core into two areas and dividing the flow into two areas, the flow demand of the coolant of the system can be reduced by more than 16% on the premise that the thermal safety margin of the reactor core is not reduced, and the temperature of the coolant at the outlet of the reactor core can be improved by more than 4 ℃.
Example 4
A flow and power two-zone control method for a pressurized water reactor core is characterized in that a first flow zone 1 and a second flow zone 2 are sequentially arranged on a cross section of the pressurized water reactor core in an outward extending mode along the radial direction, and the first flow zone 1 wraps the second flow zone 2. The first flow area 1 is filled with coolant with the average mass flow rate of 127% of the whole pressurized water reactor core, and the second flow area 2 is filled with coolant with the average mass flow rate of 72% of the whole pressurized water reactor core. The distribution centers of the first flow area 1 and the second flow area 2 are both arranged concentrically with the axis of the reactor core. The outer contour of the first flow field 1 coincides with the inner contour of the second flow field 2, and in this embodiment, the outer contour of the first flow field 1 and the inner and outer contours of the second flow field 2 are both circular.
Through the test: in the embodiment, by adopting the design technology of dividing the power of the reactor core into two areas and dividing the flow into two areas, the flow demand of the coolant of the system can be reduced by more than 15 percent on the premise that the thermal safety allowance of the reactor core is not reduced, and the temperature of the coolant at the outlet of the reactor core can be improved by more than 4 ℃.
Example 5
A flow and power two-zone control method for a pressurized water reactor core is characterized in that a first flow zone 1 and a second flow zone 2 are sequentially arranged on a cross section of the pressurized water reactor core in an outward extending mode along the radial direction, and the first flow zone 1 wraps the second flow zone 2. The first flow area 1 is filled with coolant with the average mass flow rate of 123.9 percent of the whole pressurized water reactor core, and the second flow area 2 is filled with coolant with the average mass flow rate of 70.3 percent of the whole pressurized water reactor core. The distribution centers of the first flow area 1 and the second flow area 2 are both arranged concentrically with the axis of the reactor core. The outer contour of the first flow field 1 coincides with the inner contour of the second flow field 2, and in this embodiment, the outer contour of the first flow field 1 and the inner and outer contours of the second flow field 2 are both circular.
As shown in fig. 2, the radial power partitions obtained in the core design in fig. 2 at the beginning of the core life, during the core life and at the end of the core life can be further colored by changing the radial power according to different gray values. It has been found that throughout the life of the core, the central region is maintained at a higher power level and the peripheral regions are maintained at a lower power level.
Through the test: in the embodiment, by adopting the design technology of dividing the power of the reactor core into two areas and dividing the flow into two areas, the flow demand of the coolant of the system can be reduced by more than 16% on the premise that the thermal safety margin of the reactor core is not reduced, and the temperature of the coolant at the outlet of the reactor core can be improved by more than 5 ℃.
Example 6
A flow and power two-zone control method for a pressurized water reactor core is characterized in that a first flow zone 1 and a second flow zone 2 are sequentially arranged on a cross section of the pressurized water reactor core in an outward extending mode along the radial direction, and the first flow zone 1 wraps the second flow zone 2. The first flow area 1 is filled with coolant with the average mass flow rate of 123.9 percent of the whole pressurized water reactor core, and the second flow area 2 is filled with coolant with the average mass flow rate of 70.3 percent of the whole pressurized water reactor core. The distribution centers of the first flow area 1 and the second flow area 2 are both arranged concentrically with the axis of the reactor core. The outer contour of the first flow field 1 coincides with the inner contour of the second flow field 2, and in this embodiment, the outer contour of the first flow field 1 and the inner and outer contours of the second flow field 2 are regular octagons.
Through the test: in the embodiment, by adopting the design technology of dividing the power of the reactor core into two areas and dividing the flow into two areas, the flow demand of the coolant of the system can be reduced by more than 15 percent on the premise that the thermal safety allowance of the reactor core is not reduced, and the temperature of the coolant at the outlet of the reactor core can be improved by more than 5 ℃.
1. Power partition design
Firstly, power partition design is developed, and the work belongs to the field of reactor physical design. The aim is to realize the stable distribution of the reactor core radial power in the whole life through the radial partition of the reactor core fuel and the burnable poison and the matching between different burnable poison types, namely the reactor core radial power has the same or similar distribution shape under different burning time. The core radial power distribution research firstly needs to meet the requirements of the core life, reactivity control and core overall power distribution, so the core radial power distribution research and the core optimization design research are synchronously developed.
For a rod-controlled reactor core, reactivity control is generally completed by control rods and burnable poison together, the power distribution can be greatly changed when the control rods act to compensate fuel consumption, and the use of the burnable poison can cause the power distribution to be changed and the loss of service life, so that reasonable control rod arrangement, rod lifting programs, burnable poison type selection, type matching and reasonable space arrangement are important measures for optimizing the reactor core of the reactor.
Control rod placement is almost unique for a given core geometry due to limitations in the control rod drive mechanism center-to-center spacing, overall core reactivity control capability, and the like. Thus, two core optimization measures, core radial zoning and poison matching, are mainly studied.
The core radial zoning is achieved by a suitable assembly Kinf gradient, which is constructed mainly by two ways: the reactor core radial fuel phase volume partition; secondly, the reactor core is divided into radial burnable poison areas. For a high leakage core it is common for the core to be built with components Kinf from inside to outside in order to flatten the core radial power distribution.
The burnable poison matching is mainly realized by different reactivity release sizes and different speeds of different burnable poison types, for example, the initial reactivity of a dispersion poison assembly is larger, the release of the reactivity is larger and faster in the service life, the initial reactivity of a burnable poison rod assembly is smaller, the release of the reactivity is smaller and slower in the service life, the reasonable matching of the dispersion poison assembly and the burnable poison rod assembly can ensure that the reactivity is released relatively stably in the whole service life, the reactivity control in the whole service life is facilitated, and the power distribution cannot be changed greatly.
Therefore, the reasonable matching between the reactor core radial partition and different burnable poison types is an important means for realizing the stable reactor core radial power distribution in the whole life.
The effect of power division is realized by the radial power of the reactor core (nuclear enthalpy rise factor F) at each burning time△H) The distribution is characterized by the variation of the burn-up, and F can be seen from the figure△HHaving a distinct zoning characteristic, while F△HThe distribution shape of (2) is less changed with the burn-up.
Through the research on the reactor core radial power partition, the feasibility of the reactor core radial power partition technology is preliminarily verified by adopting the measures of the reactor core radial partition, the reasonable matching of burnable poison and the like, and a physical basis is provided for the flow partition design. The following measures are mainly considered in the research process of the reactor core radial power partition:
1) dividing the reactor core into two regions from inside to outside according to the size of the initial Kinf of the component;
2) the content of dispersed poison and combustible poison is optimized, so that the reactivity release speed and the reactivity release size of different assemblies are different, the reactivity matching in the service life is better realized, and the power distribution in the service life is ensured not to be changed sharply.
2. Flow zoning design
After the reactor power zoning is completed, a reactor flow zoning design is developed. The work belongs to the category of thermal hydraulic design of reactor cores.
According to the idea of flow partition and power partition collaborative design, according to the flow distribution principle that a region with high core power is matched with larger coolant flow and a region with low core power is matched with less coolant flow, 123.9% of core average flow is distributed to high-power region components, 70.3% of core average flow is distributed to low-power components, and the improvement condition of the flow partition scheme on main limiting factors influencing thermal design margins is analyzed.
Under the scheme of considering the flow subareas, the thermodynamic key parameters (DNBR, hot channel outlet steam content and maximum fuel temperature) of each component are calculated and counted at each burn-up time in the whole service life. Aiming at key thermotechnical parameters concerned in thermotechnical hydraulic design, a power partition and flow partition collaborative design strategy is adopted, and the calculation result considering a flow partition scheme can be mainly summarized as follows:
the critical parameters of thermal engineering, such as DNBR and vapor content of hot channel outlet, which are greatly influenced by the flow, can be improved by increasing the flow supply in the assembly. The highest vapor fraction in the hot aisle occurs at the aisle exit, which is determined primarily by the coolant flow in the aisle and the energy released into the aisle by the fuel elements in the aisle, so that increasing the flow can significantly reduce the hot aisle exit vapor fraction. Increasing the flow rate is also beneficial to increasing the critical heat flux density, and as can be seen from the definition of DNBR, the increasing of the flow rate has a significant effect on increasing the DNBR safety margin under the premise of considering the same component power distribution.
3. Reactor design
After the success rate and the flow rate are partitioned, structure and flow field optimization design work needs to be carried out on a lower cavity of the reactor, and the work belongs to the field of reactor structure design. There is no flow distribution structure in the lower chamber of the prototype reactor. Several design schemes of the lower chamber flow distribution device are provided, and the pressure container loaded with the flow distribution device is subjected to grid division and calculation. A CFD method is used for analyzing and evaluating a plurality of reactor internals having flow field optimization, a lower chamber structure which can effectively inhibit transient eddy current and enables pressure distribution to be stable is selected, and the lower chamber structure is realized through structural design.
The speed field and the pressure field of each type of pressure container are obtained through calculation, and the comparison of the pressure cloud pictures of the lower chamber shows that the pressure distribution is obviously homogenized after the flow distribution device is additionally arranged, so that the flow field of the lower chamber is greatly optimized. And meanwhile, the reactor core flow is extracted, and the reactor core flow distribution is obtained. Through comparing with the calculation result of the pressure vessel of the unloaded flow distribution device, the distribution cover improves the nonuniformity of the flow distribution of the reactor core, and the design concept of power flow partition is fully satisfied structurally.
The working principle is as follows: compared with the existing three-region control technology, the core design complexity is effectively reduced and the flexibility of the flow and power cooperative control of the pressurized water reactor core in the practical application process is stronger, and the practical use cost is reduced and higher; the flow demand of the system coolant can be reduced by 15-16 ℃ on the premise that the thermal safety allowance of the reactor core is not reduced, and the temperature of the reactor core outlet coolant is increased by 3-5 ℃.
The above-mentioned embodiments are intended to illustrate the objects, technical solutions and advantages of the present invention in further detail, and it should be understood that the above-mentioned embodiments are merely exemplary embodiments of the present invention, and are not intended to limit the scope of the present invention, and any modifications, equivalent substitutions, improvements and the like made within the spirit and principle of the present invention should be included in the scope of the present invention.
Claims (10)
1. A flow and power two-subarea control method for a pressurized water reactor core is characterized by comprising the following steps:
the cross section of the pressurized water reactor core is sequentially provided with a first flow area (1) and a second flow area (2) by extending outwards along the radial direction, and the first flow area (1) wraps the second flow area (2);
the flow rate of the coolant introduced into the first flow rate area (1) is greater than that of the coolant introduced into the second flow rate area (2).
2. The method for controlling the flow and the power of the pressurized water reactor core according to claim 1, wherein the first flow area (1) is filled with the coolant with the average mass flow rate of 122 to 132 percent of the whole pressurized water reactor core, and the second flow area (2) is filled with the coolant with the average mass flow rate of 65 to 75 percent of the whole pressurized water reactor core.
3. The method for controlling the flow and the power of the pressurized water reactor core according to claim 1, wherein the first flow area (1) is filled with the coolant with the average mass flow rate of 122-127% of the whole pressurized water reactor core, and the second flow area (2) is filled with the coolant with the average mass flow rate of 67-72% of the whole pressurized water reactor core.
4. The method for controlling the flow and the power of the pressurized water reactor core according to claim 1, wherein the first flow area (1) is filled with the coolant with the average mass flow rate of 123.9 percent of the whole pressurized water reactor core, and the second flow area (2) is filled with the coolant with the average mass flow rate of 70.3 percent of the whole pressurized water reactor core.
5. The method for controlling the flow rate and the power of the pressurized water reactor core according to claim 1, wherein the distribution centers of the first flow rate region (1) and the second flow rate region (2) are both concentric with the axis of the core.
6. The method for controlling the flow rate and the power of the pressurized water reactor core according to claim 1, wherein the outer contour line of the first flow rate zone (1) is any one of a circle, an ellipse, a prism and a regular polygon.
7. The method for controlling the flow rate and the power of the pressurized water reactor core according to claim 1, wherein the inner contour line of the second flow rate area (2) is any one of a circle, an ellipse, a prism and a regular polygon.
8. The method for controlling the flow rate and the power of the pressurized water reactor core according to claim 1, wherein the outer contour line of the second flow rate zone (2) is any one of a circle and a regular polygon.
9. The method for controlling the flow rate and the power of the pressurized water reactor core according to any one of claims 6 to 8, wherein the regular polygon is a regular quadrangle, a regular hexagon or a regular octagon.
10. The method for controlling the flow rate and the power of the pressurized water reactor core according to claim 1, wherein the outer contour line of the first flow rate zone (1) is overlapped with the inner contour line of the second flow rate zone (2).
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| WO2011040989A1 (en) * | 2009-04-09 | 2011-04-07 | The Regents Of The University Of California | Annular core liquid-salt cooled reactor with multiple fuel and blanket zones |
| CN102737735A (en) * | 2012-07-04 | 2012-10-17 | 中国核动力研究设计院 | Combined square fuel assembly, reactor core and two-pass flowing method of super-critical water reactor |
| CN104882183A (en) * | 2015-04-09 | 2015-09-02 | 中国核动力研究设计院 | Flow partitioning method for reactor core of pressurized water reactor |
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2021
- 2021-11-11 CN CN202111333210.9A patent/CN114038595A/en active Pending
Patent Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
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| US5524128A (en) * | 1993-11-17 | 1996-06-04 | Entergy Operations, Inc. | Boiling water reactor stability control |
| WO2011040989A1 (en) * | 2009-04-09 | 2011-04-07 | The Regents Of The University Of California | Annular core liquid-salt cooled reactor with multiple fuel and blanket zones |
| CN102737735A (en) * | 2012-07-04 | 2012-10-17 | 中国核动力研究设计院 | Combined square fuel assembly, reactor core and two-pass flowing method of super-critical water reactor |
| CN104882183A (en) * | 2015-04-09 | 2015-09-02 | 中国核动力研究设计院 | Flow partitioning method for reactor core of pressurized water reactor |
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