CN112071451A - Pressurized water reactor multifunctional double-layer concrete containment system - Google Patents
Pressurized water reactor multifunctional double-layer concrete containment system Download PDFInfo
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- CN112071451A CN112071451A CN202010965745.7A CN202010965745A CN112071451A CN 112071451 A CN112071451 A CN 112071451A CN 202010965745 A CN202010965745 A CN 202010965745A CN 112071451 A CN112071451 A CN 112071451A
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/08—Vessels characterised by the material; Selection of materials for pressure vessels
- G21C13/093—Concrete vessels
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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
- G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
- G21C15/12—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from pressure vessel; from containment vessel
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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
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D1/00—Details of nuclear power plant
- G21D1/02—Arrangements of auxiliary equipment
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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
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
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- 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
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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Abstract
The invention provides a pressurized water reactor multifunctional double-layer concrete containment system, which is based on the existing double-layer concrete containment of a nuclear power plant, an annular water pool is arranged by reasonably utilizing the annular space of the double-layer containment, and the water in the water pool has the functions of various water bodies inside and outside the containment, such as a suppression water pool (SP) water body, a reactor core refueling water pool (IRWST) water body, a reactor cavity water injection system (CIS) water body, a safety injection system water tank water body and a containment passive heat export system (PCS) water body, so that the existing nuclear power plant containment system is greatly simplified, the IRWST, the CIS, the safety injection water tank and the PCS water tank outside the containment can be cancelled, the volume of the safety shell can be further reduced, the construction cost of the containment can be greatly reduced, and the economy of the nuclear power plant can be improved.
Description
Technical Field
The invention relates to a pressurized water reactor multifunctional double-layer concrete containment system, and belongs to the field of nuclear power.
Background
The containment vessel is the last safety barrier of the nuclear power plant and is also the most important safety barrier. A large amount of high-temperature high-pressure steam enters the containment under the accident condition of a nuclear power plant, so that the temperature and the pressure in the containment are rapidly raised, if the temperature and the pressure limit value which can be borne by the containment are exceeded, the integrity of the containment is damaged, and the radiated substances in the reactor are uncontrollably released to the external environment at the time, so that the harm is brought to the public and the environment. In order to ensure the integrity of the containment, a double-layer concrete containment design is generally adopted in the design of a new generation pressurized water reactor nuclear power plant, such as a nuclear power plant with Chinese proprietary intellectual property-Hualong I. The safety of a nuclear power plant is improved by the double-layer containment, but the manufacturing cost of the containment is also greatly improved, and the economy of nuclear power is sacrificed.
The pressurized water reactor nuclear power plant is generally provided with a spraying system and a containment passive heat exporting system, the spraying system condenses steam in a shell after an accident occurs through spraying liquid drops, so that the temperature and pressure in the shell are reduced, and the containment is prevented from being damaged due to overpressure. The passive containment heat exporting system transmits the energy of high-temperature and high-pressure steam in the shell to the outside of the shell by arranging the heat exchanger in the shell. However, spray systems typically require active components (pumps) to be activated, and cannot be activated in the event of a loss of power. The heat exchange capacity of the containment passive heat exporting system is related to the natural circulation flow, the natural circulation needs a certain time to be established, and before the natural circulation is established, the interior of the shell is still in a rapid temperature rise and pressure rise state, namely, the system has slow response to the pressure change in the shell. In addition, the cooling capacity of the containment passive heat exporting system is influenced by the volume of the cooling water tank, and according to the design requirement of the containment passive heat exporting system of the nuclear power plant, the cooling capacity of the containment passive heat exporting system can meet the requirement that the cooling capacity is not less than 72 hours, namely the system finally loses the effect of the containment passive heat exporting system due to the fact that water in the cooling water tank is evaporated to dryness after 72 hours. Furthermore, the water tank of the containment passive heat exporting system of the nuclear power station such as Hualong I is positioned at the top of the containment, the water tank is difficult to construct, the water tank can bring load to the containment, the investment of structural design of the containment is increased, and the high elevation of the water tank is unfavorable for the anti-seismic design of the containment.
In the conceptual design of a pressurized water reactor nuclear power plant, a scholars puts forward that water is added into an annular space between the outer side of a steel containment and a concrete shielding layer, and heat in the containment is taken away by utilizing the evaporation of the water in the annular space. However, the design is only suitable for the steel containment vessel, and the characteristic of good heat conductivity of the steel containment vessel is needed. Because concrete has poor thermal conductivity, it is not suitable for double-layer concrete containment. In addition, the water body in the annular space is only used as a cold source for absorbing the energy in the shell, and the function is single. And the water volume of the annular space is limited, the cooling capacity of the water body of the annular space to the shell is gradually weakened along with the reduction of the water evaporation amount of the water body, the long-time cooling of the containment is difficult to realize, and finally, the pressure in the shell is gradually increased along with the reduction of the water amount of the annular space under the condition of no external intervention (such as water replenishing of the annular space).
The energy in the shell is absorbed by the passive suppression system of the boiling water reactor nuclear power plant, and the suppression system absorbs the steam energy by utilizing the principle that steam and water are directly contacted and condensed, so that the power plant has the characteristic of high pressure response speed. However, if it is applied to a pressurized water reactor, a suppression water pool needs to be added in the shell, which not only occupies a compact space and limited overall resources in the shell (adding a system, increasing the matched periodic test and in-service inspection, etc.), but also adds additional system design and cost of the power plant, and is not suitable for the pressurized water reactor. Furthermore, the system is also unable to continue to absorb the energy of the steam inside the shell after a certain time, since the water inside it reaches saturation.
Disclosure of Invention
The invention aims to provide a pressurized water reactor multifunctional double-layer concrete containment system.
The purpose of the invention is realized as follows: the reactor comprises a double-layer containment vessel and a reactor arranged in the double-layer containment vessel, wherein an annular water pool is arranged in an annular space formed by the double-layer containment vessel, the bottom of the annular water pool is higher than the upper end face of a reactor core of the reactor, at least one group of pressure-suppressing pipelines are arranged in the annular water pool, the end parts of the pressure-suppressing pipelines penetrate through an inner shell of the double-layer containment vessel and extend into a large space of the containment vessel, and when the number of the pressure-suppressing pipelines is two or more, the pressure-suppressing pipelines are symmetrically arranged in the.
The invention also includes such structural features:
1. when a reactor is subjected to a breach accident, high-temperature and high-pressure steam enters a large containment space, the pressure in the shell rises rapidly, the pressure difference between the large containment space and an annular pool gas space is increased, mixed gas of the steam and uncondensed gas in the large containment space enters the annular pool through a pressure-restraining pipeline under the action of the pressure difference, the steam is absorbed by supercooled water in the pool, the uncondensed gas is stored in the annular pool gas space, and the rise of the pressure in the containment is restrained.
2. A pool cooling heat exchanger is arranged in the annular pool, an inlet and an outlet of the heat exchanger penetrate through the shell of the double-layer containment and are communicated with the atmosphere, air enters the heat exchanger from the lower inlet, the heat of the annular pool is absorbed in a heat transfer pipe of the heat exchanger and then is discharged from the upper outlet, and under the driving of the density difference of the air inside and outside the heat exchanger, external power is not needed, the air continuously transfers the heat of the pool to the external environment, so that the pool is kept in a supercooled state all the time.
3. The annular water pool is connected with the reactor through the reactor core safety injection pipeline and is connected with the reactor cavity through the reactor cavity water injection pipeline, the water pool is higher than the reactor core and the reactor cavity, external power is not needed, only water gravity is relied on, and the function of a safety injection system or a reactor cavity water injection system can be realized.
4. A passive reactor core cooling system or a secondary side passive waste heat removal system heat exchanger is arranged in the annular water tank, and heat of a primary loop or a secondary loop of the reactor is led into the water tank through a pipeline, so that the function of reactor core cooling or secondary side waste heat removal after an accident is realized.
Compared with the prior art, the invention has the beneficial effects that: 1. the containment vessel has multiple system functions, so that the volume of the containment vessel can be greatly reduced, and the economical efficiency of a nuclear power plant is improved; 2. the containment cooling is non-time-limited and passive, and the safety of a nuclear power plant is greatly improved; 3. rapidly suppressing the rise of pressure in the shell; 4. by means of the existing double-layer containment annular space, a small amount of water is added, so that the influence on the containment structure is small, and the reconstruction cost is low; 5. the water body in the annular space also serves as a shielding layer to play a role in shielding radioactivity. 6. The elevation of the annular water tank is low, the integral gravity center of the containment vessel is low, and the anti-seismic design of the containment vessel is facilitated.
Drawings
FIG. 1 is a schematic view of a suppressed double containment system of the present invention.
In the attached figure 1, 1 is a reactor core, 2 is an annular water tank, 3 is a pressure suppression pipeline, 4 is a water tank cooling heat exchanger, 5 is an inner containment, 6 is an outer containment, 7 is a reactor core safety injection pipeline, 8 is a reactor cavity water injection pipeline, 9 is a passive reactor core cooling system or secondary side passive waste heat removal system heat exchanger, 10 is a containment large space, 11 is an annular water tank air space, and 12 is a reactor cavity.
Detailed Description
The present invention will be described in further detail with reference to the accompanying drawings and specific embodiments.
As shown in figure 1, a large annular space is arranged in the middle of the double-layer containment, a section of annular space which is positioned at the lower part of the containment and is slightly higher than a reactor core is transformed into an annular water pool 2, and a large containment space 10 and the annular water pool 2 are connected through a pressure suppression pipeline 3. If a reactor breaks open, a large amount of high-temperature and high-pressure steam enters the large containment space 10, the pressure in the shell rises rapidly, the pressure difference between the large containment space 10 and the annular pool gas space 11 increases, under the action of the pressure difference, the mixed gas of the steam and the uncondensed gas in the large containment space enters the annular pool 2 through the pressure-restraining pipeline 3, the steam is absorbed by the supercooled water in the pool, the uncondensed gas is stored in the annular pool gas space, and the rise of the pressure in the containment vessel is restrained rapidly and effectively.
A pool cooling heat exchanger 4 is arranged in the annular pool 2, an inner pipeline of the heat exchanger is communicated with the atmosphere, air enters the heat exchanger from an inlet at the lower part, heat of the annular pool is absorbed in a heat transfer pipe of the heat exchanger and then is discharged from an outlet at the upper part, and the air continuously transfers the heat of the pool to the external environment under the driving of the density difference of the air inside and outside the heat exchanger, so that the pool is always kept in a supercooled state, the containment cooling is free of time limit and is passive, and the containment performance of a nuclear power plant is greatly improved.
A passive core cooling system or a secondary side passive waste heat removal system heat exchanger 9 is arranged in the annular water tank 2, and heat of a primary loop or a secondary loop of the reactor can be conducted into the water tank through a pipeline, so that the function of core cooling or secondary side waste heat removal after an accident is realized. Therefore, the annular pool has the functions of reactor core safety injection, reactor cavity water injection, reactor core cooling/secondary side waste heat discharge and the like besides the function of pressure inhibition, so that the design of a containment system can be greatly simplified, the volume of the containment can be further reduced, and the economical efficiency of a nuclear power plant is improved.
Aiming at the existing containment pressure control technology, the invention aims to solve the technical problem of providing a passive containment system design based on a pressurized water reactor double-layer concrete containment. The system is arranged by means of a nuclear power plant double containment annular space. The water body of the system simultaneously takes the functions of various water bodies inside and outside the containment vessel into consideration, such as a pressure-restraining pool (SP) water body, a reactor core refueling pool (IRWST) water body, a reactor cavity water injection system (CIS) water body, a safety injection system water tank water body, a containment vessel passive heat removal system (PCS) water body and a reactor core/secondary side passive heat removal system (PRS) water body. The system has the passive characteristic, does not need additional power (pumps and the like), and can realize various functions by depending on natural forces such as pressure difference, gravity, density difference and the like. For example, the pressure-restraining function of the water body is realized by means of the pressure difference between the containment gas space and the annular space; the water injection function of the reactor core and the reactor cavity is realized by means of the gravity of the water body; and the natural circulation cooling function of the reactor core/secondary side is realized by the driving force formed by the density difference.
The invention is applied to a new generation of pressurized water nuclear power plant, so that the containment system of the current nuclear power plant can be greatly simplified, the SP, the IRWST, the CIS, the safety injection water tank, the PCS water tank and the PRS water tank in the containment can be cancelled, and the volume of the containment system can be further reduced. And the water body of the system positioned in the annular space of the containment can also be used as a shielding layer, so that the possibility of leakage of radioactive substances in the reactor is reduced. Meanwhile, the invention can provide 'no-time-limit' passive cooling for the containment vessel, theoretically, the energy in the containment vessel is continuously taken away under the condition of no external intervention, and the temperature and the pressure of the containment vessel are always kept not to exceed the design limit values, so that people have sufficient time to deal with the nuclear power plant accidents, and the requirement that the nuclear power plant does not intervene for at least 72 hours after the accidents specified by the nuclear safety supervision department is greatly met. In addition, the heat in the containment vessel is continuously transferred to the external environment, a large amount of water bodies in the annular space of the containment vessel are not needed, the influence of the added water bodies on the containment vessel structure is small, and the original double-layer containment vessel is not needed to be greatly reformed. The invention improves the safety of the nuclear power plant, greatly reduces the cost of the containment vessel and improves the economy of the nuclear power plant.
In summary, the invention designs a pressurized water reactor multifunctional double-layer containment system, based on the existing double-layer concrete containment of the nuclear power plant, the annular space of the double-layer containment is reasonably utilized, an annular water pool is arranged, and the water in the water pool has the functions of various water bodies inside and outside the containment, such as a suppression water pool (SP) water body, a reactor core refueling water pool (IRWST) water body, a reactor cavity water injection system (CIS) water body, a safety injection system water tank water body and a containment passive heat export system (PCS) water body, so that the existing nuclear power plant containment system is greatly simplified, the IRWST, the CIS, the safety injection water tank and the PCS water tank outside the containment can be cancelled, the volume of the safety shell can be further reduced, the construction cost of the containment can be greatly reduced, and the economy of the nuclear power plant can be improved. The water body in the annular space of the containment can also be used as a shielding layer, so that the possibility of leakage of radioactive substances in the reactor is further reduced. Meanwhile, the invention can provide non-time-limit passive cooling for the containment vessel, continuously take away the energy in the containment vessel without external intervention, maintain the temperature and the pressure of the containment vessel not to exceed the design limit values, and greatly improve the safety of the nuclear power plant. In addition, the heat in the containment is continuously transferred to the external environment, and a large amount of water bodies in the annular space of the containment do not need to be arranged, so that the double-layer containment does not need to be greatly reformed, and the water bodies in the annular space have small influence on the containment structure.
Claims (9)
1. The utility model provides a multi-functional double-deck concrete containment system of pressurized water reactor, includes double-deck containment, sets up the reactor in double-deck containment, its characterized in that: an annular water pool is arranged in an annular space formed by the double-layer safety shell, the bottom of the annular water pool is higher than the upper end face of a reactor core of the reactor, at least one group of suppression pipelines are arranged in the annular water pool, the end parts of the suppression pipelines penetrate through the inner shell of the double-layer safety shell and extend into the large space of the safety shell, and when the number of the suppression pipelines is two or more, the suppression pipelines are symmetrically arranged in the annular space.
2. The pressurized water reactor multifunctional double-layered concrete containment system according to claim 1, characterized in that: when a reactor is subjected to a breach accident, high-temperature and high-pressure steam enters a large containment space, the pressure in the shell rises rapidly, the pressure difference between the large containment space and an annular pool gas space is increased, mixed gas of the steam and uncondensed gas in the large containment space enters the annular pool through a pressure-restraining pipeline under the action of the pressure difference, the steam is absorbed by supercooled water in the pool, the uncondensed gas is stored in the annular pool gas space, and the rise of the pressure in the containment is restrained.
3. The pressurized water reactor multifunctional double-layered concrete containment system according to claim 1 or 2, characterized in that: a pool cooling heat exchanger is arranged in the annular pool, an inlet and an outlet of the heat exchanger penetrate through the shell of the double-layer containment and are communicated with the atmosphere, air enters the heat exchanger from the lower inlet, heat of the annular pool is absorbed in a heat transfer pipe of the heat exchanger and then is discharged from the upper outlet, and the air continuously transfers the heat of the pool to the external environment under the driving of the density difference of the air inside and outside the heat exchanger, so that the pool is kept in a supercooled state all the time.
4. The pressurized water reactor multifunctional double-layered concrete containment system according to claim 1 or 2, characterized in that: the annular water pool is connected with the reactor through a reactor core safety injection pipeline and is connected with the reactor cavity through a reactor cavity water injection pipeline, and the function of a safety injection system or a reactor cavity water injection system is realized.
5. The pressurized water reactor multifunctional double-layered concrete containment system according to claim 3, characterized in that: the annular water pool is connected with the reactor through a reactor core safety injection pipeline and is connected with the reactor cavity through a reactor cavity water injection pipeline, and the function of a safety injection system or a reactor cavity water injection system is realized.
6. The pressurized water reactor multifunctional double-layered concrete containment system according to claim 1 or 2, characterized in that: a passive reactor core cooling system or a secondary side passive waste heat removal system heat exchanger is arranged in the annular water tank, and heat of a primary loop or a secondary loop of the reactor is led into the water tank through a pipeline, so that the function of reactor core cooling or secondary side waste heat removal after an accident is realized.
7. The pressurized water reactor multifunctional double-layered concrete containment system according to claim 3, characterized in that: a passive reactor core cooling system or a secondary side passive waste heat removal system heat exchanger is arranged in the annular water pool, and the heat of a primary loop or a secondary loop of the reactor is conducted into the water pool through a pipeline, so that the function of reactor core cooling or secondary side waste heat removal after an accident is realized.
8. The pressurized water reactor multifunctional double-layered concrete containment system according to claim 4, characterized in that: a passive reactor core cooling system or a secondary side passive waste heat removal system heat exchanger is arranged in the annular water pool, and the heat of a primary loop or a secondary loop of the reactor is conducted into the water pool through a pipeline, so that the function of reactor core cooling or secondary side waste heat removal after an accident is realized.
9. The pressurized water reactor multifunctional double-layered concrete containment system according to claim 5, characterized in that: a passive reactor core cooling system or a secondary side passive waste heat removal system heat exchanger is arranged in the annular water pool, and the heat of a primary loop or a secondary loop of the reactor is conducted into the water pool through a pipeline, so that the function of reactor core cooling or secondary side waste heat removal after an accident is realized.
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| CN113035393A (en) * | 2021-03-05 | 2021-06-25 | 哈尔滨工程大学 | Self-driven air extraction type passive containment heat removal system |
| CN113035397A (en) * | 2021-03-05 | 2021-06-25 | 哈尔滨工程大学 | Containment built-in efficient heat exchanger adopting tangential type air suction system |
| CN113148092A (en) * | 2020-12-17 | 2021-07-23 | 武汉第二船舶设计研究所(中国船舶重工集团公司第七一九研究所) | Overall arrangement structure of water surface nuclear power ship reactor cabin |
| CN113270213A (en) * | 2021-06-22 | 2021-08-17 | 中国舰船研究设计中心 | Self-sealing shielding system for pressure control of nuclear power vessel containment |
| CN113593731A (en) * | 2021-06-29 | 2021-11-02 | 中国核电工程有限公司 | Passive containment depressurization filtering system |
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| CN113148092A (en) * | 2020-12-17 | 2021-07-23 | 武汉第二船舶设计研究所(中国船舶重工集团公司第七一九研究所) | Overall arrangement structure of water surface nuclear power ship reactor cabin |
| CN113148092B (en) * | 2020-12-17 | 2023-06-30 | 武汉第二船舶设计研究所(中国船舶重工集团公司第七一九研究所) | Overall arrangement structure of reactor cabin of water surface nuclear power ship |
| CN113035393A (en) * | 2021-03-05 | 2021-06-25 | 哈尔滨工程大学 | Self-driven air extraction type passive containment heat removal system |
| CN113035397A (en) * | 2021-03-05 | 2021-06-25 | 哈尔滨工程大学 | Containment built-in efficient heat exchanger adopting tangential type air suction system |
| CN113035393B (en) * | 2021-03-05 | 2022-11-18 | 哈尔滨工程大学 | Self-driven air extraction type passive containment heat removal system |
| CN113035397B (en) * | 2021-03-05 | 2023-10-27 | 哈尔滨工程大学 | Safety shell built-in efficient heat exchanger adopting cutting and striking type air suction system |
| CN113270213A (en) * | 2021-06-22 | 2021-08-17 | 中国舰船研究设计中心 | Self-sealing shielding system for pressure control of nuclear power vessel containment |
| CN113593731A (en) * | 2021-06-29 | 2021-11-02 | 中国核电工程有限公司 | Passive containment depressurization filtering system |
| CN113593731B (en) * | 2021-06-29 | 2023-12-22 | 中国核电工程有限公司 | Passive containment depressurization filtration system |
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