GB2619465A - Design method and apparatus for containment integrity test of advanced pressurized water reactor nuclear power plant - Google Patents
Design method and apparatus for containment integrity test of advanced pressurized water reactor nuclear power plant Download PDFInfo
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- 238000000034 method Methods 0.000 title claims abstract description 109
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- 238000011016 integrity testing Methods 0.000 claims description 163
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- 238000012795 verification Methods 0.000 claims description 15
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- 238000002955 isolation Methods 0.000 claims description 13
- 230000037361 pathway Effects 0.000 claims description 9
- 239000000446 fuel Substances 0.000 claims description 8
- 230000000149 penetrating effect Effects 0.000 claims description 8
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/001—Computer implemented control
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/003—Remote inspection of vessels, e.g. pressure vessels
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01M—TESTING STATIC OR DYNAMIC BALANCE OF MACHINES OR STRUCTURES; TESTING OF STRUCTURES OR APPARATUS, NOT OTHERWISE PROVIDED FOR
- G01M3/00—Investigating fluid-tightness of structures
- G01M3/02—Investigating fluid-tightness of structures by using fluid or vacuum
- G01M3/26—Investigating fluid-tightness of structures by using fluid or vacuum by measuring rate of loss or gain of fluid, e.g. by pressure-responsive devices, by flow detectors
- G01M3/28—Investigating fluid-tightness of structures by using fluid or vacuum by measuring rate of loss or gain of fluid, e.g. by pressure-responsive devices, by flow detectors for pipes, cables or tubes; for pipe joints or seals; for valves ; for welds
- G01M3/2807—Investigating fluid-tightness of structures by using fluid or vacuum by measuring rate of loss or gain of fluid, e.g. by pressure-responsive devices, by flow detectors for pipes, cables or tubes; for pipe joints or seals; for valves ; for welds for pipes
- G01M3/2815—Investigating fluid-tightness of structures by using fluid or vacuum by measuring rate of loss or gain of fluid, e.g. by pressure-responsive devices, by flow detectors for pipes, cables or tubes; for pipe joints or seals; for valves ; for welds for pipes using pressure measurements
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/002—Detection of leaks
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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
A design method and design apparatus for a containment integrity test of an advanced pressurized water reactor nuclear power plant. The design method comprises: determining each test item during a containment integrity test; determining pressure steps and corresponding durations in each test item; determining an upper limit of a pressure increase/decrease rate of the containment integrity test; and obtaining a design result of a containment integrity test scheme according to the determined test items, the pressure steps and the corresponding durations in each test item, and the upper limit of the pressure increase/decrease rate of the containment integrity test. By means of an integrity test scheme obtained according to the design method, the safety and the feasibility of a test can be ensured to the greatest extent, and the economy of a nuclear power plant can also be improved.
Description
DESIGN METHOD AND APPARATUS OF CONTAINMENT INTEGRITY TEST OF ADVANCED PRESSURIZED WATER REACTOR NUCLEAR POWER PLANT
The present disclosure claims priority from the Chinese patent application No. 202110312538.6, filed on March 24, 2021, and entitled "A DESIGN METHOD OF CONTAINMENT INTEGRITY TEST OF ADVANCED PRESSURIZED WATER REACTOR NUCLEAR POWER PLANT", and the contents of which are incorporated herein by reference in their entirety.
Technical Field
The present disclosure relates to the field of nuclear power plant design, and in particular, to a design method and apparatus of containment integrity testing/test for advanced pressurized water reactor (PWR) nuclear power plant.
Background Art
As the last barrier for limiting the release of radioactive substances to the environment, the containment (also called "the containment vessel") of a PWR nuclear power plant has safety functions of containing radioactive substances, shielding radiation, and protecting the reactor from being influenced by external natural or man-made events under both normal operation or accident conditions. The design of the containment needs to ensure that any radioactivity released to the environment from a nuclear power plant is kept at a reasonable and feasible level as low as possible, i.e., not exceeding the regulatory emission limit of radioactivity release under an operating condition, and not exceeding the acceptable limit of radioactivity release under an accident condition. Further, based on operability requirements, the design of the containment should also provide passages for: mechanical and electrical connections inside and outside the containment; and access for personnel during normal operation. In order to verify the above safety and operability functions, related performance testing of the containment needs to be carried out during commissioning stage before initial fuel loading and the periodical test after operation.
As the containment integrity testing occupies the main-line testing period of commissioning stage before initial fuel loading and the periodical testing after operation, reasonability and feasibility of the design for containment testing are crucial to improving the availability for nuclear power plant.
At present, the containment integrity testing for in-service PWR nuclear power plant mainly adopt quality-point-based methods to measure the overall leakage rate of the containment, and verify structural integrity and related functions of the containment during the integrity testing. The existing testing is not obviously different in the testing principle/mechanism. However, due to the differences in the designs of structure and functions of the containment, the design of containment integrity testing varies greatly in the aspects of pressurizing and depressurizing rates, pressure steps and durations, testing projects or contents of the respective steps for different nuclear power plants, and problems including unreasonable pressure step design, overlong testing durations, imperfect pressurizing and depressurizing curve design, or the like are present.
How to define an execution policy for the containment integrity testing for advanced PWR nuclear power plant so as to standardize specific execution of the containment integrity testing and improve safety and economic efficiency of the nuclear power plant operation is a difficult problem to be solved urgently.
Summary
The technical problem to be solved by the present disclosure is, in view of the above deficiencies in the existing techniques, to provide a design method and apparatus for containment integrity testing for advanced PWR nuclear power plant, according to which a scheme for integrity testing that can ensure the testing safety and feasibility to the maximum while effectively improving operation efficiency of the nuclear power plant can be obtained.
The present disclosure provides a design method for containment integrity testing for advanced PWR nuclear power plant. The method includes: determining testing projects during the containment integrity testing; determining pressure steps in the respective testing projects and corresponding durations (step durations); determining upper limits for pressurizing and depressurizing rates in the containment integrity testing; and then obtaining a design result of a scheme for containment integrity testing according to the determined testing projects, pressure steps in the respective testing projects and the corresponding durations, and upper limits for pressurizing and depressurizing rates in the containment integrity testing.
Preferably, the determining testing projects during the containment integrity testing specifically includes: determining, according to containment safety and operability function requirements, testing projects during the containment integrity testing. The testing projects include: leakage rate testing; structural integrity testing; isolation valve trigger logic function testing; combustible gas mixing function testing; personnel gate function testing; effectiveness verification of a leakage rate measuring system, and effectiveness verification of a structural integrity measuring system.
Preferably, the determining the pressure steps and the corresponding durations of the testing projects specifically includes: determining, according to regulations, guidelines and standards for containment testing, mandatory pressure steps in the respective testing projects and corresponding durations, and determining, according to pressure requirements on the execution of pre-testing for the containment structural integrity testing and function testing, non-mandatory pressure steps in the respective testing projects and corresponding durations.
Preferably, before determine testing projects during the containment integrity testing, the design method for containment integrity testing for advanced PWR nuclear power plant further includes: carding (collating) boundary penetrations and process pipelines of the containment to obtain configurations and functions of the penetrations and the process pipelines of the containment; and acquiring, according to the configurations and functions of the penetrations and the process pipelines of the containment and testing feasibility and safety requirements, prerequisites of the containment integrity testing to ensure feasibility and safety of the scheme for containment integrity testing.
Preferably, the carding boundary penetrations and process pipelines of the containment to obtain configurations and functions of the penetrations and the process pipelines of the containment specifically includes: carding all penetrations and process pipelines penetrating through the containment, and analyzing the configurations and functions of the process pipelines and the penetrations in a list form, wherein the penetrations include: process penetrations, electrical penetrations, personnel and emergency gates, equipment hatches, fuel transfer pathways, and standby penetrations.
Preferably, the acquiring, according to the configurations and functions of the penetrations and the process pipelines of the containment and testing feasibility and safety requirements, prerequisites of the containment integrity testing specifically includes: designing, according to the configurations and functions of the penetrations and the process pipelines of the containment and the testing feasibility requirement, a boundary state to form boundary state related testing prerequisites; and designing, according to the configurations and functions of the penetrations and the process pipelines of the containment and testing safety requirements, related testing conditions of personnel, process systems and equipment protection during testing to form safety related testing prerequi sites.
Preferably, the boundary state related testing prerequisites include that: penetrations at a testing boundary are isolated, the penetrations are closed in a normal mode, and the penetrations are unable be operated manually or in other modes after being isolated; except for a system which needs to be operated during testing or a system for ensuring that a unit is in a safe state during testing, related process systems or pipelines are drained; meanwhile, in order to avoid leakage from steam generators to the secondary circuit during testing, the secondary circuit is synchronously pressurized; and a pressurizing/depressurizing device is installed in place, and the corresponding pipeline penetration meets corresponding requirement of leakage rate. The safety related testing prerequisites include that: during testing, all personnel in the containment are required to stop working, a corresponding safety zone is marked, where access of the containment is forbidden, and influence of noises on operating pressurizing/depressurizing personnel is considered; in order to prevent equipments in the containment from being damaged by pressurizing/depressurizing, it is considered that non-pressure-bearing equipments in the containment are in connection to containment atmosphere or is moved out of the containment; and meanwhile, in order to avoid false operations of engineered safety features during testing, drive signals for related systems are locked; and as the ignition point of combustible substances will reduce due to an increase of pressure in the containment, before testing, combustible materials in the containment need to be removed, and a corresponding emergency fire protection plan should be made.
Further, the present disclosure provides a design apparatus for containment integrity testing for advanced PWR nuclear power plant, including a first determining module, a second determining module, a third determining module and a combined module.
The first determining module is configured to determine testing projects during the containment integrity testing. The second determining module is configured to determine pressure steps in the respective testing projects and corresponding step durations. The third determining module is configured to determine upper limits for pressurizing and depressurizing rates in the containment integrity testing. The combined module is respectively connected to the first determining module, the second determining module and the third determining module, and is configured to obtain a design result of a scheme for containment integrity testing according to the determined testing projects, pressure steps in the respective testing projects and corresponding durations, and upper limits for pressurizing and depressurizing rates in the containment integrity testing.
Preferably, the design apparatus for containment integrity testing for advanced PWR nuclear power plant further includes a carding module and an acquisition module. The carding module is configured to card boundary penetrations and process pipelines of the containment to obtain configurations and functions of the penetrations and the process pipelines of the containment. The acquisition module is respectively connected to the carding module and the combined module, and is configured to acquire, according to the configurations and functions of the penetrations and the process pipelines of the containment and testing feasibility and safety requirements, prerequisites of the containment integrity testing and transmit the prerequisites of the containment integrity testing to the combined module so that the combined module obtains the design result of the scheme for containment integrity testing while meeting the prerequisites of the containment integrity testing, to ensure feasibility and safety of the scheme for containment integrity testing.
Compared with the existing techniques, the design method for containment integrity testing for advanced PWR nuclear power plant provided in the present disclosure has the following beneficial effects: (1) By carding all process pipelines and penetrations for advanced PWR nuclear power unit, and analyzing configurations and the functions of the process pipelines and the penetrations in detail, this step of the technical scheme covers all processes and penetrations of the containment to the maximum extent, ensures boundary integrity of the containment integrity testing, and lays a foundation for feasibility of later development of the containment integrity testing.
(2) By designing boundary state requirements during testing based on the carding result of the containment boundary penetrations and process pipelines, and carding prerequisites of the containment integrity testing in consideration of requirements on personnel, process system and equipment protection, the prerequisites of the containment integrity testing formed by these two aspects can guarantee the testing safety and feasibility to the maximum extent.
(3) By designing testing projects during the containment integrity testing based on nuclear safety regulations, guidelines and standards, and determining designs of safety function related and operability related testing projects during the containment integrity testing based on a carding result of the containment function requirements, while sufficiently considering designs of other testing projects related to design characteristics of the containment, this step of the technical scheme can ensure comprehensively verification of safety function and operability of the containment during testing, guarantee legality, comprehensiveness and effectiveness in design of the testing projects, and lay a foundation for design of the pressurizing and depressurizing curve of the containment integrity testing.
(4) After the testing project design is completed, by designing the pressure steps for the testing projects, and compressively considering selections of each step pressure and a duration thereof, this step of the technical scheme, based on mandatory pressure steps required in nuclear safety regulations, guidelines and standards, requires to clarify the requirements on step pressure and duration according to the regulations, guidelines and standards, and guarantees legality and effectiveness in design of the pressure step design with combined reference to the testing projects to be conducted under such pressure steps; and based on non-mandatory pressure steps, requires to set the step pressures and durations on the basis of sufficiently considering requirements on low-pressure pre-testing and operability related testing of safety function related testing while combining with engineering experience, and to effectively reduce an execution period of the containment integrity testing and improve testing execution efficiency on the basis of having feasibility.
(5) By designing the pressurizing and depressurizing rates during the containment integrity testing within upper limit ranges for pressurizing and depressurizing stipulated in relative nuclear safety regulations, guidelines and standards, on the basis of legality, influences of the pressurizing and depressurizing rates on the structural integrity of the containment and the testing data collection are fully considered, and the testing safety and feasibility are fully guaranteed, while the design effectiveness of the pressurizing and depressurizing rates is guaranteed, thereby reducing the execution duration of the containment integrity testing to the maximum extent, and improving the economic efficiency of the testing execution.
(6) By integrating technical schemes to form a pressurizing and depressurizing curve of containment integrity testing for advanced PWR nuclear power plant, and combining with boundary carding of the containment integrity testing and testing prerequisite design to form the final testing scheme of containment integrity testing for advanced PWR nuclear power plant, that is, a design result of the integrity testing scheme, reasonability and integrity of the testing design are ensured.
The containment integrity testing scheme designed based on the above steps of the technical scheme has great potential to be widely applied to design of the containment integrity testing for the advanced PWR nuclear power unit, and can provide reference for the design of containment integrity testing of other reactor type nuclear power units.
Brief Description of the Drawings
FIG. 1 is a schematic flowchart of a design method for containment integrity testing for advanced PWR nuclear power plant according to the present disclosure; and FIG. 2 shows a schematic diagram of a pressurizing and depressurizing curve in a containment integrity testing for a China's third-generation PWR nuclear power unit.
Detailed Description of the Embodiments
For further understanding of the present disclosure, implementations of the present disclosure are described below in conjunction with embodiments, but it needs to be understood that the description is merely for the purpose of further illustrating features and advantages of the present disclosure, not for limiting the present disclosure.
The China's third-generation PWR nuclear power plant adopts a dual-containment structure having an inner containment and an outer containment. The inner containment has a pre-stressed concrete structure with a steel lining. The inner containment uses the pre-stressed concrete and a reinforced concrete foundation to bear pressure, and uses the steel lining to ensure the sealing performance. The outer containment has a reinforced concrete structure. Since the design of containment integrity testing mainly aims at the inner containment and is not necessarily related to the outer containment structure, the inner containment is simply referred to as the containment herein after to avoid confusion.
An embodiment of the present disclosure provides a design method for containment integrity testing for advanced PWR nuclear power plant. The design method includes the following steps S1 to S5.
Step Sl: carding (collating) boundary penetrations and process pipelines of the containment.
Step S1 specifically includes: carding all penetrations and process pipelines penetrating through the containment, and analyzing the configurations and functions of the process pipelines and the penetrations in a list form, wherein the penetrations include: process penetrations, electrical penetrations, personnel and emergency gates, equipment hatches, fuel transfer pathways, and standby penetrations.
Step S2: designing prerequisites of the containment integrity testing.
Step S2 specifically includes: designing a boundary state according to a carding result of the penetrations and the process pipelines in combination with testing feasibility and accuracy requirements, to form boundary state related testing prerequisites (testing prerequisites related to boundary state); and designing, in combination with fire protection and personnel protection requirements during testing, related testing conditions of personnel, process systems and equipment protection during testing, to form safety related testing prerequisites (testing prerequisites related to safety).
In step S2, the boundary state related testing prerequisites include: isolation of penetrations, evacuation or drainage of process systems, and conditions to be satisfied by testing equipment.
The safety related testing prerequisites include personnel protection, protection of process systems and equipment, and conditions to be satisfied by fire protection measures.
The isolation of penetrations should satisfy the conditions that: penetrations at a testing boundary are isolated, the penetrations are closed in a normal mode, and the penetrations are unable be operated manually or in other modes after being isolated.
The evacuation or drainage of the process systems should satisfy the conditions that: except for a system which needs to be operated during testing or a system for ensuring that a unit is in a safe state during testing, it needs to be considered that related process systems or pipelines are evacuated or drained; and meanwhile, in order to avoid leakage from the steam generator to the secondary circuit during testing, it needs to be considered that the secondary circuit is synchronously pressurized.
The conditions to be satisfied by the testing equipment include that: a pressurizing/depressurizing device need to be installed in place, and a corresponding pipeline penetration meets corresponding requirement of leakage rate.
The personnel protection should satisfy the conditions that: during testing, all personnel in the containment are required to stop working, a corresponding safety zone is marked, where access of the containment is forbidden; and to influence of noises on operating pressurizing/depressurizing personnel should be considered.
The protection of process systems and equipment should satisfy the conditions that: in order to prevent equipment in the containment from being damaged by pressurizing/depressurizing, it is considered that non-pressure-bearing equipment in the containment is in connection to the containment atmosphere or is moved out of the containment; and meanwhile, in order to avoid false operations of dedicated safety facilities during testing, drive signals for related systems need to be locked.
The conditions to be satisfied by fire protection measures are: the combustible substances in the containment need to be removed before testing, and a corresponding emergency fire protection plan is made.
Step S3: designing testing projects based on function requirements of the containment, i.e., determining the respective testing projects during the containment integrity testing.
Step S3 specifically includes: designing leakage rate testing during the containment integrity testing based on safety function requirements; and determining containment function testing projects based on an operability function of the containment and in view of effectiveness pre-validation requirements for a measuring system, including: structural integrity testing; isolation valve trigger logic function testing; combustible gas mixing function testing; personnel gate function testing; effectiveness verification of a leakage rate measuring system and effectiveness verification of a structural integrity measuring system.
Step S4: designing pressure steps and pressurizing and depressurizing rates for the containment integrity.
In step S4, the designing of the pressure steps for the containment integrity specifically includes: designing, according to related regulations, guidelines and standards for containment testing and in consideration of pressure requirements of structural integrity testing, pre-testing of leakage amount and function testing, pressure steps for the respective testing projects, including selecting a step pressure and determining a duration of the corresponding step pressure.
In step S4, the designing of the pressurizing and depressurizing rates includes: determining, within the limit value and in consideration of influences of the pressurizing and depressurizing rates on the structural integrity of the containment and the data collection, an upper limit for a pressurizing rate and an upper limit for a depressurizing rate in the containment integrity testing.
Step S5 includes: completing design of the scheme for containment integrity testing for the advanced PWR nuclear power plant.
Step S5 specifically includes: completing, based on a design result of the pressure steps and the pressurizing and depressurizing rates in the containment integrity testing, the design of a pressurizing and depressurizing curve of the containment integrity testing for the advanced PWR nuclear power unit, and forming, in combination with the design of the testing prerequisites, the scheme for containment integrity testing for the advanced PWR nuclear power unit.
For further understanding of the present disclosure, detailed description of the design method for containment integrity testing for advanced PWR nuclear power plant according to the present disclosure is provided in combination with embodiments as follows. However, the protection scope of the present disclosure is not limited to the following embodiments.
Embodiment 1 The following description is made with specific reference to FIG. 1.
(1) Carding boundary penetrations and process pipelines of the containment Based on the requirements of China's laws and regulations, guidelines and standards for nuclear safety, and in combination with the containment structural design of the reactor, all process pipelines and penetrations penetrating through the containment are carded, and the configurations and functions of the process pipelines and the penetrations are analyzed in a list form. The formed list is as shown in table 1: Table 1 List of the containment penetrations of a China's third-generation advanced PWR Category Number Configuration and function Process 91 guaranteeing, through a containment isolation valve, an isolation function for an inside and an outside of the containment after an accident; providing a pathway for a process system pipeline penetrating through the containment penetrations Electrical 87 An internal pressurized integrated structure; providing a pathway for a cable penetrating through the containment penetrations Personnel and 2 A double-door structure with an interlocking mechanism between two doors; providing a pathway for personnel access during normal operation emergency gate Equipment hatch 1 A single-door structure connected to the steel lining of the containment through bolts; providing a pathway for transportation of large equipment Fuel transfer 1 A blind flange in the containment; configured for fuel transfer during a refueling operation pathway Standby 14 Connected to the steel lining of the containment through a blind flange or by welding; acting as standbys of the process penetrations penetrations (2) Designing prerequisites of the containment integrity testing The boundary state requirements are designed according to a carding result of the process pipelines and the penetrations penetrating the containment in combination with testing feasibility and accuracy requirements, to form boundary state related testing prerequisites as follows: Isolation of penetrations: penetrations at a testing boundary are isolated, the penetrations are closed in a normal mode, and the penetrations are unable be operated manually or in other modes after being isolated.
Evacuation or drainage of process systems: except for a system which needs to be operated during testing or a system for ensuring that a unit is in a safe state during testing, it needs to be considered that related process systems or pipelines are evacuated or drained; meanwhile, in order to avoid leakage from the steam generator to the secondary circuit during testing, it needs to be considered that the secondary circuit is synchronously pressurized.
Testing equipment: a pressurizing/depressurizing device need to be installed in place, and a corresponding pipeline penetration meets corresponding requirement of leakage rate.
In order to ensure the testing safety, related testing conditions of personnel, process systems and equipment protection during testing need to be designed. In combination with the fire protection requirements during testing, the following safety related testing prerequisites (personnel and requirements) are formed: Personnel protection: during testing, all personnel in the containment are required to stop working, a corresponding safety zone is marked, where access of the containment is forbidden, and influence of noises on operating pressurizing/depressurizing personnel needs to be considered.
Protection of process systems and equipment: in order to prevent equipment in the containment from being damaged by pressurizing/depressurizing, it is considered that non-pressure-bearing equipment in the containment is in connection to containment atmosphere or is moved out of the containment; and meanwhile, in order to avoid false operations of engineered safety features during testing, drive signals for related systems need to be locked.
Fire protection measures: as the ignition point of combustible substances will be reduced due to an increase of pressure in the containment, the combustible substances in the containment should be removed before testing, and a corresponding emergency fire protection plan should be made.
(3) Designing testing projects based on function requirements of the containment The designed safety function of the containment of for advanced PWR nuclear power unit is: under a loss of coolant accident or a main steam line break accident in the containment, the containment is used to prevent the radioactivity leakage to the environment. Based on such safety function requirement, particular attention needs to pay on the leakage rate testing design during the containment integrity testing, so as to ensure that the overall leakage rate of the containment does not exceed an initial assumption in the design-basis accident analysis.
Considering the operability function requirements of the containment, the containment function testing projects of the advanced PWR nuclear power unit should further include: Structural integrity testing: verifying pressure-bearing characteristics of the containment (including visual inspection inside and outside the containment); Isolation valve trigger logic function testing: verifying drive logic of engineered safety features related to a state of the containment atmosphere; combustible gas mixing function testing: verifying an atmosphere mixing function of the combustible gas after an accident; and personnel gate function testing: emergency evacuation of personnel in the containment through a personnel gate or an emergency gate after an accident.
In addition, effectiveness of a measuring system is considered, which means effectiveness of the measuring system should be verified before the testing or at a low-pressure step during the testing, and other testing projects include: effectiveness verification of a leakage rate measuring system; and effectiveness verification of a structural integrity measuring system.
Due to the related function testing of containment-related energy and radioactivity control functions, auxiliary systems and ventilation systems required in China's nuclear safety regulations, guidelines and standards do not require simulation of an atmospheric state in the containment after an accident, those tests may be not considered in the containment integrity testing design.
(4) Designing pressure steps of the containment integrity testing After the design of the testing projects during the containment integrity testing is completed, it is required to design the pressure steps for the testing projects, which mainly includes requirements on step pressure selections and corresponding durations. In China's related regulations, guidelines and standards for containment testing, requirements on design of the pressure steps in the containment integrity testing mainly include: setting a maximum pressure in the containment structural integrity testing before loading to 1.15 times of the design pressure (testing pressure); measurement of the overall leakage rate to verify effectiveness of the measuring system at atmosphere pressure condition (testing pressure); performing, when the pressure rises to half of the design pressure, a first measurement of the leakage rate to learn a general leakage level (testing pressure); reading instrument data in at least 20 similar time intervals for an overall leakage rate lasting for 24 hours under the design pressure (testing pressure and duration); performing, if necessary, verification testing under the design pressure to verify representativeness of a measuring instrument (testing pressure); and starting, when the overall leakage rate testing and the structural integrity testing are to be carried out simultaneously before loading, measurement of the overall leakage rate only when the design pressure has been stabilized for 24 hours after the pressure is reduced to 0.85 times of the design pressure when the structural integrity testing reaches its testing pressure (testing pressure and duration).
It can be seen from the above that in the related regulations, guidelines and standards for containment testing, the mandatory requirements on step pressure selections include: 0, 0.5P, P, 1.15P, 0.85P, P and 0. For durations of the steps, except for the durations of the pressure steps 0.85P and P, there is no mandatory requirement for other pressure steps. In addition to the above, considering pressure requirements on the execution of pre-testing for the containment structural integrity testing and function testing, in the pressurizing stage, pressure step requirements for 0.01P and 0.25P are further added (for example, a isolation valve needs to be triggered to perform function verification in the isolation valve trigger logic testing at pressures 0.01P and 0.25P);and in the depressurizing stage, considering differences between the structural integrity testing data in this stage and that in the pressurizing stage, pressure steps 0.5P and 0.25P are further added, and meanwhile, in combination with design of the testing projects, the duration of each pressure step in each testing project requirement is clarified. In this embodiment, the determined (or designed) pressure steps and corresponding durations in the testing projects not only include mandatory pressure steps and corresponding durations so that the containment integrity testing is legal and effective, but also include non-mandatory pressure steps and corresponding durations so that the execution period of the containment integrity testing can be effectively shortened and the economic efficiency of the testing execution can be improved on the basis of having testing feasibility, because the non-mandatory pressure steps and corresponding durations are determined according to engineering experience, and pre-testing of the structural integrity testing, and function testing requirements.
(5) Designing pressurizing and depressurizing rates in the containment integrity testing In China's related standards for nuclear safety, the stipulation about the pressurizing/depressurizing rate in the containment integrity testing is that "the pressurizing/depressurizing rate per hour shall not exceed 20% of the highest testing pressure; and after each pressure level is reached, the constant pressure time shall be not less than 111". Within such limits, settings of the pressurizing and depressurizing rates need to further consider influences of the testing on the containment structure and data collection. A too fast pressurizing rate may cause air suction on internal components of the containment, and affect accuracy of the testing data measurement, while a too fast depressurizing rate may cause damages to the containment (the coating or paint) structure. Therefore, within the limit values of the pressurizing and depressurizing rates in the containment integrity testing, and comprehensively considering influences of the testing on the containment structure and data collection while referring to engineering experience of domestic PWR nuclear power units in-service or under construction, an upper limit for the pressurizing rate in containment integrity testing for advanced PWR nuclear power unit is set to 15kPa/h, and an upper limit for the depressurizing rate is set to 14kPa/h.
(6) Designing containment integrity testing for advanced PWR nuclear power unit Based on the whole design process as described above, a containment integrity testing scheme for the advanced PWR nuclear power unit is formed, and which scheme includes testing boundary design, testing prerequisite design, testing project design, and pressurizing and depressurizing curve design of the containment integrity testing combined with pressure steps and pressurizing and depressurizing rates. The depressurizing curve design of the containment integrity testing includes pressure steps corresponding to the testing projects, durations corresponding to the pressure steps and the pressurizing and depressurizing rates.
According to the above design process, the formed pressurizing and depressurizing curve of the containment integrity testing is as shown in FIG. 2. Before the containment integrity testing, an isolation boundary of the containment integrity testing is established according to the contents of (1) and (2) in the above technical scheme, and risk identification and corresponding preventive measures are completed according to the requirements of testing prerequisites before starting the containment integrity testing.
The containment integrity testing is carried out according to the pressurizing and depressurizing curve. As shown in FIG. 2, at a pressure step 0, effectiveness verifications of a leakage rate measuring system and a structural integrity measuring system are performed, and after initially checking of the structural integrity, the pressure is increased at a rate of 15kPa/h. In the pressurizing stage, when the pressure steps are reached, the pressure can be continued to be increased after a corresponding testing project is completed according to the pressurizing and depressurizing curve, until 1.15 times of the design pressure (i.e., 1.15P) is reached. After the structural integrity testing of 1.15 times of the design pressure is completed, a first depressurizing operation is performed at a depressurizing rate of 14kPa/h, until 0.85 times of the design pressure step is reached, and a second pressurizing operation is performed after mandatory stabilization at the pressure for 24 hours according to the requirements of regulations and standards and the leakage rate is measured, until the design pressure step is reached. After 24-hour containment leakage rate measurement and structural integrity verification are performed at the design pressure steps, the final depressurizing operation can be performed, and after related testing of the pressure steps in the depressurizing stage is completed, the whole containment integrity testing is ended.
Embodiment 2 This embodiment provides a design method for containment integrity testing for advanced PWR nuclear power plant, including the following steps 201 to 204.
Step 201 includes determining testing projects during the containment integrity testing.
Optionally, step 201 includes: determining testing projects during the containment integrity testing, which specifically includes: determining, according to containment safety and operability function requirements, testing projects during the containment integrity testing. As shown in FIG. 2, the determined testing projects include: leakage rate testing; structural integrity testing; isolation valve trigger logic function testing; combustible gas mixing function testing; personnel gate function testing; effectiveness verification of a leakage rate measuring system, and effectiveness verification of a structural integrity measuring system.
Step 202 includes determining pressure steps in the respective testing projects and corresponding durations.
Optionally, step 202 includes: determining pressure steps in the respective testing projects and corresponding durations, which specifically includes: determining, according to regulations, guidelines and standards for containment testing, mandatory pressure steps in the respective testing projects and corresponding durations, and determining, according to pressure requirements on the execution of pre-testing for the containment structural integrity testing and function testing, non-mandatory pressure steps in the respective testing projects and corresponding durations.
In this embodiment, the determined mandatory pressure gradients and the corresponding durations include: 0, 0.5P, P, 1.15P, 0.85P, P and 0, where the durations of the pressure steps 0.85P and P are mandatorily required to be at least 24 hours. The determined non-mandatory pressure steps and corresponding durations include: pressure steps 0.01P and 0.25P added in the pressurizing stage, and pressure steps of 0.5P and 0.25P added in the depressurizing stage. Since only the durations of the pressure steps 0.85P and P are mandatorily required, durations corresponding to other pressure steps are flexibly set according to the requirements of the testing projects. Therefore, the integrity testing scheme determined in this embodiment can effectively reduce an execution period of the containment integrity testing and improve testing execution efficiency on the basis of feasibility of the containment integrity testing. For example, compared with the existing techniques where the containment integrity testing with an execution period of 11 days in the commissioning stage before loading of a certain nuclear power unit, the testing according to the present embodiment requires an execution period of 9 days.
Step 203 includes determining upper limits for pressurizing and depressurizing rates in the containment integrity testing.
In this embodiment, within the limit values of the pressurizing and depressurizing rates in the containment integrity testing, and comprehensively considering influences of the testing on the containment structure and data collection while referring to engineering experience of domestic PWR nuclear power units in-service or under construction, an upper limit for the pressurizing rate in containment integrity testing for advanced PWR nuclear power unit is set to 151(13a/h, and an upper limit for the depressurizing rate is set to 141cPa/h. Since the determined upper limits for pressurizing and depressurizing rates are lower than the limits in the existing techniques, the execution duration of the containment integrity testing is shortened on the basis of ensuring effectiveness of the pressurizing and depressurizing rates, and thus, the economic efficiency of the testing execution is improved. In addition, the determined upper limits for the pressurizing and depressurizing rates can avoid adverse influences of an over high pressurizing/depressurizing rate on the containment structural integrity or testing data collection, thereby improving the testing safety and feasibility.
Step 204 includes obtaining a design result of a scheme for containment integrity testing according to the determined testing projects, pressure steps in the respective testing projects and corresponding durations, and upper limits for pressurizing and depressurizing rates in the containment integrity testing.
In this embodiment, as shown in FIG. 2, the obtained design result of the scheme for containment integrity testing includes testing projects, pressure steps corresponding to the testing projects, durations corresponding to the pressure steps and the pressurizing and depressurizing rates.
Optionally, in step 201: before determine testing projects during the containment integrity testing, the design method for containment integrity testing for advanced PWR nuclear power plant further includes: carding boundary penetrations and process pipelines of the containment to obtain configurations and functions of the penetrations and the process pipelines of the containment; and acquiring, according to the configurations and functions of the penetrations and the process pipelines of the containment and testing feasibility and safety requirements, prerequisites of the containment integrity testing to ensure feasibility and safety of the scheme for containment integrity testing.
Optionally, the carding boundary penetrations and process pipelines of the containment to obtain configurations and functions of the penetrations and the process pipelines of the containment specifically includes: carding all penetrations and process pipelines penetrating through the containment, and analyzing the configurations and functions of the process pipelines and the penetrations in a list form. The penetrations include: process penetrations, electrical penetrations, personnel and emergency gates, equipment hatches, fuel transfer pathways, and standby penetrations.
Optionally, the acquiring, according to the configurations and functions of the penetrations and the process pipelines of the containment and testing feasibility and safety requirements, prerequisites of the containment integrity testing specifically includes: designing, according to the configurations and functions of the penetrations and the process pipelines of the containment and the testing feasibility requirement, a boundary state to form boundary state related testing prerequisites; and designing, according to the configurations and functions of the penetrations and the process pipelines of the containment and testing safety requirement, related testing conditions of personnel, process systems and equipment protection during testing to form safety related testing prerequisites.
Optionally, the boundary state related testing prerequisites include that: penetrations at a testing boundary are isolated, the penetrations are closed in a normal mode, and the penetrations are unable be operated manually or in other modes after being isolated; except for a system which needs to be operated during testing or a system for ensuring that a unit is in a safe state during testing, it needs to be considered that related process systems or pipelines are evacuated or drained; meanwhile, in order to avoid leakage from the steam generator to secondary circuit during testing, it needs to be considered that the secondary circuit is synchronously pressurized; and a pressurizing/depressurizing device need to be installed in place, and a corresponding pipeline penetration meets corresponding requirement of leakage rate. The safety related testing prerequisites include that: during testing, all personnel in the containment are required to stop working, a corresponding safety zone is marked, where access of the containment is forbidden, and influence of noises on hearing of personnel operating pressurizing/depressurizing is considered; in order to prevent equipment in the containment frombeing damaged by pressurizing/depressurizing, it is considered that non-pressure-bearing equipment in the containment is in connection to containment atmosphere or is moved out of the containment; and meanwhile, in order to avoid false operations of engineered safety features during testing, drive signals for related systems need to be locked; and as the ignition point of combustible substances will reduce due to an increase of pressure in the containment, before testing, combustible materials in the containment need to be removed, and a corresponding emergency fire protection plan should be made.
In this embodiment, by carding boundary penetrations and process pipelines of the containment before step 201,alI processes and penetrations of the containment are covered to the maximum extent, boundary integrity of the containment integrity testing is ensured, and a foundation is laid for feasibility of later development of the containment integrity testing. Further, by acquiring the integrity testing prerequisites based on the carding result, the acquired testing prerequisites are met before the containment integrity testing is carried out, and thus, the testing safety and feasibility are fully guaranteed.
Embodiment 3 This embodiment provides a design apparatus for containment integrity testing for advanced PWR nuclear power plant, including a first determining module, a second determining module, a third determining module and a combined module.
The first determining module is configured to determine testing projects during the containment integrity testing.
The second determining module is configured to determine pressure steps in the respective testing projects and corresponding durations.
The third determining module is configured to determine upper limits for pressurizing and depressurizing rates in the containment integrity testing.
The combined module is respectively connected to the first determining module, the second determining module and the third determining module, and is configured to obtain a design result of a scheme for containment integrity testing according to the determined testing projects, pressure steps in the respective testing projects and corresponding durations, and upper limits for pressurizing and depressurizing rates in the containment integrity testing.
Optionally, the design apparatus for containment integrity testing for advanced PWR nuclear power plant further includes a carding module and an acquisition module.
The carding module is configured to card boundary penetrations and process pipelines of the containment to obtain configurations and functions of the penetrations and the process pipelines of the containment.
The acquisition module is respectively connected to the carding module and the combined module, and is configured to acquire, according to the configurations and functions of the penetrations and the process pipelines of the containment and testing feasibility and safety requirements, prerequisites of the containment integrity testing and transmit the prerequisites of the containment integrity testing to the combined module so that the combined module obtains the design result of the scheme for containment integrity testing while meeting the prerequisites of the containment integrity testing, to ensure feasibility and safety of the scheme for containment integrity testing.
The description of the above embodiments is only used to help understand the methods and the core idea of the present disclosure. It should be noted that, for those skilled in the art, it is possible to make various improvements and modifications to the present disclosure without departing from the principle of the present disclosure, and those improvements and modifications also fall within the scope of the claims of the present disclosure.
The previous description of the disclosed embodiments is provided to enable those skilled in the art to implement or use the present disclosure. Various modifications to these embodiments will be readily apparent to those skilled in the art, and the generic principles defined herein may be applied to other embodiments without departing from the spirit or scope of the present disclosure. Thus, the present disclosure is not intended to be limited to the embodiments shown herein, but is to be accorded the widest scope consistent with the principles and novel features disclosed herein.
It will be appreciated that the above implementations are merely exemplary implementations for the purpose of illustrating the principle of the invention, and the invention is not limited thereto. It will be apparent to one of ordinary skill in the art that various modifications and variations can be made to the invention without departing from the spirit or essence of the invention. Such modifications and variations should also be considered as falling into the protection scope of the invention.
Claims (9)
- What is claimed is: 1. A design method for containment integrity testing for advanced PWR nuclear power plant, characterized in comprising: determining testing projects during the containment integrity testing; determining pressure steps in the respective testing projects and corresponding durations; determining upper limits for pressuriz ng and depressurizing rates in the containment integrity testing; and obtaining a design result of a scheme for containment ntegrity testing according to the determined testing projects, the pressure steps in the respective testing projects and corresponding durations, and the upper limits for the pressurizing and depressurizing rates in the containment integrity testing.
- 2. The design method for containment integrity testing for advanced PWR nuclear power plant according to claim 1, characterized in that, the determining testing projects during the containment integrity testing specifically comprises: determining, according to containment safety and operability function requirements, the testing projects during the containment integrity testing, wherein the testing projects comprise: leakage rate testing; structural integrity testing; isolation valve trigger logic function testing; combustible gas mixing function testing; personnel gate function testing; effectiveness verification of a leakage rate measuring system, and effectiveness verification of a structural integrity measuring system.
- 3. The design method for containment integrity testing for advanced PWR nuclear power plant according to claim 1, characterized in that, the determining the pressure steps and the corresponding durations of the testing projects specifically comprises: determining, according to regulations, guidelines and standards for containment testing, mandatory pressure steps in the respective testing projects and corresponding durations, and determining, according to pressure requirements on the execution of pre-testing for the containment structural integrity testing and function testing, non-mandatory pressure steps in the respective testing projects and corresponding durations.
- 4. The design method for containment integrity testing for advanced PWR nuclear power plant according to claim 1, characterized in that, prior to the determining testing projects during the containment integrity testing, the method further comprises: carding boundary penetrations and process pipelines of the containment to obtain configurations and functions of the penetrations and the process pipelines of the containment; and acquiring, according to the configurations and functions of the penetrations and the process pipelines of the containment and testing feasibility and safety requirements, prerequisites of the containment integrity testing to ensure feasibility and safety of the scheme for containment integrity testing.
- 5. The design method for containment integrity testing for advanced PWR nuclear power plant according to claim 4, characterized in that, the carding boundary penetrations and process pipelines of the containment to obtain configurations and functions of the penetrations and the process pipelines of the containment specifically comprises: carding all penetrations and process pipelines penetrating through the containment, and analyzing the configurations and functions of the process pipelines and the penetrations in a list form, wherein the penetrations comprise: process penetrations, electrical penetrations, personnel and emergency gates, equipment hatches, fuel transfer pathways, and standby penetrations.
- 6. The design method for containment integrity testing for advanced PWR nuclear power plant according to claim 4, characterized in that, the acquiring, according to the configurations and functions of the penetrations and the process pipelines of the containment and testing feasibility and safety requirements, prerequisites of the containment integrity testing specifically comprises: designing, according to the configurations and functions of the penetrations and the process pipelines of the containment and the testing feasibility requirement, a boundary state to form boundary state related testing prerequisites; and designing, according to the configurations and functions of the penetrations and the process pipelines of the containment and the testing safety requirement, related testing conditions of personnel, process systems and equipment protection during testing to form safety related testing prerequisites.
- 7. The design method for containment integrity testing for advanced PWR nuclear power plant according to claim 6, characterized in that, the boundary state related testing prerequisites comprise that: penetrations at a testing boundary are isolated, the penetrations are closed in a normal mode, and the penetrations are unable be operated manually or in other modes after being isolated; except for a system which needs to be operated during testing or a system for ensuring that a unit is in a safe state during testing, it needs to be considered that related process systems or pipelines are evacuated or drained; meanwhile, in order to avoid leakage from a steam generator to secondary circuit during testing, it needs to be considered that the secondary circuit is synchronously pressurized; and a pressurizing/depressurizing device need to be installed in place, and a corresponding pipeline penetration meets corresponding requirement of leakage rate, and the safety related testing prerequisites comprise that: during testing, all personnel in the containment are required to stop working, a corresponding safety zone is marked, where access of the containment is forbidden, and influence of noises on operating pressurizing/depressurizing personnel is considered; in order to prevent equipment in the containment from being damaged by pressurizing/depressurizing, it is considered that non-pressure-bearing equipment in the containment is in communication with a containment atmosphere or is moved out of the containment; and meanwhile, in order to avoid false operations of engineered safety features during testing, drive signals for related systems need to be locked; and since the ignition point of combustible substances will reduce due to an increase of pressure in the containment, the combustible substances in the containment need to be removed before testing, and a corresponding emergency fire protection plan is made.
- 8. A design apparatus for containment integrity testing for advanced PWR nuclear power plant, characterized in comprising a first determining module, a second determining module, a third determining module and a combined module, wherein the first determining module is configured to determine testing projects during the containment integrity testing, the second determining module is configured to determine pressure steps in the respective testing projects and corresponding durations, the third determining module is configured to determine upper limits for pressurizing and depressurizing rates in the containment integrity testing; and the combined module is respectively connected to the first determining module, the second determining module and the third determining module, and is configured to obtain a design result of a scheme for containment integrity testing according to the determined testing projects, pressure steps in the respective testing projects and corresponding durations, and upper limits for pressurizing and depressurizing rates in the containment integrity testing.
- 9. The design apparatus for containment integrity testing for advanced PWR nuclear power plant according to claim 8, characterized in further comprising a carding module and an acquisition module, the carding module is configured to card boundary penetrations and process pipelines of the containment to obtain configurations and functions of the penetrations and the process pipelines of the containment, and the acquisition module is respectively connected to the carding module and the combined module, and is configured to acquire, according to the configurations and functions of the penetrations and the process pipelines of the containment and testing feasibility and safety requirements, prerequisites of the containment integrity testing, and transmit the prerequisites of the containment integrity testing to the combined module so that the combined module obtains the design result of the scheme for containment integrity testing while meeting the prerequisites of the containment integrity testing, to ensure feasibility and safety of the scheme for containment integrity testing.
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| PCT/CN2021/141566 WO2022199178A1 (en) | 2021-03-24 | 2021-12-27 | Design method and apparatus for containment integrity test of advanced pressurized water reactor nuclear power plant |
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