CN207991832U - The passive core cooling system bulk testing rack of pressurized-water reactor nuclear power plant - Google Patents

Abstract

The utility model is related to the passive core cooling system bulk testing racks of pressurized-water reactor nuclear power plant.A kind of ACME test-beds include：The loop of the circuit system and equipment of full simulation prototype nuclear power plant, wherein the four of full simulation prototype nuclear power plant into scene 2 is arranged；The arrangement and pipeline rout of the system and equipment of the passive core cooling system of full simulation prototype nuclear power plant, wherein scale modeling system and equipment；Partial simulation reactor secondary circuit system and equipment；The system and equipment that partial simulation is connected with reactor circuit.

Description

The passive core cooling system bulk testing rack of pressurized-water reactor nuclear power plant

Technical field

The utility model is related to nuclear powers to test field, in particular to the passive Core cooling system of pressurized-water reactor nuclear power plant System bulk testing rack（Abbreviation ACME racks）.

Background technology

CAP1400 nuclear power stations are the third generation large size advanced pressurized water reactor nuclear power plants of China's independent research, using passive peace Total system copes with nuclear power plant accident, ensures the safety of reactor.The design concept of " passive " is pressurized-water reactor nuclear power plant safety A significant innovation in system design, makes full use of the natural characteristic of substance, as gravity, Natural Circulation, compressed gas are swollen Swollen equal natural forces, need not pump, AC power, 1E grade Emergency diesel, and corresponding ventilation, cooling water etc. support system, Enormously simplify security system（They are only just acted in the event of an accident）, reduce human-equation error and cause the general of power station accident Rate；Nuclear Safety is greatly improved and has taken into account economy.Passive core cooling system can effectively prevent reactor core serious The generation of accident meets requirement of the public to npp safety and economy.But that there are driving forces is small, easy for passive system Interaction such as is influenced at the characteristics between by system, therefore how fully to be grasped and played passive technology to improve the safety of nuclear power station It is a most important problem, and it is a kind of important and irreplaceable means to test.

According to the requirement of security legislation, before actually approval nuclear power station can be built, it is necessary to be set to its security system Meter and performance adequately verify and assess, wherein it is the most reliably, most to take the verification mode of actual accidents simulation test It is easy received technological means.But the artificial manufacturing contingences on true nuclear power station is clearly impossible to be verified, Therefore generally use is that design and construction carry out examination with a certain proportion of, simulation prototype nuclear power plant bulk testing rack Verification assesses safety system performance by test result, and examines computer security to analyze program using test data.Cause This designs in the exploitation verification process of CAP1400 and to build a thermal-hydraulic system for passive Core cooling whole Body test-bed is important and required condition.In all types of test-bed of nuclear power, scale is the hugest, system the most Complicated, surely belong to integrality test rack.For the passive core cooling system performances of comprehensive verification CAP1400, designs and build up The large-scale synthesis Thermal hydrodynamic test rig of globality（ACME）.It is tested by ACME, can not only carry out passive reactor core The experiment of system analyzes program using test data verification associated safety, supports the review of CAP1400, additionally it is possible to pass through Experimental study key thermal-hydraulic phenomenon discloses the coupling mechanism between passive system and inherent crucial rule, is Nuclear Power Development It stands non-passive safety technology, advanced optimizes passive Power Plant Design and experimental study basis is provided and as a result, is also correlation computations Machine program development and improvement provide test data, and long term service is in the development of nuclear power technology.

But the domestic mostly nuclear power Thermal hydrodynamic test rig of individual event and minisystem, it there is no for commercial large-scale The globality Thermal hydrodynamic test rig of pressurized-water reactor nuclear power plant.In the prior art, there are still some defects.Currently available technology In usually require the review that the cooperation of three racks could be completed and work.Previous test-bed can substantially be divided into total head and Low pressure two major classes.The system design temperature that full-scale test rack is chosen is identical as prototype nuclear power plant, is 15.5MPa or so, such as ROSA、SPES.Overall height total head rack is due to design pressure height, and container wall thickness and pipeline wall thickness are larger in system design, meeting More serious surface radiating and structure heat accumulation is brought to be distorted.It is another kind of then according to different Proportionality design methods, choose relatively low Design parameter of the design pressure as test-bed, such as APEX and PUMA, pressure is respectively 2.7MPa and 1MPa.Low pressure rack The isobaric step simulations for developing the later stage in accident are preferable, but in the high pressure phase of accident early period, due to using low-voltage simulation high pressure Method, there are the larger distortion factors in terms of the physical property of test fluid, therefore the test data of early period is difficult to analyzing processing.

For example, in SPES racks and ROSA/LSTF gantry designs, power-volumetric method is used, this method is straight It connects and simple, is the common method in early test gantry designs.Power-volumetric method ratio generally by the way of overall height, total head Example simulation prototype system, therefore built rack is mostly tall and thin type.Total head, the friction loss in tall and thin rack, system heat loss, All there is larger distortion in metal heat accumulation etc., lack theory analysis guidance for the thermohydraulics phenomena simulation of part.One Chief reason is exactly for passive system, some local thermal-hydraulic phenomenons show even more important, also increasingly complex, Power volume originally is a kind of overall, macroscopical design method, and careful local phenomenon cannot be handled well.This Requirement still some gaps of kind method for the comprehensive proportion grading of complexity of the passive pilot system of large-scale globality.

Utility model content

For the defects in the prior art, it is proposed that the utility model, and independent research and build up the first non-energy in China Kinetonucleus power station large size thermal-hydraulic bulk testing rack ACME, support CAP1400 nuclear power station demonstration projects pass through review.

The utility model proposes the rack global design schemes of innovation, realize on same rack to passive system The Whole Process Simulation of significant process phenomenon.The utility model completes completely new isobaric simulation, 1/3 height is designed than overall plan, Realized on same rack for the first time etc. physical property simulation cut spurts, Natural Circulation, ADS pressure releases are spurted, IRWST injections, melt pit The significant process and accident transient state of whole passive safety system equipment investments such as long-term cooling recycling, are realized to passive core Accurate simulation and the research of power station minor break accident important development process and physical phenomenon.

Typical minor break accident process of the ACME test-beds of the utility model according to passive PWR nuclear power station, is borrowed Mirror analysis has pilot system technical experience, has selected the design pressure scheme of 10MPa, the isobaric simulation of energy passive initiatively Natural Circulation that power station minor break accident is paid close attention to after occurring, ADS spurt pressure release, IRWST peaces note and melt pit, and cooling follows for a long time Loop order section.This pressure design scheme effectively reduces heat accumulation caused by Vessel Design under high pressure and is distorted, and can isobaric simulation Natural Circulation after passive system accident and automatic pressure reduction, realize accident simulation context most on the same rack Bigization.Process is spurted for minor break accident early period, there is physical process identical with two generations active power station in passive power station, Have many researchs in previous experiment, can make full use of and use for reference.

The selection of the 1/3 height ratio of the utility model makes rack to select rational circulation diameter ratio to provide possibility Scale and construction, operation budget are preferably controlled, under the conditions of avoiding identical bench scale, possessed by tall and thin rack Larger surface area/volume ratio distortion, and rack is made to be more conducive to ensure the simulation of three-dimensional phenomenon, this point is for passive system For it is particularly important.And in the world existing 1/2,1/4 contracting is than the presurized water reactor test-bed of height, increase state The diversity of border upper stage ratio scale.

The utility model improves passive experiment proportion grading method, is applied to bulk testing gantry designs and part knot Structure optimizes, and improves the accuracy of important thermal-hydraulic phenomena simulation.The utility model obtains and has analysed in depth minor break examination Test data, it was found that new experimental phenomena discloses accident transient state inherent law and important thermal-hydraulic phenomenon mechanism.

The utility model achieves large-scale rack engineering design new method, new process, the complicated, work for ACME pilot systems The features such as condition is numerous, transient changing is violent consider test simulation performance requirement and engineering design requirements and realizability, adopt The technique and structure design for taking a series of new solve reactor core simulation electrically heated rod positioning support and flow of installation, heap Under support positioning, thermal walking compensation, region or the big temperature difference condition of transient process under inner member high intensity transient state load impacting Instrument runs through a series of experimental technique problems such as the big temperature difference transition sealing of structure design, high-pressure large-caliber rustless steel container, While ensureing to obtain sufficient test data, rack has been effectively ensured being capable of safe and reliable operation.The ACME of the utility model Test-bed instrument control electric system is for acute variation transient process, wide parameter area, multi-parameter type, multi-measuring point, high-precision, height A series of technological difficulties such as safety form advanced test data measuring technique and control technology.

It will be apparent from seeing the more suitable application areas of the utility model by the description provided.It should be appreciated that this part Description and specific examples be merely to illustrate, be not intended to limit the scope of the utility model.

The term table of comparisons：

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Description of the drawings

The embodiments of the present invention and other aspects are discussed in detail below in conjunction with attached drawing, in attached drawing：

Fig. 1 shows passive core cooling system principle schematic.

Fig. 2 shows the ACME three dimensional design figures according to another embodiment of the utility model.

Fig. 3 shows ACME rack Major Systems layout drawings.

Fig. 4 shows ACME rack cut accident schematic diagrames.

Fig. 5 shows the comparison in different tests bench simulation stage.

Fig. 6 shows the basic composition of H2TS proportion gradings.

Fig. 7 shows the dimensionless phase space overlapping curve between prototype system and model system.

Specific implementation mode

Attached drawing and following description describe the optional embodiments of the utility model to instruct those of ordinary skill in the art How to implement and reproduce the utility model.In order to instruct technical solutions of the utility model, some routine sides are simplified or have been omitted Face.It should be understood by one skilled in the art that modification from these embodiments or replacing and will fall guarantor in the utility model It protects in range.It should be understood by one skilled in the art that following characteristics can be combined in various ways to form the utility model Multiple modifications.The utility model is not limited to following optional embodiments as a result, and only by claim and they etc. Jljl limits.

Referring now to fig. 1, ACME test-beds are using CAP1400 nuclear power stations as prototype, using advanced proportion grading side Method, the passive core cooling system overall performance test-bed according to 1/3 height than, 10MPa pressure designs.ACME rack masters The transient process and important thermal-hydraulic phenomenon for being used to simulate based on the minor break accident of CAP1400 prototypes power station, evaluation are different The runnability and system performance of passive core cooling system, understanding are high under cut condition and different safety equipment failure conditions The interaction mechanism of a variety of non-passive safety equipment under power condition explores the complicated physical machine of thermal-hydraulic phenomenon and process Reason is the reliable test data of verification accumulation of Safety analysis code, and to support CAP1400 design of nuclear power plant by commenting safely It examines and verification experimental verification is provided.ACME racks take up an area about 4000 cubic metres, including about 16 process systems and more than 20 platform pressure resistant vessels；Platform Frame design pressure 10MPa, 310 DEG C of design temperature, reactor core limit heating power about 8MW, nearly 100 tons of water loading amount always weigh about more than 300 Ton.

ACME bulk testing gantry designs pressure designs are 10MPa, are all different with previous bulk testing rack.This Pressure limit isobaric can simulate whole accident processes in the minor break accident process of prototype power station after Natural Circulation.For first The underheat blowdown phase of beginning, passive PWR nuclear power station and the accident process of conventional presurized water reactor are essentially identical, and this accident Stage has had a large amount of test data and accurately analysis program is verified, therefore not as the weight of ACME verification experimental verifications Point.In passive PWR nuclear power station minor break accident, underheat can be divided into substantially after spurting Natural Circulation, automatic decompression, Stages, these stages such as long-term cooling are also the stage that passive safety system plays a major role, and emphasis is answered to simulate.ACME is tested It is that isobaric simulation originates that rack, which selects the end point of minor break accident underheat blowdown phase and the starting point in Natural Circulation stage, Point is capable of all follow-up accident transient processes of the simulation of the physical property such as equipressure since the Natural Circulation stage, avoids anisobaric mould The ratio distortion of the processes such as Natural Circulation, decompression caused by quasi-.The selection of this design parameter has fully considered the mesh of experiment Mark, and the further investigation of proportion grading and design is combined, some intrinsic problems of ratio test rack, work are avoided from source Journey realizability is good, is more leading at present and innovation design scheme.

With continued reference to Fig. 1 and with reference to Fig. 2, in design, ACME rack full simulations CAP1400 primary heat transport systems and non- The system and equipment of the non-security grade of active core cooling system and part, including：Full simulation CAP1400 prototypes power station Primary Ioops system and equipment, including reactor core, reactor pressure vessel（RPV）And in-pile component（RI）, two steam hairs Raw device（SGs）, voltage-stablizer（PZR）, four main pumps（MCPs）, four cold pipes（CLs）, two heat pipes（HLs）, and full simulation is former The loop of the four of type power station into scene 2 is arranged；The system and equipment of the passive core cooling systems of full simulation CAP1400, including Passive residual heat removal heat exchanger（PRHR HX）, two reactor core safety injection tanks（CMTs）, two accumulators（ACCs）, safety Material-changing water tank built in shell（IRWST）, 1-4 grades of releasing pressure automatically systems（ADS）, direct safety injection pipe（DVI）, cool down for a long time in containment Compartment in recirculation line, containment（SUMP, Secondary SUMP）And related pipeline and valve etc., and it is in proportion and former The arrangement and pipeline rout of these systems of type design simulation and equipment；Partial simulation reactor secondary circuit system and equipment, including Main feed system, main steam system, PORV pipelines etc., meet test function demand；Partial simulation is connected with reactor-loop System and equipment, including change appearance system（CVS）, normal residual heat removal system（RNS）Deng the operating condition of test such as support depth defense Research；Multiple experiment dedicated system are designed to realize the development of experiment, include in simulating Safety shell condensing circuit it is cold Solidifying return water system, the drainage collection system for collecting the draining of high temperature and pressure steam discharge, the discharge of steam for discharging a large amount of steam System, etc..

In order to obtain comprehensive accurate test data, ACME racks are disposed with more than 1300 measuring points, cover temperature pressure Flow liquid level pressure difference water loading amount various parameter measurements such as power.It is surveyed in addition, rack has been specifically designed 5 sets of steam-water separations Amount system can implement vapor-liquid separation measurement to the two phase flow of the discharges such as cut and ADS, efficiently solve two phase flow and spurt quality stream The difficulty of measurement.The real-time high-precision that reactor core three dimensional temperature distribution can be achieved in reactor core thermocouple stick group measures.In order to be Trigger action is accurately simulated in effective control of system, and ACME racks also possess advanced control system.ACME rack DCS data are adopted Collection and control system are made of engineer station, operator station, data memory, site monitor etc., it can be achieved that testing stable state fortune The foundation of row condition and the signal triggering under emergency conditions and logical response, the work(such as collection experiment manipulation, data storage, on-site supervision It can be in one.ACME rack Major Systems layout drawings are as shown in Figure 3.

For responses of the comprehensive simulated CAP1400 under various minor break accidents, it includes cold tube top portion that ACME racks, which are provided with, With the different break locations such as bottom, heat pipe bottom, peace note pipeline double, balance pipeline double, from 2.5cm, 5cm to The difference break size such as 20cm, and the minor break experimental study under superposition distinct device failure condition, simulate various accident winks State process and important thermal-hydraulic physical phenomenon, research break location, size, failure mode etc. are for system response and accident The validity of passive core cooling system is verified in the influence of process.Particularly, by the way that separation valve door is arranged on ACC pipelines, Influence of the incondensable gas nitrogen to cooling system performance can also be studied.ACME racks specially design cut simulation system, tool Body cut analog position is as shown in the table, and Fig. 4 shows ACME bench simulation minor break accident schematic diagrames.

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In the present invention, ACME test-beds are based on multi-level two-layer proportion grading method（Hierarchical Two- Tiered Scaling, H2TS）Proportion grading method carries out ratio and sets.H2TS is a kind of knot for complicated multinomial streaming system Structure proportion grading method.ACME test-bed proportion grading method flows are as follows.Fig. 6 shows the basic of H2TS proportion gradings Composition, this method are made of four fundamentals.

Specifically, " multistage " refers to that complication system is decomposed to the proportion grading grade that can develop similarity criterion with determination Not.That is, first step system decomposition：CAP1400 electric power station systems are decomposed into reactor main circuit coolant system（RCS）With non-energy Dynamic security system（PXS）Two main systems；Each main system can be divided into the subsystem of interaction（Or module）；Subsystem It is refined as the constituent element of interaction again（Substance）；Constituent element can be divided into component（Gas phase, liquid phase and solid phase）；Component can pass through several spies Property parameter describe, and these characterisitic parameters and its variation describe physical phenomenon different in accident process, need satisfaction three The conservation equation of a key（Quality, energy and momentum conservation equation）.

Second step carries out proportion grading hierarch recognition after this：After system decomposition, according to the physical phenomenon studied, know The level of other proportion grading simultaneously obtains its similarity criterion.Such as：Thermohydraulics process in system（Loop natural circulation or master Circuit pressure reduction）It is analyzed in system level；PRHR waste heats set out process, the passive peace note process of CMT, ACC and IRWST, ADS Pressure reduction, melt pit cool down Natural Circulation process in subsystem layer surface analysis for a long time；For single component for example reactor core, voltage-stablizer, Steam generator, hot pipe section, cold tube section, main pump, return etc. are in module level analysis；Vehicle repair major mixture and solid side Interaction is in constituent element level analysis between boundary；Quality, momentum and energy transmission between vehicle repair major is in component level analysis.

In addition, " bilayer " refers to the proportion grading for carrying out two levels for each feasible proportion grading rank, one layer is Proportion grading from bottom to top, to important phenomenon grade hierarchical table PIRT (Phenomena Identificat1n and Ranking Tables) in important Local physical process carry out proportion grading and obtain similarity criterion, system proportional was analyzed Cheng Jinhang is supplemented.Another layer is proportion grading from bottom to top, and dimensionless is carried out to the governing equation of each proportion grading rank Change obtains corresponding characteristic time ratio and similarity criterion.

The third for the H2TS methods that the utility model uses walks as from bottom to top（Top-Down）Proportion grading.From bottom to top The process of proportion grading is concerned with the crucial object to interact between the system components of important phenomenon grade hierarchical table PIRT identifications Reason process obtains corresponding similarity criterion and characteristic time ratio according to the corresponding conservation equation of the different proportion level of analysis, and really It is fixed it is subsequent from bottom to top（Bottom-Up）The important physical phenomena that proportion grading need to be paid close attention to.

4th step of the H2TS methods that the utility model uses is from bottom to top（Bottom-Up）Proportion grading：From lower and Upper proportion grading obtains specific physical process（Such as change of flow and diabatic process）Similarity criterion.Proportion grading from bottom to top It is concerned with the local separate physical process vital to system working performance that PIRT is identified, and corresponding component is provided and is set Count the requirement that should meet.

The utility model is directed in important phenomenon and carries out in-depth analysis research, i.e., on H2TS method original bases, into One step has expanded the range of bulk testing simulation, improves the accuracy of phenomena simulation.ACME test-beds can be more true The physical process and phenomenon of accurate comprehensive reflection nuclear power plant accident transient state.In the integrality aspect of pilot system, more existing skill The similar rack of art, the prototype system configuration more complete and accurate that the utility model is simulated.In terms of the comparison of rack distortion, The larger place of the similar rack localized distortion of the prior art, the localized distortion degree smaller of ACME.Compare in instrumentation system Aspect, the utility model technological precedence.In terms of operating condition of test comparison, operating condition of test used by minor break accident research is more It is complete and comprehensive.

For scale bulk testing system, meet between test-bed and prototype system in thermal-hydraulic process and important Similar in phenomenon is the basis of experimental study.ACME racks have carried out detailed proportion grading and design thus, ensure non-energy Dynamic system important physical phenomena of interest can carry out similar simulation, and can reflect the coupling between true system equipment Cooperation is used.

The utility model utilizes H2TS methods, the reactor that CAP1400 has been carried out in the Proportionality design of ACME racks cold But the proportion grading of agent system unit and passive core cooling system component, for the PIRT institutes of the power stations CAP1400 SBLOCA Row key physical phenomenon has carried out system, comprehensive proportion grading, has obtained similarity criterion and the Proportionality design rule of ACME racks Lattice, it is ensured that ACME racks can accurately simulate the important thermal-hydraulic physical phenomenon under SBLOCA in prototype, be ACME racks The Basic Design input condition of engineering design.

The proportion grading of each equipment of major loop should ensure that the Natural Circulation process that gravity dominates first, therefore major loop is respectively set Standby design considers to meet overall system ratio first, it is desirable that has same time, flow velocity, power equal proportion.For whole system The proportion grading and design scheme of system, it is also necessary to ensure that gross mass is similar with the change procedure of gross energy in system, this requirement It can be realized by system pressure reduction similarity analysis.Under the premise of system drains or dip time meets system time ratio, It can determine the quality and energy population proportion relationship of the system of flowing into and out, including：The volume and correspondence peace beam amount of PXS, Cut and ADS emission flow equal proportion relationships.In addition, the important local process phenomenon to appearance also will be in proportion grading and design It pays attention in scheme.Reactor core it is also contemplated that CHF etc. is as similar as possible, therefore proposes the four of Core Design in addition to Natural Circulation Key criteria, so that it is determined that ACME test-bed core structure parameters and heating rod placement scheme.For the top knot of RPV Structure, the large space entrainment of reactor core upper chamber, deentrainment phenomenon, the CCFL phenomenons of upper support board are required for being analyzed, with this Reactor core upper chamber ∏ groups and similarity criterion have been obtained, further determined the Proportionality design of ACME test-bed RPV upper components Parameter.The change of flow phenomenon of main pipeline is key events in major loop, it will directly affect the working condition of CMT and ADS4, It needs to ensure that main pipeline amendment Froude numbers are identical similar to meet change of flow thus.Surge line piping is using CCFL similarity analysis as base Plinth determines corresponding Proportionality design parameter.

The proportion grading of passive core cooling system is set based on Natural Circulation process and pressure reduction analysis Meter equally must satisfy overall system proportion requirement, should have same time, flow velocity, power, water loading amount equal proportion.In addition, right Important local process and phenomenon will also pay attention in proportion grading and design scheme.First, to pipeline flow resistance drawn game The analysis of portion's resistance determines rational pipe resistance ratio to meet desired flow rate of than requiring.Cut and ADS spurt middle critical flow It is important local phenomenon, by adjusting the throat diameter of pipeline, the condition for meeting and spurting flow-rate ratio can be reached.

The similarity criterion obtained with proportion grading is evaluated into line distortion, it can be seen that obtained by CAP1400 proportion gradings The ACME Proportionality designs arrived can guarantee test generally analog distortion it is smaller, therefore ACME can be simulated accurately The transient process of CAP1400 minor break accidents and wherein important thermohydraulics phenomenon.Pass through the detailed proportion grading institute of system Obtained Proportionality design can ensure there is good similitude between ACME racks and CAP1400.Specific H2TS analysis steps It is rapid to add and be described in detail below.

The major portion parameter of method according to the present utility model, finally obtained ACME racks is as follows：

Table 1：

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Fig. 5 shows the comparison in different tests bench simulation stage.By comparison as can be seen that being mostly single in the prior art The nuclear power Thermal hydrodynamic test rig of item and minisystem, there is no extensive globality nuclear power Thermal hydrodynamic test rig, and The utility model fills up this blank.And experiment overall plan compares, and is compared compared with several similar racks of technology, because ACME is designed using advanced overall plan, be can be completed using mono- rack of ACME and is needed two rack cooperation ability in the world The review of completion works.

With continued reference to Fig. 6, the step of determining parameter it illustrates the utility model, system decomposition is carried out first：By nuclear power System decomposition of standing is main system；Each main system can be divided into the subsystem of interaction；Subsystem is refined as phase interaction again Constituent element；Constituent element can be divided into component；Component can be described by several characterisitic parameters.After system decomposition, according to what is studied Physical phenomenon identifies the level of proportion grading and obtains its similarity criterion.Then each feasible proportion grading rank is carried out The proportion grading of two levels, one layer is proportion grading from bottom to top, to office important in important phenomenon grade hierarchical table PIRT Portion's physical process carries out proportion grading and obtains similarity criterion, supplements system proportional analytic process.Another layer be from lower and On proportion grading, nondimensionalization is carried out to the governing equation of each proportion grading rank and obtains corresponding characteristic time ratio and phase Like criterion.Proportion grading has obtained series of features time ratio（Dimensionless ∏ groups）And similarity criterion.Then to proportion grading Obtained similarity criterion is evaluated into line distortion, if distortion is larger, repeats the proportion grading of two levels；If distortion compared with It is small, it is determined that parameter.

Wherein, H2TS analysis the specific steps are：Control volume conservation equation is listed according to the phenomenon that paying close attention to first, profit Nondimensionalization is carried out to equation with primary condition and boundary condition, feature ∏ groups and dynamic relaxation time are obtained, by different physics The sequence of the corresponding ∏ groups of each components for obtaining key physical process that sort of process.Due to geometric dimension and physical parameter etc. Difference, subscale test rack can not possibly simulate whole physical processes, can only preferentially ensure the similitude of most critical process, to secondary Physical process carries out ratio distortion evaluation.By ensureing that accident transient state ∏ groups of similitudes of key physical process can be obtained model examination Test the geometry design parameter and initial launch operating mode of rack.Concrete analysis process is as follows：

（1）Characteristic time ratio

H2TS proportion gradings method will obtain the characteristic time ratio ∏ of related physical process.Derivation is as follows, for even Continuous phase " k ", control volume conservation equation are：

(1-1)

Wherein,For conservation parameter（OrDeng）,Body volume in order to control,For volume flow Amount,For by transmitting area A_knFrom " k ", " n " is mutually transmitted in opposite directionsParameter flux, therefore,Represent tradition Quality, momentum and convection of energy item；It represents and such as condenses transmission process, andFor source item, such as decay power Or body force item.

If：

By equation nondimensionalization：

(1-2)

Equation both sides simultaneously divided byIt can obtain：

(1-3)

Wherein, the relaxation time of k phases is：

(1-4)

It is respectively corresponding to the characteristic time of transmission process and source item ratio：

(1-5)

(1-6)

Each transmission process corresponds to a characteristic time ratio（Dimensionless ∏ groups）, therefore characteristic time ratio can be passed through （I.e. each ∏ values）Comparison obtain the importance of respective physical process.Physics if you need to reappear prototype power station on model stand passes Defeated process then needs to ensure that the corresponding characteristic time ratio of physical process is equal between prototype and model.As shown in Figure 7, if it is possible to The physical process change rate for ensureing primary condition and dimensionless space, then can ensure that prototype is similar to the simulation of model.

（2）Process importance is classified

The characteristic time ratio of different physical processes is in definition accident transient process： , whereini, j, N _i, N _jParticular procedure serial number, proportion grading level, total physical process quantity and proportion grading are indicated respectively Level quantity.

Due to the difference of geometric dimension and physical parameter etc., can not possibly be kept and prototype power station institute in subscale test rack Some characteristic times are than identical, that is to say, that it cannot be guaranteed that the similitude of all physical processes, namely：

(1-7)

SubscriptpPrototype power station is represented,mRepresentative model rack.

A test-bed can be designed to simulate the physical process of most critical in prototype power station, ensure its corresponding feature Time ratioPrototype is similar to model.Ensure these characteristic times than can be weighed with the design of Optimized model test-bed The crucial physical process of point research.

For the key physical process in the entire transient state accident of determination, it is necessary to obtain model and original in the different proportion level of analysis The characteristic time ratio of type.This feature time than the product for physical process characteristic frequency and relaxation time, namely：

(1-8)

Characteristic frequency defines specific physical process quality, the transmission rate of momentum and energy, and the relaxation time then provides The time needed for the transmission process occurs in control volume,

(1-9)

Indicate that only have a small amount of conservation physical quantity within the relaxation time is transmitted in control volume, the transmission process pair It is inessential for accident transient state,

(1-10)

Expression there is a large amount of conservation physical quantity to be transmitted in control volume within the relaxation time, the transmission process for It is important for accident transient state.

（3）Ratio criterion

Proportion grading has obtained series of features time ratio（Dimensionless ∏ groups）And similarity criterion.Ensure what PIRT was identified The similarity criterion of important physical phenomena, i.e., so that the characteristic time ratio of important physical process is equal between prototype and model, you can Obtain the similarity criterion of test-bed：

(1-11)

By adjusting rack geometric dimension, physical properties of fluids parameter and operating condition, the above criterion can be met.

（4）Ratio distortion evaluation

The purpose of ratio distortion evaluation is the geometric dimension for assessment models test-bed, boundary condition and operating condition Caused by be distorted size.The specific physical process ratio distortion factor of model test stand can be expressed as：

(1-12)

The physical essence of distortion factor DF can be construed in prototype and pass through control volume in the model corresponding relaxation time The conserved quantity prototype of transmission and the ratio between the difference of model and prototype transmission quantity.DF=0 indicates that model stand simulates the physics mistake completely Journey.DF=0.05 indicates the physical quantity transmitted in model after scale fewer than the physical quantity transmitted in prototype 5%.Distortion factor It can be expressed as：

(1-13)

Or

(1-14)

By contrast characteristic's time than size can obtain influence degree of the different physical processes for accident transient state, lead to It crosses and ensures that the characteristic time of crucial physical process in PIRT evaluations is more similar to model than prototype, you can obtain overall performance experiment Be in similar proportion criterion and the design parameter of rack.

Compared with the test-bed of the prior art, pilot system configuration is the most complete, and experimental design is more perfect, such as right Than 2 and table 3 can be shown in Table：

Table 2：The integrality comparison of test bench system configuration

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Table 3：Experimental design compares

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By comparison it is found that proportion of utilization analysis and experimental design improve and optimizate, bulk testing bench simulation is improved Accuracy and integrality：H2TS proportion gradings method is extended into Surge line piping CCFL, ADS4 entrainment for the first time, descending branch flow pattern turns It is accurate to improve simulation of the bulk testing on local key events for the analysis of the complicated physical phenomenas such as change, PRHR HX localized heat transfers Exactness；Using new process design method, the accurate mould of the labyrinths such as reactor core, in-pile component, pressure vessel ontology is realized It is quasi-, capture the high pressure sealing of heating cluster, upper-part in-reactor component effectively supports, measuring instrumentss are through technological difficulties such as multilayered shells； Wide-range, high-precision vehicle repair major separating and measuring system and reactor core three dimensional temperature field measurement device are developed, is obtained more Accurately, comprehensive thermal hydraulic test data.ACME test-bed full simulations prototype power station primary heat transport system and passive System, critical function component and local labyrinth use a series of special designings, more preferably to simulate prototype power station.

The ACME rack proportion gradings of the utility model cover four accident winks of CAP1400 small break LOCAs State has obtained the similarity criterion of simulation CAP1400 reactor main circuits coolant system and passive core cooling system, and has given Go out the Proportionality design parameter of its primary structure.

The utility model has been described in detail with reference to particular embodiments above, it is clear that do not departing from appended claims Defined in the scope of the utility model in the case of, can be modified and change.More specifically, although the utility model Some aspects are identified herein as preferred or advantageous, but the utility model should not necessarily be limited by the utility model These preferred embodiments.

Claims (7)

1. a kind of passive core cooling system bulk testing rack of pressurized-water reactor nuclear power plant, which is characterized in that it includes：

The circuit system and equipment of full simulation prototype nuclear power plant comprising in reactor core, reactor pressure vessel and heap Component, two steam generators, voltage-stablizer, four main pumps, four cold pipes, two heat pipes, wherein full simulation prototype nuclear power plant Four into scene 2 loop arrange；

The system and equipment of the passive core cooling system of full simulation prototype nuclear power plant comprising passive residual heat removal system And material-changing water tank built in passive residual heat removal heat exchanger, two reactor core safety injection tanks, two accumulators, containment, 1-4 grades Releasing pressure automatically system, direct safety injection pipe cool down recirculation line in containment, compartment, wherein scale modeling in containment for a long time The arrangement and pipeline rout of system and equipment；

Partial simulation reactor secondary circuit system and equipment comprising main feed system, main steam system, PORV pipelines are expired Sufficient test function demand；

The system and equipment that partial simulation is connected with reactor circuit comprising change appearance system, normal residual heat removal system, branch Hold the research of operating condition of test.

2. the passive core cooling system bulk testing rack of pressurized-water reactor nuclear power plant according to claim 1, feature exist In comprising for multiple experiment dedicated system to be tested, the multiple experiment dedicated system includes in simulating Safety shell The condensate return system of condensing circuit, for collect high temperature and pressure steam discharge draining drainage collection system, for discharging a large amount of steamings The steam-dump system of vapour.

3. the passive core cooling system bulk testing rack of pressurized-water reactor nuclear power plant according to claim 1, feature exist In for the passive core cooling system overall performance test-bed according to 1/3 height than, isobaric design.

4. the passive core cooling system bulk testing rack of pressurized-water reactor nuclear power plant according to claim 1, feature exist In being disposed with more than 1300 measuring points, cover temperature, pressure, flow, liquid level, pressure difference, water loading amount, the various parameters of power It measures, the ACME test-beds have 5 sets of steam-water separation measuring systems, and the two phase flow for being discharged to cut is implemented separation and surveyed Amount.

5. the passive core cooling system bulk testing rack of pressurized-water reactor nuclear power plant according to claim 1, feature exist In further including DCS data collection and control systems, by engineer station, operator station, data memory, site monitor Composition, the signal triggering under the foundation and emergency conditions for testing steady state operating conditions and logical response, collection experiment manipulation, number According to storage, on-site supervision.

6. the passive core cooling system bulk testing rack of pressurized-water reactor nuclear power plant according to claim 1, feature exist In it includes cold pipe top and bottom, heat pipe bottom, peace note pipeline double, balance pipeline pair that the ACME racks, which are provided with, End is broken different break locations, under the different break sizes of 2.5cm, 5cm to 20cm, and superposition distinct device failure condition Minor break experimental study, for simulating various accident transient processes and important thermal-hydraulic physical phenomenon, research cut position It sets, the influence of size, failure mode for system response and accident process, verifies the validity of passive core cooling system.

7. the passive core cooling system bulk testing rack of pressurized-water reactor nuclear power plant according to claim 1, feature exist In the major portion parameter of the ACME racks is：Height ratio 1:3；Circulation area is than 1:31.36；Diameter is than 1:5.6；Volume Than 1:94.08；Power ratio 1:54.32；Speed ratio 1:1.732；Time is than 1:1.732.