CN103871513B - Reactor pressure vessel distributed simulation structure in integral simulation test - Google Patents

Reactor pressure vessel distributed simulation structure in integral simulation test Download PDF

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Publication number
CN103871513B
CN103871513B CN201210538720.4A CN201210538720A CN103871513B CN 103871513 B CN103871513 B CN 103871513B CN 201210538720 A CN201210538720 A CN 201210538720A CN 103871513 B CN103871513 B CN 103871513B
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simulation
ring cavity
container
reactor
pressure vessel
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CN103871513A (en
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李长林
刘逊
卓文彬
许世杰
刘莉
张显群
郑华
聂常华
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Nuclear Power Institute of China
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Nuclear Power Institute of China
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    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Abstract

The present invention relates to reactor pressure vessel modelling technique field, specifically disclose reactor pressure vessel distributed simulation structure in a kind of integral simulation test.This model configuration includes reactor core simulation container and ring cavity simulation container, reactor core simulation container generally cylindrical structure, its upper and lower two ends adopt Flange joint, and reactor core simulation container has ozzle, and be connected by the ring cavity discharge connection of pipeline with ring cavity simulation container lower end, wherein, part on ring cavity simulation container mock-up reactor container prototype ring cavity, reactor core simulation container simulates, with ring cavity, the pipeline A reactor vessel prototype ring cavity lower part being connected between container.This model configuration simulates the circular passage of reactor pressure vessel prototype decline ring cavity, can better meeting geometric similarity criterion, kinetics criterion, meet economy and associated analog criterion, simultaneously, this simple in construction, arranged apart at decline ring cavity analogue body and reactor core analogue body, be conducive to the measurement of core flow.

Description

Reactor pressure vessel distributed simulation structure in integral simulation test
Technical field
The invention belongs to reactor pressure vessel modelling technique field, be specifically related to reactor pressure vessel distributed simulation structure in a kind of integral simulation test.
Background technology
In integral simulation test, it is necessary to reactor pressure vessel and internals are simulated, and the functional requirement according to assay device, the method for simulation is also different.At present, the simulation of reactor pressure vessel decline ring cavity is mainly had monoblock type decline ring cavity and two kinds of analog forms of external independence descending branch.
Adopt the assay device of monoblock type decline ring cavity analog form, the structure of reactor pressure vessel analogue body is similar to prototype reactor structure, decline ring cavity is the ring cavity surrounded by the outer wall of internal pressure vessel walls Yu core barrel, this analog form conveniently has advantage in the multidimensional phenomenon of the Flow and heat flux of mock-up reactor decline ring cavity, but kinetics criterion can not be met, and structure is more complicated, manufacturing cost is higher.The pressure vessel analogue body of APEX integral simulation test device is similar with reactor structure, and decline ring cavity is the ring cavity surrounded by the outer wall of internal pressure vessel walls Yu core barrel.ATLAS integral simulation test device, when design reactor vessel descending branch, it is more consider the reproduction that immediate container injects the multidimensional phenomenon that (directvesselinjection (DVI)) causes, and such as the maintenance of bubble-cap etc. surface tension effect Yu fluid state, therefore also use monoblock type decline ring cavity analog form.INER total system test (IIST) device also uses the analog form of monoblock type decline ring cavity.
Adopting the assay device of external independence descending branch analog form, utilize the ring-like decline chamber of external decline pipe simulation prototype reactor pressure vessel, this analog form facilitates core flow to measure, resistance simulation is accurate, disclosure satisfy that scale modeling criterion, simple in construction, have higher economy.France BETHSY power station PWR integral simulation test device, BUSHEHR Integrated test facility (BITF), PSB-VVER integral simulation test device, ISB-VVER integral simulation test device, PACTEL integral simulation test device, SPES-2 integral simulation test device etc. all have employed external independence descending branch analog form.At home, nuclear power institute reactor Natural Circulation entirety analogue experiment installation (is called for short NCIF) and is also adopted by the container Simulation Core equipped with axial uniformly electrical heating elements and control rod guide pipe simulating piece indirectly, adopts the ring-like decline chamber of external decline pipe simulation prototype reactor.
In the assay device of existing employing external independence descending branch analog form, the simulation of reactor decline ring cavity all have employed the analog form of external pipe, although disclosure satisfy that geometric similarity criterion, kinetics criterion equal proportion simulation rules, also cannot reflecting the multidimensional phenomenon of the Flow and heat flux of decline ring cavity, shortcoming is obvious.
Summary of the invention
It is an object of the invention to provide reactor pressure vessel distributed simulation structure in a kind of integral simulation test, overcome the deficiency of reactor pressure vessel distributed simulation structure in existing integral simulation test, meet scale modeling criterion and thermal-hydraulic phenomena simulation better, simplify core structure, facilitate the measurement of core flow.
Technical scheme is as follows: reactor pressure vessel distributed simulation structure in a kind of integral simulation test, this model configuration includes reactor core simulation container and ring cavity simulation container, reactor core simulation container generally cylindrical structure, its upper and lower two ends adopt Flange joint, and reactor core simulation container has ozzle, and be connected by the ring cavity discharge connection of pipeline with ring cavity simulation container lower end, wherein, part on ring cavity simulation container mock-up reactor container prototype ring cavity, reactor core simulation container simulates, with ring cavity, the pipeline A reactor vessel prototype ring cavity lower part being connected between container.
Described ring cavity simulation container includes cylinder, upper cover, low head, wherein, cylinder is sealed by upper cover, and in upper cover upper end, vent connection is installed, cylinder lower end is sealed by low head, and be provided with ring cavity discharge connection on low head, and the ozzle simulating lower vessel portion with reactor core by pipeline is connected.
Be additionally provided with peace note adapter on the described cylinder body outer wall in ring cavity simulation container, ring cavity interface is taken over gill cribbing, and wherein, two ring cavity entrance sleeves are positioned opposite, and peace note adapter becomes 75 ° of angles to arrange with one of them ring cavity entrance sleeve.
Between described reactor core simulation container and ring cavity simulation container, the sectional area of pipeline reduces with certain proportion by reactor vessel prototype ring cavity sectional area, and ring cavity simulation inside diameter of vessel reduces by same ratio.
Described inner barrel is provided with hanging basket, and the scaling that the external diameter of hanging basket simulates container according to ring cavity is determined.
Described reactor core simulation container is interior high high with in reactor vessel prototype equal, and reactor core simulation container epimere cavity simulates reactor vessel prototype upper plenum, and epimere cavity height is highly consistent with reactor vessel prototype epicoele.
Described reactor core simulation upper vessel portion is provided with core exit pipe.
Described cylinder is cylindrical structure, and upper cover is lid-like.
It is consistent with reactor vessel prototype that the difference in height of reactor core upper surface in container is simulated in described peace note adapter with reactor core.
The remarkable result of the present invention is in that: the reactor pressure vessel distributed simulation structural simulation circular passage of reactor pressure vessel prototype decline ring cavity in a kind of integral simulation test of the present invention, can better meeting geometric similarity criterion, kinetics criterion, relative and external pipe simulates annular decline chamber, while meeting economy, associated analog criterion can be met better, simultaneously, this simple in construction, there is good economy, and decline ring cavity analogue body is arranged apart with reactor core analogue body, is conducive to the measurement of core flow.
Accompanying drawing explanation
Fig. 1 is reactor pressure vessel distributed simulation structural representation in a kind of integral simulation test of the present invention;
Fig. 2 is ring cavity simulation structure of container schematic diagram in Fig. 1;
Fig. 3 is Fig. 2 other direction view;
Fig. 4 is the top view of Fig. 2;
In figure: 1, reactor core simulation container;2, ring cavity simulation container;3, core exit pipe;4, ring cavity inlet tube;5, peace note adapter;6, cylinder;7, upper cover;8, low head;9, hanging basket;10, vent connection;11, ring cavity entrance sleeve;12, ring cavity discharge connection;13, ear cribbing.
Detailed description of the invention
Below in conjunction with drawings and the specific embodiments, the present invention is described in further detail.
As shown in Fig. 1 ~ 4, reactor pressure vessel distributed simulation structure in a kind of integral simulation test, container 1 and ring cavity simulation container 2 is simulated including reactor core, wherein, reactor core simulation container 1 generally cylindrical structure, its upper and lower two ends all adopt Flange joint, in reactor core simulation container 1, height is high with in reactor vessel prototype equal, reactor core simulation container 1 epimere cavity simulation reactor vessel prototype upper plenum, and reactor core simulation container 1 epimere cavity height is highly consistent with reactor vessel prototype epicoele, and on reactor core simulation container 1 top, core exit pipe 3 is installed;Reactor core simulation container 1 lower cylindrical cylinder is provided with ozzle, and be connected by the ring cavity discharge connection 12 of pipeline with ring cavity simulation container 2 lower end, wherein, part on ring cavity simulation container 2 mock-up reactor container prototype ring cavity, reactor core simulation container 1 simulates, with ring cavity, the pipeline A reactor vessel prototype ring cavity lower part that container 2 is connected, and this pipeline section amasss and reduces with certain proportion by reactor vessel prototype ring cavity sectional area, ring cavity simulation container 2 internal diameter reduces by same ratio;Ring cavity simulation container 2 includes cylinder 6, upper cover 7, low head 8 and hanging basket 9, wherein, cylinder 6 upper end of cylindrical structure is sealed by the upper cover 7 of lid, and in upper cover 7 upper end, vent connection 10 is installed, the lower end of cylinder 6 is sealed by low head 8, and ring cavity discharge connection 12 is installed on low head 8, and be connected by the ozzle of pipeline with reactor core simulation container 1 bottom, cylinder 6 outer wall is also equipped with peace note adapter 5, ring cavity entrance sleeve 11 is with gill cribbing 13, wherein, two ring cavity entrance sleeves 11 are positioned opposite, peace note adapter 5 is arranged with 11 one-tenth 75 ° of angles of one of them ring cavity entrance sleeve, internally installed at cylinder 6 has hanging basket 9, the scaling that the external diameter of hanging basket 9 simulates container 2 according to ring cavity is determined, wherein, after ring cavity simulation container 2 is installed, ensure that peace note adapter 5 is consistent with reactor vessel prototype with the difference in height of reactor core upper surface in reactor core simulation container 1 (i.e. heating heating section peak position in reactor core simulation container 1).

Claims (8)

1. reactor pressure vessel distributed simulation structure in an integral simulation test, it is characterized in that: this model configuration includes reactor core simulation container (1) and ring cavity simulation container (2), reactor core simulation container (1) generally cylindrical structure, its upper and lower two ends adopt Flange joint, and reactor core simulation container (1) has ozzle, and be connected by the ring cavity discharge connection (12) of pipeline with ring cavity simulation container (2) lower end, wherein, part on ring cavity simulation container (2) mock-up reactor container prototype ring cavity, reactor core simulation container (1) simulates, with ring cavity, the pipeline A reactor vessel prototype ring cavity lower part being connected between container (2);Described ring cavity simulation container (2) includes cylinder (6), upper cover (7), low head (8), wherein, cylinder (6) is sealed by upper cover (7), and in upper cover (7) upper end, vent connection (10) is installed, cylinder (6) lower end is sealed by low head (8), and be provided with ring cavity discharge connection (12) on low head (8), and the ozzle simulating container (1) bottom with reactor core by pipeline is connected.
2. reactor pressure vessel distributed simulation structure in a kind of integral simulation test according to claim 1, it is characterized in that: described cylinder (6) outer wall in ring cavity simulation container (2) is additionally provided with peace note adapter (5), ring cavity interface adapter (11) with gill cribbing (13), wherein, two ring cavity entrance sleeves (11) are positioned opposite, and peace note adapter (5) becomes 75 ° of angles to arrange with one of them ring cavity entrance sleeve (11).
3. reactor pressure vessel distributed simulation structure in a kind of integral simulation test according to claim 1, it is characterized in that: between described reactor core simulation container (1) and ring cavity simulation container (2), the sectional area of pipeline reduces with certain proportion by reactor vessel prototype ring cavity sectional area, ring cavity simulation container (2) internal diameter reduces by same ratio.
4. reactor pressure vessel distributed simulation structure in a kind of integral simulation test according to claim 1 and 2, it is characterized in that: described cylinder (6) is internal is provided with hanging basket (9), and the scaling that the external diameter of hanging basket (9) simulates container (2) according to ring cavity is determined.
5. reactor pressure vessel distributed simulation structure in a kind of integral simulation test according to claim 1, it is characterized in that: described reactor core simulation container (1) Nei Gao is high with in reactor vessel prototype equal, reactor core simulation container (1) epimere cavity simulation reactor vessel prototype upper plenum, and epimere cavity height is highly consistent with reactor vessel prototype epicoele.
6. reactor pressure vessel distributed simulation structure in a kind of integral simulation test according to claim 1 or 5, it is characterised in that: described reactor core simulation container (1) top is provided with core exit pipe (3).
7. reactor pressure vessel distributed simulation structure in a kind of integral simulation test according to claim 1 and 2, it is characterised in that: described cylinder (6) is cylindrical structure, and upper cover (7) is lid-like.
8. reactor pressure vessel distributed simulation structure in a kind of integral simulation test according to claim 2, it is characterised in that: it is consistent with reactor vessel prototype that described peace note adapter (5) simulates the difference in height of reactor core upper surface in container (1) with reactor core.
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CN105006260A (en) * 2015-07-31 2015-10-28 中科华核电技术研究院有限公司 Reactor core simulation body used for bulk effect thermotechnical hydraulic test
CN106653116A (en) * 2017-01-11 2017-05-10 中国核动力研究设计院 Pressure bearing vessel suitable for out-of-pile test of reversely inserted drive wire
CN106803431B (en) * 2017-01-22 2017-12-12 中国核动力研究设计院 The external that can accurately measure core flow declines chamber arrangement apparatus and measuring method
CN110097990B (en) * 2018-01-31 2023-01-17 中国辐射防护研究院 Simulation container of high-density polyethylene high-integral container
CN112071450B (en) * 2020-08-05 2023-08-18 中国原子能科学研究院 External pressure type reactor pressure vessel
CN114550955A (en) * 2022-02-16 2022-05-27 中国核动力研究设计院 Nuclear power reactor core thermal simulation device
CN115367287A (en) * 2022-09-13 2022-11-22 中国核动力研究设计院 Cylindrical pressure-bearing container with branch pipe and window

Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4828787A (en) * 1986-07-17 1989-05-09 Rheinisch-Westfalisches Elektrizitatswerk Akteingesellschaft Apparatus for simulation of the operation of a pressurized water nuclear reactor
US5660617A (en) * 1996-05-16 1997-08-26 Southwest Research Institute System and method for maintaining multiphase flow with minimal solids degradation
JP2008116334A (en) * 2006-11-06 2008-05-22 Toshiba Corp Natural circulation reactor and method for controlling its output
CN102693765A (en) * 2011-03-23 2012-09-26 巴布科克和威尔科克斯核能股份有限公司 Emergency core cooling system for pressurized water reactor

Patent Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4828787A (en) * 1986-07-17 1989-05-09 Rheinisch-Westfalisches Elektrizitatswerk Akteingesellschaft Apparatus for simulation of the operation of a pressurized water nuclear reactor
US4828787B1 (en) * 1986-07-17 1991-09-03 Rhein Westfael Elect Werk Ag
US5660617A (en) * 1996-05-16 1997-08-26 Southwest Research Institute System and method for maintaining multiphase flow with minimal solids degradation
JP2008116334A (en) * 2006-11-06 2008-05-22 Toshiba Corp Natural circulation reactor and method for controlling its output
CN102693765A (en) * 2011-03-23 2012-09-26 巴布科克和威尔科克斯核能股份有限公司 Emergency core cooling system for pressurized water reactor

Non-Patent Citations (2)

* Cited by examiner, † Cited by third party
Title
Nodalization qualification process of the psb-vver facility for the cathare2 thermal-hydraulic code;Alessandro Del Nevo et al;《5th international on nuclear opion countries with small and medium electricity grid》;20040520;第9页附图1 *
simulation of the kozloduy npp loss-of-feed-water transient in PSB-VVER facility;Andrey Kapustin et al;《12th International Conference on Nuclear Engineering》;20040429;全文 *

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