CN105006260A - Reactor core simulation body used for bulk effect thermotechnical hydraulic test - Google Patents
Reactor core simulation body used for bulk effect thermotechnical hydraulic test Download PDFInfo
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- CN105006260A CN105006260A CN201510460322.9A CN201510460322A CN105006260A CN 105006260 A CN105006260 A CN 105006260A CN 201510460322 A CN201510460322 A CN 201510460322A CN 105006260 A CN105006260 A CN 105006260A
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- reactor core
- hydraulic test
- copper rod
- blind flange
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C23/00—Adaptations of reactors to facilitate experimentation or irradiation
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C5/00—Moderator or core structure; Selection of materials for use as moderator
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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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- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention discloses a reactor core simulation body used for a bulk effect thermotechnical hydraulic test. The reactor core simulation body comprises a load-bearing barrel body, a basket, a padding body, a reactor core fuel simulation part and copper bars; the load-bearing barrel body is of a hollow structure, and the upper end and the lower end of the load-bearing barrel body are connected with a blind flange and a spherical head in a sealed mode respectively; the basket which is of a hollow structure is hung in the load-bearing barrel body, and a certain gap exists between the basket and the inner wall of the load-bearing barrel body; the padding body is arranged inside the basket, and a required channel is defined by the padding body; the reactor core fuel simulation part is fixed in the channel, and a certain gap exists between the reactor core fuel simulation part and the inner wall of the padding body; the copper bars are fixed to the blind flange and sealed with the blind flange through insulating materials, and the two ends of each copper bar are electrically connected with an external electric power system and the reactor core fuel simulation part respectively. According to the reactor core simulation body used for the bulk effect thermotechnical hydraulic test, an electric power input interface is arranged above the reactor core simulation body, the problem of insufficient sealing caused by bottom heating is solved, the convenience of electric power assembly is guaranteed, the structure is simple, the size is small, the safety is high, the economical efficiency is good, and the reactor core simulation body can fully satisfy the needs of relevant scientific research and practical activities funtionally.
Description
Technical field
The present invention relates to nuclear power plant reactor modelling technique field, particularly relate to a kind of reactor core analogue body for group effect thermal hydraulic test.
Background technology
In the primary Ioops system of pressurized-water reactor nuclear power plant, the fuel fission of reactor in-core produces huge heat energy, the water being pumped into reactor core by main pump is heated to form high-temperature high pressure water, high-temperature high pressure water is taken reactor pressure vessel out of the heat energy that reactor core produces and is entered steam generator, when high-temperature high pressure water is by steam generator, by thousands of heat-transfer pipes, the secondary circuit that heat is passed to outside pipe is fed water, feedwater after release heat is sent back to reactor core by main pump again, and feedwater is constantly at airtight primary Ioops Inner eycle.
In view of spatial volume and the economy of the reactor pressure vessel of primary Ioops system, directly cannot carry out entirety according to its prototype to quote in process of scientific research and practical activity, but need to simplify literary writing by leaving out superfluous words on the basis of reactor pressure vessel and internals thereof and entirety can be carried out and simulate.But existingly a kind ofly adopt external decline cylinder to carry out the analogue means of mock-up reactor Pressure vessel downcomer, comparatively large with the difference of reactor prototype, can not meet the scientific research and practical activity demand of being correlated with completely; And the analogue means similar to reactor pressure vessel prototype, all there is complex structure, defect that manufacturing cost is high.And in above-mentioned analogue means, electric power input all realizes from the bottom of pressure vessel, has increased the weight of the burden of low head thus, easily causes the poorly sealed of bottom.
Therefore, be necessary to provide a kind of structure simple, install convenient, security is high, the reactor core analogue body of good economy performance, to overcome above-mentioned the deficiencies in the prior art.
Summary of the invention
The object of the present invention is to provide a kind of structure simple, install convenient, security is high, the reactor core analogue body for group effect thermal hydraulic test of good economy performance.
For achieving the above object, technical scheme of the present invention is: provide a kind of reactor core analogue body for group effect thermal hydraulic test, it comprises pressure cylinder, hanging basket, obturator, reactor fuel simulating piece and copper rod; Described pressure cylinder is hollow structure, and the upper and lower end of described pressure cylinder is connected with blind flange and dome head respectively hermetically; Described hanging basket is hollow structure and hangs in described pressure cylinder, has certain interval between the inwall of described hanging basket and described pressure cylinder; Described obturator to be located in described hanging basket and to be surrounded required passage; Described reactor fuel simulating piece is fixed in described passage and also and between the inwall of described obturator has certain interval; Described copper rod is fixed on described blind flange and two ends are electrically connected with external power system, described reactor fuel simulating piece respectively, is sealed between described copper rod and described blind flange by insulating material.
Preferably, described reactor fuel simulating piece comprises the many groups of heating tube bundles be in series, the two ends of the described heating tube bundle after series connection are electrically connected with described copper rod respectively, and be equipped with insulator between heating tube bundle described in adjacent two groups, reactor fuel simulating piece adopts many group heating tube bundles to be in series, meet the power demand of different reactor core analogue bodies, there is extraordinary adjustment convenience.
Preferably, described insulator comprises multiple spaced ceramic rod, is isolated by heating tube bundle by ceramic rod, ensure that the convenience of assembling on the one hand, ensure that the security of plant running on the other hand.
Preferably, the electric heating tube that described heating tube bundle includes multiple parallel connection is often organized.
Preferably, the top of described obturator and bottom are fixed with copper bar, back up pad respectively, and described back up pad is all fixed in the lower end of the described heating tube bundle of many groups, and the upper end of the described heating tube bundle of many groups is all welded in described copper bar.
Preferably, described blind flange offers two through hole, copper rod described in two to be individually fixed in through hole described in two and to stretch out outside described blind flange, and copper rod described in two is electrically connected with the two ends of described reactor fuel simulating piece respectively; By the special construction that copper rod, reactor fuel simulating piece are connected, make electricity interface be positioned at the top of pressure cylinder, ensure that the convenience that electric power assembles, also solve the poorly sealed problem that bottom-heated brings.
Preferably, be electrically connected respectively by two groups of copper pigtails between the two ends of copper rod described in two and described reactor fuel simulating piece.
Preferably, the described reactor core analogue body for group effect thermal hydraulic test also comprises sleeve and asbestos pad, described jacket casing is located at described copper rod and is also pressed between the outer wall of described copper rod and the inwall of described through hole hermetically outward, and described asbestos pad presses between described copper rod and described blind flange hermetically; Realized the sealing of copper rod and blind flange by sleeve, asbestos pad, solve the poorly sealed problem that bottom-heated in prior art brings.
Preferably, one end of described copper rod is radially convexly equipped with contact part, and described asbestos pad presses between the base plate of described contact part and described blind flange hermetically.
Compared with prior art, due to of the present invention for the reactor core analogue body of group effect thermal hydraulic test, its hanging basket suspension is in pressure cylinder, the inside of hanging basket surrounds a passage by obturator, reactor fuel simulating piece is fixed in passage, and power positive cathode being arranged in the head and the tail two ends of reactor fuel simulating piece, reactor fuel simulating piece realizes the electric connection with external power system by the copper rod on the blind flange of the side of being located thereon.First, power input interface is located at the top of reactor core analogue body, solves the poorly sealed problem that bottom-heated in prior art brings, and ensure that the convenience that electric power assembles; Secondly, reactor fuel simulating piece is formed by the series connection of many group heating tube bundles, meet different reactor core analogue body power demands, there is extraordinary adjustment convenience, and the insulator for isolating arranged between adjacent heating tube bundle, ensure that the convenience of assembling on the one hand, ensure that the security of operation on the other hand; Moreover, the structure of reactor core analogue body and the reactor core flow passage structure of reactor prototype more close, therefore, ratio criterion can better be met, better reflection reactor thermo-hydraulics phenomenon; In addition, the structure of this reactor core analogue body is simple, volume is little, good economy performance.
Accompanying drawing explanation
Fig. 1 is the cut-open view of the present invention for the reactor core analogue body of group effect thermal hydraulic test.
Fig. 2 is the present invention's another cut-open view for the reactor core analogue body of group effect thermal hydraulic test.
Fig. 3 is the vertical view of the present invention for the reactor core analogue body of group effect thermal hydraulic test.
Fig. 4 is the enlarged schematic partial view of blind flange in Fig. 1.
Fig. 5 is the partial schematic diagram of heating tube bundle in Fig. 1.
Embodiment
With reference now to accompanying drawing, describe embodiments of the invention, element numbers similar in accompanying drawing represents similar element.
As Figure 1-3, the reactor core analogue body 100 for group effect thermal hydraulic test provided by the present invention, comprises pressure cylinder 110, hanging basket 120, obturator 130, reactor fuel simulating piece 140 and copper rod 150.Wherein, pressure cylinder 110 is in hollow structure, and the upper end of pressure cylinder 110 is sealed by blind flange 160, and is provided with octangonal ring with fitted seal between pressure cylinder 110 and blind flange 160, and the lower end of pressure cylinder 110 is welded with dome head 170 hermetically; Pressure cylinder 110 ensures whole system security of operation at high temperature under high pressure.Described hanging basket 120 is hollow structure and hangs in pressure cylinder 110, and all has certain interval between the inwall of hanging basket 120 and pressure cylinder 110, between hanging basket 120 and dome head 170.Obturator 130 to be located in hanging basket 120 and the square duct 131 surrounded needed for, and this obturator 130 be ceramic.Described reactor fuel simulating piece 140 is fixed in passage 131 and also and between the inwall of obturator 130 has certain interval, and reactor fuel simulating piece 140 is furnished with power positive cathode.Copper rod 150 is fixed on blind flange 160 and two ends are electrically connected with the power positive cathode of external power system, reactor fuel simulating piece 140 respectively, is sealed between copper rod 150 and blind flange 160 by insulating material.
Shown in Fig. 1-2,5, the top of obturator 130 is fixed with copper bar 132, is fixed with back up pad 133 bottom it, and reactor fuel simulating piece 140 is fixed between copper bar 132, back up pad 133.Particularly, described reactor fuel simulating piece 140 comprises the many groups of heating tube bundles be in series 141 and is located at the insulator 142 between two groups of adjacent heating tube bundles 141, back up pad 133 is all fixed in many groups heating tube bundle 141 lower end, and the upper end of many group heating tube bundles 141 is all welded in copper bar 132; Further, power positive cathode is arranged respectively in the two ends of the many groups heating tube bundle 141 after series connection, and this power positive cathode is electrically connected with copper rod 150 respectively, thus above reactor core analogue body 100, realize electric power input; Reactor fuel simulating piece 140 adopts many group heating tube bundles 141 to be in series, and meets the power demand of different reactor core analogue bodies 100, has extraordinary adjustment convenience.
Shown in Fig. 5, in the present embodiment, be in series by four groups of heating tube bundles 141 and form reactor fuel simulating piece 140, and four groups of heating tube bundles 141 are in vertical, often organize the electric heating tube 1411 that heating tube bundle 141 includes multiple parallel connection, multiple electric heating tube 1411 arranges equably, preferably, often organizes heating tube bundle 141 and includes 64 electric heating tubes 1411 in parallel.Therefore, all-in resistance meets Electric Design demand.And, by the insulator 142 in decussate texture, four groups of heating tube bundles 141 are isolated, this insulator 142 is made up of multiple spaced ceramic rod 1421, by ceramic rod 1421, four groups of heating tube bundles 141 are isolated, to avoid short circuit burning apparatus, ensure that the convenience of assembling on the one hand, ensure that the security of plant running on the other hand.
Again referring to shown in Fig. 1-4, in the present invention, in order to ensure the convenience that electric power is installed, electricity interface is arranged on blind flange 160.Particularly, blind flange 160 offers two through hole 161, two copper rods 150 to be individually fixed in two through hole 161 and to stretch out outside blind flange 160, two copper rods 150 stretch out one end outside blind flange 160 and external power system is electrically connected, the other end of two copper rods 150 is electrically connected with the power positive cathode of reactor fuel simulating piece 140 by two groups of copper pigtails 180.Meanwhile, for the ease of installing two copper rods 150, two chapelets 190 being set on the top of blind flange 160 and pre-installing.
For one of them copper rod 150, its structure and assembling are described.As shown in Figure 4, the sleeve 153 that one end of copper rod 150 is radially convexly equipped with contact part 151, asbestos pad 152, polyimide material is socketed on outside copper rod 150 successively, that is, asbestos pad 152 is between contact part 151 and sleeve 153.During installation, this copper rod 150 penetrates in a through hole 161 from the below of blind flange 160, contact part 151 is made to be positioned at below the base plate of blind flange 160, sleeve 153 presses between the outer wall of copper rod 150 and the inwall of through hole 161 hermetically, and asbestos pad 152 presses between the base plate of contact part 151 and blind flange 160 hermetically.After two copper rod 150 installations, be electrically connected respectively by two groups of copper pigtail 180 between two copper rods 150 and the power positive cathode of heating tube bundle 141.By the special construction that copper rod 150, heating tube bundle 141 are connected, make electricity interface be positioned at the top of integral device, ensure that the convenience that electric power assembles; Simultaneously, the sealing of copper rod 150 and blind flange 160 is realized by sleeve 153, asbestos pad 152, solve the poorly sealed problem that bottom-heated in prior art brings, make the flow passage structure of reactor core analogue body 100 more similar to the flow passage structure of reactor prototype simultaneously.
Again referring to shown in Fig. 1-4, described pressure cylinder 110 is also provided with induction pipe interface 111, outlet interface 112 and blow-off pipe interface, wherein, induction pipe interface 111, outlet interface 112 are a little less than the hanging position of hanging basket 120 with pressure cylinder 110.
Shown in composition graphs 1-5, reactor core analogue body 100 of the present invention is for the thermal source simulation of reactor-loop in the test of nuclear industry group effect.
Particularly, when carrying out simulation test, Main Coolant enters in pressure cylinder 110 through induction pipe interface 111, and flowed downward by the passage between the inwall of pressure cylinder 110 and hanging basket 120, in dome head 170, Main Coolant by the bottom admission passage 131 of hanging basket 120, is heated when Main Coolant flows through heating tube bundle 141 after assignment of traffic, and the High Temperature High Pressure cooling medium after heating flows out to enter secondary coolant circuit system via outlet interface 112 again.The flow passage structure of reactor core analogue body 100 of the present invention and the flow passage structure of reactor prototype are consistent substantially, the heating to Main Coolant in reactor integral simulation test loop can be realized by this reactor core analogue body 100, and ensure security and the convenience of heating.
Because the present invention is used for the reactor core analogue body 100 of group effect thermal hydraulic test, its hanging basket 120 hangs in pressure cylinder 110, the inside of hanging basket 120 surrounds a passage 131 by obturator 130, reactor fuel simulating piece 140 is fixed in passage 131, and power positive cathode being arranged in the head and the tail two ends of reactor fuel simulating piece 140, reactor fuel simulating piece 140 realizes the electric connection with external power system by the copper rod 150 on the blind flange 160 of the side of being located thereon.First, power input interface is located at the top of reactor core analogue body 100, solves the poorly sealed problem that bottom-heated in prior art brings, and ensure that the convenience that electric power assembles; Secondly, reactor fuel simulating piece 140 is connected by many group heating tube bundles 141 and is formed, meet different reactor core analogue body 100 power demands, there is extraordinary adjustment convenience, and, being provided with the insulator 142 for isolating between adjacent heating tube bundle 141, ensure that the convenience of assembling on the one hand, ensure that the security of operation on the other hand; Moreover, the structure of reactor core analogue body 100 and the reactor core flow passage structure of reactor prototype more close, therefore, ratio criterion can better be met, better reflection reactor thermo-hydraulics phenomenon; In addition, the structure of this reactor core analogue body 100 is simple, volume is little, good economy performance.
Above disclosedly be only the preferred embodiments of the present invention, certainly can not limit the interest field of the present invention with this, therefore according to the equivalent variations that the present patent application the scope of the claims is done, still belong to the scope that the present invention is contained.
Claims (9)
1., for a reactor core analogue body for group effect thermal hydraulic test, it is characterized in that: comprise
Pressure cylinder, described pressure cylinder is hollow structure, and the upper and lower end of described pressure cylinder is connected with blind flange and dome head respectively hermetically;
Hanging basket, described hanging basket is hollow structure and hangs in described pressure cylinder, has certain interval between the inwall of described hanging basket and described pressure cylinder;
Obturator, described obturator to be located in described hanging basket and to be surrounded required passage;
Reactor fuel simulating piece, described reactor fuel simulating piece is fixed in described passage and also and between the inwall of described obturator has certain interval;
Copper rod, described copper rod is fixed on described blind flange and two ends are electrically connected with external power system, described reactor fuel simulating piece respectively, is sealed between described copper rod and described blind flange by insulating material.
2. as claimed in claim 1 for the reactor core analogue body of group effect thermal hydraulic test, it is characterized in that: described reactor fuel simulating piece comprises the many groups of heating tube bundles be in series, the two ends of the described heating tube bundle after series connection are electrically connected with described copper rod respectively, and are equipped with insulator between heating tube bundle described in adjacent two groups.
3., as claimed in claim 2 for the reactor core analogue body of group effect thermal hydraulic test, it is characterized in that: described insulator comprises multiple spaced ceramic rod.
4., as claimed in claim 2 for the reactor core analogue body of group effect thermal hydraulic test, it is characterized in that: often organize the electric heating tube that described heating tube bundle includes multiple parallel connection.
5. as claimed in claim 2 for the reactor core analogue body of group effect thermal hydraulic test, it is characterized in that: the top of described obturator and bottom are fixed with copper bar, back up pad respectively, described back up pad is all fixed in the lower end of many groups of described heating tube bundles, and the upper end of the described heating tube bundle of many groups is all welded in described copper bar.
6. as claimed in claim 1 for the reactor core analogue body of group effect thermal hydraulic test, it is characterized in that: described blind flange offers two through hole, copper rod described in two to be individually fixed in through hole described in two and to stretch out outside described blind flange, and copper rod described in two is electrically connected with the two ends of described reactor fuel simulating piece respectively.
7. as claimed in claim 6 for the reactor core analogue body of group effect thermal hydraulic test, it is characterized in that: be electrically connected respectively by two groups of copper pigtail between the two ends of copper rod described in two and described reactor fuel simulating piece.
8. as claimed in claim 6 for the reactor core analogue body of group effect thermal hydraulic test, it is characterized in that: also comprise sleeve and asbestos pad, described jacket casing is located at described copper rod and is also pressed between the outer wall of described copper rod and the inwall of described through hole hermetically outward, and described asbestos pad presses between described copper rod and described blind flange hermetically.
9., as claimed in claim 8 for the reactor core analogue body of group effect thermal hydraulic test, it is characterized in that: one end of described copper rod is radially convexly equipped with contact part, described asbestos pad presses between the base plate of described contact part and described blind flange hermetically.
Priority Applications (2)
| Application Number | Priority Date | Filing Date | Title |
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| CN201510460322.9A CN105006260A (en) | 2015-07-31 | 2015-07-31 | Reactor core simulation body used for bulk effect thermotechnical hydraulic test |
| PCT/CN2015/097236 WO2017020474A1 (en) | 2015-07-31 | 2015-12-14 | Reactor core simulation body for overall effect thermal hydraulic test |
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| Application Number | Priority Date | Filing Date | Title |
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| CN201510460322.9A CN105006260A (en) | 2015-07-31 | 2015-07-31 | Reactor core simulation body used for bulk effect thermotechnical hydraulic test |
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| CN105006260A true CN105006260A (en) | 2015-10-28 |
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| WO (1) | WO2017020474A1 (en) |
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| CN107240427A (en) * | 2017-06-26 | 2017-10-10 | 中国核动力研究设计院 | High temperature resistant cluster fuel assembly analogue means based on Diffusion Welding |
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| WO2017020474A1 (en) * | 2015-07-31 | 2017-02-09 | 中广核研究院有限公司 | Reactor core simulation body for overall effect thermal hydraulic test |
| CN106409363A (en) * | 2016-11-25 | 2017-02-15 | 中国核动力研究设计院 | Reactor simulator and assembly process thereof |
| CN107146643A (en) * | 2016-11-25 | 2017-09-08 | 中国核动力研究设计院 | A kind of novel reaction heap analogue body |
| CN106409363B (en) * | 2016-11-25 | 2017-12-01 | 中国核动力研究设计院 | A kind of reactor analogue body and its packaging technology |
| CN107146643B (en) * | 2016-11-25 | 2018-11-20 | 中国核动力研究设计院 | A kind of reactor analogue body |
| CN107240427A (en) * | 2017-06-26 | 2017-10-10 | 中国核动力研究设计院 | High temperature resistant cluster fuel assembly analogue means based on Diffusion Welding |
| CN107240427B (en) * | 2017-06-26 | 2018-03-20 | 中国核动力研究设计院 | High temperature resistant cluster fuel assembly analogue means based on Diffusion Welding |
| CN109637679B (en) * | 2019-02-01 | 2024-05-14 | 中国原子能科学研究院 | Reactor core vessel and method of installing the same |
| CN109637679A (en) * | 2019-02-01 | 2019-04-16 | 中国原子能科学研究院 | Core vessel and its installation method |
| CN110415841A (en) * | 2019-07-01 | 2019-11-05 | 国核华清（北京）核电技术研发中心有限公司 | Critical heat flux density enhances experimental rig |
| CN110415841B (en) * | 2019-07-01 | 2024-02-27 | 国核华清（北京）核电技术研发中心有限公司 | Critical heat flux density enhancement test device |
| CN113096840A (en) * | 2021-03-29 | 2021-07-09 | 中山大学 | Reaction kettle for simulating dynamic test of reactor fuel rod cladding material |
| CN113658727A (en) * | 2021-07-30 | 2021-11-16 | 中山大学 | Device for simulating overheating in fuel cladding pipe of nuclear power station |
| CN114336336A (en) * | 2022-02-16 | 2022-04-12 | 中国核动力研究设计院 | Insulation device of thermal simulation device of nuclear power reactor core |
| 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 |
| CN114336336B (en) * | 2022-02-16 | 2023-06-20 | 中国核动力研究设计院 | Insulation device of nuclear power reactor core thermal simulation device |
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| WO2017020474A1 (en) | 2017-02-09 |
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