CN85100182A - Adopt the nuclear power station light water reactor of double pressure shell - Google Patents
Adopt the nuclear power station light water reactor of double pressure shell Download PDFInfo
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- CN85100182A CN85100182A CN198585100182A CN85100182A CN85100182A CN 85100182 A CN85100182 A CN 85100182A CN 198585100182 A CN198585100182 A CN 198585100182A CN 85100182 A CN85100182 A CN 85100182A CN 85100182 A CN85100182 A CN 85100182A
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- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title claims abstract description 72
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 claims abstract description 16
- 229910052796 boron Inorganic materials 0.000 claims abstract description 16
- 239000002826 coolant Substances 0.000 claims abstract description 3
- 239000000446 fuel Substances 0.000 claims description 9
- 238000005253 cladding Methods 0.000 claims description 5
- 230000002457 bidirectional effect Effects 0.000 claims description 4
- 239000002245 particle Substances 0.000 claims description 3
- 208000036366 Sensation of pressure Diseases 0.000 abstract 1
- 238000001816 cooling Methods 0.000 description 6
- 230000018044 dehydration Effects 0.000 description 3
- 238000006297 dehydration reaction Methods 0.000 description 3
- 238000013461 design Methods 0.000 description 3
- 230000005540 biological transmission Effects 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 238000005516 engineering process Methods 0.000 description 2
- 238000002347 injection Methods 0.000 description 2
- 239000007924 injection Substances 0.000 description 2
- 238000012423 maintenance Methods 0.000 description 2
- 235000014171 carbonated beverage Nutrition 0.000 description 1
- 230000001413 cellular effect Effects 0.000 description 1
- 239000003245 coal Substances 0.000 description 1
- 238000004891 communication Methods 0.000 description 1
- 230000002860 competitive effect Effects 0.000 description 1
- 230000007812 deficiency Effects 0.000 description 1
- 238000011161 development Methods 0.000 description 1
- 230000018109 developmental process Effects 0.000 description 1
- JEGUKCSWCFPDGT-UHFFFAOYSA-N h2o hydrate Chemical compound O.O JEGUKCSWCFPDGT-UHFFFAOYSA-N 0.000 description 1
- 238000007689 inspection Methods 0.000 description 1
- 239000007788 liquid Substances 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 239000003758 nuclear fuel Substances 0.000 description 1
- 230000009257 reactivity Effects 0.000 description 1
- 238000011160 research Methods 0.000 description 1
- 230000000630 rising effect Effects 0.000 description 1
- 238000000926 separation method Methods 0.000 description 1
- 239000002910 solid waste Substances 0.000 description 1
- 239000002915 spent fuel radioactive waste Substances 0.000 description 1
- 239000007921 spray Substances 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
- 239000002918 waste heat Substances 0.000 description 1
- 239000002699 waste material Substances 0.000 description 1
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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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- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
A kind of nuclear power station light water reactor that adopts the double pressure shell belongs to the improvement of used in nuclear power station light water reactor.The characteristics of this light water reactor adopt the double pressure shell, fill between two shells with boron water, and case pres-sure is higher than the working pressure of inner casing reactor water coolant, and any leakage part that makes reactor one loop can only be that the boron water loop that bleeds makes it shutdown to guarantee safety.Be arranged in inner casing light water reactor reator body and adopt (1) integrated presurized water reactor (2) boiling-water reactor or (3) overcritical presurized water reactor, reator body compact conformation and simple helps miniaturization.The present invention can significantly improve the security and the economy of light water reactor, helps applying of nuclear power station.
Description
The present invention is the improvement to the used in nuclear power station light water reactor, is intended to increase its security and reduces its initial outlay, promotes the use of in order to it.
Present general used in nuclear power station light water reactor, one loop working medium is high-temperature high pressure water.Break or Vent when leaking when a loop pipeline or equipment have, because dehydration might cause core meltdown, thereby the outer Vent of a large amount of radioactivity causes major accident (for example the U.S. took place in 1979 three mile island nuclear station accident).Therefore, adopt the maltilevel security measure in the design of modern light water-water reactor, as high pressure water injection system, low pressure water injection system, water-spray system, containment system etc., in the hope of guaranteeing safety.But this kind design causes light water reactor nuclear power plant system complexity, and cost is higher, and, even these measures have been arranged,, still can not get rid of core melt down accident safely because former design lacks intrinsic security, its contingency occurrence probability is still 10
-11～10
-5Between/the heap 1 year.So disapproving light water reactor in the nuclear safety rules of many countries (comprising China) build near the densely populated area.Like this, not only cause the nuclear power plant siting difficulty, and be difficult to utilize its waste heat to be manufacturing district and residential block heat supply steam supply, wasted the valuable energy, moreover, because nuclear power plant system complexity, cost are high, can only nationality help strengthen single-machine capacity and reduce unit price, in the hope of can with thermal power station of burning coal or power station competition.At present the economic scale of nuclear power station up to 900,000 kilowatts about, unit cost (present price) reaches about 1,000,000,000 dollars.Therefore, country that middle minor scale power net or financial resources are less or company are difficult to establish, and have influenced applying of nuclear power station.States such as nearest Sweden propose to utilize the improvement project of the intrinsic security of light water reactor, as " safety-type power reactor " (SECURE-P), though this class scheme is significantly improved aspect security, can get rid of core melt down accident safely, but the reactor core and a loop component of whole presurized water reactor all are placed in the big prestress concrete shell, bulky, cost is still suitable with present presurized water reactor, and some key problem in technology such as operation stability are still waiting exploitation, therefore do not solve the above-mentioned contradiction of used in nuclear power station light water reactor fully.
The present invention is directed to the shortcoming of aforementioned light water reactor, propose a kind ofly can utilize its inherent safety, the improvement project that again can simplified structure reduces initial outlay, the characteristics of this scheme are: at first, adopt double-deck pneumatic shell, leave suitable space between the two-layer shell, fill with boron water, pressure in the shell is greater than the working pressure of reactor light water coolant in the inner casing, and the consequence that makes any Vent leakage of reactor one loop all can only be that boron water bleeds a loop and makes it shutdown and the assurance cooling.Reactor core is dehydration never.The external pressure shell adopts the prestress concrete structure, so do not exist housing to break suddenly, boron water can outer in a large number Vent yet.Some bidirectional relief valves are housed in inner casing, lead to the boron hydrospace between two shells, these valves utilize between the inside and outside shell pressure reduction greater than or during not enough certain rated pressure, safety valve freely is opened, and makes the communication of a boron water and a loop; Boron water freely enters inner casing, causes shutdown and guarantees cooling.Therefore, this double-shell structure can guarantee that reactor in no instance core melt down accident can take place, can overcome " safety-type power reactor " again (SECURE-R) does not have the internal layer pneumatic shell in designing, and adopts cellular fluid retention system to separate the understable shortcoming of two kinds of liquid.
Secondly, the light-water reactor reator body that is arranged in inner casing partly adopts (1) integrated presurized water reactor; (2) boiling-water reactor or (3) overcritical presurized water reactor, and do not adopt the separated type of general presurized water reactor to arrange.In these reactors, adopt the hydraulic actuator of control rod, can reduce the reactor body height.So reator body compact conformation of the present invention and simple, it is less to give the stress shell.Initial outlay can reduce, and helps middle-size and small-sizeization, strengthens the competitive position of nuclear power station.
Once more, light water reactor fuel element in the present invention can adopt common rod type element, also can adopt a kind of more advanced silit-RESEARCH OF PYROCARBON multilayer of using to clad the graininess element.Directly contact cooling by light-water.This tiny fuel sphere can load and unload continuously, and reaches dark burnup.Can further improve the security and the economy of light water reactor like this from two aspects: (1) reactor core excess reactivity can reduce to minimum, just charges and also can reduce; (2) can adopt fuel sphere once by reactor core, promptly reach degree of depth burnup after cooling does not add aftertreatment and direct simplification fuel recycle as solid waste disposal.This scheme more helps the popularization of nuclear power station.
Fig. 1 is a double pressure shell boiling-water reactor synoptic diagram.
An example of the present invention as shown in Figure 1.Reator body among the figure adopts common boiling-water reactor 1, jetting pump 2(wherein is housed also can uses Natural Circulation without pump).The stress shell 3 that gives that boron water is equipped with in the reactor outside bears the pressure (being 75 atmospheric pressure in this example) that is higher than boiling-water reactor operating pressure (70 atmospheric pressure), 5 atmospheric pressure differentials are only arranged between the inside and outside shell, so inner casing needn't be too thick.Bidirectional relief valve is housed on the inner casing, and four groups of safety valve 4A are above inner casing, and other four groups of safety valve 4B are below inner casing.When pressure reduction between the inside and outside shell surpasses or during the deficiency definite value, valve opening allows the boron water cycle.This boiling-water reactor leads on the extraneous big or small pipeline multiple stop valve all is housed, and 5A is the main steam pipe stop valve.5B is the feed pipe stop valve, and 5C is a jetting pump water stop valve, and 5D is control transmission stop valve, wherein has one at least for utilizing both sides pressure reduction self-locking, closes automatically when these stop valves all can outer pipeline break, and the water in preventing to pile is Vent outward.These valves are positioned at boron water cavity 6, can prevent that breaking of valve body and valve front-end pipeline from causing dehydration.The maintenance of reactor is carried out with interior giving the stress shell with reloading all, and 7 are the maintenance operation room that reloads.Give and answer pressure vessel to have only the less manhole of diameter 8 to lead to the external world, thereby can avoid the technical difficulty of major diameter end socket and raising to give the security of stress shell.The technology that this reactor adopted is all ripe at present, need not to carry out a large amount of developments.
Fig. 2 is the overcritical presurized water reactor synoptic diagram of double pressure shell.The multilayer cladding granular fuel reactor 1 that heap body among the figure adopts supercritical pressure water directly to cool off, reactor outside are equipped with giving of boron water answers pressure vessel 3 to bear the pressure (this example is 250 atmospheric pressure) of the critical point that is higher than water, and the pressure in the inner casing is low slightly than this.Two groups of bidirectional relief valve 4A and 4B are housed on the inner casing, when both sides pressure reduction greater than or open during not enough rated differential head, allow the boron water cycle.All lead to this supercritical water cold dome on the extraneous big or small pipeline multiple stop valve all are housed, and 5A is outlet water pipe stop valve, and 5B is the feed pipe stop valve, and 5C is control transmission stop valve.These stop valves all are positioned at boron water cavity 2.Its inspection operation chamber is arranged in gives in the stress shell, and these features are all similar to last example.But this kind reactor core structure is more special, used nuclear fuel is the multilayer cladding particle about about 500 μ of diameter, entered by fuel inlet tube 6 and to give the stress shell, enter reactor core 7 after distributing, core structure is that multilayer is flat funneling, the cladding particle enters reactor core by the outside, slowly flowed to the center by funnel then, the fuel outlet 8 by the center flows out outside the inner casing at last, enters fuel cooling tank 9, out-pile is discharged by drainage conduit 10 in the cooling back, as waste storage.Also can carry out the chemical after-treatment reason when worthwhile economically.Chilled water under the supercritical pressure by water inlet pipe 14 through water inlet flow channel 11 from reactor core lateral center flow, the back that is heated enters steam turbine by the pipe core 12 out-pile rising pipe 13 of flowing through.Do not have the two-phase problem in this reactor, need not to be provided with the carbonated drink separation and the steam dryer of boiling-water reactor, so simple in structure, the thermal efficiency is also higher, and economy is better.
This shows that improvement provided by the present invention can significantly improve the security and the economy of light water reactor, helps applying of nuclear power station.
Claims (5)
1, a kind of used in nuclear power station light water reactor of being made up of heap body, moderator and cooling medium and pressure vessel is characterized in that adopting the double pressure shell, and shell is worked under a little more than the light water reactor operating pressure, fills with boron water between inside and outside two-layer shell, and reactor core is loaded within two shells.
2,, it is characterized in that reator body can adopt any among integrated presurized water reactor, boiling-water reactor and the overcritical presurized water reactor by the described light water reactor of claim 1.
3,, it is characterized in that reactor core adopts the cladding fuel particle, is directly cooled off by light-water by claim 1 and 2 described light water reactors.
4,, it is characterized in that described cladding granular fuel is loaded in the flat funneling reactor core of multilayer according to the described light water reactor of claim 3.
5, by claim 1 and 2 described light water reactors, it is characterized in that being equipped with in the inner casing bidirectional relief valve of automatic unlatching, lead to the boron hydrospace.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN198585100182A CN85100182A (en) | 1985-04-01 | 1985-04-01 | Adopt the nuclear power station light water reactor of double pressure shell |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN198585100182A CN85100182A (en) | 1985-04-01 | 1985-04-01 | Adopt the nuclear power station light water reactor of double pressure shell |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN85100182A true CN85100182A (en) | 1986-08-20 |
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Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN198585100182A Pending CN85100182A (en) | 1985-04-01 | 1985-04-01 | Adopt the nuclear power station light water reactor of double pressure shell |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN85100182A (en) |
Cited By (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN1319074C (en) * | 2005-03-18 | 2007-05-30 | 张育曼 | Supercritical water nuclear reactor utilizing sleeve fuel assembly |
| CN103377722A (en) * | 2012-04-27 | 2013-10-30 | 上海核工程研究设计院 | V-shaped reactor external melt retention device used after nuclear power plant accident |
| CN103377723A (en) * | 2012-04-27 | 2013-10-30 | 上海核工程研究设计院 | Type-III out-of-core melt retention device after nuclear power station accidents |
| CN103377721A (en) * | 2012-04-27 | 2013-10-30 | 上海核工程研究设计院 | Type-II out-of-core melt retention device after nuclear power station accidents |
| CN107369479A (en) * | 2017-07-31 | 2017-11-21 | 清华大学天津高端装备研究院 | The passive reactor shut-off system and nuclear reactor based on pressure difference for integrated heap |
| CN107507652A (en) * | 2017-07-31 | 2017-12-22 | 清华大学天津高端装备研究院 | The core structure and nuclear reactor of a kind of integral reactor |
| CN111508623A (en) * | 2020-04-29 | 2020-08-07 | 中国核动力研究设计院 | Overpressure protection device for pressure-bearing containment vessel for ship and application of overpressure protection device |
| WO2021109622A1 (en) * | 2019-12-04 | 2021-06-10 | 上海核工程研究设计院有限公司 | Integrated passive reactor system |
-
1985
- 1985-04-01 CN CN198585100182A patent/CN85100182A/en active Pending
Cited By (13)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN1319074C (en) * | 2005-03-18 | 2007-05-30 | 张育曼 | Supercritical water nuclear reactor utilizing sleeve fuel assembly |
| CN103377722A (en) * | 2012-04-27 | 2013-10-30 | 上海核工程研究设计院 | V-shaped reactor external melt retention device used after nuclear power plant accident |
| CN103377723A (en) * | 2012-04-27 | 2013-10-30 | 上海核工程研究设计院 | Type-III out-of-core melt retention device after nuclear power station accidents |
| CN103377721A (en) * | 2012-04-27 | 2013-10-30 | 上海核工程研究设计院 | Type-II out-of-core melt retention device after nuclear power station accidents |
| CN107369479B (en) * | 2017-07-31 | 2023-08-22 | 清华大学天津高端装备研究院 | Differential pressure-based passive shutdown system for an integrated stack and a nuclear reactor |
| CN107369479A (en) * | 2017-07-31 | 2017-11-21 | 清华大学天津高端装备研究院 | The passive reactor shut-off system and nuclear reactor based on pressure difference for integrated heap |
| CN107507652A (en) * | 2017-07-31 | 2017-12-22 | 清华大学天津高端装备研究院 | The core structure and nuclear reactor of a kind of integral reactor |
| CN107507652B (en) * | 2017-07-31 | 2023-05-23 | 清华大学天津高端装备研究院 | Reactor core structure of integrated reactor and nuclear reactor |
| WO2021109622A1 (en) * | 2019-12-04 | 2021-06-10 | 上海核工程研究设计院有限公司 | Integrated passive reactor system |
| GB2593389A (en) * | 2019-12-04 | 2021-09-22 | Shanghai Nuclear Eng Res & Design Inst Co Ltd | Integrated passive reactor system |
| US11894151B2 (en) | 2019-12-04 | 2024-02-06 | Shanghai Nuclear Engineering Research & Design Institute Co., Ltd. | Integrated reactor system having passive removal of residual heat |
| CN111508623A (en) * | 2020-04-29 | 2020-08-07 | 中国核动力研究设计院 | Overpressure protection device for pressure-bearing containment vessel for ship and application of overpressure protection device |
| CN111508623B (en) * | 2020-04-29 | 2022-07-15 | 中国核动力研究设计院 | Overpressure protection device for pressure-bearing containment vessel for ship and application of overpressure protection device |
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Legal Events
| Date | Code | Title | Description |
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| C06 | Publication | ||
| PB01 | Publication | ||
| CI01 | Correction of invention patent gazette |
Correct: Zhang Zhidong|Luo Wenqun False: Yao Guifen|Luo Wenqun Number: 14 Page: 60 Volume: 2 |
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| C10 | Entry into substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| WD01 | Invention patent application deemed withdrawn after publication | ||
| ERR | Gazette correction |
Free format text: CORRECT FROM: YAO GUIFEN LUO WENQUN TO: ZHANG ZHIDONG LUO WENQUN |