CN1992094A - High power 'water boiler' solution nuclear reactor gas loop - Google Patents
High power 'water boiler' solution nuclear reactor gas loop Download PDFInfo
- Publication number
- CN1992094A CN1992094A CNA2005101352691A CN200510135269A CN1992094A CN 1992094 A CN1992094 A CN 1992094A CN A2005101352691 A CNA2005101352691 A CN A2005101352691A CN 200510135269 A CN200510135269 A CN 200510135269A CN 1992094 A CN1992094 A CN 1992094A
- Authority
- CN
- China
- Prior art keywords
- gas
- water
- nuclear reactor
- high power
- air circuit
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Granted
Links
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title claims abstract description 68
- 239000007789 gas Substances 0.000 claims abstract description 36
- 239000007921 spray Substances 0.000 claims abstract description 15
- 125000004122 cyclic group Chemical group 0.000 claims description 13
- 239000001301 oxygen Substances 0.000 claims description 12
- 229910052760 oxygen Inorganic materials 0.000 claims description 12
- ZCYVEMRRCGMTRW-UHFFFAOYSA-N 7553-56-2 Chemical compound [I] ZCYVEMRRCGMTRW-UHFFFAOYSA-N 0.000 claims description 8
- 229910052740 iodine Inorganic materials 0.000 claims description 8
- 239000011630 iodine Substances 0.000 claims description 8
- GRYLNZFGIOXLOG-UHFFFAOYSA-N Nitric acid Chemical compound O[N+]([O-])=O GRYLNZFGIOXLOG-UHFFFAOYSA-N 0.000 claims description 5
- 229910017604 nitric acid Inorganic materials 0.000 claims description 5
- 210000000952 spleen Anatomy 0.000 claims description 5
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 claims description 4
- 229910000831 Steel Inorganic materials 0.000 claims description 2
- 239000003463 adsorbent Substances 0.000 claims description 2
- 239000010959 steel Substances 0.000 claims description 2
- 239000001257 hydrogen Substances 0.000 abstract description 3
- 229910052739 hydrogen Inorganic materials 0.000 abstract description 3
- 239000000203 mixture Substances 0.000 abstract description 2
- 238000005507 spraying Methods 0.000 abstract description 2
- 239000011148 porous material Substances 0.000 abstract 1
- XLYOFNOQVPJJNP-ZSJDYOACSA-N Heavy water Chemical compound [2H]O[2H] XLYOFNOQVPJJNP-ZSJDYOACSA-N 0.000 description 12
- 239000000243 solution Substances 0.000 description 12
- HEMHJVSKTPXQMS-UHFFFAOYSA-M Sodium hydroxide Chemical compound [OH-].[Na+] HEMHJVSKTPXQMS-UHFFFAOYSA-M 0.000 description 6
- BASFCYQUMIYNBI-UHFFFAOYSA-N platinum Substances [Pt] BASFCYQUMIYNBI-UHFFFAOYSA-N 0.000 description 4
- 238000000926 separation method Methods 0.000 description 4
- 239000007864 aqueous solution Substances 0.000 description 3
- 238000006243 chemical reaction Methods 0.000 description 3
- 150000001875 compounds Chemical class 0.000 description 3
- 238000001816 cooling Methods 0.000 description 3
- 230000004992 fission Effects 0.000 description 3
- 239000001307 helium Substances 0.000 description 3
- 229910052734 helium Inorganic materials 0.000 description 3
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 description 3
- 241000156978 Erebia Species 0.000 description 2
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 description 2
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 description 2
- 230000003197 catalytic effect Effects 0.000 description 2
- 238000009833 condensation Methods 0.000 description 2
- 230000005494 condensation Effects 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 239000012634 fragment Substances 0.000 description 2
- 230000005484 gravity Effects 0.000 description 2
- 239000007788 liquid Substances 0.000 description 2
- 229910052697 platinum Inorganic materials 0.000 description 2
- 230000001172 regenerating effect Effects 0.000 description 2
- 238000007789 sealing Methods 0.000 description 2
- MYMOFIZGZYHOMD-UHFFFAOYSA-N Dioxygen Chemical compound O=O MYMOFIZGZYHOMD-UHFFFAOYSA-N 0.000 description 1
- 150000001224 Uranium Chemical class 0.000 description 1
- 229910052770 Uranium Inorganic materials 0.000 description 1
- 230000001133 acceleration Effects 0.000 description 1
- 238000006555 catalytic reaction Methods 0.000 description 1
- 239000002131 composite material Substances 0.000 description 1
- 230000008602 contraction Effects 0.000 description 1
- 239000002826 coolant Substances 0.000 description 1
- 239000000498 cooling water Substances 0.000 description 1
- 238000000354 decomposition reaction Methods 0.000 description 1
- 229910001882 dioxygen Inorganic materials 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 238000002347 injection Methods 0.000 description 1
- 239000007924 injection Substances 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- YPJKMVATUPSWOH-UHFFFAOYSA-N nitrooxidanyl Chemical compound [O][N+]([O-])=O YPJKMVATUPSWOH-UHFFFAOYSA-N 0.000 description 1
- 238000007747 plating Methods 0.000 description 1
- 229910052573 porcelain Inorganic materials 0.000 description 1
- 230000003134 recirculating effect Effects 0.000 description 1
- 230000006798 recombination Effects 0.000 description 1
- 238000005215 recombination Methods 0.000 description 1
- 238000005245 sintering Methods 0.000 description 1
- 239000012086 standard solution Substances 0.000 description 1
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 1
- 125000005289 uranyl group Chemical group 0.000 description 1
Images
Classifications
-
- 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
Landscapes
- Gas Separation By Absorption (AREA)
- Preventing Corrosion Or Incrustation Of Metals (AREA)
Abstract
The invention belongs to the field of solution reactors, and particularly relates to an optimized design of a gas loop of a high-power 'water boiler' solution reactor. The gas loop comprises a circulating pipeline communicated with the stack body, a flow pore plate, an electric heater and an oxygen-hydrogen recombiner are sequentially arranged on the pipeline, a sprayer for providing power for gas circulation is arranged on the circulating pipeline, and a circulating water tank and a fully-sealed water pump for providing a lift for spraying water are connected below the sprayer. The invention changes the cooler on the traditional solution nuclear reactor gas loop into a spray thrower, utilizes the mixture of spray water and high-temperature gas to cool the gas, utilizes the spray thrower to carry out forced circulation on the gas in normal operation, and has certain natural circulation capability when the external power supply is powered off.
Description
Technical field
The invention belongs to solution reaction heap field, be specially a kind of optimal design of air circuit of high power water boiler solution nuclear reactor.
Background technology
Medical-isotope production heap (MIPR) is " homogeneous solution-type reactor " type nuclear reactor.Because adopt the uranium salt aqueous solution to act as a fuel, uranium fission takes place in solution, its fission fragment has very high kinetic energy, and fission fragment bombardment water makes hydrone be decomposed into hydrogen and oxygen.Its hydrogen-oxygen generation of the MIPR of 200kW is about 1.5L/s, and its output is very large, and 70～80 ℃ down its reversed reactions compound quantity seldom, it is compound to take this part hydrogen or oxygen gas out of out-pile catalysis by gas carrier.
Beijing 7MW of atomic energy institute heavy water reactor selects heavy water to make moderator and cooling medium.Design heavy water decomposition rate under strong gamma-rays effect is 0.41L/kWh, utilizes helium to cover the gas carrier of heap heavy water upper strata as hydrogen-oxygen, helium gas flow 166HM
3/ h.Air circuit is two branch roads in parallel, a job, and one is standby.Draw gas through condenser from heap, the heavy water condensation separation that the straight line separation vessel carries helium enters heavy water and stores little cylinder.Then, gas is divided into two loops, and there are contact chamber, porcelain filtrator, condenser and fan blower in every loop.
Russia " Argus " heap is UO
2(SO
4) the aqueous solution homogeneous reactor, heap power 20kW, its hydrogen-oxygen compound system is a natural recirculating type.Its principle of work is that hydrogeneous, carrier of oxygen is synthetic with hydrogen-oxygen through catalytic bed again by heating, because synthetic is themopositive reaction, gas is further heated up, heated gas rises to the condensation of refrigeratory place, and cold and hot end gas density is poor, to quicken be the power source of gas circulation to the gravity of contraction of gas and water droplet.Its natural circulation mode can expand heap power 50kW to, and more high power has just been had any problem.
Japan's JRR-1 heap is that the 50kW standard solution that the U.S. manufactures and designs one of is piled.Feed liquid is UO
2(SO
4) solution, its hydrogen-oxygen compound system is to be the forced circulation of power with the jetting pump.Its principle of work is the water that the gas recombination water tank is equipped with 1/2 height, and a refrigeratory is arranged below, and cooled water is squeezed in the water vapor injection device by water pump, and the negative pressure that thrower produces the 49.5cm water column drives gas flow.Spray and use pump head 0.28MPa, flow 5.76m
3/ h has multistage gas-water separation before entering multiple-hearth.
As from the foregoing, remove all the other each heap types of " Argus " out-pile and all do not have natural-circulation capacity, more do not have the forced circulation air circuit of natural-circulation capacity concurrently.
Summary of the invention
The purpose of this invention is to provide and a kind ofly when normal operation, utilize power source that gas is carried out forced circulation, have the solution nuclear reactor hydrogen-oxygen composite gas loop of certain natural-circulation capacity outside during power cut-off at short notice again.
Technical scheme of the present invention is: air circuit of high power water boiler solution nuclear reactor comprises a circulating line that is communicated with the heap body, be provided with flow-through orifice, electric heater, hydrogen-oxygen recombiner on the pipeline successively, be provided with the spray thrower that power is provided for gas circulation on circulating line, the spray thrower below connects cyclic water tank and the hermetically sealed water pump of lift is provided for shower water.
Aforesaid power " homogeneous solution-type reactor " solution nuclear reactor air circuit wherein, also is provided with to remove on heap is worked off one's feeling vent one's spleen return and drips device and moisture trap.
Aforesaid power " homogeneous solution-type reactor " solution nuclear reactor air circuit, wherein, the rear end of moisture trap also is provided with except that the iodine device on heap is worked off one's feeling vent one's spleen return.
The present invention changes the refrigeratory on traditional solution nuclear reactor air circuit into spray thrower, utilizing shower water to mix to gas with high-temperature gas lowers the temperature, when normal operation, utilize spray thrower that gas is carried out forced circulation, certain natural-circulation capacity is arranged again during power cut-off outside.In addition, in heap is worked off one's feeling vent one's spleen the loop, increased to remove and dripped device and moisture trap, brought air circuit into to avoid uranyl nitrtate liquid and excessive water droplet
Description of drawings
Fig. 1 is the structural representation of solution nuclear reactor air circuit.
Fig. 2 is for removing iodine device structural representation.
Among the figure, 1. heap body 2. removes and drips device 3. cooling water jeckets 4. flow-through orifices 5. moisture traps 6. except that iodine device 7. electric heaters 8. hydrogen-oxygen recombiners 9. spray throwers 10. cyclic water tanks 11. decontaminating columns 12. water pumps 13. non-return valve 14. electromagnetic flowmeters 15. cooling tubes
Embodiment
Be example with a heap power 200kW solution-type nuclear reactor air circuit below, the present invention is described in further detail.
As shown in Figure 1, solution-type nuclear reactor air circuit comprises a circulating line that is communicated with the heap body, is provided with successively on circulating line and removes a device 2, flow-through orifice 4, moisture trap 5, removes iodine device 6, electric heater 7, hydrogen-oxygen recombiner 8, spray thrower 9, cyclic water tank 10.Wherein, flow-through orifice 4, remove to drip a device 2, moisture trap 5 and electric heater 7 and be known conventional structure form.
Remove iodine device 2 and be equivalent to a ball valve, install activated carbon adsorbent additional in the ball passage, acticarbon is being wrapped by stainless (steel) wire, avoids acticarbon to take other parts of air circuit to.Ball valve is a four-way valve, passes through for normal operation gas in the horizontal direction.Vertical direction is that the iodine duty is extracted in shutdown, soaks certain hour by adding NaOH, discharges from the bottom again.For avoiding NaOH solution to enter air circuit, in fact the twice isolating seal is arranged, whether the gas that can add high pressure between the sealing of two roads lost efficacy with the supervision sealing.
The structure of hydrogen-oxygen recombiner 8 belongs to prior art, is made up of multiple-hearth and regenerative gas-to-gas heat exchanger.Multiple-hearth is by two porous Al
2O
3The sintering cake is formed, Al
2O
3Platinum plating in the hole relies on the sizable platinum of surface area to play catalytic action.Regenerative heat exchanger is to have the strong plate type finned heat exchanger of the little exchange capability of heat of volume.
Main improvement of the present invention is that the refrigeratory that Natural Circulation is used should be to provide lift with a hermetically sealed water pump 12 by spray thrower 9, and shower water flow velocity is on request sprayed.Utilizing shower water to form negative pressure makes gas form circulation, utilizing shower water to mix with high-temperature gas lowers the temperature to gas,--water heat exchange (being finished by cyclic water tank 10) is cooled off shower water, and this has just the cancelled gas--water-to-water heat exchanger of using chilled water through water is again realized the cooling to high-temperature gas.The characteristics of spray thrower are that requirement has parallel current, avoid spraying to tube wall consuming energy.The foundation of gas negative pressure mainly is the initial velocity by current under the current high flow rate, and under low flow velocity, the acceleration of gravity of current also plays a part suitable.
Cyclic water tank 10 (hold concurrently moisture trap and shower water refrigerating function) has the not direct directive water surface of suitable kinetic energy when the high speed air-water mixture enters cyclic water tank, with the minimizing water level fluctuation.The gas that baffling makes progress also can have suitable water droplet should carry out gas-water separation.The following spatial placement cooling of cistern water level hosepipe is to cool off shower water.Run-down pipe is housed in cyclic water tank, and when cistern water level was high, water injected in the heap from run-down pipe, decontaminating column 11.In order to guarantee to keep certain height of water level in the wasteway, the pipeline behind decontaminating column 11 forms an inverted U pipe, and inverted U pipe highest point is suitable with the run-down pipe intermediate altitude.Utilize inverted U pipe water seal effect to avoid gas from the run-down pipe short circuit.Add a certain amount of nitric acid in the recirculated water of cyclic water tank, enter water tank by the compound water of hydrogen-oxygen, make to contain nitric acid aqueous solution and mend into reactor core, decompose the feed acidity that causes and reduce to remedy nitrate radical, the concentration of nitric acid maintains 1mol/L in the cyclic water tank.
The air circuit horizontal tube is advisable with the high 5～8m in top, selects between pipe diameter Φ 100～Φ 140, depends primarily on the available lift of SR and spray thrower.
Claims (5)
1. air circuit of high power water boiler solution nuclear reactor, comprise a circulating line that is communicated with the heap body, be provided with flow-through orifice, electric heater, hydrogen-oxygen recombiner on the pipeline successively, it is characterized in that: be provided with the spray thrower that power is provided for gas circulation on circulating line, the spray thrower below connects cyclic water tank and the hermetically sealed water pump of lift is provided for shower water.
2. air circuit of high power water boiler solution nuclear reactor as claimed in claim 1 is characterized in that: also be provided with to remove on heap is worked off one's feeling vent one's spleen return and drip device and moisture trap.
3. air circuit of high power water boiler solution nuclear reactor as claimed in claim 2, it is characterized in that: the rear end of moisture trap also is provided with except that the iodine device on heap is worked off one's feeling vent one's spleen return, removing the iodine device is a four-way valve, install activated carbon adsorbent additional in the ball passage, acticarbon is wrapped up by stainless (steel) wire.
4. as claim 1 or 2 or 3 described air circuit of high power water boiler solution nuclear reactor, it is characterized in that: run-down pipe is housed in cyclic water tank, and run-down pipe is connected in the heap by pipeline, and pipeline is provided with decontaminating column.
5. air circuit of high power water boiler solution nuclear reactor as claimed in claim 4 is characterized in that: add nitric acid in the recirculated water of cyclic water tank, make that the concentration of nitric acid maintains 1mol/L in the cyclic water tank.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CNB2005101352691A CN100481270C (en) | 2005-12-29 | 2005-12-29 | High power water boiler type solution nuclear reactor gas loop |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CNB2005101352691A CN100481270C (en) | 2005-12-29 | 2005-12-29 | High power water boiler type solution nuclear reactor gas loop |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN1992094A true CN1992094A (en) | 2007-07-04 |
| CN100481270C CN100481270C (en) | 2009-04-22 |
Family
ID=38214269
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CNB2005101352691A Active CN100481270C (en) | 2005-12-29 | 2005-12-29 | High power water boiler type solution nuclear reactor gas loop |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN100481270C (en) |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN101471149B (en) * | 2007-12-29 | 2011-05-04 | 中国核动力研究设计院 | Uniform water solution nuclear reactor nitrogen conversion and feed liquid automatic acid-adding system and method |
| CN102831946A (en) * | 2011-06-15 | 2012-12-19 | 中国核动力研究设计院 | Medical isotope production reactor capable of reducing reactor core uranium inventory |
| CN106448753A (en) * | 2016-10-18 | 2017-02-22 | 中国核动力研究设计院 | Method for solving water boiler solution nuclear reactor power fluctuation under high power |
Family Cites Families (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0617430B1 (en) * | 1993-03-24 | 1997-12-29 | Kazuo Furukawa | Plutonium annihilating nuclear reactor with use of liquid nuclear fuel |
-
2005
- 2005-12-29 CN CNB2005101352691A patent/CN100481270C/en active Active
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN101471149B (en) * | 2007-12-29 | 2011-05-04 | 中国核动力研究设计院 | Uniform water solution nuclear reactor nitrogen conversion and feed liquid automatic acid-adding system and method |
| CN102831946A (en) * | 2011-06-15 | 2012-12-19 | 中国核动力研究设计院 | Medical isotope production reactor capable of reducing reactor core uranium inventory |
| CN102831946B (en) * | 2011-06-15 | 2015-03-11 | 中国核动力研究设计院 | Medical isotope production reactor capable of reducing reactor core uranium inventory |
| CN106448753A (en) * | 2016-10-18 | 2017-02-22 | 中国核动力研究设计院 | Method for solving water boiler solution nuclear reactor power fluctuation under high power |
Also Published As
| Publication number | Publication date |
|---|---|
| CN100481270C (en) | 2009-04-22 |
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| C14 | Grant of patent or utility model | ||
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