CN204288821U - The experimental provision of water-cooling system working environment in a kind of simple, Fast simulation nuclear reactor - Google Patents
The experimental provision of water-cooling system working environment in a kind of simple, Fast simulation nuclear reactor Download PDFInfo
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- CN204288821U CN204288821U CN201420850951.3U CN201420850951U CN204288821U CN 204288821 U CN204288821 U CN 204288821U CN 201420850951 U CN201420850951 U CN 201420850951U CN 204288821 U CN204288821 U CN 204288821U
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- fused salt
- water pot
- water
- salt heating
- jug
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- 238000001816 cooling Methods 0.000 title claims abstract description 22
- 238000004088 simulation Methods 0.000 title claims abstract description 20
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 110
- 238000010438 heat treatment Methods 0.000 claims abstract description 67
- 150000003839 salts Chemical class 0.000 claims abstract description 59
- 238000009413 insulation Methods 0.000 claims abstract description 8
- 239000012212 insulator Substances 0.000 claims abstract description 4
- FGIUAXJPYTZDNR-UHFFFAOYSA-N potassium nitrate Chemical compound [K+].[O-][N+]([O-])=O FGIUAXJPYTZDNR-UHFFFAOYSA-N 0.000 description 30
- LPXPTNMVRIOKMN-UHFFFAOYSA-M sodium nitrite Chemical compound [Na+].[O-]N=O LPXPTNMVRIOKMN-UHFFFAOYSA-M 0.000 description 30
- 235000010333 potassium nitrate Nutrition 0.000 description 15
- 239000004323 potassium nitrate Substances 0.000 description 15
- 235000010288 sodium nitrite Nutrition 0.000 description 15
- 239000000203 mixture Substances 0.000 description 12
- 239000000463 material Substances 0.000 description 10
- XLYOFNOQVPJJNP-ZSJDYOACSA-N Heavy water Chemical compound [2H]O[2H] XLYOFNOQVPJJNP-ZSJDYOACSA-N 0.000 description 9
- 238000002474 experimental method Methods 0.000 description 6
- 239000002826 coolant Substances 0.000 description 4
- 238000004519 manufacturing process Methods 0.000 description 4
- 238000005516 engineering process Methods 0.000 description 2
- 230000004992 fission Effects 0.000 description 2
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 2
- 229910052770 Uranium Inorganic materials 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 238000009835 boiling Methods 0.000 description 1
- 230000008859 change Effects 0.000 description 1
- 239000012153 distilled water Substances 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 230000006872 improvement Effects 0.000 description 1
- 238000009434 installation Methods 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 238000010248 power generation Methods 0.000 description 1
- 230000008569 process Effects 0.000 description 1
- 230000000630 rising effect Effects 0.000 description 1
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
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- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
In simple, Fast simulation nuclear reactor, an experimental provision for water-cooling system working environment, belongs to nuclear reaction apparatus field.It comprises Molten salt heating system, high temperature pressure table, overcritical water pot and thermometer; Molten salt heating system comprises fused salt heating jug and heating electrode; Heating electrode is laid on the tank base of fused salt heating jug, and the tank body of fused salt heating jug is insulator, and fused salt heating jug tank inner surface is provided with heat insulation layer, and this heat insulation layer is positioned at below heating electrode; The water inlet of overcritical water pot is provided with screw thread, and this screw thread is connected with mechanical seal nut rotation, and the upper surface of overcritical water pot is provided with groove, the top of overcritical water pot is provided with a pressure release orifice, overcritical water pot is arranged in fused salt heating jug, thermometer penetrates fused salt heating jug and is placed in groove, and the data input pin of high temperature pressure table is arranged in overcritical water pot, is filled with fused salt water-bath between fused salt heating jug and overcritical water pot.It is mainly used in nuclear reaction.
Description
Technical field
The invention belongs to nuclear reaction apparatus field.
Background technology
The nuclear reactor of current nuclear energy power generation all over the world about has 440, total installation of generating capacity about 353 m. gigawatt (GW).Heavy water reactor and light-water reactor is mainly comprised as commercial off-the-shelf nuclear reactor.Heavy water reactor is the one of heavy water pressurised water reactor, with natural uranium fuel (U-238) running, and using heavy water (D2O) as cooling medium and moderator.Light-water reactor is the reactor using water and gas-vapor mix as cooling medium and moderator, is a kind of mode of the peaceful utilization of atomic energy.Light-water i.e. general water, compared with heavy water, light-water has cheap strong point, and light-water retardation efficiency is also very high in addition.According to statistics, in 413 nuclear power stations that 1992 run, light water reactor accounts for 64.15%, and installed capacity accounts for 80%, and add that the light water reactor built and produced will account for 80%, installed capacity will account for 90%.Light-water reactor has a main coolant loop (primary Ioops), chilled water can flow through reactor core under more than the high pressure of 15MPa, and take the heat energy of nuclear fission generation out of, then steam generator is flowed into, pass through heat interchange, producing steam at secondary circuit, to promote turbogenerator, is electric power thermal energy.During operating, the water temperature of primary Ioops up to more than 300 DEG C Celsius, and can keep the high pressure of more than 15MPa, in case light-water boiling.Light-water reactor technology is the business fission reactor being the most successfully applied to electrical production now, in current light-water reactor, only has the original nuclear energy of 0.5% to convert useful heat energy to.EU Committee the 5th framework agreement plan Development of New Generation nuclear reactor, the essential object of this novel reaction heap is to improve reactor capacity usage ratio, improve the temperature and pressure that capacity usage ratio must improve chilled water, the temperature of existing reactor coolant water is at about 300 DEG C, pressure is at below 20MPa, and novel reaction heap adopts supercritical water as heat eliminating medium, therefore this reactor is also high energy light-water reactor or supercritical water reaction heap.So-called supercritical water is that finger pressure is greater than 22.1MPa, and temperature is higher than 374 DEG C.This reactor duration of work, water-cooling system pressure is about 25MPa, and temperature is at 400 DEG C.In this case, cooling system can convert more nuclear energy to heat energy, significantly improves the energy utilization efficiency of reactor.But water in the supercritical state, have high dissolving power and corrosive power, therefore, this has higher requirement to the clad material of reactor.The clad material of supercritical water reaction heap is one of principal element limiting reactor real work of future generation, for this reason, just novel for the clad material under supercritical water environment at Devoting Major Efforts To Developing in the world at present.In order to develop, evaluate and examine novel clad material, often need by clad material as in real reactor environment, and supercritical water reaction heap real at present does not also come into operation.Therefore, limit the exploitation of clad material, and the exploitation of clad material be obstructed hinder supercritical water reaction heap really put into production.
Therefore, current each state is all being devoted to develop the equipment of high temperature, water under high pressure of producing, and dissimilar equipment develops, but these equipment are all difficult to reach water is warmed up to 400 DEG C and more than 20MPa.
Utility model content
The present invention is to solve the low problem of existing light-water reactor nuclear energy uses rate, the invention provides the experimental provision of water-cooling system working environment in a kind of simple, Fast simulation nuclear reactor.
An experimental provision for water-cooling system working environment in simple, Fast simulation nuclear reactor, it comprises Molten salt heating system, high temperature pressure table, overcritical water pot and thermometer;
Described Molten salt heating system comprises fused salt heating jug and heating electrode; Described heating electrode is laid on the tank base of fused salt heating jug, and the tank body of fused salt heating jug is insulator, and the inside surface of fused salt heating jug tank body is provided with heat insulation layer, and this heat insulation layer is positioned at the below of heating electrode;
The water inlet of overcritical water pot is provided with screw thread, and this screw thread is connected with mechanical seal nut rotation, and the upper surface of overcritical water pot is provided with groove, and the top of overcritical water pot is provided with a pressure release orifice,
Overcritical water pot is arranged in fused salt heating jug, and thermometer penetrates fused salt heating jug and is placed in groove,
The data input pin of high temperature pressure table is arranged in overcritical water pot,
Fused salt water-bath is filled with between fused salt heating jug and overcritical water pot,
The inner volume of described fused salt heating jug is 6L to 15L, and the inner volume of overcritical water pot is 1L to 5L.
Described heating electrode adopts resistance wire to realize, and the power of resistance wire is 2000W to 3800W, and resistance wire adopts 380V three-phase alternating current as power supply.
The inner volume of fused salt heating jug is 8L to 12L.
The inner volume of described fused salt heating jug is 9L, and the inner volume of overcritical water pot is 4L.
The utility model is in order to improve light-water reactor nuclear energy uses rate, and need the raising improving water-cooling system working pressure and temperature and water-cooling system working temperature and pressure, cause having higher requirement to the clad material of supercritical water reaction heap, in order to develop, evaluate and examine novel clad material, design and develop a kind of energy Fast simulation, the experimental facilities of supercritical water environment.In a kind of simple, Fast simulation nuclear reactor described in the utility model, the experimental provision of water-cooling system working environment makes reactor nuclear energy uses rate improve more than 30%.
The beneficial effect that the present invention brings is,
1, the material needed for device fabrication and parts are simple, buy or cost of manufacture cheap;
2, device makes simple, flexible operation, and temperature and pressure controls simple, and programming rate is fast, and working temperature interval is 150-550 DEG C, pressure controllable: when pressure exceedes certain value, reaches the pressure reducing water in water pot by releasing certain gas;
3, experimentation safety, simulation supercritical water environment temperature and pressure reliability high.
Accompanying drawing explanation
Fig. 1 is the principle schematic of the experiment dress of water-cooling system working environment in a kind of simple, Fast simulation nuclear reactor described in the utility model.
Embodiment
Embodiment one: present embodiment is described see Fig. 1, the experimental provision of water-cooling system working environment in a kind of simple, Fast simulation nuclear reactor described in present embodiment, it comprises Molten salt heating system, high temperature pressure table 3, overcritical water pot 6 and thermometer 2;
Described Molten salt heating system comprises fused salt heating jug 1 and heating electrode 4; Described heating electrode 4 is laid on the tank base of fused salt heating jug 1, and the tank body of fused salt heating jug 1 is insulator, and the inside surface of fused salt heating jug 1 tank body is provided with heat insulation layer, and this heat insulation layer is positioned at the below of heating electrode 4;
The water inlet of overcritical water pot 6 is provided with screw thread, and this screw thread is connected with mechanical seal nut rotation, and the upper surface of overcritical water pot 6 is provided with groove 5, and the top of overcritical water pot 6 is provided with a pressure release orifice 6-1,
Overcritical water pot 6 is arranged in fused salt heating jug 1, and thermometer 2 penetrates fused salt heating jug 1 and is placed in groove 5,
The data input pin of high temperature pressure table 3 is arranged in overcritical water pot 6,
Fused salt water-bath is filled with between fused salt heating jug 1 and overcritical water pot 6,
The inner volume of described fused salt heating jug 1 is 6L to 15L, and the inner volume of overcritical water pot 6 is 1L to 5L.
In present embodiment, described fused salt water-bath adopts the potpourri of sodium nitrite and potassium nitrate to realize.The quality of described sodium nitrite and the potpourri of potassium nitrate is 20kg to 40kg, and the ratio of sodium nitrite and potassium nitrate is 1:1 to 1:5.
Illustrate substantive distinguishing features of the present utility model and marked improvement further below by object lesson, but the utility model structure is not only confined to example below:
Example 1. experimental provision of the present invention, runs under preset experiment condition, and to measure in real time in water pot pressure and temperature over time.In order to examine apparatus of the present invention long serviceability under high temperature, high pressure further, prerequisite is: 450.0 DEG C and 25.0MPa, keeps 15 minutes under this condition.
Various conditional parameter is as follows: resistance wire power: 2000W; Sodium nitrite and mixture of potassium nitrate quality: 20kg; Sodium nitrite and mixture of potassium nitrate mass ratio: 1:1; Fused salt heating jug 1 inner volume 6L, overcritical water pot 6 inner volume 1L; Opening power is after 16 minutes, overcritical water pot 6 temperature is increased to 450 and 25MPa, and overcritical water pot 6 temperature and pressure maintains 450.0 ± 2.0 DEG C and 25.0 ± 0.5MPa all the time in preset 15 minutes, it is fast that this illustrates that this equipment has programming rate, and pressure and temperature can accurately control.
Example 2. experimental provision of the present invention, runs under preset experiment condition, and to measure in real time in water pot pressure and temperature over time.In order to examine apparatus of the present invention long serviceability under high temperature, high pressure further, prerequisite is: 480.0 DEG C and 30.0MPa, keeps 30 minutes under this condition.
Various conditional parameter is as follows: resistance wire power: 2500W; Sodium nitrite and mixture of potassium nitrate quality: 25kg; Sodium nitrite and mixture of potassium nitrate mass ratio: 1:2; Fused salt heating jug 1 inner volume 8L, overcritical water pot 6 inner volume: 1.5L; Opening power is after 22 minutes, overcritical water pot 6 temperature is increased to 480 and 30MPa, and overcritical water pot 6 temperature and pressure maintains 480.0 ± 2.0 DEG C and 30.0 ± 0.6MPa all the time in preset 30 minutes, it is fast that this illustrates that this equipment has programming rate, and pressure and temperature can accurately control.
Example 3. experimental provision of the present invention, runs under preset experiment condition, and to measure in real time in water pot pressure and temperature over time.In order to examine apparatus of the present invention long serviceability under high temperature, high pressure further, prerequisite is: 500.0 DEG C and 35.0MPa, keeps 40 minutes under this condition.
Various conditional parameter is as follows: resistance wire power: 3500W; Sodium nitrite and mixture of potassium nitrate quality: 30kg; Sodium nitrite and mixture of potassium nitrate mass ratio: 1:3; Fused salt heating jug 1 inner volume 10L, overcritical water pot 6 inner volume: 2.5L; Opening power is after 31 minutes, overcritical water pot 6 temperature is increased to 500 and 35MPa, and overcritical water pot 6 temperature and pressure maintains 500.0 ± 1.5 DEG C and 35.0 ± 0.5MPa all the time in preset 30 minutes, it is fast that this illustrates that this equipment has programming rate, and pressure and temperature can accurately control.
Example 4. experimental provision of the present invention, runs under preset experiment condition, and to measure in real time in water pot pressure and temperature over time.In order to examine apparatus of the present invention long serviceability under high temperature, high pressure further, prerequisite is: 520.0 DEG C and 40.0MPa, keeps 50 minutes under this condition.
Various conditional parameter is as follows: resistance wire power: 3500W; Sodium nitrite and mixture of potassium nitrate quality: 35kg; Sodium nitrite and mixture of potassium nitrate mass ratio: 1:4; Fused salt heating jug 1 inner volume 12L, overcritical water pot 6 inner volume 4L; Opening power is after 40 minutes, overcritical water pot 6 temperature is increased to 520 and 40MPa, and overcritical water pot 6 temperature and pressure maintains 520.0 ± 1.2 DEG C and 40.0 ± 0.4MPa all the time in preset 50 minutes, it is fast that this illustrates that this equipment has programming rate, and pressure and temperature can accurately control.
Example 5. experimental provision of the present invention, runs under preset experiment condition, and to measure in real time in water pot pressure and temperature over time.In order to examine apparatus of the present invention long serviceability under high temperature, high pressure further, prerequisite is: 540.0 DEG C and 48.0MPa, keeps 60 minutes under this condition.
Various conditional parameter is as follows: resistance wire power: 3800W; Sodium nitrite and mixture of potassium nitrate quality: 40kg; Sodium nitrite and mixture of potassium nitrate mass ratio: 1:5; Fused salt heating jug 1 inner volume 15L, overcritical water pot 6 inner volume: 5L; Opening power is after 48 minutes, overcritical water pot 6 temperature is increased to 540 and 48MPa, and overcritical water pot 6 temperature and pressure maintains 540.0 ± 1.0 DEG C and 48.0 ± 0.3MPa all the time in preset 60 minutes, this illustrates the increase of this equipment along with fused salt quality, programming rate reduces, but the accuracy of temperature increases, along with the quality of water in water pot increases, the accuracy of pressure increases.
As can be seen from above-mentioned several embodiment: the present invention can realize fast coolant-temperature gage in water pot more than 450 DEG C, pressure is more than 25MPa, and it is fast that this equipment has programming rate, and pressure and temperature can accurately control, this equipment is along with the increase of fused salt quality, programming rate reduces, but the accuracy of temperature increases, along with the quality of water in water pot increases, the accuracy of pressure increases.These advantages are enough to enable this equipment in nuclear industry design or obtain practical application in for nuclear reactor Applied experimental study.
Embodiment two: in a kind of simple, the Fast simulation nuclear reactor described in present embodiment and embodiment one, the difference of the experimental provision of water-cooling system working environment is, described heating electrode 4 adopts resistance wire to realize, the power of resistance wire is 2000W to 3800W, and resistance wire adopts 380V three-phase alternating current as power supply.
Embodiment three: in a kind of simple, the Fast simulation nuclear reactor described in present embodiment and embodiment two, the difference of the experimental provision of water-cooling system working environment is, the inner volume of fused salt heating jug 1 is 8L to 12L.
Present embodiment, by resistance wire, sodium nitrite and mixture of potassium nitrate are heated, make sodium nitrite and potassium nitrate fusing, and temperature stable rising gradually, free control temperature change in 150-550 DEG C of temperature range, then by fused salt heating supercritical water tank 6, overcritical water pot 6 temperature is freely controlled in 150-550 DEG C of temperature range.A certain amount of distilled water is added in overcritical water pot 6, varying with temperature in process, the pressure of the water in water pot raises gradually, realize temperature at 374-550 DEG C and pressure consecutive variations in 22.1-50MPa, when pressure exceedes preset value, automatically discharge certain water by pressure release orifice and pressure in water pot is reduced.
Embodiment four: in a kind of simple, the Fast simulation nuclear reactor described in present embodiment and embodiment three, the difference of the experimental provision of water-cooling system working environment is, the inner volume of described overcritical water pot 6 is 3L to 4.5L.
Embodiment five: in a kind of simple, the Fast simulation nuclear reactor described in present embodiment and embodiment four, the difference of the experimental provision of water-cooling system working environment is, the inner volume of described fused salt heating jug 1 is 9L, and the inner volume of overcritical water pot 6 is 4L.
In present embodiment, the inner volume of described fused salt heating jug 1 is 9L, the optimum value of the experimental provision of water-cooling system working environment in the inner volume of overcritical water pot 6 to be 4L be a kind of simple, Fast simulation nuclear reactor described in the utility model.
Claims (5)
1. the experimental provision of water-cooling system working environment in simple, Fast simulation nuclear reactor, it is characterized in that, it comprises Molten salt heating system, high temperature pressure table (3), overcritical water pot (6) and thermometer (2);
Described Molten salt heating system comprises fused salt heating jug (1) and heating electrode (4); Described heating electrode (4) is laid on the tank base of fused salt heating jug (1), the tank body of fused salt heating jug (1) is insulator, the inside surface of fused salt heating jug (1) tank body is provided with heat insulation layer, and this heat insulation layer is positioned at the below of heating electrode (4);
The water inlet of overcritical water pot (6) is provided with screw thread, and this screw thread is connected with mechanical seal nut rotation, and the upper surface of overcritical water pot (6) is provided with groove (5), the top of overcritical water pot (6) is provided with a pressure release orifice (6-1)
Overcritical water pot (6) is arranged in fused salt heating jug (1), and thermometer (2) penetrates fused salt heating jug (1) and is placed in groove (5),
The data input pin of high temperature pressure table (3) is arranged in overcritical water pot (6),
Fused salt water-bath is filled with between fused salt heating jug (1) and overcritical water pot (6),
The inner volume of described fused salt heating jug (1) is 6L to 15L, and the inner volume of overcritical water pot (6) is 1L to 5L.
2. the experimental provision of water-cooling system working environment in a kind of simple, Fast simulation nuclear reactor according to claim 1, it is characterized in that, described heating electrode (4) adopts resistance wire to realize, the power of resistance wire is 2000W to 3800W, and resistance wire adopts 380V three-phase alternating current as power supply.
3. the experimental provision of water-cooling system working environment in a kind of simple, Fast simulation nuclear reactor according to claim 2, it is characterized in that, the inner volume of fused salt heating jug (1) is 8L to 12L.
4. the experimental provision of water-cooling system working environment in a kind of simple, Fast simulation nuclear reactor according to claim 3, it is characterized in that, the inner volume of described overcritical water pot (6) is 3L to 4.5L.
5. the experimental provision of water-cooling system working environment in a kind of simple, Fast simulation nuclear reactor according to claim 4, it is characterized in that, the inner volume of described fused salt heating jug (1) is 9L, and the inner volume of overcritical water pot (6) is 4L.
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN108511088A (en) * | 2018-06-13 | 2018-09-07 | 中国科学院上海应用物理研究所 | Deuterium oxide moderated molten salt reactor reactor core and deuterium oxide moderated fused salt shut-down system |
| CN113740373A (en) * | 2020-05-28 | 2021-12-03 | 应急管理部化学品登记中心 | Test device for determining whether oily substances belong to bulk persistent oils |
-
2014
- 2014-12-29 CN CN201420850951.3U patent/CN204288821U/en not_active Expired - Fee Related
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN108511088A (en) * | 2018-06-13 | 2018-09-07 | 中国科学院上海应用物理研究所 | Deuterium oxide moderated molten salt reactor reactor core and deuterium oxide moderated fused salt shut-down system |
| CN108511088B (en) * | 2018-06-13 | 2023-07-28 | 中国科学院上海应用物理研究所 | Heavy water moderated molten salt reactor core and heavy water moderated molten salt reactor system |
| CN113740373A (en) * | 2020-05-28 | 2021-12-03 | 应急管理部化学品登记中心 | Test device for determining whether oily substances belong to bulk persistent oils |
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Granted publication date: 20150422 |