CN104008785B - A kind of metal mold spentnuclear fuel after-treatment device - Google Patents
A kind of metal mold spentnuclear fuel after-treatment device Download PDFInfo
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- CN104008785B CN104008785B CN201410263418.1A CN201410263418A CN104008785B CN 104008785 B CN104008785 B CN 104008785B CN 201410263418 A CN201410263418 A CN 201410263418A CN 104008785 B CN104008785 B CN 104008785B
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- insulation layer
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Abstract
The invention provides a kind of metal mold spentnuclear fuel after-treatment device, described device includes that sensing heating part, cooling changeover portion and fission product collects part three part, and each several part seam uses Flange joint.Described sensing heating part is double-decker, and outer layer furnace shell is made up of double-layer stainless steel water collar, and internal layer burner hearth is high purity graphite pipe, surface of burner hearth coiling copper pipe induction coil, and bottom arranges liftable workbench, is lifted by external motor drive operational platform.Described cooling changeover portion is made up of three sections of independent water collars.Fission product in the present invention is collected partial interior and is set to ledge structure, and outer layer is provided with heat-insulation layer.The after-treatment device of the present invention, it is possible to realize radioactive sample carried out high-temperature heat treatment, and the fission product produced is collected, the sealing of device can be ensured simultaneously under the high temperature conditions, it is to avoid radioactive substance is to external diffusion.
Description
Technical field
The invention belongs to spentnuclear fuel after-treatment device field, be specifically related to a kind of metal mold spentnuclear fuel after-treatment device, especially
It relates in the circulation of a kind of hybrid reactor fission fuel fission gas and volatile fission product removal efficiency in metal mold spentnuclear fuel
Annealing device.
Background technology
At present, Calculation and Study shows, the neutronics characteristic that energy mix system is excellent can maintain nuclear fuel in 300 years all
There is good nuclearity energy, but due to the accumulation of fission gas He other various fission products, the void swelling problem of fuel, mechanics
Hydraulic performance decline, heat transfer property etc. cannot meet use requirement, need post processing, add natural uranium or thorium is made fuel and returned reaction
Heap, it is achieved fuel closed circulation, improves resource utilization.Therefore, fuel post processing is that the circulation of energy mix system fuel is with secondary
Critical covering conceptual approach needs the key issue solved.
The fission fuel post processing of fusion-fission energy mix system is different from conventional spentnuclear fuel post processing, it is not necessary to
The separation of the fissioners such as U, Pu, Th, it is not required that the highest fission product decontamination factor, to split except fission gas and volatility
Selling of one's property thing is target, on the basis of keeping nuclear fuel mechanical property, improves the nuclearity energy preparing fuel more as far as possible.According to Ke, Xe
Deng fission gas thermal diffusion in solids and dissolution characteristics, propose " easy dry method post processing " concept, use high-temperature vacuum skill
Art, reaches to remove the purpose of fission gas, and removes volatile fission product as far as possible.
Can " easy dry method post processing " be a technical strategies, reach to completely remove fission gas, to volatility
The removal efficiency of fission product is how, after process material can meet the technology of preparation of fuel and performance requirement, processing method can
The problem such as row and economic feasibility needs systematic study.Therefore, " easy dry method post processing " technical feasibility analysis is to maintain
Subcritical covering fuel material performance, improve caryogram energy, embody fusion-fission energy mix system overall technology advanced and excellent
More one of most important technology carrier of property, is the key technology that must solve of fission covering conceptual design." locate after easy dry method
Reason " core of technical research just carries out high-temperature heat treatment to sample, fissions removing the fission gas in spentnuclear fuel and volatility
Product.In order to improve the fission gas in sample and volatile fission product removal efficiency as far as possible, it is necessary to carry as much as possible
The heat treatment temperature of high sample, sample also has radioactivity simultaneously, it is necessary to assure sample carries out heat treatment in closed environment, because of
This proposes the highest requirement to annealing device, yet there are no report and can fully meet fission product removal effect in spentnuclear fuel
The annealing device that rate research requires.
Summary of the invention
The purpose of the present invention, is to provide a kind of metal mold spentnuclear fuel after-treatment device, and assembly of the invention can be used for mixing
Metal mold spentnuclear fuel in heap conceptual design carries out post processing, to the fission gas produced in spentnuclear fuel and volatile fission product
Efficiency of going study, can be that the key technology that must solve of covering conceptual design of fissioning in hybrid reactor provides solution route.
Apply also for the fission gas in the metal mold spentnuclear fuel that other heap-type produces and volatile fission product removal efficiency simultaneously
Research.
The technical scheme is that
The metal mold spentnuclear fuel after-treatment device of the present invention, is characterized in, described device is followed successively by from lower to upper and includes
Sensing heating part, cooling changeover portion and fission product collect part.Described sensing heating part is set to furnace shell and stove
The double-decker of thorax, containing spherical furnace shell, the burner hearth of tubular that is arranged in furnace shell, is arranged on the heat-insulation layer that burner hearth is peripheral
Ⅱ.Described cooling changeover portion contains heat-insulation layer III, water collar.Described fission product collects part containing heat-insulation layer I, aerofluxus
Mouth, temperature detection the installation of TC mouth.Its annexation is, described sensing heating part, cooling changeover portion and fission product
Collect part each several part seam and pass through Flange joint respectively.Described furnace shell is made up of Double water-cooled set, and the one side of furnace shell divides
Not being provided with vaccum exhaust outlet, electrode outlet, the top of furnace shell is respectively arranged with the installing port of thermocouple, infrared rays survey
Mouthful, electrode is drawn by side electrode outlet.Described burner hearth is arranged on the central shaft in furnace shell, and lower furnace portion is by insulation
Layer II is fixed in furnace shell, and the surface of heat-insulation layer II is wound with induction coil, and the freeze profile that induction coil is corresponding becomes in high temperature
Frequently bringing-up section, high temperature cooling changeover portion is formed at the top of high temperature heating in medium frequency section.The bottom of furnace shell is provided with liftable work
Platform, is lifted by external motor drive operational platform.The bottom of workbench, bottom are respectively arranged with burner hearth air inlet, ray detection
Mouthful.The surface of burner hearth being positioned at furnace shell upper port is provided with heat-insulation layer III, and the periphery of heat-insulation layer III is provided with water collar, the shell of water collar
It is connected with furnace shell by flange, forms cooling changeover portion.Burner hearth periphery in fission product collection part is provided with heat-insulation layer I,
One end of heat-insulation layer I is connected by the heat-insulation layer III of flange with cooling changeover portion, and the other end is bound by flange.At fission product
The top of collection part, top are respectively arranged with the thermocouple port of air vent, temperature detection.Described furnace shell is fixed on operation
On platform.Described sensing heating part, cooling changeover portion and fission product are collected part and are arranged for concentric.
Described furnace shell and burner hearth are respectively arranged with independent air inlet, and furnace shell is provided with furnace shell air inlet, and burner hearth is arranged
There is burner hearth air inlet, can respectively throughput be controlled.
Water collar in described cooling changeover portion is set to three sections, and three sections of water collars all can independently carry out into water control
System, is used for combining adjustment fission product collecting region temperature.
Described fission product is collected partial interior and is provided with the T-shaped step for filter material, and ledge structure is used for filtering material
Install.
Described burner hearth material is high purity graphite pipe, the graphite heat-insulation layer of graphite-pipe outer wrapping zirconia refractory.
The material of three sections of independent water collars on described heat-insulation layer III surface uses 316L rustless steel.
The invention has the beneficial effects as follows and can realize radioactive sample is carried out high-temperature heat treatment, utilize fission product collecting region
High efficiency particulate air filter, and fission product is collected, and is used for determining its removal efficiency, can ensure device under the high temperature conditions simultaneously
Sealing, it is to avoid radioactive substance is to external diffusion.
Accompanying drawing explanation
Fig. 1 is the structural representation of the metal mold spentnuclear fuel after-treatment device of the present invention；
In figure: 1. thermocouple I 2. fission product collects part 3. heat-insulation layer I 4. cooling changeover portion 5. insulating barrier 6.
High temperature cooling changeover portion 7. thermocouple II 8. sensing heating part 9. induction coil 10. high temperature heating in medium frequency section 11. electrode
Outlet 12. lifts sample stage 13. operating platform 14. gamma-rays detection mouth 15. burner hearth air inlet 16. furnace shell air inlet
17. heat-insulation layer II 18. vaccum exhaust outlet 19. furnace shell 20. infrared rays survey mouth 21. water collar 22. heat-insulation layer III 23. rows
QI KOU.
Detailed description of the invention
The present invention is described in detail below in conjunction with the accompanying drawings.
Embodiment 1.
Fig. 1 is the structural representation of the metal mold spentnuclear fuel after-treatment device of the present invention, in FIG, the metal of the present invention
Type spentnuclear fuel after-treatment device is followed successively by from lower to upper and includes sensing heating part 8, cooling changeover portion 4 and fission product collection
Part 2.The design power of device is 35kW, and maximum heating temperature is up to 2100 DEG C.Described sensing heating part 8 is set to stove
The double-decker of shell and burner hearth, containing spherical furnace shell 19, the burner hearth of tubular that is arranged in furnace shell 19, is arranged on burner hearth peripheral
Heat-insulation layer II 17.Described cooling changeover portion 4 is containing heat-insulation layer III 22, water collar 21.Described fission product collects part 2
Containing heat-insulation layer I 3, air vent 23, temperature detection the installation of TC mouth.Its annexation is, described sensing heating part 8,
Cooling changeover portion 4 and fission product are collected part 2 each several part seam and are passed through Flange joint respectively.Described furnace shell 19 is by bilayer
Water collar is constituted, and the one side of furnace shell 19 is respectively arranged with vaccum exhaust outlet 18, electrode outlet 11, and the top of furnace shell 19 is respectively
Being provided with the installing port 7 of thermocouple, infrared rays survey mouth 20, during for installing less than 1000 DEG C, thermocouple and the temperature of thermometric are big
The infrared temperature probe of thermometric in 1000 DEG C time, electrode is drawn by side electrode outlet 11.Described burner hearth is arranged at furnace shell
On central shaft in 19, lower furnace portion is fixed in furnace shell 19 by heat-insulation layer II 17, the surface coiling thoughts of heat-insulation layer II 17
Answering coil 9, the freeze profile of induction coil 9 correspondence to become high temperature heating in medium frequency section 10, the top of high temperature heating in medium frequency section 10 is formed
High temperature cooling changeover portion 6.The bottom of furnace shell 19 is provided with liftable workbench 12, by external motor drive operational platform 12 liters
Fall；The bottom of workbench 12, bottom are respectively arranged with burner hearth air inlet 15, ray detection mouth 14, enter for carrier gas and γ visits
Head is installed.The surface of burner hearth being positioned at furnace shell 19 upper port is provided with heat-insulation layer III 22, and the periphery of heat-insulation layer III 22 is provided with water collar 21,
The shell of water collar 21 is connected with furnace shell 19 by flange, forms cooling changeover portion 4.Fission product collects the burner hearth in part 2
Periphery is provided with heat-insulation layer I 3, and one end of heat-insulation layer I 3 is connected by the heat-insulation layer III 22 of flange with cooling changeover portion 4, the other end
Bound by flange；Collect the top of part 2, top at fission product and be respectively arranged with the heat of air vent 23, temperature detection
Galvanic couple mouth 1, is respectively used to tail gas and discharges and the installation of TC.Described furnace shell 19 is fixed on operating platform 13, and bottom is far from ground
Face height is 1 meter.Described sensing heating part 8, cooling changeover portion 4 and fission product are collected part 2 and are arranged for concentric.
Described furnace shell and burner hearth are respectively arranged with independent air inlet, and described furnace shell 19 is provided with furnace shell air inlet
16, burner hearth is provided with burner hearth air inlet 15.
Water collar 21 in described cooling changeover portion 4 is set to three sections, and three sections of water collars all can independently be carried out into water
Control.
Described fission product is collected part 2 and is internally provided with the T-shaped step for filter material.
Described burner hearth material is high purity graphite pipe, the graphite heat-insulation layer of graphite-pipe outer wrapping zirconia refractory.
The material of three sections of independent water collars on described heat-insulation layer III 22 surface uses 316L rustless steel.
In assembly of the invention heating process, by adjusting the gas flow of two independent air inlets 14 and 16 to furnace shell and stove
Pressure in thorax is controlled, and adjustment makes the pressure in furnace shell slightly larger than pressure in the burner hearth, it is ensured that the gas in burner hearth is not to stove
Shell external diffusion；In heating process, by temperature detection thermocouple 1, the temperature of fission product collecting region is monitored, from
And determining the compound mode of linear three sections of independent water collars of temperature descending section, it is ensured that the temperature bottom fission product collecting region controls
In the range of 600 ~ 800 DEG C；Being set to ledge structure inside fission product collecting region, filter material is arranged on step and seals, outward
Portion's heat-insulation layer has heating function, it is ensured that in the range of interior temperature is in 600 ~ 800 DEG C, in order to volatile fission product
Collect.
Claims (6)
1. a metal mold spentnuclear fuel after-treatment device, it is characterised in that described device is followed successively by from lower to upper and includes sensing
Add part (8), cooling changeover portion (4) and fission product and collect part (2)；Described sensing heating part (8) is set to stove
The double-decker of shell and burner hearth, containing spherical furnace shell (19), the burner hearth of tubular that is arranged in furnace shell (19), is arranged on burner hearth
Peripheral heat-insulation layer II (17)；Described cooling changeover portion (4) contains heat-insulation layer III (22), water collar (21)；Described fission
Product collection section (2) contains heat-insulation layer I (3), air vent (23), temperature detection the installation of TC mouth；Its annexation is, institute
Sensing heating part (8), cooling changeover portion (4) and the fission product stated is collected part (2) each several part seam and is passed through method respectively
Blue connection；Described furnace shell (19) is made up of Double water-cooled set, the one side of furnace shell (19) be respectively arranged with vaccum exhaust outlet (18),
Electrode outlet (11), the top of furnace shell (19) is respectively arranged with the installing port (7) of thermocouple, infrared rays survey mouth (20), electricity
Pole is drawn by side electrode outlet (11)；Described burner hearth is arranged on the central shaft in furnace shell (19), and lower furnace portion is passed through
Heat-insulation layer II (17) is fixed in furnace shell (19), and the surface of heat-insulation layer II (17) is wound with induction coil (9), induction coil (9)
Corresponding freeze profile becomes high temperature heating in medium frequency section (10), and high temperature cooling changeover portion is formed at the top of high temperature heating in medium frequency section (10)
(6)；The bottom of furnace shell (19) is provided with liftable workbench (12), is lifted by external motor drive operational platform (12)；Work
The bottom of station (12), bottom are respectively arranged with burner hearth air inlet (15), ray detection mouth (14)；It is positioned at furnace shell (19) upper port
Surface of burner hearth be provided with heat-insulation layer III (22), the periphery of heat-insulation layer III (22) is provided with water collar (21), the shell of water collar (21)
It is connected with furnace shell (19) by flange, forms cooling changeover portion (4)；Fission product is collected the burner hearth periphery in part (2) and is arranged
Having heat-insulation layer I (3), one end of heat-insulation layer I (3) is connected by the heat-insulation layer III (22) of flange with cooling changeover portion (4), the other end
Bound by flange；Collect the part top of (2) at fission product, top is respectively arranged with air vent (23), temperature detection is used
Thermocouple port (1)；Described furnace shell (19) is fixed on operating platform (13)；Described sensing heating part (8), transition of lowering the temperature
It is that concentric is arranged that section (4) and fission product collect part (2).
Metal mold spentnuclear fuel after-treatment device the most according to claim 1, it is characterised in that described furnace shell (19) is arranged
Having furnace shell air inlet (16), burner hearth is provided with burner hearth air inlet (15).
Metal mold spentnuclear fuel after-treatment device the most according to claim 1, it is characterised in that described cooling changeover portion (4)
In water collar (21) be set to three sections, three sections of water collars all can independently carry out into water control.
Metal mold spentnuclear fuel after-treatment device the most according to claim 1, it is characterised in that described fission product collection portion
(2) are divided to be internally provided with the T-shaped step for filter material.
Metal mold spentnuclear fuel after-treatment device the most according to claim 1, it is characterised in that described burner hearth material is high
Pure graphite-pipe, the graphite heat-insulation layer of graphite-pipe outer wrapping zirconia refractory.
Metal mold spentnuclear fuel after-treatment device the most according to claim 1, it is characterised in that described heat-insulation layer III (22)
The material of three sections of independent water collars on surface uses 316L rustless steel.
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201410263418.1A CN104008785B (en) | 2014-06-16 | 2014-06-16 | A kind of metal mold spentnuclear fuel after-treatment device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201410263418.1A CN104008785B (en) | 2014-06-16 | 2014-06-16 | A kind of metal mold spentnuclear fuel after-treatment device |
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| Publication Number | Publication Date |
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| CN104008785A CN104008785A (en) | 2014-08-27 |
| CN104008785B true CN104008785B (en) | 2016-08-17 |
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| CN201410263418.1A Expired - Fee Related CN104008785B (en) | 2014-06-16 | 2014-06-16 | A kind of metal mold spentnuclear fuel after-treatment device |
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Families Citing this family (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP3734615A4 (en) * | 2017-12-29 | 2021-08-11 | State Atomic Energy Corporation "Rosatom" on Behalf of The Russian Federation | Method for reprocessing nitride spent nuclear fuel in molten salts |
| CN112670005B (en) * | 2020-12-18 | 2022-10-21 | 中广核研究院有限公司 | Spent fuel rod treatment method |
| CN113012841B (en) * | 2021-03-17 | 2023-01-03 | 中国科学院上海应用物理研究所 | Device for desorbing multiple nuclides in graphite |
Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN201123144Y (en) * | 2007-12-11 | 2008-09-24 | 中国原子能科学研究院 | Miniature high-temperature combustion furnace |
| JP2009288178A (en) * | 2008-05-30 | 2009-12-10 | Toshiba Corp | Method for reprocessing spent nuclear fuel |
| CN202221662U (en) * | 2011-08-19 | 2012-05-16 | 中国核动力研究设计院 | Safety control and alarm system used for post-treatment corrosion test of spent fuel |
| CN203882635U (en) * | 2014-06-16 | 2014-10-15 | 中国工程物理研究院核物理与化学研究所 | Metal mold spent fuel reprocessing device |
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2014
- 2014-06-16 CN CN201410263418.1A patent/CN104008785B/en not_active Expired - Fee Related
Patent Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN201123144Y (en) * | 2007-12-11 | 2008-09-24 | 中国原子能科学研究院 | Miniature high-temperature combustion furnace |
| JP2009288178A (en) * | 2008-05-30 | 2009-12-10 | Toshiba Corp | Method for reprocessing spent nuclear fuel |
| CN202221662U (en) * | 2011-08-19 | 2012-05-16 | 中国核动力研究设计院 | Safety control and alarm system used for post-treatment corrosion test of spent fuel |
| CN203882635U (en) * | 2014-06-16 | 2014-10-15 | 中国工程物理研究院核物理与化学研究所 | Metal mold spent fuel reprocessing device |
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