CN105347305A - Tritium gas purified tail gas storage and tinning system - Google Patents
Tritium gas purified tail gas storage and tinning system Download PDFInfo
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- CN105347305A CN105347305A CN201510800409.6A CN201510800409A CN105347305A CN 105347305 A CN105347305 A CN 105347305A CN 201510800409 A CN201510800409 A CN 201510800409A CN 105347305 A CN105347305 A CN 105347305A
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- tritium
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Abstract
The invention belongs to the technical field of gas purification and discloses a tritium gas purification system. The system comprises a tritium gas introduction system which is connected with each other or disconnected via valves, a circulation separation system and a tail gas monitoring system. The tritium gas introduction system comprises a vacuum pump, a cold trap, a buffer bottle, a vacuum gauge and a bottle for storing tritium and uranium to be purified. The circulation separation system comprises two flow-type uranium beds, a tritium-storing uranium bed and a circulating pump, wherein the two flow-type uranium beds and the tritium-storing uranium bed are serially connected through pipelines and are all provided with an electric-heating device. The two flow-type uranium beds respectively adsorbs impurity gas other than tritium gas or helium gas, and stores the tritium gas and releases the tritium gas after storing the tritium gas; the tritium-storing uranium bed stores the released-purified tritium gas and is connected with a tail gas tank of the tail gas monitoring system through pipelines; the tail gas monitoring system comprises the tail gas tank, a tail gas monitoring pressure meter and the circulating pump. The purification system has advantages of almost 100% recovery rate of tritium gas and more than 99% purity of tritium gas.
Description
Technical field
The invention belongs to gas purification technology field, be specifically related to a kind of tritium gas purification system.
Background technology
Tritium is the radio isotope of hydrogen, has the advantage that toxicity is lower, specific activity is higher, radioactive automatic developing is well-behaved, has been widely used in the fields such as science tracer study, self-emissive light source, tritium target development, but also has been the fuel of controllable nuclear fusion.A large amount of tritium is usually with the storage of metal tritides form, especially general with uranium tritide.
Uranium tritide is a kind ofly acknowledged as desirable storage tritium material, and this is mainly because it has lower balance decomposition pressure, desorption temperature, larger reversible suction tritium capacity, faster desorption rate, can effectively avoid the seeping at high temperature of tritium to lose and the advantage such as tritium aging is slight.Its storage tritium principle is that the heating in hydrogen (containing tritium gas) of uranium metal bits can adsorb tritium, and be wherein heated to 150 DEG C, the speed of uranium powder absorption tritium is the fastest, and being heated to 255 DEG C is to react generation uranium hydride, and uranium hydride is the best storage form of tritium.When using tritium gas, uranium hydride is warmed up to 350 ~ 400 DEG C and can decomposes and discharge tritium gas.The chemical reaction of tritium and uranium is: 2U+3T
2→ 2UT
3.
Above-mentioned reaction is a reversible reaction, generates while uranium tritide in the reaction of uranium absorption tritium gas, and uranium tritide also decomposes and discharges tritium gas in heat-processed, when the gas molecule adsorbed is identical with the gas molecula number that desorb discharge, reacts and namely reaches balance.
When tritium is stored for a long time in uranium tritide powder bottle, the tritium in uranium tritide decays into through β
3he, when
3after the amount of He reaches threshold concentration, will discharge in a large number, reduce the purity of tritium, directly affect the application of tritium.In addition, in the storage, the process such as cooling or transport of tritium, steam effect in tritium and ambiance, can produce O
2, N
2, NH
3, CH
4, CO and CO
2etc. assorted gas.Therefore the tritium of long storage periods necessary purifying before use, to ensure the purity of tritium.At present conventional tritium gas purifying utilizes Pd-Ag diffusion barrier to carry out purifying, and this method is suitable for extensive tritium gas purifying, and cost is higher and remain tritium in tail gas, and the tritium rate of recovery is relatively low.Therefore, the system being applicable to short run tritium gas purifying that a kind of tritium gas rate of recovery is high, purity is high and simple to operate is needed at present.
Summary of the invention
(1) goal of the invention
Problem existing for prior art, the invention provides the tritium gas purification system that a kind of tritium gas rate of recovery is high, purity is high and simple to operate.
(2) technical scheme
In order to solve the problem existing for prior art, the present invention is achieved by the following technical solutions:
A kind of tritium gas purification system, this system comprises the tritium gas drawing-in system, circulation separation system and the tail gas Monitoring systems that to be interconnected by valve or to disconnect; Described tritium gas drawing-in system comprises vacuum pump, cold-trap, surge flask, vacuumometer and storage tritium uranium powder bottle to be purified, wherein storage tritium uranium powder bottle to be purified provides tritium gas for whole purification system, vacuum pump is connected by pipeline with cold-trap, and is connected with surge flask, vacuumometer, detritiation uranium powder bottle to be purified and circulation separation system respectively from the pipeline that cold-trap is drawn by four-way;
Described circulation separation system comprises two flow type uranium beds, a storage tritium uranium bed and a recycle pump; Wherein two flow type uranium beds are respectively first-class general formula uranium bed and second general formula uranium bed according to apart from storage tritium uranium powder bottle to be purified order from the close-by examples to those far off, and first-class general formula uranium bed, second general formula uranium bed and storage tritium uranium bed are connected in series by pipeline and are provided with electrical heating device; First-class general formula uranium bed realizes attached to the assorted aspiration beyond tritium helium; Second general formula uranium bed realizes the release after the storage of tritium gas and storage, and tritium gas after the purifying discharged from second general formula uranium bed store by storage tritium uranium bed, and stores tritium uranium bed and be connected with the tail gas hold tank of tail gas Monitoring systems by pipeline;
Described tail gas Monitoring systems comprises tail gas hold tank, tail gas monitoring pressure table and recycle pump; Wherein tail gas monitoring pressure table and recycle pump are positioned at the top of tail gas hold tank, and this recycle pump is connected with tritium gas drawing-in system and first-class general formula uranium bed with threeway respectively by pipeline.
Preferably, the Heating temperature of electrical heating device storage tritium uranium powder bottle to be purified arranged is 400 ~ 500 DEG C; The Heating temperature of the electrical heating device that first-class general formula uranium bed is arranged is 600 ~ 700 DEG C; The Heating temperature of the electrical heating device that second general formula uranium bed is arranged is set to 150 DEG C when storing tritium, is set to 400 ~ 500 DEG C during release tritium; The temperature of the electrical heating device that storage tritium uranium bed is arranged is set to 150 ~ 255 DEG C.
Preferably, uranium powder is all filled with in described first-class general formula uranium bed, second general formula uranium bed and storage tritium uranium bed.
Preferably, be provided with in described tritium gas drawing-in system and introduce gas-monitoring tensimeter, to indicate the pressure of the tritium gas discharged in storage tritium uranium powder bottle to be purified, when pressure is more than 1 normal atmosphere, the valve opened below surge flask makes tritium gas enter surge flask.
Preferably, the material of described detritiation uranium powder bottle to be purified, cold-trap, surge flask and pipeline is stainless steel; Wherein pipeline is the stainless steel pipes of internal surface polishing, to reduce tritium gas adsorptive capacity, helium and other gas.
Preferably, first-class general formula uranium bed, second general formula uranium bed and storage tritium uranium bed are the uranium bed utilizing Hydrogen activation in advance, and the upper end of these three uranium beds all seals.
Before tritium gas purifying is carried out to storage tritium uranium powder bottle to be purified, first utilize hydrogen it fully to be activated to first-class general formula uranium bed and second general formula uranium bed and hydrogen is removed clean after, and access purification system respectively.
When adopting this purification system purifying tritium gas, its working method is: first utilize vacuum pump to vacuumize purification system, makes vacuum tightness be better than 10
-2pa; Open the heating installation on first-class general formula uranium bed and second general formula uranium bed, making to arrange its temperature is respectively 600 DEG C, 150 DEG C, then the heating installation opened on storage tritium uranium powder bottle to be purified makes its temperature slowly be warming up to 430 DEG C, and the mixed gass such as tritium helium start discharge from storage tritium uranium powder bottle to be purified and enter in tritium gas drawing-in system.The pressure increase that the mixed gas introduced in tritium gas drawing-in system makes tensimeter indicate, observe the pressure of tensimeter instruction, control pressure is no more than 101KPa, if pressure is more than 101KPa, opens the valve below surge flask, portion gas is introduced in surge flask and carries out purifying again.Mixed gas enters first-class general formula uranium bed by other gas adsorption except tritium and helium by pipeline, tritium helium gas mixture body enters second general formula uranium bed by tritium gas quick adsorption, helium and do not entered tail gas hold tank by the tritium gas adsorbed on a small quantity, open turbine recycle pump will be mixed gas circular treatment, again first-class general formula uranium bed, second general formula uranium bed and storage tritium uranium bed is entered, then by assorted gas throughputs such as tail gas hold tank upward pressure table instruction helium through pipeline.When needing the gas of separation and purification all by cyclic separation device, and the display of tail gas hold tank upward pressure table is after atmospheric pressure value no longer changes, the separation of halt system.Close all valves except two valves above storage tritium uranium bed, heating second general formula uranium bed (control temperature is 400 ~ 500 DEG C) and storage tritium uranium bed (control temperature 255 DEG C), the tritium gas adsorbed in second general formula uranium bed can be transferred in storage tritium uranium bed through pipeline in a heated condition and store.
(3) beneficial effect
When adopting tritium gas purification system provided by the invention to carry out purifying to tritium gas, have the tritium gas rate of recovery close to 100%, tritium purity reaches more than 99% and operational safety, simple beneficial effect.Specific explanations is:
1) the present invention adopts tritium gas drawing-in system, circulation separation system and tail gas Monitoring systems to carry out purifying to storage tritium uranium powder bottle to be purified, utilize uranium under condition of different temperatures to the difference of tritium gas and the absorbent properties to mixed gass such as tritium helium, devise the sharp separation that tripping device that multiple temperature control uranium bed combines reaches the assorted gas such as tritium and helium, and system is the stainless steel system of sealing, the risk that tritium leaks effectively can be reduced.
2) the cold-trap design in tritium gas drawing-in system, can improve further and keep vacuum tightness.This is mainly due under condition of high vacuum degree, and intrasystem gas reaches statical equilibrium, and vacuum tightness is difficult to improve again, and utilizes liquid nitrogen can destroy balance after cooling gas, improves system vacuum.The gas be not easily drawn out of residual in system, when low temperature, is also more easily extracted out by vacuum pump.
3) recycle pump provided in tail gas Monitoring systems makes not continued through first-class general formula uranium bed, second general formula uranium bed and storage tritium uranium bed by the tritium gas and other assorted gas storing the absorption of tritium uranium bed, removes O further
2, N
2, NH
3, CH
4, CO and CO
2etc. foreign gas, and further remaining tritium gas is adsorbed in storage tritium uranium bed.
Accompanying drawing explanation
Fig. 1 is the tritium gas purification system schematic diagram that the application provides; Wherein 1 is vacuum pump; 2,4,5,6,8,12,13,14,18,19,20,22,23,25,26,27,28,31,32,34,35 valve is; 3 is cold-traps; 7,9 surge flask is; 10 for introducing gas-monitoring tensimeter; 11 is storage tritium uranium powder bottles to be purified; 15 is vacuumometers; 16,21,29,33 temperature sensor is; 17 is first-class general formula uranium beds; 24 is second general formula uranium beds; 28 is recycle pumps; 30 is storage tritium uranium beds; 36 is tail gas hold tanks; 37 is tail gas monitoring pressure table.
Embodiment
The present invention will the present invention is further elaborated in conjunction with embodiment and Figure of description.
A kind of tritium gas purification system, as shown in Figure 1.This system comprises the tritium gas drawing-in system, circulation separation system and the tail gas Monitoring systems that to be interconnected by valve or to disconnect; Described tritium gas drawing-in system comprise vacuum pump 1, cold-trap 3, surge flask 7,9, vacuumometer 15 and storage tritium uranium powder bottle 11 to be purified, wherein storage tritium uranium powder bottle 11 to be purified provides tritium gas for whole purification system, vacuum pump 1 is connected by pipeline with cold-trap 3, and the pipeline of drawing from cold-trap 3 by four-way respectively with surge flask 7,9, vacuumometer 15, detritiation uranium powder bottle 11 to be purified and circulation separation system be connected;
Described circulation separation system comprises two flow type uranium beds, a storage tritium uranium bed and a recycle pump; Wherein two flow type uranium beds are respectively first-class general formula uranium bed 17 and second general formula uranium bed 24 according to apart from storage tritium uranium powder bottle to be purified order from the close-by examples to those far off, and first-class general formula uranium bed 17, second general formula uranium bed 24 and storage tritium uranium bed 30 are connected in series by pipeline and are provided with electrical heating device, storage tritium uranium bed 30 is connected with the tail gas hold tank 36 of tail gas Monitoring systems by pipeline; Wherein all be filled with uranium powder in first-class general formula uranium bed 17, second general formula uranium bed 24 and storage tritium uranium bed 30 and first-class general formula uranium bed 17, second general formula uranium bed 24 and storage tritium uranium bed 30 are the uranium bed utilizing Hydrogen activation in advance, and the upper end of these three uranium beds all seals.
Described tail gas Monitoring systems comprises tail gas hold tank 36, tail gas monitoring pressure table 37 and recycle pump 28; Wherein tail gas monitoring pressure table 37 and recycle pump 28 are positioned at the top of tail gas hold tank 36, and this recycle pump 28 is connected with tritium gas drawing-in system and first-class general formula uranium bed 17 with threeway respectively by pipeline;
Wherein, the Heating temperature of electrical heating device storage tritium uranium powder bottle 11 to be purified arranged is 400 ~ 500 DEG C; The Heating temperature of the electrical heating device that first-class general formula uranium bed 17 is arranged is 600 ~ 700 DEG C; The Heating temperature of the electrical heating device that second general formula uranium bed 24 is arranged is set to 150 DEG C when storing tritium, is set to 400 ~ 500 DEG C during release tritium; The temperature of the electrical heating device that storage tritium uranium bed 30 is arranged is set to 150 ~ 255 DEG C.
Be provided with in described tritium gas drawing-in system and introduce gas-monitoring tensimeter 10, to indicate the pressure of the tritium gas discharged in storage tritium uranium powder bottle to be purified, when pressure is more than 1 normal atmosphere, open surge flask 7 or/and the valve below 9 makes tritium gas enter surge flask;
The material of described detritiation uranium powder bottle 11 to be purified, cold-trap 3, surge flask 7,9 and pipeline is stainless steel; Wherein pipeline is the stainless steel pipes of internal surface polishing, to reduce absorption tritium gas, helium and other gas.
Before tritium gas purifying is carried out to storage tritium uranium powder bottle to be purified, first utilize hydrogen it fully to be activated to first-class general formula uranium bed and second general formula uranium bed and hydrogen is removed clean after, and access purification system respectively.
When adopting this purification system purifying tritium gas, its working method is: first open valve used, utilizes vacuum pump to vacuumize purification system, makes vacuum tightness be better than 10
-2pa; Open the heating installation on first-class general formula uranium bed and second general formula uranium bed, making to arrange its temperature is respectively 600 DEG C, 150 DEG C, then the heating installation opened on storage tritium uranium powder bottle to be purified makes its temperature slowly be warming up to 430 DEG C, and the mixed gass such as tritium helium start discharge from storage tritium uranium powder bottle to be purified and enter in tritium gas drawing-in system.The pressure increase that the mixed gas introduced in tritium gas drawing-in system makes tensimeter indicate, observe the pressure of tensimeter instruction, control pressure is no more than 101KPa, if pressure is more than 101KPa, opens the valve below surge flask, portion gas is introduced in surge flask and carries out purifying again.Mixed gas enters first-class general formula uranium bed by other gas adsorption except tritium and helium by pipeline, tritium helium gas mixture body enters second general formula uranium bed by tritium gas quick adsorption, helium and do not entered tail gas hold tank by the tritium gas adsorbed on a small quantity, open turbine recycle pump will be mixed gas circular treatment, again enter first-class general formula uranium bed, second general formula uranium bed and storage tritium uranium bed, then by assorted gas throughputs such as tail gas hold tank upward pressure table instruction helium through pipeline.When needing the gas of separation and purification all by tripping device, and the display of tail gas hold tank upward pressure table is after atmospheric pressure value no longer changes, the separation of halt system.Close all valves except two valves above storage tritium uranium bed, heating second general formula uranium bed (control temperature is 400 ~ 500 DEG C) and storage tritium uranium bed (control temperature 255 DEG C), the tritium gas adsorbed in second general formula uranium bed can be transferred in storage tritium uranium bed through pipeline in a heated condition.
Utilize this system to carry out purifying to depositing the storage tritium uranium powder bottle reaching more than 10 years, result shows: through gas chromatographic analysis, and before process, sampling analysis tritium purity is 69.6%, and after process, sampling analysis tritium purity reaches 99.9%, and the rate of recovery is 99.97%.
Claims (6)
1. a tritium gas purification system, is characterized in that, this system comprises the tritium gas drawing-in system, circulation separation system and the tail gas Monitoring systems that to be interconnected by valve or to disconnect; Described tritium gas drawing-in system comprises vacuum pump, cold-trap, surge flask, vacuumometer and storage tritium uranium powder bottle to be purified, wherein storage tritium uranium powder bottle to be purified provides tritium gas for whole purification system, vacuum pump is connected by pipeline with cold-trap, and is connected with surge flask, vacuumometer, detritiation uranium powder bottle to be purified and circulation separation system respectively from the pipeline that cold-trap is drawn by four-way;
Described circulation separation system comprises two flow type uranium beds, a storage tritium uranium bed and a recycle pump; Wherein two flow type uranium beds are respectively first-class general formula uranium bed and second general formula uranium bed according to apart from storage tritium uranium powder bottle to be purified order from the close-by examples to those far off, and first-class general formula uranium bed, second general formula uranium bed and storage tritium uranium bed are connected in series by pipeline and are provided with electrical heating device; First-class general formula uranium bed realizes attached to the assorted aspiration beyond tritium helium; Second general formula uranium bed realizes the release after the storage of tritium gas and storage, and tritium gas after the purifying discharged from second general formula uranium bed store by storage tritium uranium bed, and stores tritium uranium bed and be connected with the tail gas hold tank of tail gas Monitoring systems by pipeline;
Described tail gas Monitoring systems comprises tail gas hold tank, tail gas monitoring pressure table and recycle pump; Wherein tail gas monitoring pressure table and recycle pump are positioned at the top of tail gas hold tank, and this recycle pump is connected with tritium gas drawing-in system and first-class general formula uranium bed with threeway respectively by pipeline.
2. a kind of tritium gas purification system according to claim 1, is characterized in that, the Heating temperature of the electrical heating device that storage tritium uranium powder bottle to be purified is arranged is 400 ~ 500 DEG C; The Heating temperature of the electrical heating device that first-class general formula uranium bed is arranged is 600 ~ 700 DEG C; The Heating temperature of the electrical heating device that second general formula uranium bed is arranged is set to 150 DEG C when storing tritium, is set to 400 ~ 500 DEG C during release tritium; The temperature of the electrical heating device that storage tritium uranium bed is arranged is set to 150 ~ 255 DEG C.
3. a kind of tritium gas purification system according to claim 1, is characterized in that, is all filled with uranium powder in described first-class general formula uranium bed, second general formula uranium bed and storage tritium uranium bed.
4. a kind of tritium gas purification system according to claim 1, it is characterized in that, be provided with in described tritium gas drawing-in system and introduce gas-monitoring tensimeter, to indicate the pressure of the tritium gas discharged in storage tritium uranium powder bottle to be purified, when pressure is more than 1 normal atmosphere, the valve opened below surge flask makes tritium gas enter surge flask.
5. a kind of tritium gas purification system according to claim 1, is characterized in that, the material of described detritiation uranium powder bottle to be purified, cold-trap, surge flask and pipeline is stainless steel; Wherein pipeline is the stainless steel pipes of internal surface polishing.
6. a kind of tritium gas purification system according to claim 1, is characterized in that, first-class general formula uranium bed, second general formula uranium bed and storage tritium uranium bed are the uranium bed utilizing Hydrogen activation in advance, and the upper end of these three uranium beds all seals.
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Cited By (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106082150A (en) * | 2016-06-02 | 2016-11-09 | 中国工程物理研究院材料研究所 | One is used for preparing high-purity3the device of He and preparation high-purity3the method of He |
| CN106782733A (en) * | 2016-12-30 | 2017-05-31 | 中国工程物理研究院材料研究所 | One kind storage tritium uranium bed deactivating process for the treatment of |
| CN109663456A (en) * | 2019-01-09 | 2019-04-23 | 中国工程物理研究院材料研究所 | A kind of hydrogen displacement sorption method is enriched with the method and system of trace heavy nucleus hydrogen isotope in hydrogen isotope |
| CN110690087A (en) * | 2019-11-18 | 2020-01-14 | 成都国光电气股份有限公司 | Inflation system of high-energy ignition gas discharge tube and charging method thereof |
| WO2020224304A1 (en) * | 2019-05-08 | 2020-11-12 | 中国科学技术大学 | Enrichment and purification device for single gas in mixed gas |
| CN112331366A (en) * | 2020-11-21 | 2021-02-05 | 中国工程物理研究院材料研究所 | Deuterium-tritium fuel storage and supply demonstration system and application |
| CN114252317A (en) * | 2021-12-24 | 2022-03-29 | 中国原子能科学研究院 | Carbon-14 radiolabelling systems and methods |
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| CN104485146A (en) * | 2014-12-12 | 2015-04-01 | 中国工程物理研究院材料研究所 | High-efficiency tritium removal purification device and tritium removal method thereof |
| CN205204816U (en) * | 2015-11-19 | 2016-05-04 | 中国原子能科学研究院 | Tritium gas purification system |
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| JPS5381899A (en) * | 1976-12-27 | 1978-07-19 | Power Reactor & Nuclear Fuel Dev Corp | Manufacturing method of tritium |
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Cited By (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106082150A (en) * | 2016-06-02 | 2016-11-09 | 中国工程物理研究院材料研究所 | One is used for preparing high-purity3the device of He and preparation high-purity3the method of He |
| CN106782733A (en) * | 2016-12-30 | 2017-05-31 | 中国工程物理研究院材料研究所 | One kind storage tritium uranium bed deactivating process for the treatment of |
| CN109663456A (en) * | 2019-01-09 | 2019-04-23 | 中国工程物理研究院材料研究所 | A kind of hydrogen displacement sorption method is enriched with the method and system of trace heavy nucleus hydrogen isotope in hydrogen isotope |
| CN109663456B (en) * | 2019-01-09 | 2021-07-13 | 中国工程物理研究院材料研究所 | Method and system for enriching trace heavy nuclear hydrogen isotopes in hydrogen isotopes by hydrogen replacement adsorption method |
| WO2020224304A1 (en) * | 2019-05-08 | 2020-11-12 | 中国科学技术大学 | Enrichment and purification device for single gas in mixed gas |
| CN110690087A (en) * | 2019-11-18 | 2020-01-14 | 成都国光电气股份有限公司 | Inflation system of high-energy ignition gas discharge tube and charging method thereof |
| CN110690087B (en) * | 2019-11-18 | 2024-04-30 | 成都国光电气股份有限公司 | Inflation system of high-energy ignition gas discharge tube and charging method thereof |
| CN112331366A (en) * | 2020-11-21 | 2021-02-05 | 中国工程物理研究院材料研究所 | Deuterium-tritium fuel storage and supply demonstration system and application |
| CN112331366B (en) * | 2020-11-21 | 2022-12-13 | 中国工程物理研究院材料研究所 | Deuterium-tritium fuel storage and supply demonstration system and application |
| CN114252317A (en) * | 2021-12-24 | 2022-03-29 | 中国原子能科学研究院 | Carbon-14 radiolabelling systems and methods |
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