CN104538074A - Tritium trap device used for removing tritium in helium-3 gas, and tritium-removing method - Google Patents
Tritium trap device used for removing tritium in helium-3 gas, and tritium-removing method Download PDFInfo
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- CN104538074A CN104538074A CN201410721594.5A CN201410721594A CN104538074A CN 104538074 A CN104538074 A CN 104538074A CN 201410721594 A CN201410721594 A CN 201410721594A CN 104538074 A CN104538074 A CN 104538074A
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/02—Treating gases
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/007—Recovery of isotopes from radioactive waste, e.g. fission products
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Abstract
The invention discloses a tritium trap device used for removing tritium in helium-3 gas, and a tritium-removing method. The tritium trap device comprises an outer housing, an inner housing positioned inside the outer housing, a gas inlet pipe with a gas outlet port positioned in a lower part inside the inner housing, a heating chamber fixed inside the inner housing, a titanium sponge arranged above the gas outlet port of the gas inlet pipe and filled between the heating chamber and the inner housing, an expansion reserved space arranged inside the inner housing and positioned above the titanium sponge, and a gas outlet pipe with a gas inlet port positioned in the expansion reserved space. The invention also comprises a method for removing tritium with the tritium trap device. The device is suitable for removing tritium in a high-temperature high-pressure helium-3 loop, and has the advantages of reliable performance and compact structure. Also, with the device, heat loss and tritium permeation amount can be reduced. The device and the method have important significance in ensuring the safety and successful running of a power sharp-increase test.
Description
Technical field
The present invention relates to a kind of tritium trap device, what be specifically related to is a kind of tritium trap device for removing tritium in helium-3 gas, and utilizes this tritium trap device to remove the method for tritium in helium-3 gas.
Background technology
Within the whole phase in longevity of nuclear power station, because reactivity controls to cause the power of fuel element local or entirety to increase in a leap.To high burnup fuel structure, when steady state irradiation is tested, element can not be damaged, but then likely breakage occurs under power increases in a leap condition.Therefore, in fuel element heap, transient performance test is the important step that research high performance fuel assembly keeps its integrality under I, II class operating mode.
Helium-3 loop is the important step of carrying out the safety and reliability test of high performance fuel element under power increases in a leap operating mode, this test can not be carried out on power reactor, general method is in research reactor, simulate various changed power mode, obtain fuel behaviour data, founding mathematical models, thus parameter reasonable in design or restriction operational mode improve the security of fuel element.
Helium-3 loop can utilize gas absorption body to change single test Irradiated Fuel Rod power fast, equably when not changing test reactor power, and the pace of change in helium-3 loop and amplitude easily control, therefore become most Foreign Research Reactors and carry out the method that power increases in a leap test.Helium-3 is gas absorption bodies of larger neutron-absorption cross-section, proportional with absorption neutrons characteristic based on helium-3 gas density, the pressure of helium-3 gas in ring screen pipe around fuel element is changed by compression or release, thus change gas neutron-absorbing bulk concentration, control the transient power of fuel element in irradiation test.Therefore the reaction of tritium titanium carries out in a larger pressure limit, and the pressure range in helium-3 loop is for reaching 0.15 ~ 4.5MPa.
And in helium-3 loop, helium-3 gas absorbs neutron in heap can produce radioactivity tritium by (n, p) reaction.Tritium has high diffusivity and harmfulness, is difficult to protection, and requires very high to the environmental emission of tritium, therefore designs the safe tool of " removing " tritium device to whole test loop and plays a very important role.
In prior art, detritiation device is the catalytic oxidation-absorption detritiation method adopted, the method is that the tritium in helium-3 gas is oxidized to tritiated water, then is adsorbed removing by desiccant bed, in the process, tritiated water steam or liquid may spread, and causing still has tritium to exist in helium-3 gas.The present invention selects titanium sponge as detritiation material, solves the problems referred to above.That is, after being reacted under the high temperature conditions by tritium and titanium sponge, gasiform tritium is effectively generated solid-state tritium titanium compound by titanium sponge, and then prevents tritium to be again diffused in helium-3 gas, effectively makes tritium separate from helium-3 gas.Thus, the present invention is applicable to helium-3 gaseous environment of High Temperature High Pressure.
Current widely used tritium storied vessel generally selects depleted nuclear fuel or ZrCo, although it is very low to inhale tritium temperature of reaction, the tritide generated very easily catches fire meeting air, is not suitable for the needs in helium-3 loop long-time running.Carry out detritiation because helium-3 gas is circulated through tritium trap, therefore helium-3 gas must be less by air resistance during tritium trap, and depleted nuclear fuel or ZrCo bed are solid robust materials, and air resistance is larger simultaneously.The present invention selects titanium sponge as detritiation material, it belongs to open structure, the comparison of resistance that gas flows through is little, the titanium tritide stability simultaneously generated is fine, at room temperature can not spontaneous combustion in air, ignition temperature is minimum also wants more than 400 DEG C, does not also react with water, can ensure that helium-3 loop is in the long-term normal safety run with large danger does not occur in the state of accident like this.Therefore, the present invention is applicable to circular flow and the safety requirements in helium-3 loop.
In the present invention due to the release of tritium in high pressure helium-3 loop and material helium crisp very serious, then need the validity problem taking into full account that tritium contains, by the bilayer setting of outer casing and internal layer shell, can effectively solve the problem.That is, the present invention adopts double-deck wrapping structure, and the internal layer shell of tritium trap forms the elementary containing system of tritium, and when internal layer shell inefficacy crisp because of helium, the tritium trap of abrupt release enters the outer casing of double-deck wrapping structure, forms the secondary containing barrier of tritium.
Simultaneously, arranged by the bilayer of outer casing and internal layer shell, the present invention is highly suitable for high pressure tritium source and runs under the continuous long period, effectively can be reduced the tritium amount being infiltrated through environment by shell by this setting, namely decrease the burst size of radioactivity tritium, during operation, security is high.The present invention is frequent because tritium trap uses, and at higher temperature and pressure operation, therefore adopts double-contracting cover containing mode, greatly reduce the High Temperature High Pressure infiltration of tritium.That is, the outer casing in the present invention had both played the adiabatic effect of insulation, and the second layer that can form again tritium contains barrier, and effect is very remarkable.
Volumetric expansion can be there is due to during titanium sponge hydrogenation in the present invention, powerful differential expansion stress may be produced and burst internal layer shell, thus for these reasons, the top of the present invention above titanium sponge in internal layer shell is provided with expansion headspace, because too large free space can increase the volume of helium-3 gas, in the present invention, this expansion headspace is preferably the free space of reserved 25%.
Because tritium belongs to strong penetrating radiation nucleic, the heating cavity of tritium trap and the wall body of internal layer shell utilize chemical vapour deposition technique prepare the Al that one deck 2 ~ 2.5um is set
2o
3ceramic coat, improves the anti-tritium-permeation ability of its High Temperature High Pressure.
As one preferably set-up mode, arrange or/and be filled with insulation material in vacuum between described outer casing and internal layer shell.That is, place microporous calcium silicate heat insulation layer between outer casing of the present invention and internal layer shell, and be pumped into certain vacuum, to increase its insulation effect, tritium can be reduced simultaneously and leak.
Due to titanium sponge inhale tritium certain hour after also can powdered supervene tiny oxide particle, these oxidation particles with the flow expansion of gas in system in whole helium-3 loop, and then can cause tritium contamination.Thus, the present invention is also provided with gas filter on described escape pipe, in order to reach effect best, this draft tube is also provided with another gas filter.
Described internal layer shell inner bottom is provided with gas distributor, and this gas distributor is positioned at below titanium sponge, above the outlet side port of draft tube.The setting of gas distributor in the present invention, effectively helium-3 gas being disperseed, namely when helium-3 gas containing tritium is by titanium sponge, avoiding gas by there is the situation of bias current during titanium sponge, effectively obtain high absorption detritiation efficiency, and improve the serviceable life of equipment in the present invention.
Further, the outlet side port of described draft tube to extend into from outer casing top in internal layer shell and extends to below gas distributor after running through titanium sponge from internal layer shell top.Run through the setting of titanium sponge by draft tube, effectively can carry out preheating to the gas entered in titanium sponge, and then helium-3 gas effectively avoiding normal temperature to contain tritium directly enters reaction chamber, to cause abnormal expansion and the β phase transformation of titanium.The present invention first can will be preheating to about 40 DEG C ~ 70 DEG C containing tritium gas, then enters in titanium sponge and react with titanium, thus effectively ensures that titanium sponge reaction chamber strictly can control operational temperature conditions, is conducive to the serviceable life of raising reaction chamber.
Further, the inlet end port of described escape pipe extends in internal layer shell from the top of outer casing, and the draft tube of this outer casing outside and escape pipe are also respectively arranged with a valve, and this outer casing outer tip end is also provided with head protector.The setting of this head protector is that conveniently tritium trap is in transport and retired process, and available protecting top structure, prevents valve invalidation from causing the leakage of tritium.Valve location in the present invention on draft tube and escape pipe should have with a certain distance from outer casing surface, reduces the heat trnasfer owing to inhaling tritium process.This valve should use compact valve, and then reduces the size of valve.
In order to avoid gas by there is the situation of bias current during titanium sponge further, after preventing titanium sponge from inhaling tritium powdered, fall into internal layer shell bottom, blocking draft tube lower port simultaneously; The silk screen for placing titanium sponge is provided with above described gas distributor.
What the tritium trap in the present invention adopted is all-metal construction, adopts welding connecting mode as far as possible, ensures the sealing of equipment.Consider the needs that system maintenance is safeguarded, internal layer shell lower end is the position that should not connect with welding connecting mode, thus metallic packing Flange joint is adopted, namely, internal layer shell between described silk screen and gas distributor is provided with Inner shell connecting sewing, pass through Flange joint respectively between described head protector and outer casing and on Inner shell connecting sewing, the junction of described flange is also provided with metallic packing.This metallic packing need avoid the organic one-tenth elaxtic seal using anti-tritium irradiation behaviour poor.
For removing a detritiation method for the tritium trap device of tritium in helium-3 gas, comprise the following steps:
(1) will be passed into the lower inside of internal layer shell after helium-3 air preheat by draft tube, after preheating, temperature reaches 40 DEG C ~ 70 DEG C;
(2) helium-3 gas is by titanium sponge, and the tritium in titanium sponge and helium-3 gas reacts and generates solid-state tritium titanium compound under 370 DEG C ~ 400 DEG C conditions;
(3) namely this solid-state tritium titanium compound completes the process of tritium in removing helium-3 gas after being separated from this helium-3 gas.
The present invention compared with prior art, has the following advantages and beneficial effect:
1, the present invention effectively can meet the condition of high temperature, high pressure in helium-3 loop by the setting of titanium sponge, while not affecting helium-3 loop, this setting effectively can trap tritium, solidification tritium in helium-3 gas, the purity of helium-3 gas in warranty test loop, has vital role to the realization of transient test in fuel element heap;
2, select titanium sponge as detritiation material in the present invention, it belongs to open structure, and the comparison of resistance that helium-3 gas flows through is little, is applicable to the needs of helium-3 circuit cycle detritiation; The titanium tritide good stability simultaneously generated, at room temperature can not spontaneous combustion in air, does not also react, be applicable to the safety of helium-3 loop long-time running with water;
3, double-contracting cover containing mode in the present invention, when internal layer shell inefficacy crisp because of helium, the tritium of abrupt release enters the outer casing of double-deck wrapping structure, forms the secondary containing barrier of tritium, effectively prevent radioactivity tritium to be discharged in environment, improve Environmental security performance further; Meanwhile, this double-contracting cover containing mode is suitable at higher temperature and pressure operation, is convenient to the frequent use of tritium trap device;
4, in the present invention, tritium trap device uses the heating cavity of internal layer shell inside to heat, the mode of outer casing insulation, compact conformation, and thermal loss is little;
5, design safety, compact and efficient tritium treatment facility, effect is very remarkable.
Summary of the invention
The object of the invention is to solve the radioactivity tritium produced in existing helium-3 loop be difficult to trap and the problem of protection, thering is provided a kind of tritium trap device for removing tritium in helium-3 gas for fuel element power transience test helium-3 loop, present invention also offers the detritiation method of this kind of tritium trap device for removing tritium in helium-3 gas.
Because helium-3 loop is not built up at home, not yet have referential experience, only have several developed country to grasp technique abroad, and this technology belongs to core technology, disclosed tritium trap detailed design data is considerably less.In order to capture the gordian technique of helium-3 loop apparatus design, possess the key equipment of basing on our country to helium-3 loop and carry out Design and manufacture ability, inventor is according to the factor such as output, tritium titanium chemical reaction, temperature, pressure, in addition tritium decay he-lium release of tritium, devise the device that tritium trap is removed the tritium that helium-3 loop carries out producing in power adjustment procedure, this device has very important effect to the success that the security and power that ensure helium-3 loop increase in a leap test.
For solving above-mentioned shortcoming, technical scheme of the present invention is as follows:
A kind of tritium trap device for removing tritium in helium-3 gas, comprise outer casing, be positioned at the internal layer shell of outer casing inside, outlet side port is positioned at the draft tube of internal layer shell lower inside, be fixed on the heating cavity of internal layer shell inside, above the outlet side port being arranged on draft tube and the titanium sponge be filled between heating cavity and internal layer shell, be arranged on internal layer shell inside and the expansion headspace be positioned at above titanium sponge, and inlet end port is positioned at the escape pipe of expansion headspace.
Accompanying drawing explanation
Fig. 1 is one-piece construction schematic diagram of the present invention.
Wherein, the parts name that in figure, Reference numeral is corresponding is called:
1-outer casing, 2-internal layer shell, 3-gas distributor, 4-draft tube, 5-heating cavity, 6-titanium sponge, 7-expansion headspace, 8-escape pipe, 9-insulation material, 10-valve, 11-head protector, 12-silk screen, 13-flange.
Embodiment
Below in conjunction with embodiment and accompanying drawing thereof, the present invention is described in further detail, but embodiments of the present invention are not limited thereto.
Embodiment 1
A kind of tritium trap device for removing tritium in helium-3 gas, as shown in Figure 1, comprise outer casing 1, be positioned at the internal layer shell 2 of outer casing 1 inside, outlet side port is positioned at the draft tube 4 of internal layer shell 2 lower inside, be fixed on the heating cavity 5 of internal layer shell 2 inside, above the outlet side port being arranged on draft tube 4 and the titanium sponge 6 be filled between heating cavity 5 and internal layer shell 2, be arranged on internal layer shell 2 inside and the expansion headspace 7 be positioned at above titanium sponge 6, and inlet end port is positioned at the escape pipe 8 of expansion headspace 7.
Wherein, the present embodiment ectomesoderm housing 1 and internal layer shell 2 are all arranged to column type, and titanium sponge 6 thickness between internal layer shell 2 and heating cavity 5 is arranged to thinner state, and then is conducive to the homogeneity of heat trnasfer, ensure the homogeneous temperature of titanium sponge 6.Internal layer shell belongs to thin oval annulated column, and therefore its vapour lock is smaller, can reduce the adherence pressure of subsequent gases ebullator.
Meanwhile, for making the titanium sponge 6 in internal layer shell 2 be heated evenly, and have the long residence time when helium-3 gas flows through titanium sponge 6, thus the annular thickness of titanium sponge 6 selects smaller value as far as possible, the height of the whole titanium sponge 6 of corresponding increase, as shown in Figure 1.
And due to helium-3 loop be continuous circulation run, helium-3 gas after its detritiation needs again to send in heap to react, fuel metering element power, therefore helium-3 gas can not be too large by resistance during tritium trap device, otherwise follow-up gas circulator adherence pressure can be caused too high, and thus the annular thickness of titanium sponge 6 is arranged in the scope ensureing the permission of titanium sponge 6 air resistance with highly needing.
In order to accelerate the pressure controlled response time, reducing the minimum cylinder volume of pressure regulator, therefore reducing void volume in tritium trap device as far as possible, so just can reduce the gas volume in whole helium-3 loop.Meanwhile, helium-3 gas costly, therefore reduces the economy that helium-3 volume can increase test.Outer casing 1 in the present embodiment on tritium trap device is highly preferably arranged to 560mm, and the diameter of this outer casing 1 is then arranged to 240mm.
In the present invention, heating cavity is heated by heater strip, and because considering that the heater strip in inner chamber may produce fault, in the present invention, the quantity of this electrical heating wire selects two, and wherein one is standby electricity heater strip, and then ensure that the replacement of easily worn part.And owing to needing higher temperature of reaction when titanium sponge 6 contacts with tritium, thus two points for measuring temperature can be set at heating cavity 5 inwall with internal layer shell 2 outer wall place, be used for controlling the heating power of electrical heating wire.
Tritium trap device of the present invention adopts all-metal construction, adopts welding connecting mode as far as possible, ensures the sealing of equipment.
Utilize the specific works step of above-mentioned tritium trap device detritiation as follows in the present invention:
(1) tritium trap must first activate before being taken into use, and tritium trap is evacuated, the titanium sponge in tritium trap is heated to more than 600 DEG C about two hours, remove the oxygen on volatile impurity and titanium sponge surface.Be filled with the high-purity hydrogen of 0.1MPa after abundant degasification, after fully absorbing, and then be heated to 600 DEG C of degasification, slowly be down to room temperature, terminate activation for storage tritium and prepare.
(2) switch of electrical heating wire is opened, electrical heating wire heats, and heat transmits to titanium sponge 6 from heating cavity 5, until titanium sponge 6 place temperature reaches 370 DEG C ~ 400 DEG C, control electrical heating wire continuous heating, make titanium sponge 6 place temperature remain on 370 DEG C ~ 400 DEG C always;
(3) preheating helium-3 gas, can reach 40 DEG C ~ 70 DEG C by temperature after preheating, then helium-3 gas after preheating is passed into the lower inside of internal layer shell by draft tube;
(4) helium-3 gas after preheating is through the titanium sponge of internal layer shell inner upper, and the tritium in titanium sponge and helium-3 gas reacts and generates solid-state tritium titanium compound under 370 DEG C ~ 400 DEG C conditions;
(5) namely this solid-state tritium titanium compound completes the process of tritium in removing helium-3 gas after being separated from this helium-3 gas.
Embodiment 2
The difference of the present embodiment and embodiment 1 is, embodiment adds some supplementary structures, and then reaches effect better, and concrete set-up mode is as follows:
Arrange or/and be filled with insulation material 9 in vacuum between described outer casing 1 and internal layer shell 2.Namely only can arrange in vacuum between ectomesoderm housing 1 of the present invention and internal layer shell 2, also can only be filled with insulation material 9, also can recharge insulation material 9 while arranging in vacuum simultaneously.Structure between the present embodiment ectomesoderm housing 1 and internal layer shell 2 recharges insulation material 9 while being preferably and arranging in vacuum.Namely between outer casing 1 and internal layer shell 2, place microporous calcium silicate heat insulation layer in the present embodiment, and be pumped into certain vacuum, to increase its insulation effect, tritium can be reduced simultaneously and leak.By above-mentioned setting, the outside wall temperature of this tritium trap device outer casing 1 can be maintained until room temperature state.
The wall body of described heating cavity 5 and internal layer shell 2 is arranged the Al of one deck 2 ~ 2.5um
2o
3ceramic coat.Described escape pipe 8 and draft tube 4 are provided with gas filter.The solid-state tritium titanium compound powder existed in helium-3 gas effectively can be filtered out by gas filter.
Embodiment 3
The difference of the present embodiment and embodiment 1 or embodiment 2 is, the present embodiment optimizes concrete structure in internal layer shell and arranges, thus makes the distribution of gas that passes in titanium sponge more even, and concrete set-up mode is as follows:
The inner bottom of internal layer shell 2 described in the present embodiment is provided with gas distributor 3, and this gas distributor 3 is positioned at below titanium sponge 6, above the outlet side port of draft tube 4.The silk screen 12 for placing titanium sponge 6 is provided with above described gas distributor 3.
The outlet side port of described draft tube 4 to extend into from outer casing 1 top in internal layer shell 2 and extends to below gas distributor 3 after running through titanium sponge 6 from internal layer shell 2 top.
Helium-3 gas in the present invention is by after the distribution of gas distributor 3, be distributed to below silk screen 12 effectively and uniformly, then helium-3 gas evenly enters into titanium sponge 6 by the mesh on silk screen 12, effectively improves the utilization ratio of titanium sponge 6, thus increases serviceable life of the present invention.
Embodiment 4
The difference of the present embodiment and embodiment 3 is, considers and optimize the concrete structure of internal layer shell and outer casing by the needs that system maintenance is safeguarded in the present embodiment, and then effectively facilitates the retired and maintenance of tritium trap device in the present invention to dispose, and it specifically arranges as follows:
In the present embodiment, the inlet end port of described escape pipe 8 extends in internal layer shell 2 from the top of outer casing 1, the draft tube 4 of this outer casing 1 outside and escape pipe 8 are also respectively arranged with a valve 10, and this outer casing 1 outer tip end is also provided with head protector 11; Described head protector 11 is connected by flange 13 with between outer casing 1, and the junction of described flange 13 is also provided with metallic packing.
Meanwhile, the internal layer shell 2 between described silk screen 12 and gas distributor 3 is provided with Inner shell connecting sewing, this Inner shell connecting sewing is also connected by another flange 13, is also provided with another metallic packing in the junction of this flange 13.
In the present invention, the designed life of tritium trap device is 2 years, and only uses once.After tritium trap device reaches serviceable life, need change tritium trap device.The concrete operation step changed is as follows:
Tritium trap device after using is taken out from glove box, closes the valve in draft tube and escape pipe in tritium trap device, prevent the tritium stored from leaking, the head protector of tritium trap device is covered simultaneously.Then the place being transported to a safety is stored up by whole tritium trap device, in such as refuse temporary library.Whole storage space arranges ventilation, and the heat avoiding tritium to decay excessively is assembled and reduced to be discharged into the tritium concentration of operating personnel behaviour area.When decaying to acceptable level Deng the tritium in tritium trap device, whole tritium trap device can regard a low-level waste process.
Above-described embodiment is only the preferred embodiments of the present invention, not limiting the scope of the invention, as long as adopt design concept of the present invention, and the change carried out non-creativeness work on this basis and make, all should belong within protection scope of the present invention.
Claims (10)
1. one kind for removing the tritium trap device of tritium in helium-3 gas, it is characterized in that: comprise outer casing (1), be positioned at the internal layer shell (2) that outer casing (1) is inner, outlet side port is positioned at the draft tube (4) of internal layer shell (2) lower inside, be fixed on the heating cavity (5) that internal layer shell (2) is inner, above the outlet side port being arranged on draft tube (4) and the titanium sponge (6) be filled between heating cavity (5) and internal layer shell (2), be arranged on internal layer shell (2) inside and the expansion headspace (7) be positioned at above titanium sponge (6), and inlet end port is positioned at the escape pipe (8) of expansion headspace (7).
2. a kind of tritium trap device for removing tritium in helium-3 gas according to claim 1, is characterized in that: the Al wall body of described heating cavity (5) and internal layer shell (2) being arranged one deck 2 ~ 2.5um
2o
3ceramic coat.
3. a kind of tritium trap device for removing tritium in helium-3 gas according to claim 1, is characterized in that: arrange or/and be filled with insulation material (9) in vacuum between described outer casing (1) and internal layer shell (2).
4. a kind of tritium trap device for removing tritium in helium-3 gas according to claim 1, is characterized in that: described escape pipe (8) and draft tube (4) are provided with gas filter.
5. a kind of tritium trap device for removing tritium in helium-3 gas according to any one of Claims 1 to 4, it is characterized in that: described internal layer shell (2) inner bottom is provided with gas distributor (3), this gas distributor (3) is positioned at above the outlet side port of titanium sponge (6) below, draft tube (4).
6. a kind of tritium trap device for removing tritium in helium-3 gas according to claim 5, is characterized in that: the outlet side port of described draft tube (4) to extend into from outer casing (1) top in internal layer shell (2) and extends to gas distributor (3) below after running through titanium sponge (6) from internal layer shell (2) top.
7. a kind of tritium trap device for removing tritium in helium-3 gas according to claim 6, it is characterized in that: the inlet end port of described escape pipe (8) extends in internal layer shell (2) from the top of outer casing (1), the draft tube (4) that this outer casing (1) is outside and escape pipe (8) are also respectively arranged with a valve (10), and this outer casing (1) outer tip end is also provided with head protector (11).
8. a kind of tritium trap device for removing tritium in helium-3 gas according to claim 7, is characterized in that: described gas distributor (3) top is provided with the silk screen (12) for placing titanium sponge (6).
9. a kind of tritium trap device for removing tritium in helium-3 gas according to claim 8, it is characterized in that: the internal layer shell (2) between described silk screen (12) and gas distributor (3) is provided with Inner shell connecting sewing, be connected by flange (13) respectively between described head protector (11) with outer casing (1) and on Inner shell connecting sewing, the junction of described flange (13) is also provided with metallic packing.
10. the detritiation method of a kind of tritium trap device for removing tritium in helium-3 gas as described in any one of claim 1 ~ 9, is characterized in that, comprise the following steps:
(1) will be passed into the lower inside of internal layer shell after helium-3 air preheat by draft tube, after preheating, temperature reaches 40 DEG C ~ 70 DEG C;
(2) helium-3 gas is by titanium sponge, and the tritium in titanium sponge and helium-3 gas reacts and generates solid-state tritium titanium compound under 370 DEG C ~ 400 DEG C conditions;
(3) namely this solid-state tritium titanium compound completes the process of tritium in removing helium-3 gas after being separated from this helium-3 gas.
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| CN110095802A (en) * | 2018-01-31 | 2019-08-06 | 中国辐射防护研究院 | A kind of method that hydrogen generates in analog study radioactive solid waste disposal process |
| CN110491536A (en) * | 2019-08-30 | 2019-11-22 | 西南石油大学 | A kind of Tritium Protection system and method for -3 transient test of helium |
| CN110491530A (en) * | 2019-08-30 | 2019-11-22 | 西南石油大学 | A kind of -3 power transience pilot system of helium and method |
| CN111545046A (en) * | 2020-04-03 | 2020-08-18 | 中国工程物理研究院材料研究所 | Laboratory air tritium removal system |
| CN113380435A (en) * | 2021-06-23 | 2021-09-10 | 中国核动力研究设计院 | Containing box for He-3 gas loop |
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