CN105923604A - Device and method for quickly recovering deuterium and tritium in fusion reactor discharged ash gases - Google Patents
Device and method for quickly recovering deuterium and tritium in fusion reactor discharged ash gases Download PDFInfo
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- CN105923604A CN105923604A CN201610245962.2A CN201610245962A CN105923604A CN 105923604 A CN105923604 A CN 105923604A CN 201610245962 A CN201610245962 A CN 201610245962A CN 105923604 A CN105923604 A CN 105923604A
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Abstract
The invention provides a device and method for quickly recovering deuterium and tritium in fusion reactor discharged ash gases. The device is divided into a main path and a branch path according to effects and necessities of various units in treatment processes. The main path only comprises a cryogenic pump and a Pd alloy film separating unit, and 96% or more deuterium and tritium fuels in the discharged ash gases can be recovered by virtue of the two units. The method for quickly recovering deuterium and tritium in the fusion reactor discharged ash gases is short in treatment time, and better meets requirements for quick recovery of the deuterium and tritium fuels; and meanwhile, the recovery process is simplified, which is conducive to reduction of the retention volume of tritium in a system, thereby avoiding impurity gases from causing adverse effects on a Pd alloy film separator. Moreover, a small amount of deuterium and tritium not recovered by the main path are recovered by the branch path, thereby ensuring relatively high recovery efficiency. The device and method for quickly recovering deuterium and tritium in the fusion reactor discharged ash gases have the advantages of short treatment cycle, simple process, high recovery rate, good system stability, long service life and the like, and can meet design requirements of existing fusion reactors.
Description
Technical field
The invention belongs to fusion reactor field, be specifically related to the deuterium tritium Rapid recovery device in a kind of fusion reactor ash discharge gas
And method.
Background technology
Along with the shortage of Fossil fuel, and the problem such as environmental pollution is day by day serious, and fusion energy resource gradually causes people
Attention.In the evolution of fusion energy resource, deuterium tritium fuel circulation is the engineering technology problem that must solve, and is also to realize
The basis of business application.Owing in fusion flow process, the response rate of deuterium tritium is the lowest, a large amount of unreacted deuterium tritiums are present in plasma
In ash discharge gas, from safe and environment-friendly and economic angle, it is necessary to ash discharge gas is processed, deuterium tritium fuel therein is carried out
Reclaim.
Deuterium tritium fuel recovery in ash discharge gas is mainly completed by plasma ash discharge gas processing system (TEP), closes
Suitable TEP flow process must is fulfilled for claimed below: (1) has sufficiently fast processing speed, in order to reduces and throws tritium amount；(2) possesses foot
The highest enough fuel recovery efficiency, " controls oneself " realizing tritium；(3) possess sufficiently fast de-protium speed, it is achieved protium separates with deuterium tritium,
To meet the requirement of the purity that feeds intake；(4) the lowest system tritium hold-up, to guarantee safety, and reduces the quantity in stock of tritium.
The technical flow design of TEP depends on the composition of plasma ash discharge gas.Concrete group of fusion reactor ash discharge gas
Become and content and the type of fusion reactor, relevant towards factors such as the material of plasma and experiment conditions, mainly include the most not
The deuterium tritium of reaction and a small amount of impurity, impurity includes Hydrocarbon, water, carbon monoxide, nitrogen etc..Wherein it is desired to reclaim
Deuterium tritium fuel major part is the Q of elemental2(Q2It is by the simple substance of the three of protium kinds of isotopics, including: H2、HD、HT、
D2、DT、T2), fraction is compound state (such as tritium acute pyogenic infection of nails alkane, HTO etc.).
At present, the most complete TEP flow process is Germany TLK(Tritiumlabor Karlsruhe) experiment
The CAPER technique of room development.Technological process mainly includes palladium membrance separation, catalytic reaction-membrance separation and catalytic exchange film reaction three
Individual unit.At palladium film separation unit, overwhelming majority elemental hydrogen isotope is separated and recovered through palladium film, the tail of palladium membrane separator
Gas then enters catalytic reaction-film separation unit, containing more Q in tail gas2O、CQ4, the foreign gas such as He.At catalytic reaction-film
Separative element, is converted into elemental by the catalytic reaction such as methane cracking, steam reforming by the hydrogen isotope of compound state, and passes through
Palladium membrance separation reclaims, and partial tail gas then enters catalytic exchange film reaction unit, possibly together with a small amount of Q in this tail gas2O、CQ4And
He、CO、CO2Etc. foreign gas.The tail gas of catalytic reaction-film separation unit enters back into catalytic exchange film reaction unit, Q2O、CQ4
With a large amount of H2Hydrogen isotopic exchange reaction occurs, and the deuterium tritium of compound state is replaced out (being converted into elemental), and through palladium film
Separation and recovery.Through these three processing unit, in tail gas, deuterium tritium level is extremely low, and as required, tail gas can enter waste gas detritiation list
Unit processes further.
CAPER flow process is through the development of TLK laboratory decades, and its feasibility has been substantially achieved checking.But, this flow process
In, unit (i.e. catalytic reaction-film separation unit and the catalytic exchange film reaction unit) used time reclaiming compound state deuterium tritium is longer, and
Expend higher.Meanwhile, the designers of fusion reactor improve the material towards plasma in recent years, in the material of selection
Not carbon elements, makes the content of foreign gas in ash discharge gas (including compound state deuterium tritium) be substantially reduced, and this also makes CAPER flow process
Deficiency is demonstrated at aspects such as processing speed and system tritium hold-ups.And, if impurity content is higher in ash discharge gas, directly enter
Entering in Pd alloy film separator, it is the most unfavorable to cause the service life of Pd alloy film separator and system stability
Impact.
Summary of the invention
The technical problem that the invention solves the problems that is to provide the deuterium tritium Rapid recovery device in a kind of fusion reactor ash discharge gas,
Another technical problem that the invention solves the problems that is to provide the deuterium tritium fastly recovering in a kind of fusion reactor ash discharge gas.
Deuterium tritium Rapid recovery device in the fusion reactor ash discharge gas of the present invention, is characterized in, including cryopump, Pd alloy film
Separative element, chromatographic column, Pd alloy film reaction member, the ash discharge gas that fusion reaction room generates, by cryopump, is divided into A road, B
Road, A road is divided into A1 road, A2 road, A3 road after entering Pd alloy film separative element；A1 road is connected with tritium stocking system；A2 passes through on road
It is connected with tritium stocking system, hydrogen isotope separation system respectively after chromatographic column；A3 road enters useless by Pd alloy film reaction member
Gas detritiation system or hydrogen isotope separation system；B road enters waste gas detritiation system or hydrogen coordination by Pd alloy film reaction member
Element piece-rate system.
Described cryopump is combined by low temperature molecular sieve post and helium refrigeration low-temperature pump, and low temperature molecular sieve post is as prime
Pump, operating temperature is 77K, extracts out except He and Q2Foreign gas in addition, helium refrigeration low-temperature pump work temperature is 4K, extract out He and
Q2。
Described Pd alloy film separative element is composed in series by two or more Pd alloy film separators, described
Pd alloy is the one in Pd+Ag, Pd+Y, Pd+Ag+Au, Pd+Ag+Au+Y or Pd+Ag+Au+Ni alloy.
Described chromatographic column is loaded Al2O3+1%SiO2, coating Fe2O34A molecular sieve or 5A molecular sieve in one, color
Spectrum post operating temperature range is 77K ~ 150K.
Described Pd alloy film reaction member is made up of two or more Pd alloy film reactors in series, described
Pd alloy is the one in Pd+Ag, Pd+Y, Pd+Ag+Au, Pd+Ag+Au+Y or Pd+Ag+Au+Ni alloy.
Deuterium tritium fastly recovering in the fusion reactor ash discharge gas of the present invention, comprises the following steps:
6a. rough segmentation
Ash discharge gas, after cryopump is extracted out, carries out desorbing in cryopump, obtains gas I, tail gas I；Gas I includes Q2And He,
Tail gas I includes N2、Q2O、CO2And CQ4；
6b.Pd film purification
Gas I enters Pd alloy film separative element and separates, and obtains gas II, tail gas II, and gas II is Q2Gas；Tail gas II includes
He and Q2Gas, Q2The content of gas is less than 5%；
6c. processes after purification
When H/Q < 10% and T/D=0.95 ~ 1.05 in gas II, gas II enters tritium stocking system；
When H/Q >=10% in gas II, gas II enters chromatographic column and takes off protium, obtains gas III, tail gas III, the H/Q in gas III
< 10% and during T/D=0.95 ~ 1.05, gas III enters tritium stocking system；Tail gas III enters hydrogen isotope separation system；
6d. foreign gas processes
Tail gas I, tail gas II enter air accumulator and store, and when storage capacity reaches to set quantity, enter Pd alloy film reaction member and start
Catalytic membrane reaction generates Q2With tail gas IV, Q2Enter hydrogen isotope separation system, tail gas IV enters waste gas detritiation system, tail gas IV
Including N2、H2O、CO2And CH4。
The catalyst that the catalytic membrane reaction of described step 6d uses is Pt+Al2O3、Pd+Al2O3、Ni+Al2O3、Pt+
CeO2Or Pd+CeO2In one or two or more kinds.
Deuterium tritium Rapid recovery device in the fusion reactor ash discharge gas of the present invention, according to each unit effect in handling process
And necessity, main road and branch road can be divided into.Wherein, no matter main road is ash discharge gas composition, the unit that will pass through, including low
Temperature pump and Pd alloy film separative element；Branch road includes chromatographic column and Pd alloy film reaction member, and ash discharge gas is the need of through being somebody's turn to do
Unit is then depending on impurity therein and protium content situation: if foreign gas content is less than 1% in ash discharge gas, can be from cryopump
Pd alloy film separative element it is directly entered after desorbing；If impurity content is higher than 1%, then after cryopump rough segmentation, by impurity
Gas is stored in buffer unit, enters Pd alloy film reaction member after reaching to set quantity；If by Pd alloy film separative element
In the hydrogen isotope gas obtained, protium content is less than 10%, then be not required to through chromatographic column, be directly entered tritium stocking system.Such one
Coming, in the case of ash discharge gas impurity content is relatively low, the recovery of deuterium tritium fuel will be greatly shortened with the separation process cycle.
Owing to the main road of the deuterium tritium Rapid recovery device in the fusion reactor ash discharge gas of the present invention only comprising cryopump and Pd
Alloy film separative element, can be reclaimed the deuterium tritium fuel of more than 96% in ash discharge gas by the two unit.The fusion of the present invention
It is short that deuterium tritium fastly recovering in heap ash discharge gas processes the time, more conforms to quickly reclaim the requirement of deuterium tritium fuel；Meanwhile, main
The recovery process wanted is greatly simplified, and advantageously reduces the hold-up of tritium in system.And, a small amount of deuterium tritium not reclaimed by main road
Reclaimed by branch road, it is ensured that higher organic efficiency.Additionally, after cryopump rough segmentation, enter Pd alloy film and separate single
The foreign gas amount of unit reduces, the stability of beneficially raising system, and increases the service life.
Deuterium tritium Rapid recovery device in the fusion reactor ash discharge gas of the present invention and method combine the spy of existing fusion reactor
Point, in high efficiente callback fusion reactor ash discharge gas while deuterium tritium fuel, speed up processing, simplify recovery process, reduce system
The hold-up of middle tritium, it is to avoid the foreign gas adverse effect to Pd alloy film separator, has that the process cycle is short, flow process is simple
The advantage such as list, response rate height, good, the length in service life of system stability, it is possible to meet the design requirement of existing fusion reactor.
Accompanying drawing explanation
Fig. 1 is the deuterium tritium Rapid recovery device in the fusion reactor ash discharge gas of the present invention and the workflow schematic diagram of method.
Detailed description of the invention
The present invention is described in detail below in conjunction with the accompanying drawings with embodiment.
All features disclosed in this specification, or disclosed all methods or during step, except mutually exclusive
Feature and/or step beyond, all can combine by any way.
Any feature disclosed in this specification, unless specifically stated otherwise, all can by other equivalence or there is similar purpose
Alternative features is replaced.I.e., unless specifically stated otherwise, an example during each feature is a series of equivalence or similar characteristics
?.
Deuterium tritium Rapid recovery device in the fusion reactor ash discharge gas of the present invention, including cryopump, Pd alloy film separative element,
Chromatographic column, Pd alloy film reaction member, the ash discharge gas that fusion reaction room generates, by cryopump, is divided into A road, B road, and A road enters
A1 road, A2 road, A3 road it is divided into after Pd alloy film separative element；A1 road is connected with tritium stocking system；A2 road is by after chromatographic column point
It is not connected with tritium stocking system, hydrogen isotope separation system；A3 road enters waste gas detritiation system by Pd alloy film reaction member
Or hydrogen isotope separation system；B road enters waste gas detritiation system or hydrogen isotope separation system by Pd alloy film reaction member.
Described cryopump is combined by low temperature molecular sieve post and helium refrigeration low-temperature pump, and low temperature molecular sieve post is as prime
Pump, operating temperature is 77K, extracts out except He and Q2Foreign gas in addition, helium refrigeration low-temperature pump work temperature is 4K, extract out He and
Q2。
Described Pd alloy film separative element is composed in series by two or more Pd alloy film separators, described
Pd alloy is the one in Pd+Ag, Pd+Y, Pd+Ag+Au, Pd+Ag+Au+Y or Pd+Ag+Au+Ni alloy.
Described chromatographic column is loaded Al2O3+1%SiO2, coating Fe2O34A molecular sieve or 5A molecular sieve in one, color
Spectrum post operating temperature range is 77K ~ 150K.
Described Pd alloy film reaction member is made up of two or more Pd alloy film reactors in series, described
Pd alloy is the one in Pd+Ag, Pd+Y, Pd+Ag+Au, Pd+Ag+Au+Y or Pd+Ag+Au+Ni alloy.
Deuterium tritium fastly recovering in the fusion reactor ash discharge gas of the present invention, comprises the following steps:
6a. rough segmentation
Ash discharge gas, after cryopump is extracted out, carries out desorbing in cryopump, obtains gas I, tail gas I；Gas I includes Q2And He,
Tail gas I includes N2、Q2O、CO2And CQ4；
6b.Pd film purification
Gas I enters Pd alloy film separative element and separates, and obtains gas II, tail gas II, and gas II is Q2Gas；Tail gas II includes
He and Q2Gas, Q2The content of gas is less than 5%；
6c. processes after purification
When H/Q < 10% and T/D=0.95 ~ 1.05 in gas II, gas II enters tritium stocking system；
When H/Q >=10% in gas II, gas II enters chromatographic column and takes off protium, obtains gas III, tail gas III, the H/Q in gas III
< 10% and during T/D=0.95 ~ 1.05, gas III enters tritium stocking system；Tail gas III enters hydrogen isotope separation system；
6d. foreign gas processes
Tail gas I, tail gas II enter air accumulator and store, and when storage capacity reaches to set quantity, enter Pd alloy film reaction member and start
Catalytic membrane reaction generates Q2With tail gas IV, Q2Entering hydrogen isotope separation system, tail gas IV enters waste gas detritiation system, tail gas IV
Including N2、H2O、CO2And CH4。
The catalyst that the catalytic membrane reaction of described step 6d uses is Pt+Al2O3、Pd+Al2O3、Ni+Al2O3、Pt+
CeO2Or Pd+CeO2In one or two or more kinds.
Embodiment 1
Component and the content of ash discharge gas are as follows: Q299.10%, He 0.50%, Q2O 0.10%, CQ40.08%, CO 0.06%, CO2
0.03%, N20.10%, O2 0.03%。
It is in the present embodiment, due to the content of foreign gas the lowest (less than 1.0%), less to the performance impact of Pd alloy film,
Before and after cryopump, level desorbing simultaneously obtains gas, it is directly entered Pd alloy film separative element, oozing of Pd alloy film separative element
Breathe freely the Q for high-purity (＞ 99.999%)2(it is designated as gas), gasMiddle protium, deuterium, tritium level (percentage by volume) are respectively
2.0%, 48.7%, 49.3%, it is directly entered tritium stocking system.The tail gas that Pd alloy film separative element separates (is designated as tail gasIn)
Containing a small amount of Q2And He, Q2O、CQ4、CO、CO2、N2、O2Etc. foreign gas, (in the present embodiment, buffering fills to be stored in buffer unit
Put employing air accumulator) in.After the tail gas in air accumulator reaches 1L, send into Pd alloy film reaction member, at Pt/Al2O3Catalyst
Reacting through three grades of hydrogen isotopic exchange under effect, the infiltration gas of Pd alloy film reaction member is high-purity Q2, enter hydrogen coordination
Element piece-rate system (uses low temperature distillation system) in the present embodiment, to remove protium therein；The tail gas that reaction produces (is designated as tail gasIn), deuterium tritium level extremely low (＜ 0.01%), enter waste gas detritiation system and process further.
After measured, needed for processing same composition, the ash discharge gas of volume, the present invention, the process time is only CAPER technological process
0.3 ~ 0.35 times.
Embodiment 2
In the present embodiment, component and the content of ash discharge gas are as follows: Q294.10%, He 2.80%, Q2O 0.80%, CQ40.65%,
CO 0.35%, CO20.28%, N20.90%, O2 0.12%。
In the present embodiment, owing to the content of foreign gas is of a relatively high, the prime of cryopump and rear class desorbing respectively, prime
Low temperature molecular sieve post desorbing at normal temperatures obtain tail gas, helium refrigeration low-temperature pump desorbing under 77K of rear class obtains gas.Gas
BodyBe mainly composed of Q2And He, tail gasContaining a small amount of Q2And He, Q2O、CQ4、CO、CO2、N2、O2Etc. foreign gas.Gas
Enter Pd alloy film separative element, obtain gasAnd tail gas, gasMiddle protium, deuterium, tritium level be respectively 11.0%, 44.2%,
44.8%.Due to gasMiddle protium content is higher, enters filling Al2O3+1%SiO2Chromatographic column in carry out de-protium and process, chromatographic column
Temperature is 77K, it is thus achieved that protium, deuterium, tritium level are respectively the product gas of 1.0%, 49.2%, 49.8% and (are designated as gas), gas
Enter tritium stocking system.The tail gas of chromatographic column (is designated as tail gasIn), protium, deuterium, the content of tritium are respectively 95.2%, 2.5%, 2.3%,
Enter hydrogen isotope separation system (using low temperature distillation system in the present embodiment) again to separate.Tail gasAnd tail gasStorage
It is stored in buffer unit (in the present embodiment, buffer unit uses air accumulator).After the tail gas in air accumulator reaches 1L, send into Pd
Alloy film reaction member, at Ni/Al2O3And Pt/CeO2Hydrogen isotopic exchange reaction and steam weight is there is respectively under catalyst action
Whole reaction, the infiltration gas of Pd alloy film reaction member is high-purity Q2, enter hydrogen isotope separation system and (the present embodiment use
Low temperature distillation system), to remove protium therein；The tail gas that reaction produces (is designated as tail gasIn), the extremely low (＜ of deuterium tritium level
0.01%), enter waste gas detritiation system to process further.
After measured, needed for processing same composition, the ash discharge gas of volume, the present invention, the process time is only CAPER technological process
0.4 ~ 0.55 times.
The invention is not limited in aforesaid detailed description of the invention.The present invention expands to any disclose in this manual
New feature or any new combination, and the arbitrary new method that discloses or the step of process or any new combination.
Claims (7)
1. the deuterium tritium Rapid recovery device in a fusion reactor ash discharge gas, it is characterised in that: described device includes cryopump, Pd
Alloy film separative element, chromatographic column, Pd alloy film reaction member, the ash discharge gas that fusion reaction room generates, by cryopump, is divided into A
Road, B road, A road is divided into A1 road, A2 road, A3 road after entering Pd alloy film separative element；A1 road is connected with tritium stocking system；A2 road
By being connected with tritium stocking system, hydrogen isotope separation system respectively after chromatographic column；A3 road is entered by Pd alloy film reaction member
Enter waste gas detritiation system or hydrogen isotope separation system；B road enters waste gas detritiation system or hydrogen by Pd alloy film reaction member
Isotopic separation system.
Deuterium tritium Rapid recovery device in fusion reactor ash discharge gas the most according to claim 1, it is characterised in that described is low
Temperature pump is combined by low temperature molecular sieve post and helium refrigeration low-temperature pump, and low temperature molecular sieve post as backing pump, operating temperature is
77K, extracts out except He and Q2Foreign gas in addition, helium refrigeration low-temperature pump work temperature is 4K, extracts He and Q out2。
Deuterium tritium Rapid recovery device in fusion reactor ash discharge gas the most according to claim 1, it is characterised in that described Pd
Alloy film separative element is composed in series by two or more Pd alloy film separators, and described Pd alloy is Pd+Ag, Pd
One in+Y, Pd+Ag+Au, Pd+Ag+Au+Y or Pd+Ag+Au+Ni alloy.
Deuterium tritium Rapid recovery device in fusion reactor ash discharge gas the most according to claim 1, it is characterised in that described color
Spectrum post loads Al2O3+1%SiO2, coating Fe2O34A molecular sieve or 5A molecular sieve in one, chromatographic column operating temperature range
For 77K ~ 150K.
Deuterium tritium Rapid recovery device in fusion reactor ash discharge gas the most according to claim 1, it is characterised in that described Pd
Alloy film reaction member is made up of two or more Pd alloy film reactors in series, and described Pd alloy is Pd+Ag, Pd
One in+Y, Pd+Ag+Au, Pd+Ag+Au+Y or Pd+Ag+Au+Ni alloy.
6. the deuterium tritium fastly recovering in fusion reactor ash discharge gas, comprises the following steps:
6a. rough segmentation
Ash discharge gas, after cryopump is extracted out, carries out desorbing in cryopump, obtains gas I, tail gas I；Gas I includes Q2And He, tail
Gas I includes N2、Q2O、CO2And CQ4；
6b.Pd film purification
Gas I enters Pd alloy film separative element and separates, and obtains gas II, tail gas II, and gas II is Q2Gas；Tail gas II includes
He and Q2Gas, Q2The content of gas is less than 5%；
6c. processes after purification
When H/Q < 10% and T/D=0.95 ~ 1.05 in gas II, gas II enters tritium stocking system；
When H/Q >=10% in gas II, gas II enters chromatographic column and takes off protium, obtains gas III, tail gas III, the H/Q in gas III
< 10% and during T/D=0.95 ~ 1.05, gas III enters tritium stocking system；Tail gas III enters hydrogen isotope separation system；
6d. foreign gas processes
Tail gas I, tail gas II enter air accumulator and store, and when storage capacity reaches to set quantity, enter Pd alloy film reaction member and start
Catalytic membrane reaction generates Q2With tail gas IV, Q2Enter hydrogen isotope separation system, tail gas IV enters waste gas detritiation system, tail gas IV
Including N2、H2O、CO2And CH4。
Deuterium tritium fastly recovering in fusion reactor ash discharge gas the most according to claim 6, it is characterised in that described step
The catalyst that the catalytic membrane reaction of rapid 6d uses is Pt+Al2O3、Pd+Al2O3、Ni+Al2O3、Pt+CeO2Or Pd+CeO2In one
Kind or more than.
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Cited By (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106474924A (en) * | 2016-11-08 | 2017-03-08 | 中国工程物理研究院材料研究所 | A kind of enrichment method of trace tritium |
| CN107469628A (en) * | 2017-09-21 | 2017-12-15 | 中国科学院上海应用物理研究所 | The device and method of gaseous state tritium and its isotope in a kind of removal fused salt |
| CN107993733A (en) * | 2017-12-07 | 2018-05-04 | 中国工程物理研究院核物理与化学研究所 | The three-level cryogenic pump processing unit and processing method of a kind of fusion reactor radioactivity tail gas |
| CN108479393A (en) * | 2018-04-18 | 2018-09-04 | 中国工程物理研究院核物理与化学研究所 | The minimizing technology of protium in a kind of isotope gas containing hydrogen tritide |
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| 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 |
| CN112834668A (en) * | 2020-12-30 | 2021-05-25 | 中国原子能科学研究院 | Low-temperature control device for analyzing hydrogen isotopes by gas chromatography |
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Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN1715179A (en) * | 2005-06-07 | 2006-01-04 | 四川材料与工艺研究所 | Hydrogen isotope separating device and method |
| CN105233691A (en) * | 2015-09-14 | 2016-01-13 | 中国工程物理研究院核物理与化学研究所 | Hydrogen isotope efficient recovery apparatus based on catalysis reaction and membrane separation cascade connection, and recovery method thereof |
-
2016
- 2016-04-20 CN CN201610245962.2A patent/CN105923604B/en not_active Expired - Fee Related
Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN1715179A (en) * | 2005-06-07 | 2006-01-04 | 四川材料与工艺研究所 | Hydrogen isotope separating device and method |
| CN105233691A (en) * | 2015-09-14 | 2016-01-13 | 中国工程物理研究院核物理与化学研究所 | Hydrogen isotope efficient recovery apparatus based on catalysis reaction and membrane separation cascade connection, and recovery method thereof |
Cited By (14)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106474924A (en) * | 2016-11-08 | 2017-03-08 | 中国工程物理研究院材料研究所 | A kind of enrichment method of trace tritium |
| CN107469628B (en) * | 2017-09-21 | 2019-10-01 | 中国科学院上海应用物理研究所 | The device and method of gaseous state tritium and its isotope in a kind of removal fused salt |
| CN107469628A (en) * | 2017-09-21 | 2017-12-15 | 中国科学院上海应用物理研究所 | The device and method of gaseous state tritium and its isotope in a kind of removal fused salt |
| CN107993733A (en) * | 2017-12-07 | 2018-05-04 | 中国工程物理研究院核物理与化学研究所 | The three-level cryogenic pump processing unit and processing method of a kind of fusion reactor radioactivity tail gas |
| CN107993733B (en) * | 2017-12-07 | 2020-11-03 | 中国工程物理研究院核物理与化学研究所 | Three-stage cryogenic pump treatment device and method for radioactive tail gas of fusion reactor |
| CN108479393A (en) * | 2018-04-18 | 2018-09-04 | 中国工程物理研究院核物理与化学研究所 | The minimizing technology of protium in a kind of isotope gas containing hydrogen tritide |
| CN109513464A (en) * | 2018-12-11 | 2019-03-26 | 中国工程物理研究院材料研究所 | A kind of rare earth oxide carries platinum hydrophobic catalyst and its preparation method and application |
| CN112037958A (en) * | 2020-09-09 | 2020-12-04 | 中国工程物理研究院核物理与化学研究所 | High-concentration tritium water treatment device |
| CN112037958B (en) * | 2020-09-09 | 2022-09-23 | 中国工程物理研究院核物理与化学研究所 | High-concentration tritium water treatment device |
| 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 |
| CN112834668A (en) * | 2020-12-30 | 2021-05-25 | 中国原子能科学研究院 | Low-temperature control device for analyzing hydrogen isotopes by gas chromatography |
| CN115385302A (en) * | 2022-07-28 | 2022-11-25 | 青岛元动芯能源科技有限公司 | Tritium recovery and purification system and method for waste neutron target |
| CN115385302B (en) * | 2022-07-28 | 2024-01-02 | 中子时代(青岛)创新科技有限公司 | Tritium recovery and purification system and method for waste neutron target |
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