CN105923604B - Deuterium tritium Rapid recovery device and method in a kind of fusion reactor ash discharge gas - Google Patents

Deuterium tritium Rapid recovery device and method in a kind of fusion reactor ash discharge gas Download PDF

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CN105923604B
CN105923604B CN201610245962.2A CN201610245962A CN105923604B CN 105923604 B CN105923604 B CN 105923604B CN 201610245962 A CN201610245962 A CN 201610245962A CN 105923604 B CN105923604 B CN 105923604B
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gas
tritium
ash discharge
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tail gas
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CN105923604A (en
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熊亮萍
王和义
龚宇
岳磊
侯京伟
陈晓军
刘云怒
夏修龙
肖成建
张勤英
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Institute of Nuclear Physics and Chemistry China Academy of Engineering Physics
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Institute of Nuclear Physics and Chemistry China Academy of Engineering Physics
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    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01B—NON-METALLIC ELEMENTS; COMPOUNDS THEREOF; METALLOIDS OR COMPOUNDS THEREOF NOT COVERED BY SUBCLASS C01C
    • C01B4/00—Hydrogen isotopes; Inorganic compounds thereof prepared by isotope exchange, e.g. NH3 + D2 → NH2D + HD

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  • Health & Medical Sciences (AREA)
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Abstract

The invention provides the deuterium tritium Rapid recovery device in a kind of fusion reactor ash discharge gas and method, according to effect and necessity of each unit in handling process, is divided into main road and branch road.Cryogenic pump and Pd alloy film separation units are only included in main road, in ash discharge gas more than 96% deuterium tritium fuel can be reclaimed by the two units.Deuterium tritium fastly recovering processing time is short in the fusion reactor ash discharge gas of the present invention, more conform to the requirement of quick recovery deuterium tritium fuel；Meanwhile recovery process simplifies, and advantageously reduces the hold-up of tritium in system, avoids adverse effect of the foreign gas to Pd alloy membrane separators.Moreover, not reclaimed by a small amount of deuterium tritium that main road reclaims by branch road, higher organic efficiency ensure that.Deuterium tritium Rapid recovery device and method in fusion reactor ash discharge gas of the present invention have the advantages that process cycle is short, flow is simple, the rate of recovery is high, the stability of a system is good, service life is long, disclosure satisfy that the design requirement of existing fusion reactor.

Description

Deuterium tritium Rapid recovery device and method in a kind of fusion reactor ash discharge gas
Technical field
The invention belongs to fusion reactor field, and in particular to the deuterium tritium Rapid recovery device in a kind of fusion reactor ash discharge gas And method.
Background technology
With the shortage of fossil fuel, and getting worse the problems such as environmental pollution, fusion energy resource gradually cause people Attention.In the evolution of fusion energy resource, deuterium tritium fuel circulation is the engineering technology problem that must be solved, and is realized The basis of business application.Because the reactivity of deuterium tritium in fusion flow is very low, 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 handled, deuterium tritium fuel therein is carried out Recovery.
Deuterium tritium fuel recovery in ash discharge gas mainly passes through plasma ash discharge gas processing system（TEP）Complete, close Suitable TEP flows must are fulfilled for claimed below：（1）With sufficiently fast processing speed, tritium amount is thrown to reduce；（2）Possesses foot Enough high fuel recovery efficiency, to realize tritium " self-holding "；（3）Possess sufficiently fast de- protium speed, realize the separation of protium and deuterium tritium, The requirement for the purity that fed intake with satisfaction；（4）Low system tritium hold-up as far as possible, to ensure safety, and reduces the quantity in stock of tritium.
TEP technical flow design depends on the composition of plasma ash discharge gas.Specific group of fusion reactor ash discharge gas Into and it is content and the type of fusion reactor, relevant towards the factor such as the material of plasma and experiment condition, it is main include it is a large amount of not The deuterium tritium and a small amount of impurity of reaction, impurity include hydrocarbon, water, carbon monoxide, nitrogen etc.., wherein it is desired to recovery Deuterium tritium fuel is largely the Q of elemental2（Q2Be by the simple substance of three kinds of isotopics of protium, including：H2、HD、HT、 D2、DT、T2）, fraction is compound state（Such as tritium is for methane, HTO）.
At present, comparatively complete TEP flows are German TLK in the world（Tritiumlabor Karlsruhe）Experiment The CAPER techniques of room development.Technological process mainly includes palladium UF membrane, catalytic reaction-UF membrane and catalysis and exchanges film reaction three Individual unit.In palladium film separation unit, most elemental hydrogen isotopes are separated through palladium film and reclaimed, the tail of palladium membrane separator Gas then enters catalytic reaction-film separation unit, contains more Q in tail gas2O、CQ4, the foreign gas such as He.In catalytic reaction-film Separative element, the hydrogen isotope of compound state is converted into by elemental by catalytic reactions such as methane cracking, steam reformings, and passed through Palladium UF membrane reclaims, and partial tail gas then enters catalysis exchange membrane reaction member, also contains a small amount of Q in the tail gas2O、CQ4And He、CO、CO2Etc. foreign gas.The tail gas of catalytic reaction-film separation unit enters back into catalysis exchange membrane reaction member, Q2O、CQ4 With a large amount of H2Generation hydrogen isotopic exchange reacts, and the deuterium tritium of compound state is replaced out（It is converted into elemental）, and pass through palladium film Separation and recovery.By these three processing units, deuterium tritium level is extremely low in tail gas, and as needed, tail gas can enter waste gas detritiation list First further processing.
CAPER flows pass through the development of TLK laboratories decades, and its feasibility has been substantially achieved checking.However, the flow In, the unit of recovery compound state deuterium tritium（That is catalytic reaction-film separation unit and catalysis exchange membrane reaction member）Used time 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, make foreign gas in ash discharge gas（Including compound state deuterium tritium）Content substantially reduce, this also causes CAPER flows Deficiency is shown in processing speed and system tritium hold-up etc..Moreover, if impurity content is higher in ash discharge gas, directly enter Enter in Pd alloy membrane separators, it is more obvious unfavorable that the service life and the stability of a system of Pd alloy membrane separators can be caused Influence.
The content of the invention
The invention solves a technical problem be to provide a kind of deuterium tritium Rapid recovery device in fusion reactor ash discharge gas, The invention solves another technical problem be to provide a kind of deuterium tritium fastly recovering in 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 cryogenic pump, Pd alloy films Separative element, chromatographic column, Pd alloy film reaction members, the ash discharge gas of fusion reaction room generation are divided into A roads, B by cryogenic pump Road, A roads are divided into A1 roads, A2 roads, A3 roads after entering Pd alloy film separation units；A1 roads are connected with tritium stocking system；A2 roads pass through It is connected respectively with tritium stocking system, hydrogen isotope separation system after chromatographic column；A3 roads are entered useless by Pd alloy films reaction member Gas removes tritium system or hydrogen isotope separation system；B roads tritium system or the same position of hydrogen are removed into waste gas by Pd alloy films reaction member Plain piece-rate system.
Described cryogenic pump sieves post by low temperature molecular and helium refrigeration low-temperature pump combines, and low temperature molecular sieves post as prime Pump, operating temperature 77K, extraction remove He and Q2Foreign gas in addition, helium refrigeration low-temperature pump work temperature are 4K, extract out He and Q2。
Described Pd alloys film separation unit is composed in series by two or more Pd alloys membrane separators, described Pd alloys are one kind in Pd+Ag, Pd+Y, Pd+Ag+Au, Pd+Ag+Au+Y or Pd+Ag+Au+Ni alloy.
Al is loaded in described chromatographic column2O3+1%SiO2, coating Fe2O34A molecular sieves or 5A molecular sieves in one kind, color It is 77K ~ 150K to compose post operating temperature range.
Described Pd alloy films reaction member is composed in series by two or more Pd alloys membrane reactors, described Pd alloys are one kind 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 segmentations
Ash discharge gas is desorbed after low temperature pumped in cryogenic pump, obtains gas I, tail gas I；Gas I includes Q2With He, tail gas I include N2、Q2O、CO2And CQ4；
6b.Pd films purify
Gas I enters the separation of Pd alloys film separation unit, obtains gas II, tail gas II, gas II is Q2Gas；Tail gas II Including He and Q2Gas, Q2The content of gas is less than 5%；
6c. purifying post processings
As H/Q in gas II<When 10% and T/D=0.95 ~ 1.05, gas II enters tritium stocking system；
As H/Q in gas II >=10%, gas II enters chromatographic column and takes off protium, obtains gas III, tail gas III, in gas III H/Q<When 10% and T/D=0.95 ~ 1.05, gas III enters tritium stocking system；Tail gas III enters hydrogen isotope separation system；
The processing of 6d. foreign gases
Tail gas I, tail gas II enter air accumulator and stored, when storage capacity reaches setting quantity, into Pd alloy film reaction members Start to be catalyzed film reaction generation Q2With tail gas IV, Q2Into hydrogen isotope separation system, tail gas IV tritium system, tail are removed into waste gas Gas IV includes N2、H2O、CO2And CH4。
The catalyst that described step 6d catalysis film reaction 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 effect of each unit 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 it is low Warm pump and Pd alloy film separation unit；Branch road includes whether chromatographic column and Pd alloy film reaction members, ash discharge gas are needed by this 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 cryogenic pump Pd alloy film separation units are directly entered after desorption；If impurity content is higher than 1%, after cryogenic pump rough segmentation, by impurity Gas is stored in buffer unit, enters Pd alloy film reaction members after reaching setting quantity；If by Pd alloy film separation units Protium content is less than 10% in obtained hydrogen isotope gas, then is not required to by chromatographic column, is directly entered tritium stocking system.Such one Come, in the case where ash discharge gas impurity content is relatively low, recovery and the separation process cycle of deuterium tritium fuel will greatly shorten.
Due to only including cryogenic pump and Pd in the main road of the deuterium tritium Rapid recovery device in the fusion reactor ash discharge gas of the present invention Alloy film separation unit, in ash discharge gas more than 96% deuterium tritium fuel can be reclaimed by the two units.The fusion of the present invention Deuterium tritium fastly recovering processing time is short in heap ash discharge gas, more conform to the requirement of quick recovery deuterium tritium fuel；It is meanwhile main The recovery process wanted greatly simplifies, and advantageously reduces the hold-up of tritium in system.Moreover, a small amount of deuterium tritium not reclaimed by main road Reclaimed by branch road, ensure that higher organic efficiency.In addition, after cryogenic pump rough segmentation, into Pd alloy UF membrane lists The foreign gas amount of member reduces, and is advantageous to the stability of raising system, and increase the service life.
Deuterium tritium Rapid recovery device and method in the fusion reactor ash discharge gas of the present invention 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, adverse effect of the foreign gas to Pd alloy membrane separators is avoided, have that process cycle is short, flow is simple The advantages that list, the rate of recovery are high, the stability of a system is good, service life is long, disclosure satisfy that the design requirement of existing fusion reactor.
Brief description of the drawings
Fig. 1 is the workflow schematic diagram of the deuterium tritium Rapid recovery device and method in the fusion reactor ash discharge gas of the present invention.
Embodiment
Describe the present invention in detail with reference to the accompanying drawings and examples.
All features disclosed in this specification, or disclosed all methods or during the step of, except mutually exclusive Feature and/or step beyond, can combine in any way.
Any feature disclosed in this specification, unless specifically stated otherwise, can be equivalent by other or with similar purpose Alternative features are replaced.I.e., unless specifically stated otherwise, each feature is an example in a series of equivalent or similar characteristics .
The present invention fusion reactor ash discharge gas in deuterium tritium Rapid recovery device, including cryogenic pump, Pd alloys film separation unit, Chromatographic column, Pd alloy film reaction members, the ash discharge gas of fusion reaction room generation are divided into A roads, B roads, A roads enter by cryogenic pump It is divided into A1 roads, A2 roads, A3 roads after Pd alloy film separation units；A1 roads are connected with tritium stocking system；A2 roads pass through after chromatographic column points It is not connected with tritium stocking system, hydrogen isotope separation system；A3 roads tritium system is removed into waste gas by Pd alloy films reaction member Or hydrogen isotope separation system；B roads tritium system or hydrogen isotope separation system are removed into waste gas by Pd alloy films reaction member.
Described cryogenic pump sieves post by low temperature molecular and helium refrigeration low-temperature pump combines, and low temperature molecular sieves post as prime Pump, operating temperature 77K, extraction remove He and Q2Foreign gas in addition, helium refrigeration low-temperature pump work temperature are 4K, extract out He and Q2。
Described Pd alloys film separation unit is composed in series by two or more Pd alloys membrane separators, described Pd alloys are one kind in Pd+Ag, Pd+Y, Pd+Ag+Au, Pd+Ag+Au+Y or Pd+Ag+Au+Ni alloy.
Al is loaded in described chromatographic column2O3+1%SiO2, coating Fe2O34A molecular sieves or 5A molecular sieves in one kind, color It is 77K ~ 150K to compose post operating temperature range.
Described Pd alloy films reaction member is composed in series by two or more Pd alloys membrane reactors, described Pd alloys are one kind 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 segmentations
Ash discharge gas is desorbed after low temperature pumped in cryogenic pump, obtains gas I, tail gas I；Gas I includes Q2With He, tail gas I include N2、Q2O、CO2And CQ4；
6b.Pd films purify
Gas I enters the separation of Pd alloys film separation unit, obtains gas II, tail gas II, gas II is Q2Gas；Tail gas II Including He and Q2Gas, Q2The content of gas is less than 5%；
6c. purifying post processings
As H/Q in gas II<When 10% and T/D=0.95 ~ 1.05, gas II enters tritium stocking system；
As H/Q in gas II >=10%, gas II enters chromatographic column and takes off protium, obtains gas III, tail gas III, in gas III H/Q<When 10% and T/D=0.95 ~ 1.05, gas III enters tritium stocking system；Tail gas III enters hydrogen isotope separation system；
The processing of 6d. foreign gases
Tail gas I, tail gas II enter air accumulator and stored, when storage capacity reaches setting quantity, into Pd alloy film reaction members Start to be catalyzed film reaction generation Q2With tail gas IV, Q2Into hydrogen isotope separation system, tail gas IV removes tritium system, tail into waste gas Gas IV includes N2、H2O、CO2And CH4。
The catalyst that described step 6d catalysis film reaction uses is Pt+Al2O3、Pd+Al2O3、Ni+Al2O3、Pt+ CeO2Or Pd+CeO2In one or two or more kinds.
Embodiment 1
The component and content of ash discharge gas are as follows：Q299.10%, He 0.50%, Q2O 0.10%, CQ40.08%, CO 0.06%, CO20.03%, N20.10%, O2 0.03%。
In the present embodiment, because the content of foreign gas is very low（Less than 1.0%）, it is smaller to the performance impact of Pd alloy films, The front stage of cryogenic pump desorbs and obtains gas simultaneously, Pd alloy film separation units are directly entered, Pd alloy film separation units ooze Breathe freely as high-purity（＞ 99.999%）Q2（It is designated as gas）, gasMiddle protium, deuterium, tritium level（Percentage by volume）Respectively 2.0%th, 48.7%, 49.3%, it is directly entered tritium stocking system.The tail gas of Pd alloys film separation unit separation（It is designated as tail gas）In contain There is a small amount of Q2And He, Q2O、CQ4、CO、CO2、N2、O2Etc. foreign gas, buffer unit is stored in（In the present embodiment, buffer unit Using air accumulator）In.After the tail gas in air accumulator reaches 1L, Pd alloy film reaction members are sent into, in Pt/Al2O3Catalyst is made Reacted with lower by three-level hydrogen isotopic exchange, the infiltration gas of Pd alloy film reaction members is high-purity Q2, into hydrogen isotope Piece-rate system（Low temperature distillation system is used in the present embodiment）, to remove protium therein；Tail gas caused by reaction（It is designated as tail gas ）In, deuterium tritium level is extremely low（＜ 0.01%）, into waste gas except tritium system is further handled.
After measured, same composition, the ash discharge gas of volume are handled, processing time needed for the present invention is only CAPER technological processes 0.3 ~ 0.35 times.
Embodiment 2
In the present embodiment, the component and content of ash discharge gas are as follows：Q294.10%, He 2.80%, Q2O 0.80%, CQ4 0.65%, CO 0.35%, CO20.28%, N20.90%, O2 0.12%。
In the present embodiment, because the content of foreign gas is of a relatively high, the prime and rear class of cryogenic pump desorb respectively, prime Low temperature molecular sieve post desorb to obtain tail gas at normal temperatures, the helium refrigeration low-temperature pump of rear class desorbs under 77K obtains gas.Gas BodyMain component be Q2And He, tail gasContain a small amount of Q2And He, Q2O、CQ4、CO、CO2、N2、O2Etc. foreign gas.GasEnter Enter Pd alloy film separation units, obtain gasAnd tail gas, gasMiddle protium, deuterium, tritium level are respectively 11.0%, 44.2%, 44.8%.Due to gasMiddle protium content is higher, into filling Al2O3+1%SiO2Chromatographic column in carry out de- protium processing, chromatographic column Temperature is 77K, obtains the product gas that protium, deuterium, tritium level are respectively 1.0%, 49.2%, 49.8%（It is designated as gas）, gasEnter Enter tritium stocking system.The tail gas of chromatographic column（It is designated as tail gas）Middle protium, deuterium, the content of tritium are respectively 95.2%, 2.5%, 2.3%, are entered Enter hydrogen isotope separation system（Low temperature distillation system is used in the present embodiment）Separated again.Tail gasAnd tail gasIt is stored in Buffer unit（In the present embodiment, buffer unit uses air accumulator）In.After the tail gas in air accumulator reaches 1L, Pd alloys are sent into Film reaction unit, in Ni/Al2O3And Pt/CeO2Hydrogen isotopic exchange reaction occurs under catalyst action respectively and steam reforming is anti- Should, the infiltration gas of Pd alloy film reaction members is high-purity Q2, into hydrogen isotope separation system（Low temperature is used in the present embodiment Distillation system）, to remove protium therein；Tail gas caused by reaction（It is designated as tail gas）In, deuterium tritium level is extremely low（＜ 0.01%）, Into waste gas except tritium system is further handled.
After measured, same composition, the ash discharge gas of volume are handled, processing time needed for the present invention is only CAPER technological processes 0.4 ~ 0.55 times.
The invention is not limited in foregoing embodiment.The present invention, which expands to, any in this manual to be disclosed New feature or any new combination, and disclose any new method or process the step of or any new combination.

Claims (3)

  1. A kind of 1. deuterium tritium Rapid recovery device in fusion reactor ash discharge gas, it is characterised in that：Described device includes cryogenic pump, Pd Alloy film separation unit, chromatographic column, Pd alloy film reaction members, the ash discharge gas of fusion reaction room generation are divided into A by cryogenic pump Road, B roads, A roads are divided into A1 roads, A2 roads, A3 roads after entering Pd alloy film separation units；A1 roads are connected with tritium stocking system；A2 roads By being connected respectively with tritium stocking system, hydrogen isotope separation system after chromatographic column；A3 roads are entered by Pd alloy film reaction members Enter waste gas and remove tritium system or hydrogen isotope separation system；B roads tritium system or hydrogen are removed into waste gas by Pd alloy films reaction member Isotopic separation system；
    Described cryogenic pump sieves post and helium refrigeration low-temperature pump by low temperature molecular and combined, and low temperature molecular sieves post as fore pump, Operating temperature is 77K, and extraction removes He and Q2Foreign gas in addition, helium refrigeration low-temperature pump work temperature are 4K, extract He and Q out2；
    Described Pd alloys film separation unit is composed in series by two or more Pd alloys membrane separators, and described Pd is closed Gold is one kind in Pd+Ag, Pd+Y, Pd+Ag+Au, Pd+Ag+Au+Y or Pd+Ag+Au+Ni alloy；
    Al is loaded in described chromatographic column2O3+1%SiO2, coating Fe2O34A molecular sieves or 5A molecular sieves in one kind, chromatographic column Operating temperature range is 77K ~ 150K；
    Described Pd alloy films reaction member is composed in series by two or more Pd alloys membrane reactors, and described Pd is closed Gold is one kind in Pd+Ag, Pd+Y, Pd+Ag+Au, Pd+Ag+Au+Y or Pd+Ag+Au+Ni alloy.
  2. 2. the deuterium tritium fastly recovering in a kind of fusion reactor ash discharge gas, comprises the following steps：
    6a. rough segmentations
    Ash discharge gas is desorbed after low temperature pumped in cryogenic pump, obtains gas I, tail gas I；Gas I includes Q2And He, tail Gas I includes N2、Q2O、CO2And CQ4；
    6b.Pd films purify
    Gas I enters the separation of Pd alloys film separation unit, obtains gas II, tail gas II, gas II is Q2Gas；Tail gas II includes He and Q2Gas, Q2The content of gas is less than 5%；
    6c. purifying post processings
    As H/Q in gas II<When 10% and T/D=0.95 ~ 1.05, gas II enters tritium stocking system；
    As H/Q in gas II >=10%, gas II enters chromatographic column and takes off protium, obtains gas III, tail gas III, the H/Q in gas III <When 10% and T/D=0.95 ~ 1.05, gas III enters tritium stocking system；Tail gas III enters hydrogen isotope separation system；
    The processing of 6d. foreign gases
    Tail gas I, tail gas II enter air accumulator and stored, and when storage capacity reaches setting quantity, start into Pd alloy film reaction members It is catalyzed film reaction generation Q2With tail gas IV, Q2Into hydrogen isotope separation system, tail gas IV tritium system, tail gas IV are removed into waste gas Including N2、H2O、CO2And CH4。
  3. 3. the deuterium tritium fastly recovering in fusion reactor ash discharge gas according to claim 2, it is characterised in that described step The catalyst that rapid 6d catalysis film reaction uses is Pt+Al2O3、Pd+Al2O3、Ni+Al2O3、Pt+CeO2Or Pd+CeO2In one Kind or more.
CN201610245962.2A 2016-04-20 2016-04-20 Deuterium tritium Rapid recovery device and method in a kind of fusion reactor ash discharge gas Expired - Fee Related CN105923604B (en)

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CN106474924B (en) * 2016-11-08 2018-01-23 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
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
CN108479393B (en) * 2018-04-18 2020-07-31 中国工程物理研究院核物理与化学研究所 Method for removing protium in gas containing tritium hydrogen isotope
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
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
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
CN112834668B (en) * 2020-12-30 2022-08-19 中国原子能科学研究院 Low-temperature control device for analyzing hydrogen isotopes by gas chromatography
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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