JPH01189598A - Tritium recovery - Google Patents
Tritium recoveryInfo
- Publication number
- JPH01189598A JPH01189598A JP1269588A JP1269588A JPH01189598A JP H01189598 A JPH01189598 A JP H01189598A JP 1269588 A JP1269588 A JP 1269588A JP 1269588 A JP1269588 A JP 1269588A JP H01189598 A JPH01189598 A JP H01189598A
- Authority
- JP
- Japan
- Prior art keywords
- tritium
- tube
- metal
- gas
- vacuum pump
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Pending
Links
- 229910052722 tritium Inorganic materials 0.000 title claims abstract description 55
- YZCKVEUIGOORGS-NJFSPNSNSA-N Tritium Chemical compound [3H] YZCKVEUIGOORGS-NJFSPNSNSA-N 0.000 title claims abstract description 54
- 238000011084 recovery Methods 0.000 title claims description 11
- 239000002184 metal Substances 0.000 claims abstract description 21
- 229910052751 metal Inorganic materials 0.000 claims abstract description 21
- 239000012528 membrane Substances 0.000 claims abstract 2
- KDLHZDBZIXYQEI-UHFFFAOYSA-N Palladium Chemical compound [Pd] KDLHZDBZIXYQEI-UHFFFAOYSA-N 0.000 claims description 23
- 229910052739 hydrogen Inorganic materials 0.000 claims description 18
- 239000001257 hydrogen Substances 0.000 claims description 18
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 claims description 17
- 239000012466 permeate Substances 0.000 claims description 9
- 229910052763 palladium Inorganic materials 0.000 claims description 6
- 239000000956 alloy Substances 0.000 claims description 3
- 229910045601 alloy Inorganic materials 0.000 claims description 3
- 230000035699 permeability Effects 0.000 claims description 2
- 230000000694 effects Effects 0.000 abstract description 6
- 238000005372 isotope separation Methods 0.000 abstract description 5
- 230000008929 regeneration Effects 0.000 abstract description 3
- 238000011069 regeneration method Methods 0.000 abstract description 3
- 238000010438 heat treatment Methods 0.000 abstract description 2
- 238000013022 venting Methods 0.000 abstract 1
- 239000007789 gas Substances 0.000 description 15
- 239000012535 impurity Substances 0.000 description 6
- 230000004927 fusion Effects 0.000 description 5
- 150000002739 metals Chemical class 0.000 description 3
- 238000000034 method Methods 0.000 description 3
- IJGRMHOSHXDMSA-UHFFFAOYSA-N Atomic nitrogen Chemical compound N#N IJGRMHOSHXDMSA-UHFFFAOYSA-N 0.000 description 2
- 238000011109 contamination Methods 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 description 1
- YZCKVEUIGOORGS-OUBTZVSYSA-N Deuterium Chemical compound [2H] YZCKVEUIGOORGS-OUBTZVSYSA-N 0.000 description 1
- YZCKVEUIGOORGS-UHFFFAOYSA-N Hydrogen atom Chemical compound [H] YZCKVEUIGOORGS-UHFFFAOYSA-N 0.000 description 1
- WHXSMMKQMYFTQS-UHFFFAOYSA-N Lithium Chemical compound [Li] WHXSMMKQMYFTQS-UHFFFAOYSA-N 0.000 description 1
- 230000004913 activation Effects 0.000 description 1
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 description 1
- 229910052799 carbon Inorganic materials 0.000 description 1
- 229910052805 deuterium Inorganic materials 0.000 description 1
- 238000004821 distillation Methods 0.000 description 1
- 230000005611 electricity Effects 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 239000001307 helium Substances 0.000 description 1
- 229910052734 helium Inorganic materials 0.000 description 1
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 description 1
- 150000002431 hydrogen Chemical class 0.000 description 1
- 230000001771 impaired effect Effects 0.000 description 1
- 229910052744 lithium Inorganic materials 0.000 description 1
- 238000012423 maintenance Methods 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 239000000203 mixture Substances 0.000 description 1
- 229910052757 nitrogen Inorganic materials 0.000 description 1
- 239000001301 oxygen Substances 0.000 description 1
- 229910052760 oxygen Inorganic materials 0.000 description 1
- 238000005086 pumping Methods 0.000 description 1
- 150000003649 tritium Chemical class 0.000 description 1
- 239000002912 waste gas Substances 0.000 description 1
Abstract
Description
【発明の詳細な説明】
〔発明の目的〕
（産業上の利用分野）
本発明は、トリチウムガスを含んだ混合ガスからトリチ
ウムを回収するためのトリチウム回収装置に関する。DETAILED DESCRIPTION OF THE INVENTION [Object of the Invention] (Industrial Application Field) The present invention relates to a tritium recovery device for recovering tritium from a mixed gas containing tritium gas.
（従来の技術）
核融合炉においては、水素同位体を核融合反応させ、そ
の際放出されるエネルギーを利用して発電が行なわれる
が、目下この熱料として、重水素及びトリチウムの組合
せが有望視されている。(Conventional technology) In a nuclear fusion reactor, hydrogen isotopes undergo a nuclear fusion reaction, and the energy released during this process is used to generate electricity.Currently, a combination of deuterium and tritium is promising as a heating material. being watched.
トカマク型の核融合炉においては、炉心に注入されたト
リチウムのたかだか数チしか核熱焼せずに排出されるた
め、トリチウムの回収をはかる必要がある。核融合炉の
炉心から排出されるガス中の不純物組成は現在のところ
、ヘリウム、炭素、窒素、酸素等が主成分になっている
と考えられており、トリチウムおよび重水素の分離をす
るため曵とくに深冷蒸留法によって定常的に同位体分離
を行おうとすると、前述の不純物を除去して、不純物の
トータル’ｚｌｐｐｍ以下にすることが必要となる。In tokamak-type fusion reactors, at most only a few inches of tritium injected into the core are ejected without being burned out, so it is necessary to recover the tritium. The impurity composition of the gas exhausted from the core of a fusion reactor is currently thought to be mainly composed of helium, carbon, nitrogen, oxygen, etc. In particular, if isotope separation is to be carried out regularly by cryogenic distillation, it is necessary to remove the above-mentioned impurities to reduce the total amount of impurities to 'zl ppm or less.
ところで、トリチウムは水素同位体であることから、軽
水素回収に用いられる方法を、トリチウムの回収に利用
することができる。軽水素の回収法は種々あるが、その
うちの一つとして、パラジウムおよびパラジウム系合金
（以下Ｐｄ（！−総称する。）に対する水素同位体分子
の透過性を利用した拡散機がある。水素同位体は金属表
面において分子から原子状水素に解離して金属内部に溶
解し、拡散する性質があり、金属両側でのトリチウム分
圧に差がある場合には、トリチウムが壁を透過するｉｆ
ｉ次式で示される。By the way, since tritium is a hydrogen isotope, the method used for recovering light hydrogen can be used for recovering tritium. There are various methods for recovering light hydrogen, one of which is a diffuser that utilizes the permeability of hydrogen isotope molecules to palladium and palladium-based alloys (hereinafter referred to as Pd (!)).Hydrogen isotope has the property of dissociating from molecules into atomic hydrogen on the metal surface, dissolving inside the metal, and diffusing, and if there is a difference in the partial pressure of tritium on both sides of the metal, tritium will penetrate the wall.
It is expressed by the i-th equation.
Ｐ＝（Ａ／ｄ ） Φ（％ｉ）Ｂ・ｅｘｐ（−Ｑ／ＲＴ
） （１）ここで、Ａは、金属表面の面積、ｄは、金属
壁の厚さ、 ＰＬは、透過側のトリチウムガス分圧。P=(A/d) Φ(%i)B・exp(-Q/RT
) (1) Here, A is the area of the metal surface, d is the thickness of the metal wall, and PL is the tritium gas partial pressure on the permeation side.
Ｐ２は％Ｍ！過側のトリチウムガス分圧、Ｂは。P2 is %M! The tritium gas partial pressure on the over side, B is.
５ｉｅｖｅｒｔｓ定数、Ｑは活性化エネルギー、Ｒは、
ガス定数、Ｔは絶対温度である。5ieverts constant, Q is activation energy, R is
The gas constant, T, is the absolute temperature.
第３図は核融合炉に用いられるトリチウム回収装置の一
般的な概略の構成を示す。非処理ガスは配管２４から拡
散機へ供給される。拡散器ジャケット２１内には、図示
されていないヒーターによって２００ ’Ｃ〜３００°
Ｃに加熱された試験管状のＰｄ管２２が収められておシ
、Ｐｄ管２２を透過して来るトリチウムは、上記管内を
配管２６を介して常時真空に排気している真空ポンプ２
３によって。FIG. 3 shows a general schematic configuration of a tritium recovery device used in a nuclear fusion reactor. Untreated gas is supplied to the diffuser via piping 24. Inside the diffuser jacket 21, a temperature of 200' to 300° is heated by a heater (not shown).
A test-tube-shaped Pd tube 22 heated to C is housed, and the tritium that permeates through the Pd tube 22 is pumped to a vacuum pump 2 that constantly evacuates the inside of the tube to a vacuum via piping 26.
By 3.
配管２７を介して同位体分離系へ供給される。また、ト
リチウムの透過によって、トリチウムガスが劣化したガ
スは配管２５から廃ガス処理系へ送られる。It is supplied to the isotope separation system via piping 27. Moreover, the gas whose tritium gas has deteriorated due to the permeation of tritium is sent from the pipe 25 to the waste gas treatment system.
しかしながら、この様な構成であると、用いる真空ポン
プには格別の性態を払わなければならない、すなわち、
ポンプオイルを必要とする真空ポンプの場合、その排気
経路においてポンプオイルとトリチウムが接触し、トリ
チウムが汚染してしまい、同位体分離系に供給できる不
純物濃度の基準をうわまわってしまう恐れが生じ、また
ポンプオイル自体にもトリチウムが溶解するため、メン
テナンスの際の安全性に問題がある。また、何種類かの
オイルフリーなトリチウム用の真空ポンプも開発されて
いるが、いずれも高価で、かつ透過側のトリチウム分圧
が低い場合には、被透過側を高真空にしなければならず
、拡散器で必要とする真空度を得るためには、低真空用
から高真空用まで数種類の何台もの真空ポンプを組合せ
た複雑な構成となってしまう。However, with such a configuration, special characteristics must be paid to the vacuum pump used, that is,
In the case of a vacuum pump that requires pump oil, there is a risk that the pump oil and tritium will come into contact with each other in the exhaust route, contaminating the tritium and exceeding the impurity concentration standards that can be supplied to the isotope separation system. Additionally, since tritium dissolves in the pump oil itself, there is a safety issue during maintenance. In addition, several types of oil-free vacuum pumps for tritium have been developed, but they are all expensive, and if the partial pressure of tritium on the permeate side is low, the permeate side must be under high vacuum. In order to obtain the degree of vacuum required by the diffuser, a complicated configuration is required that combines several types of vacuum pumps, from low vacuum to high vacuum.
（発明が解決しようとする課題）
上述したように従来のトリチウム回収の構成にあっ℃は
、真空ポンプオイルによる回収トリチウムの汚染、逆に
トリチウムによる真空ポンプオイルの汚染、あるいはト
リチウム用真空ポンプのコストの高さや真空排気系の構
成の複雑さといった問題が発生する。(Problems to be Solved by the Invention) As mentioned above, problems with the conventional tritium recovery configuration include contamination of recovered tritium by vacuum pump oil, contamination of vacuum pump oil by tritium, or cost of the tritium vacuum pump. Problems arise such as the height of the vacuum pump and the complexity of the vacuum pumping system configuration.
そこで、本発明は、この様な事情に鑑みて成されたもの
で、以上の問題の原因であるメカニカルな真空ポンプを
使用しないトリチウム回収装置を提供することを目的と
している。Therefore, the present invention has been made in view of the above circumstances, and an object of the present invention is to provide a tritium recovery device that does not use a mechanical vacuum pump, which is the cause of the above problems.
（課題を解決するための手段）
本発明のトリチウム回収装置においては、Ｐｄ膜によっ
τ隔てられたトリチウム被透過側の領域に水素吸蔵金属
を具備する。(Means for Solving the Problems) In the tritium recovery device of the present invention, a hydrogen storage metal is provided in a region on the side where tritium permeates and is separated by τ by a Pd film.
（作 用）
本発明によれば、トリチウム被透過側に透過してくるト
リチウムを水素吸蔵金属に吸蔵させ、トリチウム分圧を
下げる事によシ、結果的に真空ポンプでトリチウム被透
過側を排気しているのと同じ効果が得られる。(Function) According to the present invention, the tritium that permeates into the tritium permeate side is occluded in the hydrogen storage metal, and the partial pressure of tritium is lowered.As a result, the tritium permeate side is evacuated using a vacuum pump. You can get the same effect as you do.
゛（実施例）
第１図は１本発明の一実施例に係わる。トリチウム回収
装置の概略の構成図である。本トリチウム回収装置にお
いて、被処理ガスは配管４を介して拡散器へ供給され゛
る。拡散器ジャケラ）ｌ内には、管状に形成されたＰｄ
管２が収められており、Ｐｄ管２を透過して来るトリチ
ウムは、上記管内に収められた水素吸蔵金属３によって
吸蔵され、 Ｐｄ管内部のトリチウム分圧は低く保たれ
、真空ポンプによってＰｄ管内部を排気しているのと同
じ効果が得られ、常にトリチウムが透過してくる。また
、水素吸蔵金属については、加熱することによって、ト
リチウムを再放出し、その平衡圧力は温度に依存するた
め、再生時の温度を制御することによって、配管５を介
して、一定圧力のトリチウムガスを同位体分離系へ供給
することができる。(Embodiment) FIG. 1 relates to an embodiment of the present invention. FIG. 1 is a schematic configuration diagram of a tritium recovery device. In this tritium recovery apparatus, the gas to be treated is supplied to the diffuser via the pipe 4. Inside the diffuser jacket, there is a Pd tube shaped like a tube.
A tube 2 is housed in the tube 2, and the tritium that passes through the Pd tube 2 is absorbed by the hydrogen storage metal 3 housed in the tube.The tritium partial pressure inside the Pd tube is kept low, and the Pd tube The same effect as evacuating the interior is achieved, and tritium always passes through. In addition, when hydrogen storage metals are heated, tritium is released again, and the equilibrium pressure depends on the temperature. Therefore, by controlling the temperature during regeneration, tritium gas at a constant pressure can be can be supplied to the isotope separation system.
また、水素吸蔵金属のみで被処理ガス中からのトリチウ
ム回収をはかることも考えられるが、その場合、前述の
不純物も同時に回収してしまい、さらに不純物を吸蔵し
た金属に関しては、その再生がほとんどの場合不可能で
あり、水素吸蔵金属の水素吸蔵能力を著しく損い、短期
間でトリチウム回収が不可能になる恐れがある。このた
め、水素同位体のみを透過するＰｄ膜を用い、被処理ガ
スと水素吸蔵金属を隔てることが、特に必要となる。It is also possible to try to recover tritium from the gas to be treated using only hydrogen-absorbing metals, but in that case, the impurities mentioned above would also be recovered at the same time, and most of the metals that have occluded impurities cannot be regenerated. If this is not possible, the hydrogen storage capacity of the hydrogen storage metal will be significantly impaired, and tritium recovery may become impossible in a short period of time. For this reason, it is particularly necessary to separate the gas to be treated from the hydrogen storage metal by using a Pd film that transmits only hydrogen isotopes.
なお、上述の実施例では、拡散器を一基のみ設けである
が、連続して被処理ガスからトリチウムを回収し、トリ
チウムガスを得る場合には、第２図に示すように２基あ
るいはそれ以上を並列に設置し、順次、吸蔵、再生を行
−うことによって可能となる。また図中の数字は第１図
と同じであシ、添字ａ、ｂはそれぞれの拡散器に対応し
た各部を示す。In the above embodiment, only one diffuser is provided, but when tritium is continuously recovered from the gas to be treated and tritium gas is obtained, two or more diffusers are provided as shown in FIG. This is possible by installing the above in parallel and performing storage and regeneration in sequence. Further, the numbers in the figure are the same as in FIG. 1, and the subscripts a and b indicate each part corresponding to each diffuser.
本発明は以上に説明したように、Ｐｄ膜によって隔てら
れたトリチウム被透過側の領域に水素吸蔵金属を設置す
ることによって、真空ポンプでトリチウムを排気するの
と同じ効果が得られる。As described above, the present invention provides the same effect as evacuating tritium with a vacuum pump by installing a hydrogen storage metal in a region on the side where tritium permeates and is separated by a Pd film.
第１図は、本発明の一実施例に係わるトリチウトリチウ
ム回収装置の構成図である。
１・・・拡散器ジャケット
２・・・Ｐｄ管
３・・・水素吸蔵金属
代理人弁理士 則 近 憲 佑
同 松山光速
第 １ 図
第２図FIG. 1 is a block diagram of a tritium lithium recovery apparatus according to an embodiment of the present invention. 1...Diffuser jacket 2...Pd tube 3...Hydrogen storage metal representative patent attorney Noriyuki Ken Yudo Matsuyama Kosoku 1 Figure 2
Claims (1)
したトリチウム回収装置において、前記パラジウムおよ
びパラジウム系合金の膜によって隔てられたトリチウム
被透過側の領域に水素吸蔵金属を具備することを特徴と
するトリチウム回収装置。A tritium recovery device that utilizes the hydrogen permeability of palladium and palladium-based alloys, characterized in that a hydrogen storage metal is provided in a region on the side where tritium permeates and is separated by a membrane of palladium and palladium-based alloys. .
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1269588A JPH01189598A (en) | 1988-01-25 | 1988-01-25 | Tritium recovery |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1269588A JPH01189598A (en) | 1988-01-25 | 1988-01-25 | Tritium recovery |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH01189598A true JPH01189598A (en) | 1989-07-28 |
Family
ID=11812516
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP1269588A Pending JPH01189598A (en) | 1988-01-25 | 1988-01-25 | Tritium recovery |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH01189598A (en) |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0455397A2 (en) * | 1990-04-30 | 1991-11-06 | Ontario Hydro | Process and apparatus for tritium recovery |
| JP2013536404A (en) * | 2010-06-16 | 2013-09-19 | エネア − エイジェンジア ナチオナル ペル レ ヌオベ テクノロジー，レネルジア エ ロ スヴィルッポ エコノミコ ソステニビル | Membrane reactor for treating tritium-containing gases |
| CN112999869A (en) * | 2021-03-04 | 2021-06-22 | 中国人民解放军陆军炮兵防空兵学院 | Device and method for continuously extracting tritium from fusion reactor liquid metal lithium-lead alloy |
-
1988
- 1988-01-25 JP JP1269588A patent/JPH01189598A/en active Pending
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0455397A2 (en) * | 1990-04-30 | 1991-11-06 | Ontario Hydro | Process and apparatus for tritium recovery |
| JP2013536404A (en) * | 2010-06-16 | 2013-09-19 | エネア − エイジェンジア ナチオナル ペル レ ヌオベ テクノロジー，レネルジア エ ロ スヴィルッポ エコノミコ ソステニビル | Membrane reactor for treating tritium-containing gases |
| CN112999869A (en) * | 2021-03-04 | 2021-06-22 | 中国人民解放军陆军炮兵防空兵学院 | Device and method for continuously extracting tritium from fusion reactor liquid metal lithium-lead alloy |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| US4774065A (en) | Process and apparatus for decontaminating exhaust gas from a fusion reactor fuel cycle of exhaust gas components containing chemically bonded tritium and/or deuterium | |
| US4476105A (en) | Process for photosynthetically splitting water | |
| US3963460A (en) | Method and apparatus for treating waste gases containing radioactive impurities, particularly krypton and xenon nuclides | |
| CN104176717B (en) | A kind of helium recovery method of purification and device | |
| RU2568184C2 (en) | Method for detritiation of soft household wastes and apparatus therefore | |
| CN106283101A (en) | A kind of preparation method of ultra-pure hydrogen | |
| US4867762A (en) | Method and a device for purifying a gas containing hydrogen isotopes | |
| JPH01189598A (en) | Tritium recovery | |
| US4331522A (en) | Reprocessing of spent plasma | |
| EP3742456B1 (en) | Apparatus and method for helium-3 separation and enrichment | |
| JPH0833490B2 (en) | Method and apparatus for decontaminating waste gas from a fusion reactor fuel cycle | |
| JPS6359728B2 (en) | ||
| Hayashi et al. | Gas separation performance of a hollow-filament type polyimide membrane module for a compact tritium removal system | |
| JPS63175627A (en) | Tritium recovery apparatus | |
| Slansky | Separation processes for noble gas fission products from the off-gas of fuel-reprocessing plants | |
| JP2585327B2 (en) | Tritium separation and recovery device and multifunctional separation membrane for tritium separation and recovery | |
| JPS5838207B2 (en) | Method for removing impurities such as helium from a mixture containing deuterium and tritium | |
| Hirata et al. | Experimental and analytical study on membrane detritiation process | |
| JPH0293399A (en) | Tritium remover | |
| JPH0377626A (en) | Device for refining hydrogen isotope | |
| Labrune et al. | Separation of hydrogen isotopes from nitrogen with polyimide membrane | |
| US4021234A (en) | Method for removing impurities in liquid metal | |
| EP0032827B1 (en) | Process for removing helium and other impurities from a mixture containing deuterium and tritium especially from a fusion reactor | |
| Sze et al. | Combined gettering and molten salt process for tritium recovery from lithium | |
| Rozenkevich et al. | Concept of tritium processing and confinement in fuel cycle of Ignitor |