JPS6123520B2 - - Google Patents
Info
- Publication number
- JPS6123520B2 JPS6123520B2 JP55043198A JP4319880A JPS6123520B2 JP S6123520 B2 JPS6123520 B2 JP S6123520B2 JP 55043198 A JP55043198 A JP 55043198A JP 4319880 A JP4319880 A JP 4319880A JP S6123520 B2 JPS6123520 B2 JP S6123520B2
- Authority
- JP
- Japan
- Prior art keywords
- tritium
- storage cylinder
- containment vessel
- uranium
- sweep gas
- 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.)
- Expired
Links
- 229910052722 tritium Inorganic materials 0.000 claims description 48
- YZCKVEUIGOORGS-NJFSPNSNSA-N Tritium Chemical compound [3H] YZCKVEUIGOORGS-NJFSPNSNSA-N 0.000 claims description 47
- 229910052770 Uranium Inorganic materials 0.000 description 6
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 6
- RTAQQCXQSZGOHL-UHFFFAOYSA-N Titanium Chemical compound [Ti] RTAQQCXQSZGOHL-UHFFFAOYSA-N 0.000 description 5
- 238000011084 recovery Methods 0.000 description 5
- 238000010438 heat treatment Methods 0.000 description 3
- 229910052751 metal Inorganic materials 0.000 description 2
- 239000002184 metal Substances 0.000 description 2
- 239000012466 permeate Substances 0.000 description 2
- ZSLUVFAKFWKJRC-IGMARMGPSA-N 232Th Chemical compound [232Th] ZSLUVFAKFWKJRC-IGMARMGPSA-N 0.000 description 1
- 229910052776 Thorium Inorganic materials 0.000 description 1
- VBDWIZWBBSLYSV-UHFFFAOYSA-D [Cl-].[U+6].[Th+4].[Cl-].[Cl-].[Cl-].[Cl-].[Cl-].[Cl-].[Cl-].[Cl-].[Cl-] Chemical compound [Cl-].[U+6].[Th+4].[Cl-].[Cl-].[Cl-].[Cl-].[Cl-].[Cl-].[Cl-].[Cl-].[Cl-] VBDWIZWBBSLYSV-UHFFFAOYSA-D 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000009792 diffusion process Methods 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 238000000746 purification Methods 0.000 description 1
- 239000010936 titanium Substances 0.000 description 1
- 229910052719 titanium Inorganic materials 0.000 description 1
Classifications
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E60/00—Enabling technologies; Technologies with a potential or indirect contribution to GHG emissions mitigation
- Y02E60/30—Hydrogen technology
- Y02E60/32—Hydrogen storage
Landscapes
- Hydrogen, Water And Hydrids (AREA)
Description
【発明の詳細な説明】
本発明は、ウランベツトトリチウム貯蔵筒に於
ける透過トリチウムの回収装置に関するものであ
る。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to an apparatus for recovering permeated tritium in a uranium-bet tritium storage cylinder.
ウランベツトトリチウム貯蔵筒からトリチウム
を所要の設備へ供給する為、ウランベツトトリチ
ウム貯蔵筒をその外周に装備された加熱ヒーター
で約500℃程度まで加熱すると、前記貯蔵筒の筒
壁を透過して多量のトリチウムが拡散し、貯蔵筒
周囲のトリチウム濃度が上昇する。 In order to supply tritium from the uranium-bet tritium storage cylinder to the required equipment, when the uranium-bet tritium storage cylinder is heated to approximately 500°C using a heater installed on its outer periphery, a large amount of tritium passes through the cylinder wall of the storage cylinder. of tritium diffuses, and the tritium concentration around the storage cylinder increases.
この為、従来は前記貯蔵筒をグローブボツクス
等の中に入れ、貯蔵筒周囲のガスを他のガス精製
設備に導き、グローブボツクス等の内部のトリチ
ウム濃度を許容値以下に制御していた。 For this reason, in the past, the storage cylinder was placed in a glove box or the like, and the gas around the storage cylinder was guided to other gas purification equipment to control the tritium concentration inside the glove box or the like to below a permissible value.
然し乍ら、かかる透過トリチウムの処理方法で
は、グローブボツクス等の大がかりな格納庫を必
要とするばかりではなく、他の設備との関係上貯
蔵筒を任意に独立運転してトリチウムを所要の設
備に供給することができなかつた。 However, such a method of processing permeated tritium not only requires a large-scale hangar such as a glove box, but also requires independent operation of the storage cylinder at will to supply tritium to the required equipment due to the relationship with other equipment. I couldn't do it.
本発明はかかる問題点を解決すべくなされたも
のであり、グローブボツクス等の大がかりな格納
庫が不要で、しかも貯蔵筒を任意に独立運転して
トリチウムを供給することができるようにしたウ
ランベツトトリウム貯蔵筒に於ける透過トリチウ
ムの回収装置を提供せんとするものである。 The present invention has been made to solve these problems, and is a uranium chloride thorium that does not require a large-scale hangar such as a glove box, and can supply tritium by independently operating the storage cylinder at will. It is an object of the present invention to provide a recovery device for permeated tritium in a storage cylinder.
以下本発明の実施例を図によつて説明すると、
１はウランベツトトリチウム貯蔵筒で、その上端
にトリチウム供給管１ａが設けられ、下端にトリ
チウム導入管１ｂが設けられ、内部にトリチウム
を吸着貯蔵している金属ウラン１ｃが充填されて
いる。この貯蔵筒１は格納容器２内に格納され、
トリチウム供給管１ａ，トリチウム導入管１ｂが
格納容器２を気密に貫通して図示せぬ所要の設備
に配管接続されている。格納容器２内において貯
蔵筒１の外周には加熱ヒーター３が設けられてい
る。格納容器２内にはスイープガスが充填され、
格納容器２の下端と上端との間にはスイープガス
の循環回路４が設けられ、該循環回路４中にはス
イープガス循環機５とトリチウム除去用機器とし
て例えば外周に加熱ヒーター７を備えたチタンス
ポンジトラツプ８及び冷却器６が順次設けられて
いる。 Embodiments of the present invention will be explained below using figures.
Reference numeral 1 denotes a uranium bet tritium storage cylinder, which has a tritium supply pipe 1a at its upper end, a tritium introduction pipe 1b at its lower end, and is filled with metallic uranium 1c which adsorbs and stores tritium. This storage cylinder 1 is stored in a storage container 2,
A tritium supply pipe 1a and a tritium introduction pipe 1b hermetically penetrate the containment vessel 2 and are connected to necessary equipment (not shown). A heater 3 is provided on the outer periphery of the storage cylinder 1 within the containment vessel 2 . Containment vessel 2 is filled with sweep gas,
A sweep gas circulation circuit 4 is provided between the lower end and the upper end of the containment vessel 2, and the circulation circuit 4 includes a sweep gas circulator 5 and a titanium gas circulator equipped with a heater 7 on the outer periphery as a device for removing tritium. A sponge trap 8 and a cooler 6 are sequentially provided.
次に上述の如く構成された本発明の透過トリチ
ウムの回収装置の作用について説明する。ウラン
ベツトトリチウム貯蔵筒１内の金属ウラン１ｃに
吸着貯蔵されているトリチウムを、貯蔵筒１から
図示せぬ所要の設備へ供給すべく、加熱ヒーター
３に通電して金属ウラン１ｃを約500℃まで加熱
し、トリチウムを焼出し、貯蔵筒１の上端のトリ
チウム供給管１ａより所要の設備へ供給する。こ
の際貯蔵筒１の筒壁を透過してトリチウムが格納
容器２内に拡散してくるが、前記加熱ヒーター３
による加熱に先立つて循環回路４中にスイープガ
ス循環機５，チタンスポンジトラツプ８の加熱ヒ
ーター７及び冷却器６を作動させてあるので、前
記格納容器２内に拡散したトリチウムはスイープ
ガスと共に循環機５により循環されて格納容器２
の上端を出てチタンスポンジトラツプ８に送ら
れ、ここでトリチウムがチタンスポンジに吸着回
収されて、スイープガス中より取り除かれ、清浄
なスイープガスは冷却器６を経て冷却の上、循環
機５を通り、格納容器２の下端より内部に供給さ
れる。 Next, the operation of the permeated tritium recovery apparatus of the present invention constructed as described above will be explained. In order to supply the tritium adsorbed and stored in the uranium metal 1c in the uranium bet-tritium storage cylinder 1 from the storage cylinder 1 to necessary equipment (not shown), the heating heater 3 is energized to heat the uranium metal 1c to about 500°C. It is heated to bake out tritium, and then supplied to required equipment through the tritium supply pipe 1a at the upper end of the storage cylinder 1. At this time, tritium passes through the cylinder wall of the storage cylinder 1 and diffuses into the containment vessel 2, but the heating heater 3
Since the sweep gas circulator 5, the heater 7 of the titanium sponge trap 8, and the cooler 6 are operated in the circulation circuit 4 prior to heating by the gas, the tritium diffused into the containment vessel 2 is circulated together with the sweep gas. It is circulated by machine 5 and stored in containment vessel 2.
It exits the upper end and is sent to the titanium sponge trap 8, where the tritium is adsorbed and collected by the titanium sponge and removed from the sweep gas.The clean sweep gas is cooled through the cooler 6 and sent to the circulator 5. , and is supplied to the inside of the containment vessel 2 from the lower end.
かくして格納容器２内に拡散するトリチウムは
濃度が低く且つ温度が低くなつているので外部へ
透過漏出することがなく、従つて、従来のように
貯蔵筒を収容せるグローブボツクス等の大がかり
な格納庫は不要である。また貯蔵筒１は他の設備
に関係なく任意に独立運転してトリチウムの供給
を行なうことができる。 In this way, the tritium diffused into the containment vessel 2 has a low concentration and a low temperature, so it does not permeate and leak to the outside. Therefore, a large-scale hangar such as a glove box that can accommodate a storage cylinder as in the past is not suitable. Not necessary. Furthermore, the storage cylinder 1 can be operated independently and supplied with tritium at any time without regard to other equipment.
特に本発明の透過トリチウムの回収装置は、ス
イープガス循環機５によりスイープガスの流量を
制御することにより、格納容器２内の温度をトリ
チウム濃度の許容温度以下に押えることができる
ので、トリチウムの格納容器からの透過は確実に
防止することができる。 In particular, the permeated tritium recovery device of the present invention can suppress the temperature inside the containment vessel 2 to below the allowable temperature for the tritium concentration by controlling the flow rate of the sweep gas with the sweep gas circulator 5. Permeation from the container can be reliably prevented.
尚、本発明の透過トリチウムの回収装置に於い
ては、貯蔵筒１の周囲に断熱層を設けても格納容
器２内の温度をトリチウム拡散の許容温度以下に
押えることができる。 In the permeated tritium recovery device of the present invention, even if a heat insulating layer is provided around the storage cylinder 1, the temperature inside the containment vessel 2 can be kept below the permissible temperature for tritium diffusion.
以下詳細した通り本発明のウランベツトトリウ
ム貯蔵筒に於ける透過トリチウムの回収装置によ
れば、貯蔵筒を加熱してトリチウムを所要の設備
に供給した際、貯蔵筒を透過したトリチウムを格
納容器内のスイープガスと共にスイープガス循環
機により循環回路を循環させ、循環回路中のトリ
チウム除去用機器で回収できる。また貯蔵筒を格
納した格納容器内には清浄なスイープガスが常時
供給され、従つて前記貯蔵筒を透過したトリチウ
ムの濃度が高くなることはなく、また格納容器内
及び循環回路中の温度も高くなることがないの
で、格納容器内及び循環回路中のトリチウムが外
部へ透過漏出することがなく安全である。従つて
従来のようにグローブボツクス等の大がかりな格
納庫は不要である。また他の設備に関係なく貯蔵
筒を任意に独立運転してトリチウムを所要の設備
に供給することができる。 As described in detail below, according to the device for recovering permeated tritium in a uranium bet thorium storage cylinder of the present invention, when the storage cylinder is heated and tritium is supplied to the required equipment, the tritium that has permeated through the storage cylinder is stored in the containment vessel. The tritium is circulated through the circulation circuit by a sweep gas circulator together with the sweep gas, and can be recovered by a tritium removal device in the circulation circuit. In addition, clean sweep gas is constantly supplied to the containment vessel containing the storage cylinder, so the concentration of tritium that has permeated through the storage cylinder does not increase, and the temperature inside the containment vessel and circulation circuit remains high. Therefore, the tritium in the containment vessel and the circulation circuit will not permeate and leak to the outside, making it safe. Therefore, there is no need for a large-scale hangar such as a glove box as in the past. Moreover, the storage cylinder can be operated independently and tritium can be supplied to the required equipment regardless of other equipment.
図は本発明によるウランベツトトリチウム貯蔵
筒に於ける透過トリチウムの回収装置の一実施例
を示す系統図である。
１……貯蔵筒、２……格納容器、３……加熱ヒ
ーター、４……循環回路、５……スイープガス循
環機、６……冷却器、７……加熱ヒーター、８…
…チタンスポンジトラツプ。
The figure is a system diagram showing an embodiment of a permeated tritium recovery device in a uranium-bet tritium storage cylinder according to the present invention. DESCRIPTION OF SYMBOLS 1... Storage cylinder, 2... Containment vessel, 3... Heater, 4... Circulation circuit, 5... Sweep gas circulator, 6... Cooler, 7... Heater, 8...
...Titanium sponge trap.
Claims (1)
トリチウム貯蔵筒を格納容器内に格納し、格納容
器の下端と上端との間にスイープガスの循環回路
を設け、該循環回路中にトリチウム除去用機器と
スイープガス循環機を設けて成るウランベツトト
リチウム貯蔵筒に於ける透過トリチウムの回収装
置。1. A uranium-bet tritium storage cylinder equipped with a heater on the outer periphery is stored in a containment vessel, a sweep gas circulation circuit is provided between the lower end and the upper end of the containment vessel, and a tritium removal equipment and a sweep gas are installed in the circulation circuit. A device for recovering permeated tritium in a uranium-bet tritium storage cylinder equipped with a gas circulation machine.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP4319880A JPS56140298A (en) | 1980-04-02 | 1980-04-02 | Device for recovering transparent tritium in uranium bet tritium store cylinder |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP4319880A JPS56140298A (en) | 1980-04-02 | 1980-04-02 | Device for recovering transparent tritium in uranium bet tritium store cylinder |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS56140298A JPS56140298A (en) | 1981-11-02 |
| JPS6123520B2 true JPS6123520B2 (en) | 1986-06-06 |
Family
ID=12657223
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP4319880A Granted JPS56140298A (en) | 1980-04-02 | 1980-04-02 | Device for recovering transparent tritium in uranium bet tritium store cylinder |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS56140298A (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS62274115A (en) * | 1986-05-22 | 1987-11-28 | Koyo Seiko Co Ltd | Ball bearing |
| JPH0532602B2 (en) * | 1985-01-21 | 1993-05-17 | Ntn Toyo Bearing Co Ltd |
-
1980
- 1980-04-02 JP JP4319880A patent/JPS56140298A/en active Granted
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH0532602B2 (en) * | 1985-01-21 | 1993-05-17 | Ntn Toyo Bearing Co Ltd | |
| JPS62274115A (en) * | 1986-05-22 | 1987-11-28 | Koyo Seiko Co Ltd | Ball bearing |
Also Published As
| Publication number | Publication date |
|---|---|
| JPS56140298A (en) | 1981-11-02 |
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