JPH0360400B2 - - Google Patents
Info
- Publication number
- JPH0360400B2 JPH0360400B2 JP60178028A JP17802885A JPH0360400B2 JP H0360400 B2 JPH0360400 B2 JP H0360400B2 JP 60178028 A JP60178028 A JP 60178028A JP 17802885 A JP17802885 A JP 17802885A JP H0360400 B2 JPH0360400 B2 JP H0360400B2
- Authority
- JP
- Japan
- Prior art keywords
- container
- radioactive waste
- double
- lid
- container body
- 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 - Lifetime
Links
- 238000000034 method Methods 0.000 claims description 13
- 239000006060 molten glass Substances 0.000 claims description 12
- 239000002901 radioactive waste Substances 0.000 claims description 10
- 238000003466 welding Methods 0.000 claims description 6
- 239000011521 glass Substances 0.000 description 10
- 239000002927 high level radioactive waste Substances 0.000 description 8
- 238000001816 cooling Methods 0.000 description 3
- 238000007711 solidification Methods 0.000 description 3
- 230000008023 solidification Effects 0.000 description 3
- 238000005260 corrosion Methods 0.000 description 2
- 230000007797 corrosion Effects 0.000 description 2
- 238000005336 cracking Methods 0.000 description 2
- 238000004519 manufacturing process Methods 0.000 description 2
- 238000007789 sealing Methods 0.000 description 2
- 229910001220 stainless steel Inorganic materials 0.000 description 2
- 239000010935 stainless steel Substances 0.000 description 2
- 238000003860 storage Methods 0.000 description 2
- 238000004017 vitrification Methods 0.000 description 2
- 230000009977 dual effect Effects 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 239000007789 gas Substances 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
- 239000000463 material Substances 0.000 description 1
- 238000002844 melting Methods 0.000 description 1
- 230000008018 melting Effects 0.000 description 1
- 239000002184 metal Substances 0.000 description 1
- 231100000989 no adverse effect Toxicity 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 125000006850 spacer group Chemical group 0.000 description 1
- 239000002915 spent fuel radioactive waste Substances 0.000 description 1
- 239000002699 waste material Substances 0.000 description 1
Landscapes
- Processing Of Solid Wastes (AREA)
- Fertilizers (AREA)
Description
【発明の詳細な説明】
「産業上の利用分野」
本発明は、主として高レベルの放射性廃棄物を
容器内に封入する放射性廃棄物の処理方法に関す
る。DETAILED DESCRIPTION OF THE INVENTION "Field of Industrial Application" The present invention mainly relates to a method for treating radioactive waste in which high-level radioactive waste is sealed in a container.
「従来の技術」
高レベルの放射性廃棄物は、原子炉から取出さ
れた使用済燃料を再処理した際に生成される多量
の核分裂性生成物を含む廃棄物である。この高レ
ベルの放射性廃棄物は、強い放射能を持つと共
に、核分裂性生成物の崩壊に伴い熱を発生する。
そこで、高レベルの放射性廃棄物を安全に管理
し、将来、安全に処分するために、ガラス成分
(ホウ硅素等)と共に溶融し、ステンレス鋼等の
容器に流し込んで固化させる、いわゆるガラス固
化が行なわれる。そして、ガラス固化された高レ
ベルの放射性廃棄物は、核分裂性生成物が十分に
崩壊して安全に処分できるまで、貯蔵施設に保管
される。この場合、高レベルの放射性廃棄物のガ
ラス固化体を貯蔵するための要件は次の三つであ
る。すなわち、
強い放射能を外部に漏らさないための遮蔽
核分裂性生成物の崩壊に伴い発生する熱の除
去
二重の閉込機能
このうち、は、貯蔵施設を厚いコンクリート
で構築することで達成され、また、は通常空冷
方式が用いられる。そして、については、一重
の容器と施設構造での閉込、すなわち、一重の容
器を冷却した空気はフイルタを介して外部に放出
するもの及び二重の容器の中に閉込めるものが考
えられる。"Prior Art" High-level radioactive waste is waste containing a large amount of fissile products produced when spent fuel extracted from a nuclear reactor is reprocessed. This highly radioactive waste is highly radioactive and generates heat as the fissile products decay.
Therefore, in order to safely manage high-level radioactive waste and dispose of it safely in the future, so-called vitrification is carried out, in which it is melted together with glass components (such as borosilicate) and solidified by pouring it into containers such as stainless steel. It will be done. The vitrified high-level radioactive waste is then stored in storage facilities until the fissile products have decayed enough to be safely disposed of. In this case, there are three requirements for storing vitrified high-level radioactive waste: In other words, shielding to prevent strong radioactivity from leaking to the outside; removal of heat generated by the decay of fissile products; and dual containment functions. Also, an air cooling system is usually used. Regarding the above, confinement using a single-layered container and a facility structure, that is, one in which the air that has cooled the single-layered container is discharged to the outside through a filter, and one in which the air is confined in a double-layered container can be considered.
「発明が解決しようとする問題点」
しかしながら、上記一重の容器と施設構造との
組合わせによる閉込においては、この一重の容器
の厚さを落下等の衝撃を考慮して厚くする必要が
あるため、容器内にガラスを充填した後の凝固に
伴う容器の歪を吸収できず、大きな応力が発生
し、容器の変形、内部のガラスの割れ、容器の応
力腐食等の発生につながるという問題がある。``Problem to be solved by the invention'' However, in confinement by the combination of the above-mentioned single-layered container and facility structure, it is necessary to increase the thickness of this single-layered container in consideration of impact such as falling. As a result, the container is unable to absorb the strain caused by glass solidification after it is filled into the container, and large stresses are generated, leading to problems such as deformation of the container, cracking of the internal glass, and stress corrosion of the container. be.
一方、上記二重の容器の中に閉込めるものにあ
つては、第5図において、まず、キヤニスタ(容
器本体)1内に、高レベルの放射性廃棄物を含む
溶融ガラス5を充填した後、キヤニスタ1の開口
部に内蓋2を被せて溶接し、次いで、このキヤニ
スタ1をリパツク胴体3内に挿入し、リパツク胴
体3にリパツク蓋4を被せて溶接することによつ
て、二重構造の容器を完成するものであるから、
工程が複雑になる上に、キヤニスタ1を吊上げて
リパツク胴体3内に挿入しなければならないた
め、ハンドリング性に問題があり、かつキヤニス
タ1とリパツク胴体3との間のギヤツプを小さく
できないため、熱伝達性が悪く、熱除去の点で問
題がある。 On the other hand, in the case of a device to be confined in the double container, as shown in FIG. By covering the opening of the canister 1 with the inner lid 2 and welding it, then inserting the canister 1 into the repack body 3, and covering the repack body 3 with the repack lid 4 and welding, a double structure is created. Because it completes the container,
In addition to complicating the process, the canister 1 must be lifted and inserted into the repack body 3, which poses a problem in handling, and the gap between the canister 1 and the repack body 3 cannot be reduced, so heat It has poor conductivity and problems in terms of heat removal.
本発明は、上記事情に鑑みてなされたもので、
その目的とするところは、放射性廃棄物を封入す
る際の工程が簡略化でき、かつ吊上等のハンドリ
ング工程が不要な上に、二重構造のボトル部のギ
ヤツプを熱除去上障害にならない大きさにでき、
また、溶融ガラスの凝固、冷却時の歪を吸収でき
て、ガラス及び外部容器の健全性を保持できる放
射性廃棄物の処理方法を提供することにある。 The present invention was made in view of the above circumstances, and
The goal is to simplify the process of sealing radioactive waste, eliminate the need for handling processes such as lifting, and make the gap in the double-walled bottle large enough to not become an obstacle for heat removal. I can do it,
Another object of the present invention is to provide a radioactive waste disposal method that can absorb distortion during solidification and cooling of molten glass and maintain the integrity of the glass and external container.
「問題点を解決するための手段」
上記目的を達成するために、本発明は、あらか
じめ二重構造のボトル部を有する容器を製作し、
この容器内に放射性廃棄物を含んだ溶融ガラスを
充填した後、容器の開口部に蓋を溶着し、次いで
容器のボトル部の上部にオーバキヤツプを溶着し
たものである。"Means for Solving the Problems" In order to achieve the above object, the present invention manufactures a container having a double structure bottle part in advance,
After filling the container with molten glass containing radioactive waste, a lid is welded to the opening of the container, and an overcap is then welded to the top of the bottle portion of the container.
「作用」
本発明の放射性廃棄物の処理方法にあつては、
あらかじめ二重構造のボトル部を有する容器を製
作することによつて、ボトル部のギヤツプを熱除
去上障害にならない程度に小さく抑え、かつボト
ル部の内側容器の肉厚を薄くすると共に、上記二
重構造の容器に溶融ガラスを充填した後、蓋及び
オーバキヤツプを溶着することによつて、封入工
程を簡略化し、かつハンドリング工程を少なくす
る。"Operation" In the method of treating radioactive waste of the present invention,
By manufacturing a container with a double-walled bottle part in advance, the gap in the bottle part can be kept small to the extent that it does not become a hindrance to heat removal, and the wall thickness of the inner container of the bottle part can be thinned, and the above two points can be achieved. After filling a multi-layered container with molten glass, the lid and overcap are welded together to simplify the sealing process and reduce the handling process.
「実施例」
以下、第1図ないし第4図に基づいて本発明の
一実施例を説明する。"Embodiment" Hereinafter, an embodiment of the present invention will be described based on FIGS. 1 to 4.
図中10は、ボトル部11が二重構造となつた
容器であり、この容器11はあらかじめ工場で製
作される。すなわち、上記容器10は、開口部1
2を有する内部容器体13の首部14から下側を
外部容器体15で包み込んで構成されている。そ
して、内部容器体13のボトル部は、ガラス充填
後の熱歪を吸収できる薄さ(例えば、1〜5mm)
で製作し、また、外部容器体15は、外部からの
衝撃に耐えうる十分な厚み(例えば、5〜10mm)
を有する。さらに、ボトル部11の内外容器体1
3,15間の間隙は、高レベルの放射性廃棄物ガ
ラス固化体からの発熱の除去に障害とならないよ
うに十分小さくし(例えば、1〜3mm)、この間
隙を一定に維持するためのスペーサ(図示せず)
を内外容器体13,15間に設置する。また、必
要に応じて、外部容器体15の肩部に、内外容器
体13,15の間の雰囲気調整を行なうためのノ
ズル16を設けて、ノズル16を介して内部に
Heガス等を封入してもよい。 In the figure, reference numeral 10 denotes a container in which a bottle portion 11 has a double structure, and this container 11 is manufactured in advance at a factory. That is, the container 10 has an opening 1
The outer container body 15 wraps the lower side from the neck 14 of the inner container body 13 having the inner container body 13 having the inner container body 13 having the inner container body 13 having the inner container body 13 having the inner container body 13 having the inner container body 13 having the inner container body 13 having an inner container body 13 having an inner container body 13 and a lower side thereof. The bottle portion of the inner container body 13 is thin enough (for example, 1 to 5 mm) to absorb thermal strain after glass filling.
The outer container body 15 has a sufficient thickness (for example, 5 to 10 mm) to withstand external impact.
has. Furthermore, the inner and outer container body 1 of the bottle part 11
The gap between 3 and 15 should be small enough (for example, 1 to 3 mm) so as not to interfere with the removal of heat from the vitrified high-level radioactive waste, and a spacer (for example, 1 to 3 mm) should be provided to maintain this gap constant. (not shown)
is installed between the inner and outer container bodies 13 and 15. Further, if necessary, a nozzle 16 is provided on the shoulder of the outer container body 15 to adjust the atmosphere between the inner and outer container bodies 13 and 15, and the inside is supplied via the nozzle 16.
Helium gas or the like may be filled.
このようにして製作された容器10の開口部1
2から、高レベルの放射性廃棄物をガラス成分と
共に溶融した溶融ガラス17を、流し込んで固化
させる。次いで、上記内部容器体13の開口部1
2に蓋18を被せて、開口部12及び蓋18の外
周部を遠隔自動溶接装置にて溶接して、容器10
の内部に溶融ガラス17を封じ込める。さらに、
容器10の外部容器体15の上部にオーバキヤツ
プ19を被せて、遠隔自動溶接装置にて溶接す
る。これによりガラス固化体17の二重閉込が完
了し、貯蔵施設に保管される。 Opening 1 of the container 10 manufactured in this way
From step 2, molten glass 17 made by melting high-level radioactive waste together with glass components is poured and solidified. Next, the opening 1 of the internal container body 13
2 is covered with a lid 18, and the opening 12 and the outer periphery of the lid 18 are welded using a remote automatic welding device to complete the container 10.
Molten glass 17 is sealed inside. moreover,
An overcap 19 is placed on the top of the outer container body 15 of the container 10 and welded using a remote automatic welding device. This completes the double confinement of the vitrified material 17 and stores it in a storage facility.
上述したようにして、高レベルの放射性廃棄物
の処理が行なわれるが、この場合、容器10内に
溶融ガラス17を充填した後、蓋18及びオーバ
キヤツプ19を溶接するだけで、完全な二重構造
(閉込)が完了するから、従来のような容器本体
1の吊上等のハンドリング工程が不要となり、閉
込工程が簡略化できる。また、ボトル部11をあ
らかじめ工場で二重構造に製作しておくので、精
度の高い加工ができ、従つて内外容器体13,1
5間のギヤツプを熱除去上障害とならない大きさ
にできる上に、内部容器体13の厚みを小さくで
きるから、内部容器体13が熱歪を吸収できて、
ガラス及び外部容器体15に悪影響を及ぼすこと
がない。 As described above, high-level radioactive waste is processed, but in this case, after filling the container 10 with the molten glass 17, the lid 18 and overcap 19 are simply welded to create a complete double container. Since the structure (confinement) is completed, the conventional handling process such as lifting the container body 1 is no longer necessary, and the confinement process can be simplified. In addition, since the bottle part 11 is manufactured in advance to have a double structure at the factory, highly accurate processing is possible, and therefore the inner and outer container bodies 13, 1
5 can be made to a size that does not pose an obstacle to heat removal, and the thickness of the inner container body 13 can be reduced, so that the inner container body 13 can absorb thermal strain.
There is no adverse effect on the glass or the outer container body 15.
なお、上記容器10、蓋18、オーバキヤツプ
19は、ステンレス鋼等の耐食性金属で製作され
ている。 The container 10, lid 18, and overcap 19 are made of a corrosion-resistant metal such as stainless steel.
「発明の効果」
以上説明したように、本発明によれば、あらか
じめ二重構造のボトル部を有する容器を製作し、
この容器内に放射性廃棄物を含んだ溶融ガラスを
充填した後、容器の開口部に蓋を溶着し、次いで
容器のボトル部の上部にオーバキヤツプを溶着し
たものであるから、二重構造の容器に溶融ガラス
を充填した後、蓋及びオーバキヤツプを溶着する
ことによつて、放射性廃棄物を封入する際の工程
が簡略化でき、かつ従来行なわれていたガラス充
填容器の吊上等のハンドリング工程が不要な上
に、あらかじめ二重構造のボトル部を有する容器
を製作することによつて、ボトル部のギヤツプを
熱除去上障害にならない程度に小さく抑えること
ができ、従つて十分な熱伝達性能が確保できる。
また、ボトル部の内側容器の肉厚を薄くすること
ができることにより、該内部容器が、溶融ガラス
の凝固冷却時の熱歪を吸収できて、ガラスの割れ
を抑制でき、かつ外部容器に応力発生がなく、従
つてガラス及び外部容器の健全性が確実に保持で
きる。"Effects of the Invention" As explained above, according to the present invention, a container having a double-layered bottle part is manufactured in advance,
After filling the container with molten glass containing radioactive waste, a lid is welded to the opening of the container, and an overcap is then welded to the top of the bottle part of the container, making it a double-layered container. By filling the container with molten glass and then welding the lid and overcap, the process for enclosing radioactive waste can be simplified, and the handling process such as lifting the glass filled container, which was conventionally done, can be simplified. In addition, by manufacturing a container with a double-walled bottle part in advance, the gap in the bottle part can be kept small to the extent that it does not become an obstacle to heat removal, and therefore, sufficient heat transfer performance can be achieved. can be secured.
In addition, by making the wall thickness of the inner container of the bottle part thinner, the inner container can absorb thermal strain during solidification and cooling of the molten glass, suppressing glass cracking, and generating stress in the outer container. Therefore, the integrity of the glass and outer container can be maintained reliably.
第1図ないし第4図は本発明の一実施例を示す
もので、第1図は二重閉込完了後を示す断面図、
第2図は溶融ガラス充填時を示す断面図、第3図
は蓋溶接時を示す断面図、第4図はオーバキヤツ
プ溶接時を示す断面図、第5図は従来の二重閉込
用容器を示す断面図である。
10……容器、11……ボトル部、12……開
口部、17……溶融ガラス(ガラス固化体)、1
8……蓋、19……オーバキヤツプ。
1 to 4 show an embodiment of the present invention, and FIG. 1 is a cross-sectional view after double confinement is completed;
Figure 2 is a cross-sectional view showing when molten glass is filled, Figure 3 is a cross-sectional view when the lid is welded, Figure 4 is a cross-sectional view when overcap is welded, and Figure 5 is a conventional double confinement container. FIG. 10... Container, 11... Bottle portion, 12... Opening, 17... Molten glass (vitrification), 1
8...Lid, 19...Overcap.
Claims (1)
を製作し、この容器内に放射性廃棄物を含んだ溶
融ガラスを充填した後、上記容器の開口部に蓋を
被せて溶着し、次いで上記ボトル部の上部にオー
バキヤツプを被せて溶着することを特徴とする放
射性廃棄物の処理方法。1. Prepare a container with a double-walled bottle part in advance, fill this container with molten glass containing radioactive waste, cover the opening of the container with a lid and weld it, and then close the bottle part. A radioactive waste disposal method characterized by placing an overcap on the top and welding it.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP60178028A JPS6238400A (en) | 1985-08-13 | 1985-08-13 | Method of processing radioactive waste |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP60178028A JPS6238400A (en) | 1985-08-13 | 1985-08-13 | Method of processing radioactive waste |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS6238400A JPS6238400A (en) | 1987-02-19 |
| JPH0360400B2 true JPH0360400B2 (en) | 1991-09-13 |
Family
ID=16041322
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP60178028A Granted JPS6238400A (en) | 1985-08-13 | 1985-08-13 | Method of processing radioactive waste |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS6238400A (en) |
-
1985
- 1985-08-13 JP JP60178028A patent/JPS6238400A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS6238400A (en) | 1987-02-19 |
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