JPH0143679Y2 - - Google Patents

Info

Publication number
JPH0143679Y2
JPH0143679Y2 JP1982181573U JP18157382U JPH0143679Y2 JP H0143679 Y2 JPH0143679 Y2 JP H0143679Y2 JP 1982181573 U JP1982181573 U JP 1982181573U JP 18157382 U JP18157382 U JP 18157382U JP H0143679 Y2 JPH0143679 Y2 JP H0143679Y2
Authority
JP
Japan
Prior art keywords
filter
container
main body
emitters
lid
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
Application number
JP1982181573U
Other languages
Japanese (ja)
Other versions
JPS5985994U (en
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed filed Critical
Priority to JP1982181573U priority Critical patent/JPS5985994U/en
Publication of JPS5985994U publication Critical patent/JPS5985994U/en
Application granted granted Critical
Publication of JPH0143679Y2 publication Critical patent/JPH0143679Y2/ja
Granted legal-status Critical Current

Links

Classifications

    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Filtering Of Dispersed Particles In Gases (AREA)
  • Processing Of Solid Wastes (AREA)

Description

【考案の詳細な説明】 本考案は粉状のα放射体、特にプルトニウムで
汚染された固体廃棄物の構内輸送用に好適なコン
テナに関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a container suitable for intra-plant transportation of solid waste contaminated with powdered alpha emitters, particularly plutonium.

従来、α放射体、たとえばプルトニウムで汚染
されたバルブ、グローブボツクス、フイルタなど
の固体廃棄物は、きびしい密封包蔵が要求される
ことから、ポリ塩化ビニル製のバツグに入れ、シ
ールした後に貯蔵コンテナに収納し、貯蔵室ある
いは貯蔵庫に貯蔵されていた。
Traditionally, solid waste such as valves, glove boxes, and filters contaminated with alpha emitters, such as plutonium, have been placed in polyvinyl chloride bags, sealed, and then placed in storage containers due to the strict packaging requirements. It was stored in storage rooms or warehouses.

しかしながら近年、国策上から原子力の平和利
用、特にプルトニウム関連の有効利用に関する開
発が進展するにつれて、プルトニウムなどの微粒
子状のα放射体で汚染されたバルブやフイルタな
どの固体廃棄物の量が多くなつて貯蔵の限界に達
しつつある。
However, in recent years, as national policy has advanced the development of peaceful uses of nuclear energy, especially the effective use of plutonium, the amount of solid waste such as valves and filters contaminated with particulate alpha emitters such as plutonium has increased. storage capacity is reaching its limits.

そこでα放射体を取り扱う施設の構内に、これ
ら固体廃棄物の減容処理施設を設置する機運が高
まつており、固体廃棄物を貯蔵室あるいは貯蔵庫
から処理施設まで運搬するコンテナの製造が急務
の問題になつている。
Therefore, there is a growing momentum to install volume reduction treatment facilities for these solid wastes on the premises of facilities that handle alpha emitters, and there is an urgent need to manufacture containers to transport solid waste from storage rooms or warehouses to processing facilities. It's becoming a problem.

ところでかかる固体廃棄物を構内輸送する場
合、法規則から見た輸送容器にかかわる詳細な技
術基準は、構外輸送容器ほど厳格ではない。また
被輸送物がα放射体で汚染されたものであるの
で、特に放熱性能や遮断性能が問題となることは
なく、構内輸送用である限り、1〜2mの落下衝
撃下で微粉末状のα放射体に対して十分な密封性
を有すれば良いと考えられる。しかし、プルトニ
ウムで汚染された固体廃棄物の場合、法規上の許
容漏洩基準値に準拠しながら、十分な密封性を有
するコンテナを、大量に、また経済的に供給でき
る設計を行なうことは、従来技術では極めて難し
い問題である。
However, when such solid waste is transported on-site, the detailed technical standards regarding transport containers from the perspective of laws and regulations are not as strict as those for off-site transport containers. In addition, since the transported object is contaminated with alpha emitters, there is no particular problem with heat dissipation performance or shielding performance, and as long as it is for transportation within the premises, it will be finely powdered under the impact of a fall of 1 to 2 meters. It is considered that it is sufficient to have sufficient sealing performance against α emitters. However, in the case of solid waste contaminated with plutonium, it has not been possible to design containers with sufficient sealing performance that can be supplied economically in large quantities while complying with legal allowable leakage standards. This is an extremely difficult technical problem.

このため、現在、法規制を満足しつつ、十分に
経済的なコンテナの出現が要望さている。
For this reason, there is currently a demand for containers that are sufficiently economical while satisfying legal regulations.

そこで本考案は、かかる現状にかんがみて、な
されたものであり、構内輸送の目的に十分に給し
得るだけの密封性能を維持して微粉末状のα放射
体の漏洩をほぼ完全に防止することができ、また
漏洩の駆動力となるコンテナ内外の空気圧力差を
均等に保つことができ、1〜2mの落下衝撃にも
十分に耐え、更に構内運搬コンテナとしてばかり
でなく、貯蔵用コンテナとしても使用することが
できるなどの特長を有するものである。
Therefore, the present invention has been developed in view of the current situation, and maintains a sealing performance sufficient for the purpose of intra-plant transportation, and almost completely prevents leakage of fine powdered alpha emitters. In addition, it is possible to maintain an even air pressure difference inside and outside the container, which is the driving force for leakage, and it can withstand drops of 1 to 2 meters, making it suitable not only for on-site transport containers but also for storage containers. It has the advantage that it can also be used.

すなわち本考案にかかるα汚染固体廃棄物の構
内輸送用コンテナは、補強リブを夫々外面側に形
成した蓋部と本体部とから成り、前記蓋部およ
び/または本体部に形成した開口部に微粒子状の
α放射体捕集用フイルタを取付け、このフイルタ
の両側に着脱自在にフイルタ保護板を設けると共
に、前記蓋部と本体部との間、および前記フイル
タの取付部に密封材を介在せしめたことを特徴と
するものである。
In other words, the container for on-site transportation of α-contaminated solid waste according to the present invention is composed of a lid and a main body, each having reinforcing ribs formed on the outer surface thereof, and has an opening formed in the lid and/or the main body for transporting fine particles. A filter for collecting alpha emitters of the shape of the shape is attached, filter protection plates are provided on both sides of the filter in a removable manner, and a sealing material is interposed between the lid part and the main body part and at the attachment part of the filter. It is characterized by this.

以下、本考案を図面に示した実施例にもとづき
説明する。
The present invention will be described below based on embodiments shown in the drawings.

第1図は本考案に係るコンテナの平面図、第2
図はその断面図であり、コンテナ1は蓋部2と本
体部3とから構成されており、蓋部2、本体部3
は夫々外面側に補強リブ4が形成されている。
Figure 1 is a plan view of the container according to the present invention, Figure 2 is a plan view of the container according to the present invention;
The figure is a sectional view of the container 1, and the container 1 is composed of a lid 2 and a main body 3.
A reinforcing rib 4 is formed on each outer surface side.

また本体部3には開口部5が形成されており、
この開口部5にはα放射体の微粒子捕集用のフイ
ルタ6が取付けられている。開口部5は第2図に
示す如く、本体部3にのみ形成するばかりでな
く、蓋部2に形成しても良いし、或は蓋部2と本
体部3の両方に形成することもできる。蓋部2お
よび本体部3は、内面ステンレスライニングの炭
素鋼板または耐食高強度アルミ板で形成され、い
ずれにせよ内面はバフ仕上げ等で鏡面とするのが
望ましい。フイルタ6の1例としては、通常のα
放射体を取扱う施設で使用されている内部被曝防
止用の半面マスク中のフイルタのように、
0.3μDOPテストによる微粒子捕集効率が99.97%
以上と云うような高い粒子捕集効率を持ち、かつ
1〜2mの衝撃下でもその性能が低下しないもの
が用いられる。
Furthermore, an opening 5 is formed in the main body 3.
A filter 6 for collecting fine particles of α emitters is attached to this opening 5 . As shown in FIG. 2, the opening 5 may be formed not only in the main body 3 but also in the lid 2, or in both the lid 2 and the main body 3. . The lid part 2 and the main body part 3 are formed of a carbon steel plate or a corrosion-resistant high-strength aluminum plate with an inner surface lined with stainless steel, and in any case, it is preferable that the inner surface be buffed or otherwise polished to a mirror surface. As an example of the filter 6, a normal α
Like the filters in half-face masks to prevent internal radiation exposure used in facilities that handle radiators,
Particle collection efficiency is 99.97% by 0.3μDOP test
A material that has high particle collection efficiency as described above and whose performance does not deteriorate even under impact of 1 to 2 meters is used.

なお、DOPテスト、すなわちジオクチルフタ
レート・テストとは0.3ミクロンのDOPスモーク
で捕集効率を測定するもので、現在最も厳格なテ
スト法であり、米国原子力委員会によつて採用さ
れている。したがつて、日本においても原子力仕
様のフイルタについては、ほとんどすべてこのテ
ストに合格したものを使用している。
The DOP test, or dioctyl phthalate test, measures the collection efficiency with 0.3 micron DOP smoke, and is currently the most rigorous test method adopted by the U.S. Atomic Energy Commission. Therefore, in Japan as well, almost all nuclear power spec filters are used that have passed this test.

また本考案においては、フイルタ6の内側およ
び外側の両側に、コンテナの落下時あるいは局部
的な外力によりフイルタが破損しないように、フ
イルタ保護板7,7′が夫々設けられている。具
体的には、たとえば第3図の要部拡大図に示すよ
うにフイルタ6は本体部3に外側Aからフイルタ
固定板8で固定され、このフイルタ固定板8にフ
イルタ保護板7′が取付けられ、一方、内側Bで
は、本体部3に直接フイルタ保護板7が取付けて
ある。
Further, in the present invention, filter protection plates 7 and 7' are provided on both the inside and outside of the filter 6, respectively, to prevent the filter from being damaged when the container falls or due to local external force. Specifically, for example, as shown in the enlarged view of the main part in FIG. 3, the filter 6 is fixed to the main body 3 from the outside A with a filter fixing plate 8, and a filter protection plate 7' is attached to the filter fixing plate 8. On the other hand, on the inside B, a filter protection plate 7 is directly attached to the main body part 3.

更に本考案においては、蓋部2と本体部3のフ
ランジ部分9、フイルタ6の取付け部分は、夫々
ゴム系Oリング等の密封材10の介在によつて密
封されている。
Further, in the present invention, the flange portion 9 of the lid portion 2, the main body portion 3, and the attachment portion of the filter 6 are each sealed by a sealing member 10 such as a rubber O-ring.

かかる本考案のコンテナの密封性能は、通常の
使用条件では大気圧変動により避けられないコン
テナ内外の圧力差を恒常的にゼロにし、各部密封
材によりシールされた密封部よりの空気漏洩をほ
ぼゼロにすることができ、α放射体を含む微粒子
のコンテナ外への洩れを防止する点で重要でああ
る。
The sealing performance of the container of the present invention is such that the pressure difference between the inside and outside of the container, which is unavoidable due to atmospheric pressure fluctuations under normal usage conditions, is permanently reduced to zero, and air leakage from the sealed parts sealed with sealing materials is almost zero. This is important in preventing particles containing α emitters from leaking out of the container.

これは同じ△Pの流動の駆動力が働いたとして
も、フイルタの圧力損失は各部密封材によりシー
ルされた密封部の圧力損失に比較して、無視でき
る程度に小さいため、流動は圧力損失の無視でき
る程度に小さいフイルタを通して起こる原理を利
用したものである。コンテナ内部の空気は、フイ
ルタを通して外に出るが、空気中に含まれるα放
射体を含む微粒子は高捕集効率のフイルタで捕集
され、外に出ることはない。
This means that even if the same flow driving force of △P is applied, the pressure loss of the filter is negligibly small compared to the pressure loss of the sealed part sealed by the sealing material of each part, so the flow is less than the pressure loss. It utilizes the principle that this occurs through a filter that is so small that it can be ignored. The air inside the container passes through a filter to the outside, but fine particles containing alpha emitters contained in the air are collected by a filter with high collection efficiency and do not escape.

したがつて、コンテナの使用に先立つて、予め
気密性が通常、試験され、コンテナにかかわる各
部密封材でシールされた密封部よりの圧力損失が
極めて大きいことを、気密試験で確証することに
なる。このときには、外側のフイルタ保護板7′
をはずして盲にしたのち、空気等を気密検査孔1
3からコンテナ1内に導入して、コンテナの設計
圧力まで加圧し、石鹸気泡テスト程度の気密検査
を行ない、たとえば10-2acc/sec程度の漏洩がな
いことを確認しておけば良く、使用前の漏洩検査
は、従来の検査に比較して極めて簡便で短時間で
輸送が可能になる。
Therefore, before a container is used, its airtightness is usually tested in advance, and an airtightness test is conducted to ensure that the pressure loss from the sealed parts of each part of the container is extremely large. . At this time, the outer filter protection plate 7'
After removing the hole and making it blind, check the air tightness through hole 1.
3 into the container 1, pressurize it to the design pressure of the container, perform an airtightness test similar to a soap bubble test, and confirm that there is no leakage of, for example, 10 -2 acc/sec. The pre-leakage inspection is extremely simple and allows transportation in a short time compared to conventional inspections.

なお、従来はヘリウムリーク試験等が採用され
ており、検査機器も高級であり、判断も専門的、
かつ繁雑であつた。
In addition, conventional methods such as helium leak tests have been used, and the testing equipment is high-grade and the judgments are professional.
It was also complicated.

輸送に際しては、気密検査のための圧力を下げ
たのちに開口部5の盲板を取りはずしてコンテナ
内の圧力を大気圧と平衡させれば、輸送に供しう
るだけの気密性が維持できることになる。なぜな
らば、フイルタ6を介して空気の出入はあるもの
の、コンテナ1内部のα放射体で汚染された固体
廃棄物より空気中に浮遊したα放射体を含む微粒
子は、たとえ一次密封境界を形成するポリ塩化ビ
ニルバツグが破れていても、フイルタ6で捕集さ
れてコンテナ1より洩れることがないからであ
る。
During transportation, if the blind plate of the opening 5 is removed after reducing the pressure for airtightness inspection and the pressure inside the container is balanced with atmospheric pressure, airtightness sufficient for transportation can be maintained. . This is because, although air enters and exits through the filter 6, fine particles containing alpha emitters suspended in the air from the solid waste contaminated with alpha emitters inside the container 1 form a primary sealed boundary. This is because even if the polyvinyl chloride bag is torn, it will be collected by the filter 6 and will not leak from the container 1.

かかる本考案のコンテナを用いてα放射体で汚
染された固体廃棄物を構内運搬するにあたつて
は、第2図に示すように固体廃棄物12をポリ塩
化ビニルバツグに入れてシールし、一次密封境界
を形成した後に、これを本考案のコンテナ1の中
に入れ、蓋部2と本体部3を密封材10を介して
封じるだけで良く、気密検査も簡単であるので大
量輸送を目的とする構内輸送の目的に供すること
ができる。
When transporting solid waste contaminated with alpha emitters within the premises using the container of the present invention, the solid waste 12 is placed in a polyvinyl chloride bag and sealed, as shown in FIG. After forming a sealed boundary, it is only necessary to put it into the container 1 of the present invention and seal the lid part 2 and the main body part 3 via the sealing material 10, and the airtightness test is easy, so it is suitable for mass transportation. It can be used for the purpose of on-site transportation.

コンテナ自体で耐衝撃エネルギーを吸収しきれ
ない場合や、事業所により緩衝材をつけることを
義務づけられている場合には、コンテナ外側に更
に緩衝材を取付けて輸送することもできる。
If the container itself cannot absorb enough impact energy, or if the business is required to attach cushioning material, additional cushioning material can be attached to the outside of the container for transportation.

以上述べた如く本考案によれば、フイルタの内
側および外側にはフイルタ保護板が設けられてい
るので、α放射体で汚染された固体廃棄物を貯蔵
室あるいは貯蔵庫から構内の減容施設に運搬する
際に、フイルタが破損されることがなく、従つて
α放射体を含む微粒子のコンテナ外への漏洩を経
済性をもつて、ほぼ完全に防止することができ
る。
As described above, according to the present invention, since filter protection plates are provided on the inside and outside of the filter, solid waste contaminated with alpha emitters is transported from the storage room or warehouse to the volume reduction facility on the premises. In doing so, the filter is not damaged, and therefore leakage of particles containing α emitters to the outside of the container can be economically and almost completely prevented.

一方、蓋部および本体部には、夫々補強リブが
設けられており、フイルタも1〜2m落下衝撃に
耐え得るので、α放射体を含む微粒子の漏洩に対
して十分な密封性が保持され、耐火性能が要求さ
れない構内輸送用コンテナとして好適に用いられ
る。
On the other hand, the lid part and the main body part are each provided with reinforcing ribs, and the filter can also withstand the impact of dropping from 1 to 2 meters, so sufficient sealing performance is maintained against leakage of fine particles including α emitters. Suitable for use as a container for on-site transportation where fire resistance is not required.

更に本考案のコンテナは構内輸送用としてばか
りでなく、そのまま貯蔵コンテナとして兼用する
こともできる。
Furthermore, the container of the present invention can be used not only for intra-plant transportation, but also as a storage container.

【図面の簡単な説明】[Brief explanation of drawings]

第1図は本考案の実施例を示す平面図、第2図
はその断面図、第3図はその要部拡大断面図であ
る。 2……蓋部、3……本体部、4……補強リブ、
5……開口部、6……α放射体捕集用フイルタ、
7……フイルタ保護板、10……密封材、12…
…α放射体汚染固体廃棄物。
FIG. 1 is a plan view showing an embodiment of the present invention, FIG. 2 is a sectional view thereof, and FIG. 3 is an enlarged sectional view of the main part thereof. 2... Lid part, 3... Main body part, 4... Reinforcement rib,
5...Aperture, 6...α emitter collection filter,
7...Filter protection plate, 10...Sealing material, 12...
...Solid waste contaminated with alpha emitters.

Claims (1)

【実用新案登録請求の範囲】[Scope of utility model registration request] 補強リブを夫々外面側に形成した蓋部と本体部
とから成り、該蓋部および/または本体部に形成
した開口部に微粒子状のα放射体捕集用フイルタ
を取付け、該フイルタの両側に着脱自在にフイル
タ保護板を設けると共に、前記蓋部と本体部との
間、および前記フイルタの取付部に密封材を介在
せしめたことを特徴とするα汚染固体廃棄物の構
内輸送用コンテナ。
It consists of a lid part and a main body part each having reinforcing ribs formed on the outer surface thereof, and a filter for collecting alpha emitters in the form of fine particles is attached to the opening formed in the lid part and/or the main body part, and a filter for collecting α emitters in the form of fine particles is attached to the opening formed in the lid part and/or the main body part. A container for intra-plant transportation of α-contaminated solid waste, characterized in that a filter protection plate is provided in a detachable manner, and a sealing material is interposed between the lid part and the main body part and at the attachment part of the filter.
JP1982181573U 1982-11-30 1982-11-30 Container for on-site transportation of α-contaminated solid waste Granted JPS5985994U (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP1982181573U JPS5985994U (en) 1982-11-30 1982-11-30 Container for on-site transportation of α-contaminated solid waste

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP1982181573U JPS5985994U (en) 1982-11-30 1982-11-30 Container for on-site transportation of α-contaminated solid waste

Publications (2)

Publication Number Publication Date
JPS5985994U JPS5985994U (en) 1984-06-11
JPH0143679Y2 true JPH0143679Y2 (en) 1989-12-18

Family

ID=30393424

Family Applications (1)

Application Number Title Priority Date Filing Date
JP1982181573U Granted JPS5985994U (en) 1982-11-30 1982-11-30 Container for on-site transportation of α-contaminated solid waste

Country Status (1)

Country Link
JP (1) JPS5985994U (en)

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US8109400B2 (en) * 2007-12-05 2012-02-07 Global Nuclear Fuel-Americas, Llc. Industrial package having pressurization capability
JP2017125828A (en) * 2016-01-15 2017-07-20 卯 石井 Public exposure protection using radiation shielding reducer which is rock wool material and molded body thereof, vocational exposure protection, medical exposure protection and radioactive waste disposal

Also Published As

Publication number Publication date
JPS5985994U (en) 1984-06-11

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