JPS6189596A - Method of disposing concrete structure in tritium treating facility - Google Patents
Method of disposing concrete structure in tritium treating facilityInfo
- Publication number
- JPS6189596A JPS6189596A JP59211073A JP21107384A JPS6189596A JP S6189596 A JPS6189596 A JP S6189596A JP 59211073 A JP59211073 A JP 59211073A JP 21107384 A JP21107384 A JP 21107384A JP S6189596 A JPS6189596 A JP S6189596A
- Authority
- JP
- Japan
- Prior art keywords
- tritium
- concrete
- water
- concrete structure
- facilities
- 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.)
- Granted
Links
Landscapes
- Processing Of Solid Wastes (AREA)
Abstract
(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.
Description
【発明の詳細な説明】
〔産業上の利用分野〕
この発明は、トリチウム取扱い施設におけるコンクリー
ト構造物を廃棄処理する方法に関するものである。DETAILED DESCRIPTION OF THE INVENTION [Field of Industrial Application] The present invention relates to a method for disposing of concrete structures in tritium handling facilities.
トリチウム(三重水素)Tは、水素Hの同位体水戸、核
融合研究施設、使用済核燃料再処理施設等のトリチウム
取扱い施設においては、このトリチウムTが外部に漏れ
ないような措置がとられている。このトリチウムTfl
、H,Oの一つのH原子と代替してHTOの形態をとる
三重水となるが、この三重水は9水”であるから、上記
の外部への漏れ防止の措置としては、液体のまま、ある
いは蒸発して原子炉施設等の外部に漏れないように、ト
リチウムが発生する部分を気密にする等の措置が取られ
ている。Tritium (tritium) T is an isotope of hydrogen H. At facilities that handle tritium, such as Mito, nuclear fusion research facilities, and spent nuclear fuel reprocessing facilities, measures are taken to prevent this tritium T from leaking outside. . This tritium Tfl
By replacing one H atom of , H, and O, triple water takes the form of HTO, but since this triple water is 9 water, the above-mentioned measure to prevent leakage to the outside is necessary to keep it as a liquid. Alternatively, measures are taken to make the areas where tritium is generated airtight to prevent it from evaporating and leaking outside of nuclear reactor facilities.
ところで、現状では上記の各施設の廃棄解体がほとんど
ないため、上記の如く各施設においてトリチウムの漏れ
を防止すれば足りるが、将来、上記の各施設の廃棄、し
たがって、施設を構成するコンクリート構造物の解体廃
棄が増大することが予想される。By the way, currently there is almost no disposal and demolition of each of the above facilities, so it is sufficient to prevent the leakage of tritium at each facility as described above, but in the future, it will be necessary to dispose of each of the above facilities and, therefore, to dismantle the concrete structures that make up the facilities. It is expected that the amount of demolition and disposal will increase.
上記各施設を構成するコンクリート構造物が放射能汚染
されていると、その解体に際しては、。放射MJ−匹1
物”、L−3Rので−それらけト9ラム俗鈷めして人間
の管理下永久保管しなければならない。If the concrete structures that make up each of the above facilities are radioactively contaminated, what will happen when they are demolished? Radiation MJ - 1 animal
``Things'', L-3R, so they must be collected and stored permanently under human control.
ところで、本願出願人のもとての研究にエリ、上記のト
リチウム取扱い施設にお込で、空気中に極く微量水蒸気
として存在する三重水(HTO)が床、壁等のコンクリ
ート中の自由水もしくは結晶水と置換して、コンクリー
ト中に浸透、固定する現象を発見した。したがって、こ
れらのトリチウム汚染コンクリートは、解体に際しで、
他の核種の汚染や、中性子による放射化が存在しなくて
も、上述の如く永久保管が必要となるが、トリチウム取
扱い施設を′j31を成するコンクリート構造物すべて
を永久保管することは解体コストが莫大なものとなると
いう問題がある。By the way, in the research carried out by the present applicant, it was discovered that triple water (HTO), which exists in the air as extremely small amounts of water vapor, was found to be free water in concrete such as floors and walls. Alternatively, they discovered a phenomenon in which crystallized water penetrates and becomes fixed in concrete by replacing it with crystallized water. Therefore, upon demolition, these tritium-contaminated concretes
Even if there is no contamination with other nuclides or activation by neutrons, permanent storage is required as described above, but permanently storing all the concrete structures that make up the tritium handling facility would be costly due to demolition. The problem is that the amount is enormous.
この発明は上記事情に鑑み、トリチウム取扱い施設の解
体廃棄時において、永久保管しなければならない廃棄物
を極力減少させようとするものである。In view of the above circumstances, this invention aims to reduce as much as possible the amount of waste that must be permanently stored when a tritium handling facility is dismantled and disposed of.
(f14]題点を解決するための手段〕この発明は、上
記問題点を解決するために、コンクリート構造物を破砕
し、この破砕したコンクリート塊を加熱してコンクリー
ト塊中の水分を蒸発させつつ、蒸発した水分を捕集し、
加熱済みのコンクリート塊を廃棄することとした。(f14] Means for solving the problem) In order to solve the above problem, the present invention crushes a concrete structure, heats the crushed concrete mass, and evaporates the water in the concrete mass. , collects evaporated water,
It was decided to discard the heated concrete mass.
(作 用〕
加熱によりコンクリート塊中から水分が除去されるため
、トリチウムの水(三重水)も同様に除去され、コンク
リート塊は放射性物質でなくなる。(Effect) As water is removed from the concrete mass by heating, tritium water (triple water) is also removed, and the concrete mass ceases to be a radioactive substance.
トリチウムの水を含む蒸発した水は、補集されるが、こ
の捕集した水だけが放射性廃棄物として処理される。The evaporated water, including tritiated water, is collected, but only this collected water is treated as radioactive waste.
図面はコンクリート塊処理装置のシステム図で、加熱装
置として高周波加熱炉1が用いられている。The drawing is a system diagram of a concrete lump processing apparatus, in which a high-frequency heating furnace 1 is used as a heating device.
高周波加熱炉lは、炉体2、高周波発生装置3、高周波
ホーン4等で構成され、炉体2は、気密化されたコンク
リート搬入扉2&、コンクリート排出扉2bを持ち、内
部に収容した容器5P+3のコンクリート塊6を加熱す
る。コンクリート排出扉2bは下方に開く蝶番式で、そ
の下方にコンクリート塊受け7が置かれている。The high-frequency heating furnace 1 is composed of a furnace body 2, a high-frequency generator 3, a high-frequency horn 4, etc. The furnace body 2 has an airtight concrete loading door 2&, a concrete discharge door 2b, and a container 5P+3 housed inside. concrete mass 6 is heated. The concrete discharge door 2b is of a hinge type that opens downward, and a concrete lump receiver 7 is placed below it.
炉体2の上部に蒸気排出管8が接続ぢれ、途中に水分捕
集器9が気密性ジョイントエ0を介して接続畜れ、また
、その両側にはバルブ11が設けられ、水分捕集器9の
下流側の蒸気排出管8はζらに水分を吸収するための水
41ii112内に立ち下げられ、水Wj12の上部空
間から吸引管13が立ち上げられて、吸引ポンプ14の
吸入側に接続され、吐出側に接続された排気管15が図
示せぬ排気塔に接続されている。なお、吸引管13の吸
引ポンプ14直前部分くモニタリング用フィルタ16が
設けられている。A steam exhaust pipe 8 is connected to the upper part of the furnace body 2, and a moisture collector 9 is connected in the middle through an airtight joint 0. Valves 11 are provided on both sides of the pipe to collect moisture. The steam exhaust pipe 8 on the downstream side of the vessel 9 is lowered into the water 41ii112 for absorbing moisture, and the suction pipe 13 is raised from the upper space of the water Wj12 to the suction side of the suction pump 14. An exhaust pipe 15 connected to the discharge side is connected to an exhaust tower (not shown). Note that a monitoring filter 16 is provided in a portion of the suction pipe 13 immediately before the suction pump 14 .
実施例の作用について説明すると、トリチウム取扱い施
設を構成するコンクリート構造物を解体し、適宜の大き
さのコンクリート塊に破砕して、これを炉体2内に入れ
る。高周波加熱炉1によりコンクリート塊6が加熱され
ると、内部に浸透、固定した水(自由水あるいは結晶水
)は蒸発し、水蒸気となって蒸気排出管8を通り、水分
捕集器9で捕集塔れる。To explain the operation of the embodiment, a concrete structure constituting a tritium handling facility is dismantled, crushed into concrete blocks of appropriate size, and these are placed into the furnace body 2. When the concrete block 6 is heated by the high-frequency heating furnace 1, the water (free water or crystalline water) that has permeated and fixed inside is evaporated, becomes water vapor, passes through the steam exhaust pipe 8, and is captured by the moisture collector 9. I can gather.
分に水分を除去された排気が吸引ポンプ14により吸引
これで排気塔へ送られ、大気に排出される。The exhaust gas from which moisture has been removed is sucked by the suction pump 14 and sent to the exhaust tower, where it is discharged to the atmosphere.
なお、装置の稼動中は、例えば1時間に1回ぐらいの間
隔でモニタリング用フィルタ16を取り換え、排気中の
トリチウム濃度が許容濃度以下であることを確認する。Note that while the apparatus is in operation, the monitoring filter 16 is replaced, for example, once every hour to confirm that the tritium concentration in the exhaust gas is below the permissible concentration.
このトリチウム濃度の計測は、フィルタ16中のトリチ
ウム債を例えば液体シンチレーションカウンタを用いて
行うとよい。The tritium concentration may be measured using a liquid scintillation counter for tritium bonds in the filter 16, for example.
また、加熱条件は、例えば500℃以上の扁温で数時間
保持するとよい。これによってコンクリート中の自由水
、結晶水は完全に分離される。Further, the heating condition is preferably maintained at a temperature of 500° C. or higher for several hours, for example. This completely separates free water and crystallized water in concrete.
上記の如く加熱により水分を除去したコンクリート塊は
、もはや放射性物質ではないので、コンクリート塊受け
7に取り出し、一般廃業物として廃棄する。Since the concrete lump from which moisture has been removed by heating as described above is no longer a radioactive material, it is taken out into the concrete lump receiver 7 and disposed of as general waste.
水分捕集器9は、モレキュラーシーブ(台底ふつ石の商
品名)その他の吸水性物質を充填したものを用いるとよ
い。水分を捕集したモレキュラーシーブ等の水分捕集器
9は放射性廃棄物として処実施例の加熱方法は高周波加
熱であるが、電気加熱その他種々の加熱法を採用するこ
とができる。As the moisture collector 9, it is preferable to use one filled with molecular sieve (trade name of Daisoko Futsuishi) or other water-absorbing substance. The moisture collector 9, such as a molecular sieve, that has trapped moisture is disposed of as radioactive waste.The heating method used in the embodiment is high frequency heating, but electric heating and other various heating methods can be used.
また、実施例はコンクリート塊から蒸発した水蒸気を水
分捕集器9と水槽12とで2重に捕集す 生るもので
あるが、許容濃度以下になるのであれば水槽12だけで
もよいし、また、モニタリングにより加熱炉2から出る
水蒸気自体が許容濃度以下であることを確認できている
間は、水分捕集器9や水N12等を通さずに、加熱炉2
から水蒸気を直接大気に排出してもよい。In addition, in the embodiment, the water vapor evaporated from the concrete mass is collected twice in the moisture collector 9 and the water tank 12, but as long as the concentration is below the allowable level, only the water tank 12 may be used. In addition, as long as it is confirmed through monitoring that the water vapor itself coming out of the heating furnace 2 is below the permissible concentration, the heating furnace 2 is
The water vapor may be discharged directly to the atmosphere.
以上説明した本発明によれば、コンクリート塊を加熱し
て、内部に浸憑、固定した自由水あるいは結晶水を蒸発
させ、除去するので、トリチウム汚染されていたコンク
リート塊を一般廃棄物として廃菓することができ、放射
性廃棄物として処理するのは捕集した水分のみでよい。According to the present invention described above, the concrete mass is heated to evaporate and remove the free water or crystal water that has permeated and fixed inside, so the concrete mass contaminated with tritium is disposed of as general waste. Only the collected water needs to be disposed of as radioactive waste.
したがって、トリチウム取扱い施設を構成するコンクリ
ート構造物すべてを放射性廃棄物として処理しなければ
ならない場合と比べて、放射性廃棄物として永久保存し
なければならない廃棄物の量が著しく減少し、したがっ
て、トリチウム取扱い施設の解体時のコストを大幅に低
減することができる。Therefore, compared to the case where all the concrete structures that make up the tritium handling facility had to be treated as radioactive waste, the amount of waste that must be permanently stored as radioactive waste is significantly reduced, and therefore, the amount of waste that must be permanently stored as radioactive waste is significantly reduced. The cost of dismantling the facility can be significantly reduced.
図面は本発明の方法の一実施例を示すコンクリート塊処
理装置のシステム図である。
1・・・・・・高周波加熱炉、2・・・・・・炉体、6
・・・・・・コンクリート塊、8・・・・・・蒸気排出
管、9・・・・・・水分捕集器、12・・・・・・水槽
、13・・・・・・吸引管、15・・・・・・排気管。The drawing is a system diagram of a concrete lump processing apparatus showing an embodiment of the method of the present invention. 1... High frequency heating furnace, 2... Furnace body, 6
... Concrete lump, 8 ... Steam discharge pipe, 9 ... Moisture collector, 12 ... Water tank, 13 ... Suction pipe , 15...exhaust pipe.
Claims (1)
砕し、この破砕したコンクリート塊を加熱してコンクリ
ート塊中の水分を蒸発させつつ、蒸発した水分を捕集し
、加熱済みコンクリート塊を廃棄することを特徴とする
トリチウム取扱い施設におけるコンクリート構造物の廃
棄処理方法。The method is characterized by crushing a concrete structure in a tritium handling facility, heating the crushed concrete mass to evaporate water in the concrete mass, collecting the evaporated water, and disposing of the heated concrete mass. Disposal method for concrete structures in tritium handling facilities.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP59211073A JPS6189596A (en) | 1984-10-08 | 1984-10-08 | Method of disposing concrete structure in tritium treating facility |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP59211073A JPS6189596A (en) | 1984-10-08 | 1984-10-08 | Method of disposing concrete structure in tritium treating facility |
Publications (2)
Publication Number | Publication Date |
---|---|
JPS6189596A true JPS6189596A (en) | 1986-05-07 |
JPH0456960B2 JPH0456960B2 (en) | 1992-09-10 |
Family
ID=16599956
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP59211073A Granted JPS6189596A (en) | 1984-10-08 | 1984-10-08 | Method of disposing concrete structure in tritium treating facility |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPS6189596A (en) |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPH0341386A (en) * | 1989-07-08 | 1991-02-21 | Shimizu Corp | Non-destructive measurement of quantity of tritium in concrete and device therefor |
JP2010066047A (en) * | 2008-09-09 | 2010-03-25 | Shimizu Corp | Method for treating activated concrete |
-
1984
- 1984-10-08 JP JP59211073A patent/JPS6189596A/en active Granted
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPH0341386A (en) * | 1989-07-08 | 1991-02-21 | Shimizu Corp | Non-destructive measurement of quantity of tritium in concrete and device therefor |
JP2010066047A (en) * | 2008-09-09 | 2010-03-25 | Shimizu Corp | Method for treating activated concrete |
Also Published As
Publication number | Publication date |
---|---|
JPH0456960B2 (en) | 1992-09-10 |
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