JPS6325598A - Solidifying processing method of radioactive waste - Google Patents
Solidifying processing method of radioactive wasteInfo
- Publication number
- JPS6325598A JPS6325598A JP16839186A JP16839186A JPS6325598A JP S6325598 A JPS6325598 A JP S6325598A JP 16839186 A JP16839186 A JP 16839186A JP 16839186 A JP16839186 A JP 16839186A JP S6325598 A JPS6325598 A JP S6325598A
- Authority
- JP
- Japan
- Prior art keywords
- radioactive waste
- metal oxides
- mixture
- powder
- solidifying
- 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
- 239000002901 radioactive waste Substances 0.000 title claims description 32
- 238000003672 processing method Methods 0.000 title 1
- 238000000034 method Methods 0.000 claims description 18
- 229910044991 metal oxide Inorganic materials 0.000 claims description 17
- 150000004706 metal oxides Chemical class 0.000 claims description 17
- 239000000843 powder Substances 0.000 claims description 13
- 239000000203 mixture Substances 0.000 claims description 11
- 238000007711 solidification Methods 0.000 claims description 11
- 230000008023 solidification Effects 0.000 claims description 11
- XAGFODPZIPBFFR-UHFFFAOYSA-N aluminium Chemical compound [Al] XAGFODPZIPBFFR-UHFFFAOYSA-N 0.000 claims description 10
- 238000006243 chemical reaction Methods 0.000 claims description 10
- 239000007788 liquid Substances 0.000 claims description 9
- 239000003832 thermite Substances 0.000 claims description 7
- 238000001035 drying Methods 0.000 claims description 2
- 238000005266 casting Methods 0.000 claims 1
- 239000002699 waste material Substances 0.000 description 10
- 229910052751 metal Inorganic materials 0.000 description 9
- 239000002184 metal Substances 0.000 description 9
- 229910052782 aluminium Inorganic materials 0.000 description 7
- 239000004033 plastic Substances 0.000 description 6
- XEEYBQQBJWHFJM-UHFFFAOYSA-N Iron Chemical compound [Fe] XEEYBQQBJWHFJM-UHFFFAOYSA-N 0.000 description 5
- 238000002156 mixing Methods 0.000 description 5
- 238000003860 storage Methods 0.000 description 5
- 239000000463 material Substances 0.000 description 4
- 229920005989 resin Polymers 0.000 description 4
- 239000011347 resin Substances 0.000 description 4
- PNEYBMLMFCGWSK-UHFFFAOYSA-N aluminium oxide Inorganic materials [O-2].[O-2].[O-2].[Al+3].[Al+3] PNEYBMLMFCGWSK-UHFFFAOYSA-N 0.000 description 3
- 239000011324 bead Substances 0.000 description 3
- 238000011038 discontinuous diafiltration by volume reduction Methods 0.000 description 3
- JEIPFZHSYJVQDO-UHFFFAOYSA-N iron(III) oxide Inorganic materials O=[Fe]O[Fe]=O JEIPFZHSYJVQDO-UHFFFAOYSA-N 0.000 description 3
- 239000002925 low-level radioactive waste Substances 0.000 description 3
- 238000012545 processing Methods 0.000 description 3
- 239000010426 asphalt Substances 0.000 description 2
- 239000004568 cement Substances 0.000 description 2
- 229910052742 iron Inorganic materials 0.000 description 2
- 239000003960 organic solvent Substances 0.000 description 2
- 239000011819 refractory material Substances 0.000 description 2
- 238000012546 transfer Methods 0.000 description 2
- FYYHWMGAXLPEAU-UHFFFAOYSA-N Magnesium Chemical compound [Mg] FYYHWMGAXLPEAU-UHFFFAOYSA-N 0.000 description 1
- PMZURENOXWZQFD-UHFFFAOYSA-L Sodium Sulfate Chemical compound [Na+].[Na+].[O-]S([O-])(=O)=O PMZURENOXWZQFD-UHFFFAOYSA-L 0.000 description 1
- 239000012752 auxiliary agent Substances 0.000 description 1
- 238000009835 boiling Methods 0.000 description 1
- 238000005253 cladding Methods 0.000 description 1
- 238000007796 conventional method Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 239000000706 filtrate Substances 0.000 description 1
- 238000001914 filtration Methods 0.000 description 1
- PCHJSUWPFVWCPO-UHFFFAOYSA-N gold Chemical compound [Au] PCHJSUWPFVWCPO-UHFFFAOYSA-N 0.000 description 1
- 239000010931 gold Substances 0.000 description 1
- 229910052737 gold Inorganic materials 0.000 description 1
- 229910052749 magnesium Inorganic materials 0.000 description 1
- 239000011777 magnesium Substances 0.000 description 1
- 239000000155 melt Substances 0.000 description 1
- 238000002844 melting Methods 0.000 description 1
- 230000008018 melting Effects 0.000 description 1
- 150000002739 metals Chemical class 0.000 description 1
- 239000010446 mirabilite Substances 0.000 description 1
- 229920001225 polyester resin Polymers 0.000 description 1
- 239000004645 polyester resin Substances 0.000 description 1
- 239000000047 product Substances 0.000 description 1
- 239000012857 radioactive material Substances 0.000 description 1
- 238000011160 research Methods 0.000 description 1
- 238000007790 scraping Methods 0.000 description 1
- 239000010409 thin film Substances 0.000 description 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 1
- 238000005303 weighing Methods 0.000 description 1
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) [Abstract] This bulletin contains application data before electronic filing, so abstract data is not recorded.
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、沸騰水型原子力発電所等の放射性物質取扱い
施設で発生する中レベルないし低レベルの放射性廃棄物
の処理方法に係り、特に、金属酸化物を含む放射性廃棄
物の固化処理方法に関する。[Detailed Description of the Invention] [Object of the Invention] (Industrial Application Field) The present invention provides a method for treating medium to low level radioactive waste generated in facilities handling radioactive materials such as boiling water nuclear power plants. In particular, the present invention relates to a method for solidifying radioactive waste containing metal oxides.
（従来の技術）
従来より、沸騰水型原子力発電所（ＢＷＲ原子力発電所
）等の放射性物質取扱い施設で発生する放射性廃棄物を
長期間安定に貯蔵するため、セメント、アスファルト、
プラスチック等からなる固化材により一体に固化させ、
安定な固化体とすることが広く行われている。(Conventional technology) Cement, asphalt,
It is solidified into one piece using a solidifying material made of plastic etc.
It is widely practiced to form a stable solidified body.
第３図は同化材としてプラスチックを用いた固化処理方
法のフローチャートであって、ＢＷＲ原子力発電所から
発生する中低レベル放射性廃棄物はまず廃棄物処理設備
で処理され、濃縮廃液（芒硝的２５％、金属酸化物数％
含有）と粉末・ビーズ樹脂廃液（金属酸化物数％含有）
となる（ｍ）。Figure 3 is a flowchart of a solidification treatment method using plastic as an assimilation material, in which medium and low level radioactive waste generated from the BWR nuclear power plant is first treated in a waste treatment facility, and concentrated waste liquid (25% , metal oxide number%
(contains) and powder/bead resin waste liquid (contains several percent of metal oxides)
(m)
このうち濃縮廃液は乾燥処理され（ｎ）、乾燥粉体とな
る。また粉末・ビーズ樹脂廃液も乾燥処理されて（０）
乾燥粉体とされる。これらの乾燥粉体はポリエステル樹
脂等のプラスチック同化材を用いて同化処理される（ｐ
）。そしてこのようにして形成された同化体パッケージ
は放射性廃棄物貯蔵庫に貯蔵される。Among these, the concentrated waste liquid is subjected to drying treatment (n) and becomes a dry powder. Powder/bead resin waste liquid is also dried (0)
It is considered as a dry powder. These dry powders are assimilated using a plastic assimilator such as polyester resin (p
). The assimilate packages thus formed are then stored in a radioactive waste repository.
（発明が解決しようとする問題点）
しかし、この同化体パッケージは安全上の見地から放射
能が所定のレベルに減衰するまで長期にわたって貯蔵す
る必要があるため、貯蔵スペースを確保しつづけること
が次第に困難になってきており、したがって放射性廃棄
物の減容が今後の大ぎな課題となっている。(Problem to be solved by the invention) However, from a safety standpoint, it is necessary to store this assimilate package for a long period of time until the radioactivity decays to a predetermined level, so it is becoming increasingly difficult to secure storage space. Therefore, reducing the volume of radioactive waste has become a major issue in the future.
なおプラスチック固化処理方法は、セメント固化処理方
法やアスファルト固化処理方法に比べて比較的減容性に
優れているが、種々の有機溶剤を使用するため処理コス
トが高く、また有機溶剤の管理が繁雑であるという問題
があった。Although the plastic solidification treatment method is relatively superior in volume reduction compared to the cement solidification treatment method and the asphalt solidification treatment method, the treatment cost is high because it uses various organic solvents, and the management of organic solvents is complicated. There was a problem that.
本発明はこのような従来の事情に対処してなされたもの
で、テルミット反応を利用して同化処理を行なうことに
より、金属酸化物を含む放射性廃棄物を低処理コストで
、減容しつつ同化体とする放射性廃棄物の固化処理方法
を提供することを目的とする。The present invention has been made in response to these conventional circumstances, and by performing assimilation treatment using the thermite reaction, it is possible to assimilate radioactive waste containing metal oxides at low processing cost while reducing the volume. The purpose of this research is to provide a method for solidifying radioactive waste.
［発明の構成］
（問題点を解決するための手段）
本発明の放射性廃棄物の固化処理方法は、原子力施設で
発生した金属酸化物を含む放射性廃棄物とアルミニウム
粉末とを混合し、この混合物に点火して、テルミット反
応により前記混合物中の金属酸化物を還元しつつ融解さ
せ、しかる後この混合物を所定の形状に鋳造することを
特徴としている。[Structure of the Invention] (Means for Solving the Problems) The method for solidifying radioactive waste of the present invention involves mixing radioactive waste containing metal oxides generated at a nuclear facility with aluminum powder, and mixing this mixture with aluminum powder. is ignited to reduce and melt the metal oxide in the mixture through thermite reaction, and then this mixture is cast into a predetermined shape.
（作用）
本発明方法における処理対象の放射性廃棄物中の金属酸
化物は、通常Ｆｅ２０３（クラッド）が大部分を占めて
いる。そしてテルミット反応では、Ｆｅ２Ｏ３はＡ℃と
の混合物は次式で示されるように高熱を発生して反応し
、生成した鉄とアルミナとはこの反応熱により溶融する
。(Function) The metal oxides in the radioactive waste to be treated in the method of the present invention are usually mostly composed of Fe203 (cladding). In the thermite reaction, a mixture of Fe2O3 and A.degree. C. reacts by generating high heat as shown by the following equation, and the produced iron and alumina are melted by this reaction heat.
Ｆｅ２０３ ＋２ＡＪｌ！＝ＡＪｌ！ ｚ ０３ ＋２
Ｆｅ＋１８９１００ｃａｌまたは
３Ｆｅ ２ ０ ３ ＋８八ｉ ＝ ４Ａｆｆｌ
２ ０ ３ ＋９Ｆｅ＋７０２５００ｃａｌまた鉄
以外の金属酸化物も同様の反応により還元されて純金属
となる。この融解物を耐火物製の適当な容器に鋳造し放
冷すれば、金属とアルミナとは２層に別れて固化し減容
性が高い、また取扱いが容易な固化体が得られる。Fe203 +2AJl! =AJl! z 03 +2
Fe+189100cal or 3Fe203+88i = 4Affl
2 0 3 +9Fe+702500 cal Metal oxides other than iron are also reduced to pure metals by similar reactions. If this melt is cast into a suitable container made of refractory material and allowed to cool, the metal and alumina will solidify in two layers, yielding a solidified product that has high volume reduction properties and is easy to handle.
（実施例）
以下本発明の詳細を図面に示す一実施例について説明す
る。(Example) The details of the present invention will be described below with reference to an example shown in the drawings.
この実施例では、第１図のフローチャートに示すように
、ＢＷＲ原子力発電所から発生する中低レベル放射性廃
棄物はまず廃棄物処理設備で処理され、濃縮廃液［芒硝
約２５％、金属酸化物（主としてＦｅｚ ｏ ３ ）数
％含有］と粉末・ど−ズ樹脂廃液（金底酸化物数％含有
）となる（ａ）。In this example, as shown in the flowchart of Fig. 1, medium and low level radioactive waste generated from the BWR nuclear power plant is first treated in a waste treatment facility, and concentrated waste liquid [approximately 25% mirabilite, metal oxides ( Mainly containing several percent of Fezo 3 )] and powder/dose resin waste liquid (containing several percent of gold bottom oxide) (a).
このうち濃縮廃液はろ過処理され、ろ液は薄膜掻取乾燥
機などにより乾燥処理が施されて（Ｃ）乾燥粉体となり
、公知の方法により例えばプラスチック固化処理が施さ
れて（ｄ＞プラスチック固化体とされる。Among these, the concentrated waste liquid is filtered, and the filtrate is dried using a thin film scraping dryer or the like to form a dry powder (C), which is then subjected to, for example, plastic solidification treatment by a known method (d>Plastic solidification). It is considered a body.
一方ろ化処理工程（ｂ）においてろ別された金属酸化物
は粉末・ビーズ樹脂廃液とともに乾燥処理され（ｅ）、
さらに焼却処理が施されて（ｆ）金属酸化物と灰分とか
らなる粉体放射性廃棄物とされ、この粉体放射性廃棄物
に金属固化処理が施される（ｇ）。On the other hand, the metal oxides filtered out in the filtration process (b) are dried together with the powder/bead resin waste liquid (e),
It is further incinerated to produce (f) powdered radioactive waste consisting of metal oxides and ash, and this powdered radioactive waste is subjected to metal solidification treatment (g).
次に第２図を用いて金属同化処理工程を説明する。Next, the metal assimilation process will be explained using FIG. 2.
焼却処理により生じた金属酸化物と灰分からなる粉体放
射性廃棄物は放冷後、放射性廃棄物貯蔵ホッパー１に貯
蔵されている。そして金属同化処理を行う場合には、供
給ライン止め弁３を開いて一定量の粉体放射性廃棄物が
計量・混合槽５に送られる。一方、粉末アルミニウムは
粉末アルミニウム貯蔵ホッパー２に貯蔵されており、金
属同化処理を行う場合に、供給ライン止め弁４を開いて
粉体放射性廃棄物とほぼ周囲が計量・混合槽５に送られ
る。そして撹拌機６により粉体放射性廃棄物と粉末アル
ミニウムが充分に撹拌混合される。Powdered radioactive waste consisting of metal oxides and ash produced by incineration is left to cool and then stored in a radioactive waste storage hopper 1. When performing metal assimilation treatment, the supply line stop valve 3 is opened and a certain amount of powdered radioactive waste is sent to the measuring/mixing tank 5. On the other hand, powdered aluminum is stored in a powdered aluminum storage hopper 2, and when performing metal assimilation treatment, the supply line stop valve 4 is opened and the powdered radioactive waste and its surroundings are sent to a weighing/mixing tank 5. Then, the powdered radioactive waste and powdered aluminum are sufficiently stirred and mixed by the stirrer 6.
この後、出口ライン止め弁７を開いてこの混合物が耐火
物製の反応炉８へ送られ、点火装置９によりこの混合物
に点火されテルミット反応を起こさせる。なおこの際マ
グネシウムのような点火材が必要に応じて用いられる。Thereafter, the outlet line stop valve 7 is opened to send this mixture to a reactor 8 made of refractory material, and the mixture is ignited by an igniter 9 to cause a thermite reaction. In this case, an ignition material such as magnesium is used as necessary.
そしてこのテルミット反応により金属酸化物は還元され
融解した金属が生成する。Through this thermite reaction, the metal oxide is reduced and a molten metal is produced.
このようにして混合物中の金属酸化物が完全に還元され
た後、出口ライン止め弁１０を開いてこの融解した金属
とアルミナの混合物を高融点金属製または耐火物製の受
は容器１１に注入し、放冷して固化させる。なお図中１
２は粉体放射性廃棄物移送ライン、１３は粉末アルミニ
ウム移送ラインでおる。After the metal oxide in the mixture has been completely reduced in this way, the outlet line stop valve 10 is opened and the molten metal and alumina mixture is injected into a receptacle 11 made of a high melting point metal or refractory. Then let it cool and solidify. Note that 1 in the figure
2 is a powder radioactive waste transfer line, and 13 is a powder aluminum transfer line.
以上のようにして形成された放射性廃棄物の同化体は、
放射性廃棄物と粉末アルミニウムの体積比をほぼ１：１
で処理することができるので、従来の固化材を用いて形
成した固化体の１７２〜１／３の体積に減容することが
可能でおる。The assimilated radioactive waste formed as described above is
The volume ratio of radioactive waste and powdered aluminum is approximately 1:1.
Therefore, the volume of the solidified body can be reduced to 172 to 1/3 of that of a solidified body formed using a conventional solidification material.
またこの放射性廃棄物の固化処理方法においては、助剤
としてアルミニウムのみを用い、テルミット反応の際生
ずる反応熱を利用して同化処理を行なうので、処理工程
が簡略化され、処理能力を向上させることができ、さら
に処理コストを低減させることができる。In addition, this radioactive waste solidification treatment method uses only aluminum as an auxiliary agent and performs assimilation treatment using the reaction heat generated during the thermite reaction, which simplifies the treatment process and improves treatment capacity. It is possible to further reduce processing costs.
［発明の効果］
以上説明したように、本発明方法を用いれば、ＢＷＲ原
子力発電所等の原子力施設で発生する放射性廃棄物を、
低処理コストで、かつ高い減容率で固化処理することが
できる。[Effects of the invention] As explained above, if the method of the present invention is used, radioactive waste generated at nuclear facilities such as BWR nuclear power plants can be
Solidification treatment can be performed at low processing cost and high volume reduction rate.
第１図は本発明の一実施例の放射性廃棄物の固化処理方
法を示すフローチャト、第２図はこの実施例において使
用する装置を示す図、第３図は従来の放射性廃棄物の固
化処理方法を示すフローチャートである。
１・・・・・・・・・・・・粉体放射性廃棄物貯蔵ホッ
パー２・・・・・・・・・・・・粉末アルミニウム貯蔵
ホッパー３．４・・・・・・供給ライン止め弁
７．１０・・・出口ライン止め弁
５・・・・・・・・・・・・計量・混合槽８・・・・・
・・・・・・・反応炉
９・・・・・・・・・・・・点火装置
１１・・・・・・・・・・・・受は容器出願人
株式会社 東芝
同 日本原子力事業株式会社代理人 弁理士
須 山 佐 −
第１図Fig. 1 is a flowchart showing a method for solidifying radioactive waste according to an embodiment of the present invention, Fig. 2 is a diagram showing an apparatus used in this embodiment, and Fig. 3 is a conventional method for solidifying radioactive waste. It is a flowchart which shows. 1・・・・・・・・・Powder radioactive waste storage hopper 2・・・・・・・・・Powder aluminum storage hopper 3.4・・・・・・Supply line stop valve 7.10...Outlet line stop valve 5...Measuring/mixing tank 8...
・・・・・・Reactor 9・・・・・・・・・Ignition device 11・・・・・・・・・・・・Receptor is container applicant
Toshiba Corporation Japan Atomic Energy Corporation Representative Patent Attorney Sasu Suyama - Figure 1
Claims (3)
棄物とアルミニウム粉末とを混合し、この混合物に点火
して、テルミット反応により前記混合物中の金属酸化物
を還元しつつ融解させ、しかる後この混合物を所定の形
状に鋳造することを特徴とする放射性廃棄物の固化処理
方法。(1) Radioactive waste containing metal oxides generated at nuclear facilities is mixed with aluminum powder, this mixture is ignited, the metal oxides in the mixture are reduced and melted by the thermite reaction, and then A method for solidifying radioactive waste, which comprises casting this mixture into a predetermined shape.
ことを特徴とする特許請求の範囲第１項記載の放射性廃
棄物の固化処理方法。(2) The method for solidifying radioactive waste according to claim 1, wherein the radioactive waste mainly consists of Fe_2O_3.
乾燥処理した粉体放射性廃棄物であることを特徴とする
特許請求の範囲第１項または第２項記載の放射性廃棄物
の固化処理方法。(3) Solidification treatment of radioactive waste according to claim 1 or 2, characterized in that the radioactive waste is powder radioactive waste obtained by drying radioactive waste liquid containing metal oxides. Method.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP16839186A JPS6325598A (en) | 1986-07-17 | 1986-07-17 | Solidifying processing method of radioactive waste |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP16839186A JPS6325598A (en) | 1986-07-17 | 1986-07-17 | Solidifying processing method of radioactive waste |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS6325598A true JPS6325598A (en) | 1988-02-03 |
Family
ID=15867243
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP16839186A Pending JPS6325598A (en) | 1986-07-17 | 1986-07-17 | Solidifying processing method of radioactive waste |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS6325598A (en) |
-
1986
- 1986-07-17 JP JP16839186A patent/JPS6325598A/en active Pending
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