JPH04110799A - Disposal method for radioactive waste - Google Patents

Disposal method for radioactive waste

Info

Publication number
JPH04110799A
JPH04110799A JP23101190A JP23101190A JPH04110799A JP H04110799 A JPH04110799 A JP H04110799A JP 23101190 A JP23101190 A JP 23101190A JP 23101190 A JP23101190 A JP 23101190A JP H04110799 A JPH04110799 A JP H04110799A
Authority
JP
Japan
Prior art keywords
compressed body
radioactive
packed
waste
compressed
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
Application number
JP23101190A
Other languages
Japanese (ja)
Other versions
JP2871824B2 (en
Inventor
Hitoshi Mori
仁志 森
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
NGK Insulators Ltd
Original Assignee
NGK Insulators Ltd
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 by NGK Insulators Ltd filed Critical NGK Insulators Ltd
Priority to JP23101190A priority Critical patent/JP2871824B2/en
Publication of JPH04110799A publication Critical patent/JPH04110799A/en
Application granted granted Critical
Publication of JP2871824B2 publication Critical patent/JP2871824B2/en
Anticipated expiration legal-status Critical
Expired - Fee Related legal-status Critical Current

Links

Landscapes

  • Processing Of Solid Wastes (AREA)
  • Solid-Sorbent Or Filter-Aiding Compositions (AREA)

Abstract

PURPOSE:To allow a compressed body to have a confining property of radioactive nuclides by packing fine grained adsorbents having good performance of adsorbing radioactive nuclides around miscellaneous solid wastes thrown into a metallic vessel, thereafter compressively molding the metallic vessel. CONSTITUTION:Radioactive, miscellaneous solid wastes 1 are packed in a metallic vessel 2 such as a drum can. At this time, fine-grained adsorbents 3 having good performance of adsorbing radioactive nuclides are packed around the waste 1. Besides, the quantity of packed adsorbents 3 is set by the type of radioactive nuclide, the type of adsorbent 3, expected distribution coefficient, etc. Then, the waste 1 packed in the vessel 2 are compressively molded by the force, for example, of 1,000 to 2,000 tons to obtain a compressed body 4. The compressed body 4 contains fine-grained adsorbents 3 having good adsorptivity for radioactive nuclides inside, and has a confining property of radioactive nuclides in itself. The compressed body 4 can be directly buried in a concrete pit, but when it is put in a metallic vessel such as a drum can, and packed with solidifiers around itself to be solidified, confining property of the compressed body can be more improved.

Description

【発明の詳細な説明】 (産業上の利用分野) 本発明は不燃性の放射性廃棄物の処理方法に関するもの
である。
DETAILED DESCRIPTION OF THE INVENTION (Field of Industrial Application) The present invention relates to a method for treating non-flammable radioactive waste.

(従来の技術) 従来、金属等の不燃性の放射性雑固体廃棄物の処理方法
としては、放射性廃棄物をそのままであるいはドラム缶
のような金属容器に入れて圧縮成形し、得られた圧縮体
を更に金属容器内に収納して周囲をセメントモルタル等
で固化して廃棄体とし、これをコンクリートピット内に
埋設する方法が検討されている。
(Prior art) Conventionally, as a treatment method for non-combustible radioactive miscellaneous solid waste such as metal, radioactive waste is compressed as it is or placed in a metal container such as a drum, and the resulting compressed body is compressed. Furthermore, a method of storing the waste in a metal container, solidifying the surrounding area with cement mortar, etc., and burying the waste in a concrete pit is being considered.

ところが安全評価上では、300年程度の長い期間を経
過するとこのような廃棄体やその周囲のコンクリートビ
ットの状態が砂程度になるものと仮定し、それらの物理
的な閉し込め性は期待できないものとしている。
However, in terms of safety evaluation, it is assumed that after a long period of about 300 years, the condition of such waste bodies and the surrounding concrete bits will be reduced to the level of sand, and their physical containment properties cannot be expected. I take it as a thing.

そこでこのような廃棄体における放射能の閉し込め性を
評価するための基準として「分配係数」が検討されてい
る。二〇「分配係数」は放射性核種が固化剤を構成する
面相と地下水等の液相との間の吸着・吸着平衡を定量的
に表し、単位重量当たりの固相中の放射能と単位体積当
たりの液相中の放射能の比で定義されるもので、この値
が大きいほど放射性核種の地中への移行は遅延される。
Therefore, the ``partition coefficient'' is being considered as a standard for evaluating the radioactivity confinement in such waste bodies. 20 "Partition coefficient" quantitatively represents the adsorption/adsorption equilibrium between the surface phase in which the radionuclide constitutes the solidifying agent and the liquid phase such as groundwater, and is the ratio between radioactivity in the solid phase per unit weight and per unit volume. It is defined as the ratio of radioactivity in the liquid phase of

そして従来の圧縮体自体には放射能の閉し込め性はない
ものと考えられるので、廃棄体の放射能の閉じ込め性は
固化材の分配係数によって評価されるものとしている。
Since it is thought that the conventional compacted body itself does not have the ability to trap radioactivity, the ability of the waste body to trap radioactivity is evaluated by the distribution coefficient of the solidifying material.

(発明が解決しようとする課H) 本発明はこのような従来の問題を解決して、圧縮体自体
に放射能の閉し込め性を持たせることにより、廃棄体全
体としての放射能の閉し込め性を高めた放射性廃棄物の
処理方法を提供するために完成されたものである。
(Problem H to be solved by the invention) The present invention solves these conventional problems and makes it possible to confine radioactivity in the waste body as a whole by giving the compressed body itself the ability to confine radioactivity. It was completed to provide a method for disposing of radioactive waste with improved containment properties.

(課題を解決するための手段) 上記の課題を解決するためになされた本願第1の発明は
、金属容器中に投入された放射性の雑固体廃棄物の周囲
に、放射性核種の吸着性能に優れる粉粒状の吸着剤を充
填したのち、金属容器を圧縮成形して圧縮体を得ること
により、圧縮体に放射性核種の閉し込め性を持たせるこ
とを特徴とするものである。
(Means for Solving the Problems) The first invention of the present application made to solve the above problems has excellent adsorption performance of radionuclides around radioactive miscellaneous solid waste placed in a metal container. This method is characterized in that a metal container is compressed and molded after being filled with a powder adsorbent to obtain a compressed body, thereby giving the compressed body the ability to confine radionuclides.

また第2の発明は、第1の発明により得られた圧縮体を
金属容器に入れ、周囲に固化材を充填することを特徴と
するものである。
Further, the second invention is characterized in that the compressed body obtained according to the first invention is placed in a metal container, and the surrounding area is filled with a solidifying material.

以下に本発明を図示の実施例とともる二更に詳細に説明
する。
In the following, the invention will be explained in more detail with reference to illustrated embodiments.

(実施例) まず第1図のように、放射性の雑固体廃棄物(1)をド
ラム缶のような金属容器(2)に充填するのであるが、
このときに雑固体廃棄物(1)の周囲ムこ放射性核種の
吸着性能に優れる粉粒状の吸着剤(3)を充填する。
(Example) First, as shown in Figure 1, radioactive miscellaneous solid waste (1) is filled into a metal container (2) such as a drum.
At this time, the surrounding area of the miscellaneous solid waste (1) is filled with a powdery adsorbent (3) that has excellent adsorption performance for radionuclides.

このような吸着剤(3)としてはヘントナイトが代表的
なものであるが、その他にパーミニキュライト、活性炭
、シリカゲル、活性アルミナ、合成ゼオライト、ヘント
ナイト以外の活性白土(アロファン、パイサイト、アク
バルジャイ1〜、セビオライト)等を挙げることができ
る。特にパイプ類のような雑固体廃棄物(1)にはその
内部に吸着剤(3)を充填することが好ましい。なお吸
着剤(3)の充填量は放射性核種の種類、吸着剤(3)
の種類、期待される分配係数等により設定するものとす
る。
The typical adsorbent (3) is hentonite, but other adsorbents include perminulite, activated carbon, silica gel, activated alumina, synthetic zeolite, and activated clay other than hentonite (allophane, pisite, akbarjai). 1 to Seviolite). In particular, it is preferable to fill miscellaneous solid waste (1) such as pipes with an adsorbent (3). The filling amount of adsorbent (3) depends on the type of radionuclide and adsorbent (3).
It shall be set based on the type of data, expected distribution coefficient, etc.

次に金属容器(2)に充填された雑固体廃棄物(1)を
例えば1000〜2000 トンの力で圧縮成形し、第
2図のように圧縮体(4)を得る。この圧縮体(4)は
内部に放射性核種の吸着性能に優れる粉粒状の吸着剤(
3)を含み、それ自体で放射性核種の閉し込め性を持つ
ものである。
Next, the miscellaneous solid waste (1) filled in the metal container (2) is compression-molded with a force of, for example, 1,000 to 2,000 tons to obtain a compressed body (4) as shown in FIG. This compressed body (4) contains powder-like adsorbent (
3), which itself has the ability to confine radionuclides.

この圧縮体(4)はそのままコンクリートビット内に埋
設することもできるが、第2の発明乙こ従い、第3図の
ように圧縮体(4)を更にドラム缶のような金属容器(
5)の内部に入れ、周囲に固化材(6)を充填して固化
することが好ましい。このための固化材(6)としては
一般にセメントモルタルが用いられるが、固化材(6)
にも放射性核種の吸着性能に優れる材料を用いることが
好ましいことはいうまでもない。
This compressed body (4) can be buried in a concrete bit as it is, but according to the second invention, the compressed body (4) is further buried in a metal container such as a drum as shown in FIG.
5), and the solidifying material (6) is preferably filled around the solidifying material (6) for solidifying. Cement mortar is generally used as the solidifying material (6) for this purpose;
It goes without saying that it is preferable to use a material that has excellent adsorption performance for radionuclides.

(発明の効果) 以上に説明したように、本発明の放射性廃棄物の固化処
理方法によれば、放射性核種の吸着性能に優れる粉粒状
の吸着剤を雑固体廃棄物とともに金属容器に入れて圧縮
成形するので、圧縮体自体にも放射性核種の閉じ込め性
を持たせることができる。
(Effects of the Invention) As explained above, according to the radioactive waste solidification treatment method of the present invention, a powdery adsorbent having excellent adsorption performance for radionuclides is placed in a metal container together with miscellaneous solid waste and compressed. Since it is molded, the compressed body itself can also have the ability to confine radionuclides.

このため、従来の処分方法による廃棄体においては圧縮
体自体には放射性核種の閉じ込め性がないものとされて
いたのに対して、本発明の方法により得られた廃棄体で
は圧縮体にも閉し込め性を期待することができ、将来に
おいてコンクリートピット等が砂程度になり、物理的な
放射能閉し込め性を期待できなくなると想定した場合に
も、化学的閉し込め性を高め放射性核種の地中への移行
を遅延させることができる。また廃棄体の放射性核種の
閉し込め性を向上させたので、埋設処分場のコンクリー
トピット等の人工バリアの負荷が低減でき、低コストで
埋設処分場を造ることが可能となる。
For this reason, in waste bodies obtained by conventional disposal methods, the compressed body itself was considered to have no ability to trap radionuclides, whereas in the waste bodies obtained by the method of the present invention, the compressed body also does not contain radionuclides. Even if it is assumed that in the future concrete pits will be reduced to the level of sand and physical radioactivity containment properties cannot be expected, chemical containment properties can be expected to improve radioactivity containment properties. It is possible to delay the migration of nuclides underground. Furthermore, since the radionuclide confinement properties of waste bodies have been improved, the load on artificial barriers such as concrete pits in buried disposal sites can be reduced, making it possible to construct buried disposal sites at low cost.

なお、第2の発明に従って圧縮体をさらに金属容器に入
れて吸着性の優れたセメントモルタルにより固化すれば
、廃棄体の放射性核種の閉し込め性を更に向上できるこ
とはいうまでもない。
It goes without saying that if the compressed body is further placed in a metal container and solidified with cement mortar having excellent adsorption properties according to the second aspect of the invention, the radionuclide confinement property of the waste body can be further improved.

以上に説明したとおり、本発明は廃棄体全体としての放
射能の閉し込め性を高めたものであるから、従来の問題
点を解消した放射性廃棄物の処理方法として、産業の発
展に寄与するところは極めて大きいものがある。
As explained above, the present invention improves the radioactivity confinement properties of the waste body as a whole, so it contributes to the development of industry as a radioactive waste disposal method that solves the conventional problems. There are some things that are extremely large.

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

第1図は雑固体廃棄物を吸着剤とともに金属容器に充填
した状態を示す断面図、第2図はこれを圧縮成形した圧
縮体を示す断面図、第3図は圧縮体を更に金属容器に充
填して固化した廃棄体を示す断面図である。 (1):雑固体廃棄物、(2):金属容器、(3):吸
着剤、(4) :圧縮体、(5):金属容器、(6):
固化材。
Figure 1 is a cross-sectional view showing the state in which miscellaneous solid waste is packed together with an adsorbent into a metal container, Figure 2 is a cross-sectional view showing a compressed body formed by compression molding, and Figure 3 is a cross-sectional view showing the compressed body further packed into a metal container. FIG. 3 is a sectional view showing a filled and solidified waste body. (1): Miscellaneous solid waste, (2): Metal container, (3): Adsorbent, (4): Compressed body, (5): Metal container, (6):
Solidifying material.

Claims (1)

【特許請求の範囲】 1、金属容器中に投入された放射性の雑固体廃棄物の周
囲に、放射性核種の吸着性能に優れる粉粒状の吸着剤を
充填したのち、金属容器を圧縮成形して圧縮体を得るこ
とにより、圧縮体に放射性核種の閉じ込め性を持たせる
ことを特徴とする放射性廃棄物の処理方法。 2、請求項1の方法により得られた圧縮体を金属容器に
入れ、周囲に固化材を充填して固化することを特徴とす
る放射性廃棄物の処理方法。
[Claims] 1. After filling the surrounding area of radioactive miscellaneous solid waste put into a metal container with a powdery adsorbent that has excellent adsorption performance for radionuclides, the metal container is compression molded and compressed. A method for disposing of radioactive waste, characterized in that the compressed body has the ability to confine radionuclides by obtaining a body. 2. A method for treating radioactive waste, which comprises placing the compressed body obtained by the method according to claim 1 in a metal container, and filling the surrounding area with a solidifying material to solidify it.
JP23101190A 1990-08-31 1990-08-31 Radioactive waste treatment method Expired - Fee Related JP2871824B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP23101190A JP2871824B2 (en) 1990-08-31 1990-08-31 Radioactive waste treatment method

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP23101190A JP2871824B2 (en) 1990-08-31 1990-08-31 Radioactive waste treatment method

Publications (2)

Publication Number Publication Date
JPH04110799A true JPH04110799A (en) 1992-04-13
JP2871824B2 JP2871824B2 (en) 1999-03-17

Family

ID=16916851

Family Applications (1)

Application Number Title Priority Date Filing Date
JP23101190A Expired - Fee Related JP2871824B2 (en) 1990-08-31 1990-08-31 Radioactive waste treatment method

Country Status (1)

Country Link
JP (1) JP2871824B2 (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2008169400A (en) * 2008-02-25 2008-07-24 Mitsubishi Materials Corp Method for manufacturing photocatalytic paint
JP2012242143A (en) * 2011-05-17 2012-12-10 Nihon Technical Development Center Co Ltd Removal device and removal method for radioactive contaminants
CN104347146A (en) * 2013-07-26 2015-02-11 中广核工程有限公司 Nuclear power station high-dose-rate compressible maintenance waste disposal method

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2008169400A (en) * 2008-02-25 2008-07-24 Mitsubishi Materials Corp Method for manufacturing photocatalytic paint
JP4710919B2 (en) * 2008-02-25 2011-06-29 三菱マテリアル株式会社 Method for producing photocatalyst paint
JP2012242143A (en) * 2011-05-17 2012-12-10 Nihon Technical Development Center Co Ltd Removal device and removal method for radioactive contaminants
CN104347146A (en) * 2013-07-26 2015-02-11 中广核工程有限公司 Nuclear power station high-dose-rate compressible maintenance waste disposal method

Also Published As

Publication number Publication date
JP2871824B2 (en) 1999-03-17

Similar Documents

Publication Publication Date Title
US5169566A (en) Engineered cementitious contaminant barriers and their method of manufacture
US4919569A (en) Process for disposing of waste
JP4919528B1 (en) Storage container for contaminants caused by radioactive cesium, and storage method for contaminants caused by radioactive cesium
JPH04110799A (en) Disposal method for radioactive waste
US4622175A (en) Process for solidifying radioactive waste
JP3539928B2 (en) Buried facility and its construction method, molded body used for it
JPH07294698A (en) Formation disposal method for radioactive waste
CA2210330A1 (en) Method for solidifying waste containing radioactive iodine
Lee et al. Sorption and diffusion of 1-125 and Sr-90 in a mixture of bentonite and crushed granite backfill of a radioactive waste repository
EP0555238B1 (en) Engineered cementitious contaminant barriers and their methods of manufacture
JPS6197600A (en) Back-filling material for radioactive waste
JP2005238175A (en) Granular bentonite impervious material, impervious structure, and its construction method
JPH09501500A (en) Radioactive waste storage-backfilling of storage
JPH0641513A (en) Stopping material, its production and method of application to container storage site
JPH0554637B2 (en)
JPH0656494A (en) Cement composition for adsorbing nuclide
JPS61178698A (en) Method of hardening water glass
JPH07270597A (en) Buffer material or back-filling material for geological disposal of radioactive waste
JPH03150499A (en) Solidification of radioactive waste
JPH02236500A (en) Production of buffer material for disposition of radioactive waste
JPS63193094A (en) Storage facility for waste
Bae et al. Immobilization of Ion-Exchange Resins with a Mixture of Cement and WEP/Zeolon 900-Na Additives and Radionuclides Leaching
CA2058552A1 (en) Container
JPH0631883B2 (en) Radioactive waste disposal methods and filling materials
Nuttall et al. Canadian engineered barriers program

Legal Events

Date Code Title Description
LAPS Cancellation because of no payment of annual fees