JPH0240598A - Disposal method of radioactive waste - Google Patents
Disposal method of radioactive wasteInfo
- Publication number
- JPH0240598A JPH0240598A JP19132188A JP19132188A JPH0240598A JP H0240598 A JPH0240598 A JP H0240598A JP 19132188 A JP19132188 A JP 19132188A JP 19132188 A JP19132188 A JP 19132188A JP H0240598 A JPH0240598 A JP H0240598A
- Authority
- JP
- Japan
- Prior art keywords
- compressed
- waste
- solidifying material
- drum
- substance
- 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
- 238000000034 method Methods 0.000 title claims description 10
- 239000002901 radioactive waste Substances 0.000 title claims description 9
- 239000000463 material Substances 0.000 claims abstract description 35
- 239000002699 waste material Substances 0.000 claims abstract description 28
- 239000000178 monomer Substances 0.000 claims abstract description 11
- 125000000391 vinyl group Chemical group [H]C([*])=C([H])[H] 0.000 claims abstract description 7
- 229920002554 vinyl polymer Polymers 0.000 claims abstract description 7
- 239000002910 solid waste Substances 0.000 claims description 7
- 230000002285 radioactive effect Effects 0.000 claims description 6
- 239000000126 substance Substances 0.000 abstract description 11
- 239000004570 mortar (masonry) Substances 0.000 abstract description 8
- PPBRXRYQALVLMV-UHFFFAOYSA-N Styrene Chemical group C=CC1=CC=CC=C1 PPBRXRYQALVLMV-UHFFFAOYSA-N 0.000 abstract description 6
- 229920003023 plastic Polymers 0.000 abstract description 5
- 239000004033 plastic Substances 0.000 abstract description 5
- BZHJMEDXRYGGRV-UHFFFAOYSA-N Vinyl chloride Chemical compound ClC=C BZHJMEDXRYGGRV-UHFFFAOYSA-N 0.000 abstract description 2
- 239000012466 permeate Substances 0.000 abstract 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 12
- 206010042674 Swelling Diseases 0.000 description 9
- 230000008961 swelling Effects 0.000 description 9
- 239000003673 groundwater Substances 0.000 description 6
- 238000009933 burial Methods 0.000 description 5
- VYPSYNLAJGMNEJ-UHFFFAOYSA-N Silicium dioxide Chemical compound O=[Si]=O VYPSYNLAJGMNEJ-UHFFFAOYSA-N 0.000 description 3
- 238000010521 absorption reaction Methods 0.000 description 3
- 230000005484 gravity Effects 0.000 description 3
- 238000005470 impregnation Methods 0.000 description 3
- 239000011800 void material Substances 0.000 description 3
- VTYYLEPIZMXCLO-UHFFFAOYSA-L Calcium carbonate Chemical compound [Ca+2].[O-]C([O-])=O VTYYLEPIZMXCLO-UHFFFAOYSA-L 0.000 description 2
- 229910000831 Steel Inorganic materials 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 239000011810 insulating material Substances 0.000 description 2
- 239000010814 metallic waste Substances 0.000 description 2
- 238000007711 solidification Methods 0.000 description 2
- 230000008023 solidification Effects 0.000 description 2
- 239000010959 steel Substances 0.000 description 2
- SMZOUWXMTYCWNB-UHFFFAOYSA-N 2-(2-methoxy-5-methylphenyl)ethanamine Chemical compound COC1=CC=C(C)C=C1CCN SMZOUWXMTYCWNB-UHFFFAOYSA-N 0.000 description 1
- NIXOWILDQLNWCW-UHFFFAOYSA-N 2-Propenoic acid Natural products OC(=O)C=C NIXOWILDQLNWCW-UHFFFAOYSA-N 0.000 description 1
- 238000006424 Flood reaction Methods 0.000 description 1
- 230000004888 barrier function Effects 0.000 description 1
- 229910000019 calcium carbonate Inorganic materials 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 239000003795 chemical substances by application Substances 0.000 description 1
- 230000006835 compression Effects 0.000 description 1
- 238000007906 compression Methods 0.000 description 1
- 230000001010 compromised effect Effects 0.000 description 1
- 238000007796 conventional method Methods 0.000 description 1
- 238000011161 development Methods 0.000 description 1
- 238000011038 discontinuous diafiltration by volume reduction Methods 0.000 description 1
- 239000004744 fabric Substances 0.000 description 1
- 239000003365 glass fiber Substances 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 238000002347 injection Methods 0.000 description 1
- 239000007924 injection Substances 0.000 description 1
- 239000012774 insulation material Substances 0.000 description 1
- 239000012212 insulator Substances 0.000 description 1
- 239000000203 mixture Substances 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- -1 pipes Substances 0.000 description 1
- 239000011148 porous material Substances 0.000 description 1
- 238000012545 processing Methods 0.000 description 1
- 239000000941 radioactive substance Substances 0.000 description 1
- 239000004576 sand Substances 0.000 description 1
- 239000000377 silicon dioxide Substances 0.000 description 1
- 125000006850 spacer group Chemical group 0.000 description 1
- 230000002522 swelling effect Effects 0.000 description 1
- 238000012360 testing method Methods 0.000 description 1
Landscapes
- Processing Of Solid Wastes (AREA)
Abstract
Description
【発明の詳細な説明】
(産業上の利用分野)
本発明は原子力発電所等から発生する放射性廃棄物の処
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 radioactive waste generated from nuclear power plants and the like.
(従来の技術)
原子力発電所等の原子力施設から発生する不燃性の放射
性廃棄物は、そのままドラム缶等の容器内に密閉して貯
蔵庫に保管されているが、近年においてはその貯蔵容量
は限界に近付いている。このため、不燃性の放射性雑固
体廃棄物を大型のプレス機により圧縮減容することによ
り貯蔵スペースの減少を図る方法が開発され、特開昭6
1−84599号をはじめ多数の特許出願がなされてい
る。(Prior art) Non-flammable radioactive waste generated from nuclear power facilities such as nuclear power plants is stored in sealed containers such as drums in storage warehouses, but in recent years, the storage capacity has reached its limit. It's approaching. For this reason, a method was developed to reduce the storage space by compressing and reducing the volume of non-flammable radioactive miscellaneous solid waste using a large press.
Many patent applications including No. 1-84599 have been filed.
一方、原子力発電所等から発生する放射性廃棄物の処分
に関する国家基卓が現在検討されており、昭和66年よ
りその陸地埋設処分が開始される予定である。この場合
には圧縮減容された廃棄物もドラム缶等の容器内でモル
タルやプラスチックにより固定化された廃棄体の形で埋
設処分されることが予定されている。しかし埋設処分後
に地下水によるドラム缶の腐食や廃棄体内への水の侵入
が予想され、特に保温材やフィルタ類などの吸水性を有
する廃棄物は吸水により廃棄体内で膨潤圧を発生し、廃
棄体のバリア層にクラックを発生さ・口廃棄体の健全性
を著しく川なう可能性がある。On the other hand, a national basis for the disposal of radioactive waste generated from nuclear power plants, etc. is currently being considered, and land burial is scheduled to begin in 1986. In this case, the compressed waste is also planned to be buried in a container such as a drum in the form of a waste solidified with mortar or plastic. However, after burial, it is expected that underground water will corrode drums and water will enter the waste body. In particular, waste materials that absorb water, such as heat insulators and filters, will absorb water and generate swelling pressure within the waste body. Cracks may occur in the barrier layer and the integrity of the waste material may be significantly compromised.
ごの膨潤に伴う反力は試験の結果、保温材の2000ト
ン圧縮体で5トン以上に達することが判明したこの反力
に抗して廃棄体の健全性を確保する手段としては高強度
、高不透水性を有する固定材の使用や固定材厚さの増加
などが考えられるが、固定材コストが増加すること及び
固定材厚さの増加により容器内の有効容量が減少するこ
と等の問題があった。またフィルタ類などの圧縮体の場
合、モルタルやプラスチック等による単なる固定ではフ
ィルタ類に固着した粉状有害物は完全に固定されず、廃
棄体内へ地下水が浸入した際に有害物質や放射能が容器
外へ漏出することが考えられる。As a result of tests, it was found that the reaction force associated with the swelling of the waste material reached more than 5 tons in a 2,000 ton compressed body of heat insulating material.High strength, Possible options include using a fixing material with high water impermeability and increasing the thickness of the fixing material, but problems such as an increase in the cost of the fixing material and a decrease in the effective capacity inside the container due to the increase in the thickness of the fixing material are considered. was there. In addition, in the case of compressed bodies such as filters, simply fixing them with mortar or plastic does not completely fix the powdered harmful substances that adhere to the filters, and when groundwater infiltrates into the waste, harmful substances and radioactivity are released into the container. It is possible that it may leak outside.
一方、パイプや型鋼等の金属廃棄物の場合、圧縮減容処
理後の圧縮体内空隙は約50%に達し、従来のモルタル
、プラスチックで圧縮体を固定した場合は固定材の粘性
が高い為に空隙内への完全な進入は朋待できない。この
ため廃棄体内に空隙が残り、埋設処分後に地下水の通り
道となる可能性があり、放射能の届出を防ぐうえで好ま
しくなかった。On the other hand, in the case of metal waste such as pipes and shaped steel, the voids in the compressed body after volume reduction treatment reach approximately 50%, and when the compressed body is fixed with conventional mortar or plastic, the viscosity of the fixing material is high. Complete entry into the void cannot be expected. As a result, voids remain inside the waste, which may become a channel for groundwater after burial, which is not desirable in terms of preventing notification of radioactivity.
(発明が解決しようとする課題)
本発明は上記のような従来の問題点を解決して、地下に
埋設処分された場合にも地下水の侵入によって廃棄体の
健全性が失われるおそれのない吸水膨潤性を有する放射
性廃棄物の処理方法を目的としてなされたものである。(Problems to be Solved by the Invention) The present invention solves the conventional problems as described above, and provides a water absorption method that eliminates the risk of loss of integrity of the waste material due to intrusion of groundwater even when disposed of underground. This method was developed for the purpose of processing radioactive waste that has swelling properties.
(課題を解決するための手段)
上記の課題は放射性の固体廃棄物を圧縮減容処理したの
ち、圧縮体の内部空隙にビニール系モノマのような低粘
性固化材を含浸させて固化し、これをドラム缶の内部に
収納して周囲の隙間部分を固定材により固定し、安定な
廃棄体とすることによって達成される。またこの課題は
放射性の固体廃棄物を圧縮減容処理したのち、ドラム缶
の内部に収納し、周囲の隙間部分に骨材を充填したうえ
ビニール系モノマのような低粘性固化材を圧縮体の内部
空隙及び骨材間に含浸させて固化し、安定な廃棄体とす
ることによっても達成される。(Means for solving the problem) The above problem is achieved by compressing and reducing the volume of radioactive solid waste, and then impregnating the internal voids of the compressed body with a low-viscosity solidifying material such as a vinyl monomer to solidify it. This is accomplished by storing the waste inside a drum and fixing the surrounding gap with a fixing material to create a stable waste product. In addition, this problem involves compressing and reducing the volume of radioactive solid waste, storing it inside a drum, filling the surrounding gaps with aggregate, and then applying a low-viscosity solidifying material such as vinyl monomer inside the compacted body. This can also be achieved by impregnating it into voids and between aggregates and solidifying it to form a stable waste.
以下に本発明を凹面を参照しつつ更に詳細に説明する。The invention will now be explained in more detail with reference to concave surfaces.
第1図〜第4図は第1の発明の工程図であり、まず第1
図のように固体廃棄物がプレス機filにより圧縮減容
され、圧縮体(2)となる。この圧縮体(2)はその内
部に多くの空隙を有するものであるので、次に第2図に
示されるようにこの圧縮体(2)をタンク(3)内の容
器(4)に入れ、タンク(3)内を真空ポンプ(5)に
より減圧しつつ上方のノズル(6)から低粘性固化材を
供給して圧縮体(2)の内部空隙に含浸させる。本発明
において用いられる低粘性固化材としては、スチレンモ
ノマ、塩化ビニルモノマ、アクリル酸モノマ等のビニー
ル系モノマが代表的なものであるが、低粘性であって圧
縮体の内部空隙に確実に含浸させることができるモノマ
であればその他のモノマを用いることもできる。但し保
温材圧縮体のような緻密な圧縮体内に十分に含浸させる
ためには、粘性が1ボイズ以下の同化材を用いることが
好ましい。次に第3図に示されるようにこの圧縮体(2
)はヒータ(7)付きのタンク(8)内で加熱及び加圧
されて同化材を重合させ、固化される。Figures 1 to 4 are process diagrams of the first invention.
As shown in the figure, solid waste is compressed and reduced in volume by a press machine fil, and becomes a compressed body (2). Since this compressed body (2) has many voids inside it, next, as shown in FIG. 2, this compressed body (2) is placed in a container (4) in a tank (3), While reducing the pressure inside the tank (3) using a vacuum pump (5), a low-viscosity solidifying material is supplied from an upper nozzle (6) to impregnate the internal void of the compressed body (2). Typical low-viscosity solidifying materials used in the present invention include vinyl monomers such as styrene monomers, vinyl chloride monomers, and acrylic acid monomers. Other monomers can also be used as long as they can. However, in order to sufficiently impregnate the material into a dense compressed body such as a heat insulating compressed body, it is preferable to use an assimilated material having a viscosity of 1 void or less. Next, as shown in Fig. 3, this compressed body (2
) is heated and pressurized in a tank (8) equipped with a heater (7) to polymerize and solidify the assimilated material.
その後第4図に示すように固化された圧縮体(2)をド
ラム缶(9)の内部に複数個収納し、圧縮体(2)の周
囲をモルタル、プラスチックのような固定材Q[11で
固定する。このような状態の廃棄体は、埋設処分された
後に地下水等が外側のドラム缶(9)を腐食させ、固定
材QG+を通って圧縮体(2)まで到達することがあっ
ても、その内部空隙は固化された低粘性固化材によって
完全に満たされているので水は圧縮体(2)の内部にま
では侵入することがない。従って埋設処分後の地下水の
侵入により放射性物質の漏出や膨潤圧発生による廃棄体
破面のおそれがなく、極めて安定性及び健全性に優れた
廃棄体を得ることができる。After that, as shown in Fig. 4, a plurality of solidified compressed bodies (2) are stored inside a drum can (9), and the periphery of the compressed bodies (2) is fixed with a fixing material Q [11] such as mortar or plastic. do. After the waste body is buried in such a state, groundwater etc. may corrode the outer drum (9) and reach the compacted body (2) through the fixing material QG+, but the internal voids may Since the compressed body (2) is completely filled with the solidified low-viscosity solidifying material, water does not penetrate into the inside of the compressed body (2). Therefore, there is no risk of leakage of radioactive substances due to intrusion of underground water after burial, or fracture of the waste body due to generation of swelling pressure, and it is possible to obtain a waste body with extremely excellent stability and soundness.
第5図〜第8図は第2の発明の工程図であり、まず第5
図のように放射性の固体廃棄物をプレス機(1)により
圧縮減容して圧縮体(2)とする。次にこの圧縮体(2
)を第6図のようにドラム缶(9)の内部に複数個収納
し、圧縮体(2)の周囲の隙間部分に砂、炭酸カルシウ
ム等の骨材θυを充填したうえで、真空ポンプ(5)に
より内部を減圧しつつノズル(6)からビニール系モノ
マのような低粘性固化材を圧縮体(2)の内部空隙及び
骨材00間に含浸させる。これを第7図のようにタンク
(8)内でヒータ(7)により加熱して同化材を重合さ
せ、全体を固化させれば、第8図に示されるような廃棄
体が得られる。この第2の発明において、含浸面に骨材
αυを圧縮体(2)の周囲に予め充填しておくのは、同
化材が凝固収縮する際のクランクの発生を防止するため
である。Figures 5 to 8 are process diagrams of the second invention.
As shown in the figure, radioactive solid waste is compressed and reduced in volume using a press (1) to form a compressed body (2). Next, this compressed body (2
) are stored in a drum can (9) as shown in Figure 6, and the gap around the compressed body (2) is filled with aggregate θυ such as sand or calcium carbonate, and then the vacuum pump (5 ) while reducing the internal pressure, a low-viscosity solidifying material such as a vinyl monomer is impregnated into the internal voids of the compressed body (2) and between the aggregates 00 from the nozzle (6). If this is heated by a heater (7) in a tank (8) as shown in FIG. 7 to polymerize the assimilated material and solidify the whole, a waste body as shown in FIG. 8 will be obtained. In this second invention, the reason why the impregnated surface is filled with aggregate αυ around the compressed body (2) in advance is to prevent the occurrence of cranks when the assimilated material solidifies and shrinks.
また骨材(Illの充填により固化材強度の向上の効果
及び骨材θDの分だけ同化材が少なくてすみ、経済的で
あるという効果もある。このようにして得られた廃棄体
も第1の発明によって得られた廃棄体と同様に吸水によ
る膨潤のおそれのない安定性と健全性に優れたものであ
る。In addition, filling with aggregate (Ill) has the effect of improving the strength of the solidified material and reducing the amount of assimilated material by the amount of aggregate θD, making it economical. Like the waste obtained by the invention, this waste has excellent stability and soundness without the risk of swelling due to water absorption.
なお保温材、フィルタ類などは直接圧縮減容するほか、
ドラム缶のような容器に収納した状態で圧縮減容しても
よく、この場合には圧縮後に圧縮体外皮にいくつかの孔
を明けることにより、内部への低粘性固化材の含浸が可
能となる。また固化材が容易に含浸し得るガラス繊維や
布のような材質からなる容器又は袋に放射性廃棄物を入
れて圧縮すれば、より確実な含浸が可能である。更にま
た第9図に示すように圧縮体(2)の相互間にスペーサ
03を介在させれば、同化材の注入含浸を迅速、確実に
行わせることができる。In addition to directly compressing insulation materials and filters,
It is also possible to compress and reduce the volume while stored in a container such as a drum. In this case, by making several holes in the outer skin of the compressed body after compression, it becomes possible to impregnate the inside with a low-viscosity solidifying material. . Further, if the radioactive waste is placed in a container or bag made of a material such as glass fiber or cloth that can be easily impregnated with the solidifying material and compressed, more reliable impregnation is possible. Furthermore, as shown in FIG. 9, if a spacer 03 is interposed between the compressed bodies (2), the injection and impregnation of the assimilating material can be carried out quickly and reliably.
(実施例)
実施例1
罎比重0.17、空隙率92.5%のシリカ系保温材を
9QOkg/cfflの面圧で圧縮減容処理し、嵩比重
1.18、空隙率48%の圧縮体を得た。この圧縮体を
水中において膨潤圧を測定した結果、3.ITkg/己
(直径530龍の2001ドラム缶に換算すると7トン
)の膨潤圧を発生した。(Example) Example 1 A silica-based heat insulating material with a specific gravity of 0.17 and a porosity of 92.5% was compressed and reduced in volume with a surface pressure of 9QOkg/cffl, and compressed to a bulk specific gravity of 1.18 and a porosity of 48%. I got a body. As a result of measuring the swelling pressure of this compressed body in water, 3. A swelling pressure of ITkg/self (7 tons when converted to a 2001 drum with a diameter of 530 mm) was generated.
この圧縮体に低粘性固化材としてスチレンモノマを一5
50msl1gで1時間真空含浸した後、7kg/CA
の圧力下で加熱して重合させ、固化させた。この圧縮体
は嵩比重1.62、空隙率1.7%であって空隙率は大
幅に減少した。固化後の圧縮体を水中においた場合にも
膨潤圧の発生は全く認められなかった。ドラム缶の内部
に圧縮体を複数個収納し、その周囲にモルタルを流しこ
んで固定したところ、安定性及び健全性に優れた廃棄体
が得られた。Styrene monomer is added to this compressed body as a low-viscosity solidifying agent.
After vacuum impregnation with 50msl1g for 1 hour, 7kg/CA
It was polymerized and solidified by heating under a pressure of . This compressed body had a bulk specific gravity of 1.62 and a porosity of 1.7%, and the porosity was significantly reduced. No swelling pressure was observed even when the compressed body was placed in water after solidification. By storing a plurality of compressed bodies inside a drum and fixing them by pouring mortar around them, waste bodies with excellent stability and soundness were obtained.
実施例2
パイプ類、型鋼、弁などの金属廃棄物140kgを20
01ドラム缶に詰め、容器ごと900kg/aJの面圧
で圧縮減容し、空隙率49%の圧縮体を得た。この圧縮
体を容器に入れモルタルで固定した際に、圧縮体空隙内
へのモルタルの侵入は少なく、固化後の空隙率は35%
程度であった。しかしながらスチレンモノマーを用いて
含浸、固化した後の空隙率は3%以下となり、圧縮体内
の空隙はほとんど七ツマ−により固化された。Example 2 140 kg of metal waste such as pipes, steel molds, valves, etc.
The mixture was packed in a 01 drum and compressed and reduced in volume with a surface pressure of 900 kg/aJ to obtain a compressed body with a porosity of 49%. When this compressed body is placed in a container and fixed with mortar, there is little intrusion of mortar into the voids of the compressed body, and the porosity after solidification is 35%.
It was about. However, after impregnating and solidifying with styrene monomer, the porosity was 3% or less, and most of the pores in the compressed body were solidified by styrene monomer.
(発明の効果)
本発明は以上に説明したとおり、圧縮体の内部空隙に低
粘性固化材を含浸固化させることにより、埋設処分後に
地下水等が浸水した場合にも吸水による膨潤圧の発生の
おそれをなくしたものであり、膨潤圧により廃棄体にク
ラックを生ずる可能性がなく、極めて安定性及び健全性
に優れた廃棄体を得ることができる。更にフィルタ類な
どの圧縮体の場合、フィルタに固着した粉状有害物を確
実に固定でき、地下水等の浸水時に有害物や放射能の環
境への漏出を防止することができる。また廃棄体内の空
隙を極力低下させることができ、健全性に優れた廃棄体
を得ることができる。よって本発明は従来の問題点を一
掃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である。(Effects of the Invention) As explained above, the present invention impregnates and solidifies the internal voids of the compressed body with a low-viscosity solidifying material, thereby reducing the risk of swelling pressure due to water absorption even if groundwater etc. floods after burial. There is no possibility of cracks occurring in the waste body due to swelling pressure, and a waste body with extremely excellent stability and soundness can be obtained. Furthermore, in the case of compressed bodies such as filters, powdered harmful substances stuck to the filter can be reliably fixed, and leakage of harmful substances and radioactivity into the environment can be prevented when flooding with groundwater or the like. In addition, the voids inside the waste body can be reduced to a minimum, and a waste body with excellent soundness can be obtained. Therefore, the present invention greatly contributes to the development of industry as a radioactive waste disposal method that eliminates the problems of the conventional methods.
第1図〜第4図は第1の発明の詳細な説明する断面図、
第5図〜第8図は第2の発明の詳細な説明する断面図、
第9図はその変形例を示す断面図である。
(2) : 圧縮体、(9)ニドラム缶、al:固定材
、Qll :骨材。
第
図
第
図
第
図
第
図
第
第
図
第
図
図1 to 4 are cross-sectional views explaining the first invention in detail,
FIGS. 5 to 8 are cross-sectional views explaining the second invention in detail,
FIG. 9 is a sectional view showing a modification thereof. (2): Compressed body, (9) Nidrum can, Al: Fixing material, Qll: Aggregate. fig fig fig fig fig fig fig fig fig fig fig fig fig fig fig fig fig fig fig fig fig fig fig fig fig fig fig fig.
Claims (1)
体の内部空隙にビニール系モノマのような低粘性固化材
を含浸させて固化し、これをドラム缶の内部に収納して
周囲の隙間部分を固定材により固定し、安定な廃棄体と
することを特徴とする放射性廃棄物の処理方法。 2、放射性の固体廃棄物を圧縮減容処理したのち、ドラ
ム缶の内部に収納し、周囲の隙間部分に骨材を充填した
うえビニール系モノマのような低粘性固化材を圧縮体の
内部空隙及び骨材間に含浸させて固化し、安定な廃棄体
とすることを特徴とする放射性廃棄物の処理方法。[Claims] 1. After compressing and reducing the volume of radioactive solid waste, the internal voids of the compressed body are impregnated with a low-viscosity solidifying material such as a vinyl monomer to solidify it, and this is placed inside a drum. A method for disposing of radioactive waste characterized by storing it and fixing the surrounding gap with a fixing material to make a stable waste body. 2. After the radioactive solid waste is compressed and reduced in volume, it is stored inside a drum, the surrounding gaps are filled with aggregate, and a low-viscosity solidifying material such as vinyl monomer is applied to the internal voids of the compacted body and A method for disposing of radioactive waste characterized by impregnating it between aggregates and solidifying it to form a stable waste body.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP19132188A JPH0240598A (en) | 1988-07-30 | 1988-07-30 | Disposal method of radioactive waste |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP19132188A JPH0240598A (en) | 1988-07-30 | 1988-07-30 | Disposal method of radioactive waste |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH0240598A true JPH0240598A (en) | 1990-02-09 |
Family
ID=16272611
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP19132188A Pending JPH0240598A (en) | 1988-07-30 | 1988-07-30 | Disposal method of radioactive waste |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0240598A (en) |
-
1988
- 1988-07-30 JP JP19132188A patent/JPH0240598A/en active Pending
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