JPS6246840B2 - - Google Patents
Info
- Publication number
- JPS6246840B2 JPS6246840B2 JP56198474A JP19847481A JPS6246840B2 JP S6246840 B2 JPS6246840 B2 JP S6246840B2 JP 56198474 A JP56198474 A JP 56198474A JP 19847481 A JP19847481 A JP 19847481A JP S6246840 B2 JPS6246840 B2 JP S6246840B2
- Authority
- JP
- Japan
- Prior art keywords
- pellets
- waste liquid
- product
- power plants
- volume
- 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
Links
- 239000008188 pellet Substances 0.000 claims description 26
- 239000007788 liquid Substances 0.000 claims description 18
- 239000002699 waste material Substances 0.000 claims description 18
- 238000000034 method Methods 0.000 claims description 15
- 239000002901 radioactive waste Substances 0.000 claims description 9
- 239000007787 solid Substances 0.000 claims description 7
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 6
- 239000011230 binding agent Substances 0.000 description 8
- KGBXLFKZBHKPEV-UHFFFAOYSA-N boric acid Chemical compound OB(O)O KGBXLFKZBHKPEV-UHFFFAOYSA-N 0.000 description 4
- 239000004327 boric acid Substances 0.000 description 4
- HEMHJVSKTPXQMS-UHFFFAOYSA-M Sodium hydroxide Chemical compound [OH-].[Na+] HEMHJVSKTPXQMS-UHFFFAOYSA-M 0.000 description 3
- 238000001354 calcination Methods 0.000 description 3
- 239000004568 cement Substances 0.000 description 3
- 238000005336 cracking Methods 0.000 description 3
- 239000003599 detergent Substances 0.000 description 3
- 239000000843 powder Substances 0.000 description 3
- 239000002351 wastewater Substances 0.000 description 3
- 239000004698 Polyethylene Substances 0.000 description 2
- 239000012141 concentrate Substances 0.000 description 2
- 238000001816 cooling Methods 0.000 description 2
- 230000001186 cumulative effect Effects 0.000 description 2
- 238000011038 discontinuous diafiltration by volume reduction Methods 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 239000004744 fabric Substances 0.000 description 2
- 239000008187 granular material Substances 0.000 description 2
- 238000002156 mixing Methods 0.000 description 2
- 239000000203 mixture Substances 0.000 description 2
- 239000000123 paper Substances 0.000 description 2
- -1 polyethylene Polymers 0.000 description 2
- 229920000573 polyethylene Polymers 0.000 description 2
- 238000005245 sintering Methods 0.000 description 2
- CDBYLPFSWZWCQE-UHFFFAOYSA-L sodium carbonate Substances [Na+].[Na+].[O-]C([O-])=O CDBYLPFSWZWCQE-UHFFFAOYSA-L 0.000 description 2
- 239000007921 spray Substances 0.000 description 2
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 description 1
- 239000007864 aqueous solution Substances 0.000 description 1
- 239000010426 asphalt Substances 0.000 description 1
- 229910052796 boron Inorganic materials 0.000 description 1
- 239000001913 cellulose Substances 0.000 description 1
- 229920002678 cellulose Polymers 0.000 description 1
- 230000000052 comparative effect Effects 0.000 description 1
- 238000007796 conventional method Methods 0.000 description 1
- 238000005536 corrosion prevention Methods 0.000 description 1
- 238000001704 evaporation Methods 0.000 description 1
- 230000008020 evaporation Effects 0.000 description 1
- 230000001747 exhibiting effect Effects 0.000 description 1
- 239000012530 fluid Substances 0.000 description 1
- 238000000227 grinding Methods 0.000 description 1
- 239000012528 membrane Substances 0.000 description 1
- 238000000465 moulding Methods 0.000 description 1
- 229920000642 polymer Polymers 0.000 description 1
- 238000003672 processing method Methods 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 238000001223 reverse osmosis Methods 0.000 description 1
- 229910000029 sodium carbonate Inorganic materials 0.000 description 1
- 239000000243 solution Substances 0.000 description 1
- 238000005406 washing Methods 0.000 description 1
Landscapes
- Processing Of Solid Wastes (AREA)
- Solid-Sorbent Or Filter-Aiding Compositions (AREA)
- Treatment Of Sludge (AREA)
Description
【発明の詳細な説明】
本発明は放射性廃棄物の処理法に関し、特に加
圧水型原子力発電所において発生する放射性廃棄
物を合目的に減容化する方法を提供せんとするも
のである。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a method for disposing of radioactive waste, and in particular, it is an object of the present invention to provide a method for purposefully reducing the volume of radioactive waste generated in pressurized water nuclear power plants.
加圧水型原子炉をもつ原子力発電所においては
種々の放射性廃棄物が発生する。その内の大部分
は1次冷却系の排水あるいは2次冷却系の排
水、機器の排水などの廃液、作業衣などの洗濯
に用いられた廃水、紙、布、ポリエチレンなど
の可燃性雑固体、によつて占められている。これ
らの放射性廃棄物は、その性質上周到な注意の下
に管理、貯蔵しなければならず取扱いの便宜その
他の理由から、その容積を減少させる必要があ
る。 Nuclear power plants with pressurized water reactors generate various types of radioactive waste. Most of this is waste water from the primary cooling system or secondary cooling system, waste water from equipment, waste water used for washing work clothes, flammable miscellaneous solids such as paper, cloth, polyethylene, etc. occupied by. Due to their nature, these radioactive wastes must be managed and stored with great care, and their volume must be reduced for convenience of handling and other reasons.
これら放射性廃棄物の代表的な従来の処理、貯
蔵法は次の通りである。 Typical conventional treatment and storage methods for these radioactive wastes are as follows.
先ず前記,の廃液について述べる。前記
の廃液は減速材であるホウ素がホウ酸として溶解
しているが、この廃液に蒸発処理を加えてホウ酸
濃度を12重量%程度まで濃縮し減容する。又前記
の廃液に対しては逆浸透膜処理により洗剤濃度
を5重量%程度まで濃縮し減容する。その後、こ
れらの濃縮廃液をセメントやアスフアルト等と混
合し、ドラム缶内で固化して、発電所の敷地内や
所定の貯蔵地内に管理貯蔵する。 First, let's talk about the waste liquid mentioned above. Boron, which is a moderator, is dissolved in the waste liquid as boric acid, and this waste liquid is subjected to evaporation treatment to concentrate the boric acid concentration to about 12% by weight and reduce the volume. Further, the waste liquid is subjected to reverse osmosis membrane treatment to concentrate the detergent concentration to about 5% by weight and reduce the volume. Thereafter, these concentrated waste liquids are mixed with cement, asphalt, etc., solidified in drums, and managed and stored on the premises of the power plant or in a designated storage area.
ところが、この方法では次のような欠点があつ
た。原子力発電所は相当の長期間にわたつて運転
を続けるものであり、かつ放射性廃液の固化体も
相当の長期間にわたつて管理、貯蔵の必要があ
る。このため、原子力発電所の運転の続行に伴な
い処理・貯蔵すべき放射性廃液の累積量も増加を
続けるのに対し、従来の濃縮では減容として不十
分であり、更にセメント固化体等はセメントの付
加により相当の容積増大を伴なうので、それを収
容する貯蔵場所を次々と準備していかねばならな
い。更に、一たんセメント等と混合して固化する
と、次の処理手段としては、廃棄処分以外にな
く、その貯蔵量の増大に応じた適切な次の処理方
法が採用できない。このため、濃縮廃液の容積を
更に減少した固化物として貯蔵・管理するための
処理方法が求められている。 However, this method had the following drawbacks. Nuclear power plants continue to operate for a considerable period of time, and solidified radioactive waste liquid also needs to be managed and stored for a considerable period of time. For this reason, as nuclear power plants continue to operate, the cumulative amount of radioactive waste fluid that must be treated and stored continues to increase, but conventional concentration is insufficient to reduce the volume, and cement solidified bodies, etc. Since the addition of 2000 yen is accompanied by a considerable increase in volume, storage areas must be prepared one after another to accommodate it. Furthermore, once it is mixed with cement or the like and solidified, the only way to dispose of it is to dispose of it, and it is not possible to adopt an appropriate next disposal method in response to the increase in the amount of storage. Therefore, there is a need for a processing method for storing and managing the concentrated waste liquid as a solidified product whose volume is further reduced.
一般に、廃液を減容する方法として、流動層〓
焼法、噴霧〓焼法等の〓焼方法が従来より知られ
ている。流動層〓焼法、噴霧〓焼法共に、その〓
焼生成物は、粉粒体として得られるが、粉粒体の
ままでは取扱いの困難さ、飛散の問題、見かけ密
度が小さいことなどの欠点があるため、更にペレ
ツトに減容成型することが考えられている。 Generally speaking, as a method for reducing the volume of waste liquid, fluidized bed
Baking methods such as baking method and spray baking method are conventionally known. Both the fluidized bed sintering method and the spray sintering method
The fired product can be obtained as a powder or granule, but since it has drawbacks such as difficulty in handling, problems with scattering, and low apparent density, it is considered to further reduce the volume into pellets. It is being
一方前記の可燃性雑固体に対しては、焼却処
理により減容がなされ、残査である焼却灰はその
ままドラム詰めされ、前記,と同様に発電所
の敷地内等に管理貯蔵されている。ところが、こ
の方法では次のような欠点があつた。焼却灰の見
掛け密度が小さいために、前述の,と同様
に、原子力発電所の運転の続行に伴ない管理貯蔵
すべき放射性焼却灰の累積量も増加を続けるのに
対し、未だ減容が不十分である。かつ、焼却灰が
粉体として得られるため、取扱いの困難さ、飛散
の問題等があつた。 On the other hand, the volume of the combustible miscellaneous solids mentioned above is reduced by incineration, and the remaining incineration ash is directly packed in drums and stored under management within the premises of the power plant, etc., as described above. However, this method had the following drawbacks. Because the apparent density of incinerated ash is small, the cumulative amount of radioactive incinerated ash that must be managed and stored will continue to increase as nuclear power plants continue to operate, as mentioned above, but volume reduction is still not possible. It is enough. In addition, since the incineration ash is obtained as a powder, there are problems such as difficulty in handling and scattering.
そこで本発明者らは、従来法の欠点のない処理
法を提供すべく鋭意研究の結果、加圧水型原子力
発電所にいて発生する濃縮廃液の〓焼生成物その
ものが結合剤として優えた性質を有していること
を確認し、その知見に基づいて本発明を完成する
に至つた。すなわち本発明は加圧水型原子力発電
所において発生する可燃性雑固体の焼却灰に、同
発電所で発生する濃縮廃液の〓焼生成物を50重量
%以上になるように配合してペレツト固体化する
ことを特徴とする放射性廃棄物の処理法を要旨と
するものである。 As a result of intensive research to provide a treatment method that does not have the drawbacks of conventional methods, the present inventors found that the calcination product of concentrated waste liquid generated in pressurized water nuclear power plants itself has excellent properties as a binder. The present invention was completed based on this knowledge. That is, the present invention solidifies pellets by blending 50% by weight or more of the incineration product of concentrated waste liquid generated at pressurized water nuclear power plants with the incineration ash of combustible miscellaneous solids generated at pressurized water nuclear power plants. This article focuses on a method for disposing of radioactive waste that is characterized by the following.
以下、具体例につき詳細に説明する。 Hereinafter, specific examples will be explained in detail.
前記の濃縮廃液を模擬するものとして、ホウ
酸12重量%水溶液に、水酸化ナトリウム及び炭酸
ナトリウムを加えて腐食防止の観点よりPH=7程
度としたもの(以下、ホウ酸廃液と呼称する)
を、前記の濃縮廃液として洗剤5重量%水溶液
(以下、洗剤廃液と呼称する)を用いた。これら
を各々又は混合して流動層式の〓焼炉により、〓
焼生成物とした。 To simulate the concentrated waste liquid mentioned above, sodium hydroxide and sodium carbonate were added to a 12% by weight aqueous solution of boric acid to adjust the pH to about 7 from the viewpoint of corrosion prevention (hereinafter referred to as boric acid waste liquid).
A 5% by weight aqueous detergent solution (hereinafter referred to as detergent waste liquid) was used as the concentrated waste liquid. Each of these or a mixture of these is used in a fluidized bed kiln.
It was made into a baked product.
前記の可燃性雑固体を模擬するものとして、
紙・布・ポリエチルンを重量で等量づつ混合した
ものを用い、これを流動層式の焼却炉により焼却
残査を得た。 As a simulator of the above-mentioned combustible miscellaneous solids,
A mixture of paper, cloth, and polyethylene in equal amounts by weight was used, and the incineration residue was obtained using a fluidized bed incinerator.
これらを比較例として単独あるいは実施例とし
て混合してタブレツテイングによりペレツトを作
成した。ペレツトの形状は20〓×8程度である。 These were used alone as a comparative example or mixed as an example to form pellets by tabletting. The shape of the pellet is about 20×8.
濃縮廃液から得た〓焼生成物の性状
〓焼生成物は結合剤の添加を必要とせず、それ
単独でヒビ割れや剥離のない完全なペレツトに成
型することができる。作成したペレツトの圧縮強
度及び密度は第1図及び第2図にそれぞれ示す通
りである。Properties of calcined product obtained from concentrated waste liquid The calcined product does not require the addition of a binder and can be molded into perfect pellets without cracking or peeling on its own. The compressive strength and density of the prepared pellets are shown in FIGS. 1 and 2, respectively.
これらの図から、打錠圧4.5トン(1.4トン/
cm2)以上とすれば、現在の暫定海洋投棄指針であ
る圧縮強度150Kg/cm2以上、密度1.2g/cm3以上を
満足するため、再粉砕などの処理を必要とせず、
このままの形でポリマー固化などにより固化体と
して海洋投棄に臨める。海洋投棄を行なわない場
合においても強固な性質を有しているためその取
扱いが容易である。 From these figures, the tableting pressure is 4.5 tons (1.4 tons/
cm 2 ) or more, it satisfies the current provisional ocean dumping guidelines of compressive strength of 150 kg/cm 2 or more and density of 1.2 g/cm 3 or more, and does not require treatment such as re-grinding.
In this form, it can be solidified with polymers and dumped into the ocean. Even if they are not dumped into the ocean, they are easy to handle because of their strong properties.
可燃性雑固体から得た焼却灰の性状
一方、焼却灰については、単独では全く成型す
ることができなかつた。そこでセルロース系の結
合剤を添加してペレツトを作成することを試み
た。この結合剤の添加量に対するペレツトの状態
を第3図に示す。Properties of incinerated ash obtained from combustible miscellaneous solids On the other hand, incinerated ash could not be molded at all by itself. Therefore, an attempt was made to create pellets by adding a cellulose-based binder. FIG. 3 shows the condition of the pellets depending on the amount of binder added.
この図において領域は全くペレツトを成型で
きず、バラバラの状態にとどまる領域を示し、領
域はペレツトを成型できるがヒビ割れがあり、
剥離したり、割れやすいペレツトしか作成できな
い領域を示し、領域はヒビ割れ、剥離のない完
全なペレツトを成型できる領域を示してなる。こ
の図から明らかなように、結合剤を30%以上添加
すれば完全なペレツトを成型することができる。
ところが、このような多量の結合剤の添加は、ペ
レツト成型の主要目的の1つである減容化を相殺
する結果となり、この観点からは好ましいことで
はない。 In this figure, the areas show areas where pellets cannot be formed at all and remain in a disjointed state, and areas where pellets can be formed but have cracks.
The area shows the area where only pellets that are easily peeled or cracked can be formed, and the area shows the area where perfect pellets without cracking or peeling can be formed. As is clear from this figure, complete pellets can be formed by adding more than 30% binder.
However, the addition of such a large amount of binder has the effect of offsetting volume reduction, which is one of the main purposes of pellet molding, and is not desirable from this point of view.
そこで、〓焼生成物がそれ単独でヒビ割れ等の
ない完全なペレツトに成型できることに着目し
て、これを焼却灰に添加してペレツトを作成し
た。この作成したペレツトの状態、圧縮強度、密
度をそれぞれ第4図〜第6図に示す。 Therefore, we focused on the fact that the sintered product can be molded into perfect pellets without cracks on its own, and created pellets by adding it to the incinerated ash. The condition, compressive strength, and density of the pellets thus prepared are shown in FIGS. 4 to 6, respectively.
第4図から明らかなように〓焼生成物を50重量
%以上焼却灰に添加してペレツトを成型すればヒ
ビ割れ、剥離等のない完全なペレツトが得られ
る。第4図中、,及び領域は第3図につい
て説明したのと同じ領域を示す。 As is clear from FIG. 4, if pellets are formed by adding 50% by weight or more of the sintered product to the incinerated ash, perfect pellets without cracking or peeling can be obtained. In FIG. 4, , and regions indicate the same regions as described with respect to FIG.
第5図から〓焼生成物単独のペレツトに比較
し、焼却灰に添加したときの方が圧縮濃度は増大
する。なお図中、αは4.5トン打錠圧の場合、β
は2トン打錠圧の場合を示す。 From FIG. 5: Comparing to the pellets of the sintered product alone, the compressed density increases when it is added to the incinerated ash. In the figure, α is 4.5 tons of tableting pressure, and β
indicates the case of 2 tons tableting pressure.
このように、〓焼生成物を焼却灰と混合して成
型したペレツトは、相互の特長を発揮し合いより
良好な性質を有するようになる。又、原子力発電
所全体の発生廃棄物量の観点から見れば、増量の
要因となる結合剤の添加がないため、粉体からペ
レツトに固化した分だけ減容が図れることにな
る。ちなみに〓焼生成物の粉粒体及び焼却灰のか
さ密度は0.4〜0.8g/cm3である。 In this way, the pellets formed by mixing the sintered product with the incinerated ash exhibit better properties by exhibiting their mutual features. In addition, from the perspective of the amount of waste generated in the entire nuclear power plant, since there is no addition of binder that would cause an increase in the amount, the volume can be reduced by the amount that is solidified from powder to pellets. Incidentally, the bulk density of the granular material of the sintered product and the incinerated ash is 0.4 to 0.8 g/cm 3 .
第6図からは、〓焼生成物の添加量が多いほ
ど、ペレツトの密度は増加することが分る。なお
図中、α帯は4.5トン打錠圧の場合、β帯は2ト
ン打錠圧の場合を示す。 From FIG. 6, it can be seen that the density of the pellet increases as the amount of the calcination product added increases. In the figure, the α band shows the case of 4.5 ton tableting pressure, and the β band shows the case of 2 ton tableting pressure.
これらのことから、良好な焼却灰のペレツトを
得るためには、第4図〜第6図より焼却灰に〓焼
生成物を50重量%以上、好ましくは、50重量%に
近い割合で混入すれば圧縮強度も十分にあるペレ
ツトを成型できることが明らかである。 Based on these facts, in order to obtain good incineration ash pellets, as shown in Figures 4 to 6, incineration products should be mixed into the incineration ash at a ratio of 50% by weight or more, preferably close to 50% by weight. It is clear that it is possible to mold pellets with sufficient compressive strength.
第1図は、濃縮廃液から得た〓焼生成物の打錠
圧(トン)と圧縮強度(Kg/cm2)との関係、第2
図は同〓焼生成物の打錠圧(トン)と密度(g/
cm3)との関係を示すグラフ、第3図は可燃性雑固
体から得た焼却灰に種々の割合で結合剤を加えた
時の状態を打錠圧(トン)の関数として示すグラ
フ、第4図〜第6図は本発明の効果を示すグラフ
で、第4図は可燃性雑固体から得た焼却灰に、
種々の割合で濃縮廃液から得た〓焼生成物を加え
た時の状態を打錠圧(トン)の関数として示すグ
ラフ、第5図は焼却灰と〓焼生成物の混合物にお
ける〓焼生成物の量を基準とし、打錠圧4.5トン
及び2トンの場合に示す圧縮物の圧縮強度(Kg/
cm2)を示すグラフ、第6図は同基準に対して同じ
打錠圧の場合に示す圧縮物の密度(g/cm3)を示
すグラフである。
Figure 1 shows the relationship between tableting pressure (tons) and compressive strength (Kg/cm 2 ) of the calcined product obtained from concentrated waste liquid.
The figure shows the tableting pressure (tons) and density (g/
Figure 3 is a graph showing the relationship between tableting pressure (tons) when binders are added in various proportions to incineration ash obtained from combustible miscellaneous solids. Figures 4 to 6 are graphs showing the effects of the present invention.
A graph showing the state when calcination products obtained from concentrated waste liquid in various proportions are added as a function of tableting pressure (tons). The compressive strength of the compressed product (Kg/
Fig. 6 is a graph showing the density (g/cm 3 ) of the compressed product at the same tableting pressure based on the same standard.
Claims (1)
性雑固体の焼却灰に、同発電所で発生する濃縮廃
液の〓焼生成物を50重量%以上になるように配合
してペレツト固体化することを特徴とする放射性
廃棄物の処理法。1. The incineration ash of flammable miscellaneous solids generated at pressurized water nuclear power plants is blended with 50% by weight or more of the incineration product of concentrated waste liquid generated at the same power plants, and solidified into pellets. Radioactive waste disposal method.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP19847481A JPS58100799A (en) | 1981-12-11 | 1981-12-11 | Treatment of radioactive waste |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP19847481A JPS58100799A (en) | 1981-12-11 | 1981-12-11 | Treatment of radioactive waste |
Publications (2)
Publication Number | Publication Date |
---|---|
JPS58100799A JPS58100799A (en) | 1983-06-15 |
JPS6246840B2 true JPS6246840B2 (en) | 1987-10-05 |
Family
ID=16391702
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP19847481A Granted JPS58100799A (en) | 1981-12-11 | 1981-12-11 | Treatment of radioactive waste |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPS58100799A (en) |
Families Citing this family (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPH0636076B2 (en) * | 1985-04-12 | 1994-05-11 | 株式会社日立製作所 | Radioactive waste granulator |
Citations (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPS54101099A (en) * | 1978-01-27 | 1979-08-09 | Hitachi Ltd | Processing method of radioactive waste |
-
1981
- 1981-12-11 JP JP19847481A patent/JPS58100799A/en active Granted
Patent Citations (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPS54101099A (en) * | 1978-01-27 | 1979-08-09 | Hitachi Ltd | Processing method of radioactive waste |
Also Published As
Publication number | Publication date |
---|---|
JPS58100799A (en) | 1983-06-15 |
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