JPH071319B2 - Methods for reducing the accumulation of radioactivity in radioactive waste incinerators - Google Patents
Methods for reducing the accumulation of radioactivity in radioactive waste incineratorsInfo
- Publication number
- JPH071319B2 JPH071319B2 JP62019940A JP1994087A JPH071319B2 JP H071319 B2 JPH071319 B2 JP H071319B2 JP 62019940 A JP62019940 A JP 62019940A JP 1994087 A JP1994087 A JP 1994087A JP H071319 B2 JPH071319 B2 JP H071319B2
- Authority
- JP
- Japan
- Prior art keywords
- incinerator
- accumulation
- radioactivity
- radioactive waste
- furnace
- 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 - Lifetime
Links
- 238000009825 accumulation Methods 0.000 title claims description 12
- 239000002901 radioactive waste Substances 0.000 title claims description 11
- 238000000034 method Methods 0.000 title claims description 4
- 229910004298 SiO 2 Inorganic materials 0.000 claims description 16
- 239000000463 material Substances 0.000 claims description 11
- 239000011449 brick Substances 0.000 claims description 6
- 239000003456 ion exchange resin Substances 0.000 description 10
- 229920003303 ion-exchange polymer Polymers 0.000 description 10
- 239000002699 waste material Substances 0.000 description 10
- XEEYBQQBJWHFJM-UHFFFAOYSA-N iron Substances [Fe] XEEYBQQBJWHFJM-UHFFFAOYSA-N 0.000 description 8
- NWUYHJFMYQTDRP-UHFFFAOYSA-N 1,2-bis(ethenyl)benzene;1-ethenyl-2-ethylbenzene;styrene Chemical compound C=CC1=CC=CC=C1.CCC1=CC=CC=C1C=C.C=CC1=CC=CC=C1C=C NWUYHJFMYQTDRP-UHFFFAOYSA-N 0.000 description 7
- 239000002956 ash Substances 0.000 description 5
- 239000003960 organic solvent Substances 0.000 description 4
- 239000003921 oil Substances 0.000 description 3
- 230000005855 radiation Effects 0.000 description 3
- 239000011819 refractory material Substances 0.000 description 3
- VYPSYNLAJGMNEJ-UHFFFAOYSA-N Silicium dioxide Chemical compound O=[Si]=O VYPSYNLAJGMNEJ-UHFFFAOYSA-N 0.000 description 2
- 238000006243 chemical reaction Methods 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 239000011810 insulating material Substances 0.000 description 2
- 238000012423 maintenance Methods 0.000 description 2
- 239000007787 solid Substances 0.000 description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 2
- 229910018072 Al 2 O 3 Inorganic materials 0.000 description 1
- 239000010882 bottom ash Substances 0.000 description 1
- 238000011038 discontinuous diafiltration by volume reduction Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 239000004744 fabric Substances 0.000 description 1
- 229910052742 iron Inorganic materials 0.000 description 1
- 239000000123 paper Substances 0.000 description 1
- 239000000843 powder Substances 0.000 description 1
- 238000000746 purification Methods 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 230000008929 regeneration Effects 0.000 description 1
- 238000011069 regeneration method Methods 0.000 description 1
- 239000011347 resin Substances 0.000 description 1
- 229920005989 resin Polymers 0.000 description 1
- 239000000377 silicon dioxide Substances 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
- 239000010723 turbine oil Substances 0.000 description 1
- 239000002023 wood Substances 0.000 description 1
Landscapes
- Gasification And Melting Of Waste (AREA)
Description
【発明の詳細な説明】 技術分野 本発明は、放射性廃棄物を焼却・減容化処理する焼却炉
中に蓄積される放射性核種、特にCsの蓄積量を低減化す
る方法に関する。TECHNICAL FIELD The present invention relates to a method for reducing the amount of radioactive nuclides, particularly Cs, accumulated in an incinerator that incinerates and reduces the volume of radioactive waste.
従来技術 原子力施設で生じる放射性廃棄物は、焼却炉で焼却処理
されている。このような廃棄物としては、原子力施設内
で使用される水を浄化処理するために使用するイオン交
換樹脂、タービン廃油、有機溶剤や、作業服等の雑固体
などがある。2. Description of the Related Art Radioactive waste generated in a nuclear facility is incinerated in an incinerator. Such wastes include ion exchange resins used for purifying water used in nuclear facilities, turbine waste oil, organic solvents, and miscellaneous solids such as work clothes.
これら廃棄物、特にイオン交換樹脂、タービン廃油、有
機溶剤を、炉材中のSiO2含有率36％の従来型の焼却炉で
焼却処理していくと、焼却炉中に放射能が蓄積し、運
転、保守時の作業員の被曝問題の原因となる。When these wastes, especially ion exchange resin, turbine waste oil, and organic solvents are incinerated in a conventional incinerator with a SiO 2 content of 36% in the furnace material, radioactivity accumulates in the incinerator, This may cause a radiation exposure problem for workers during operation and maintenance.
焼却炉中への放射性核種60Co、54Mn、59Fe、137Csの蓄
積の程度は、以下のように定義される焼却炉の残存係数
で表される。The degree of accumulation of radionuclides 60 Co, 54 Mn, 59 Fe, and 137 Cs in the incinerator is expressed by the incinerator residual coefficient defined as follows.
従来型の焼却炉における残存係数としては、下記の表−
１のデータが知られている。 The table below shows the residual factors in conventional incinerators.
1 data is known.
このように、放射能を吸着させたイオン交換樹脂を焼却
した場合、特に137Csの蓄積割合が、他の核種に比べて
大きいことが問題である。 As described above, when the ion-exchange resin having adsorbed radioactivity is incinerated, the accumulation rate of 137 Cs is particularly large compared to other nuclides, which is a problem.
発明の目的 本発明は、例えばイオン交換樹脂、タービン廃油、有機
溶剤等の、灰分中のSiO2が雑固体（布、紙、木材類等）
に比べて少ない放射性廃棄物の焼却減容設備において、
特にイオン交換樹脂を焼却した場合に焼却炉中に蓄積さ
れる放射能を低減化することを目的とする。OBJECT OF THE INVENTION The present invention is a solid substance (cloth, paper, wood, etc.) containing SiO 2 in ash, such as ion exchange resins, waste turbine oil, organic solvents, etc.
In the incineration and volume reduction facility for radioactive waste, which is less than
Particularly, it is intended to reduce the radioactivity accumulated in the incinerator when the ion exchange resin is incinerated.
発明の構成 本発明者らは、上記目的を達成するために鋭意検討した
結果、137Csがキャスタブル耐火物や耐火レンガに含ま
れるSiO2（シリカ）と反応することにより炉内蓄積の原
因となることを見出し、この知見に基いて本発明を完成
するに至った。As a result of intensive studies to achieve the above object, the inventors of the present invention cause 137 Cs to react with SiO 2 (silica) contained in castable refractories or refractory bricks and cause accumulation in the furnace. Based on this finding, the present invention has been completed.
すなわち、本発明の放射性廃棄物焼却炉における放射能
の蓄積低減化方法は、放射性廃棄物を焼却炉で焼却処理
するに際し、該焼却炉の炉材であるキャスタブル耐火物
または耐火レンガ中のSiO2含有率を５％以下に減少さ
せ、該焼却炉内への放射能の蓄積を低減することを特徴
とする。That is, the method for reducing the accumulation of radioactivity in the radioactive waste incinerator of the present invention, when incinerating the radioactive waste in the incinerator, the castable refractory or refractory brick SiO 2 which is the furnace material of the incinerator. It is characterized by reducing the content rate to 5% or less and reducing the accumulation of radioactivity in the incinerator.
以下、添付図面に沿って本発明をさらに詳細に説明す
る。Hereinafter, the present invention will be described in more detail with reference to the accompanying drawings.
第１図は、本発明で用いられる焼却炉を示す概念図であ
る。SiO2含有率が５％以下のキャスタブル耐火物からな
る炉材14で構成された焼却炉内には、ガスバーナ口12か
ら予熱した空気と共に火炎が噴出されている。イオン交
換樹脂などの焼却対象物は、放射性廃棄物投入口11から
炉内に投入され、ここで焼却されて排ガスが排気口13か
ら排出され、適当な浄化処理を経たのち放出される。15
は、炉底に落ちた灰を除去するための排出口である。ま
た、16は保温材を示す。FIG. 1 is a conceptual diagram showing an incinerator used in the present invention. A flame is ejected together with preheated air from the gas burner port 12 in the incinerator made of the furnace material 14 made of castable refractory having a SiO 2 content of 5% or less. An object to be incinerated such as an ion exchange resin is introduced into the furnace through the radioactive waste inlet 11, where it is incinerated, the exhaust gas is exhausted through the exhaust port 13, and is discharged after undergoing an appropriate purification treatment. 15
Is an outlet for removing ash that has fallen to the bottom of the furnace. Further, 16 indicates a heat insulating material.
このような焼却炉で、60Co、54Mn、59Fe、137Cs等の放
射能を吸着させたイオン交換樹脂を焼却した場合、これ
ら核種が炉内に蓄積され、炉底に落ちる灰を除いたとし
ても、60Co、54Mn、59Feで15〜52％、137Csで69〜77％
が炉内に残留する。When incinerating an ion-exchange resin that has adsorbed radioactivity such as 60 Co, 54 Mn, 59 Fe, and 137 Cs in such an incinerator, these nuclides are accumulated in the furnace and ash that falls on the bottom of the furnace is removed. Even with 60 Co, 54 Mn, 59 Fe 15-52%, 137 Cs 69-77%
Remains in the furnace.
特に蓄積割合の大きい137Csに関しては、焼却中にSiO2
粉末と反応することが確かめられている。そこで、本発
明では、137Csが炉内に多く蓄積する原因が、Csと炉材
として用いられるキャスタブル耐火物の成分の１つであ
るSiO2と反応にあると考え、焼却炉を構成する耐火物の
材質としてSiO2の少ないものを選定する。Especially for 137 Cs, which has a large accumulation rate, SiO 2
It has been confirmed to react with powder. Therefore, in the present invention, it is considered that the reason why a large amount of 137 Cs is accumulated in the furnace is due to the reaction between Cs and SiO 2 which is one of the components of the castable refractory used as the furnace material. Select a material with a low SiO 2 content.
従来のキャスタブル耐火物や耐火レンガではSiO2含有率
の多いものが用いられており、既に述べたように炉底に
落ちた灰を除いたとしても、69〜77％の137Csが炉内に
蓄積する。これに対して本発明では炉材中のSiO2含有率
を少なくとも５％以下と低くすることにより、Cs蓄積割
合を、60Co、54Mn、59Feと同様に、15〜52％に減少させ
ることができる。Conventional castable refractories and refractory bricks with a high SiO 2 content are used, and 69 to 77% of 137 Cs remains in the furnace, even if the ash that has fallen to the bottom of the furnace is removed. accumulate. On the other hand, in the present invention, by lowering the SiO 2 content rate in the furnace material to at least 5% or less, the Cs accumulation rate is reduced to 15 to 52% like 60 Co, 54 Mn and 59 Fe. be able to.
本発明に従って、SiO2含有率を５％以下にした耐火物を
炉材として用いて焼却炉を構成し、60Co、54Mn、59Fe、
137Csの放射能を吸着させたイオン交換樹脂を焼却する
と、炉の残存係数として、60Co、54Mn、59Fe、で1.3〜
2.5、同様に137Csで1.3〜2.5の値が得られる。In accordance with the present invention, a refractory having a SiO 2 content of 5% or less is used as a furnace material to form an incinerator, and 60 Co, 54 Mn, 59 Fe,
When the ion-exchange resin that adsorbed 137 Cs radioactivity was incinerated, the residual coefficient of the furnace was 60 Co, 54 Mn, 59 Fe, 1.3-
2.5, similarly a value of 1.3 to 2.5 is obtained at 137 Cs.
一般に、照射線量率Ｄ（mR/h）は、以下の式（Ｉ）で表
される。Generally, the irradiation dose rate D (mR / h) is represented by the following formula (I).
Ｄ＝I0×3.7×1010×Ｅ×ｆ×Ａ …（Ｉ） I0：線源の強さ（Ci） E:γ線のエネルギー（MeV） f:換算係数 A:比例係数（形状、再生係数を含む） Ａは焼却炉の形状等に依るものである。例えば内径76c
m、外径212cmの円筒状の耐火レンガを厚さ9mmの鉄で外
装した円筒状の焼却炉を用意し、線源として0.75μCi/c
m2の60Coをこの焼却炉に入れ、焼却炉側面中央部で外面
から1m離れた地点での照射線量率Ｄを算出すると1.08mR
/hである。また、このときの焼却炉内全放射量I0は炉内
表面積より次の通りとした。D = I 0 × 3.7 × 10 10 × E × f × A (I) I 0 : Source intensity (Ci) E: Energy of γ rays (MeV) f: Conversion coefficient A: Proportional coefficient (shape, (Including regeneration coefficient) A depends on the shape of the incinerator. For example, inner diameter 76c
Prepare a cylindrical incinerator with a cylindrical fireproof brick of m, outer diameter 212 cm, and iron 9 mm thick, and use 0.75 μCi / c as a radiation source.
When 60 Co of m 2 is put into this incinerator, the irradiation dose rate D at the point 1 m away from the outer surface at the center of the side surface of the incinerator is 1.08 mR
/ h. Further, the total radiation amount I 0 in the incinerator at this time was set as follows from the surface area in the furnace.
I0（Ci）＝0.75μCi/cm2×3.47×105cm2＝0.26Ci これらの値から上記（Ｉ）式の比例係数Ａを算出すると
次のようになる。I 0 (Ci) = 0.75 μCi / cm 2 × 3.47 × 10 5 cm 2 = 0.26 Ci The proportional coefficient A of the above formula (I) is calculated from these values as follows.
1.08＝0.26×3.7×1010×（1.17＋1.33）×1.764×10-3
×Ａ ∴Ａ＝2.55×10-8 これと同じ形状の焼却炉を用い、PWR（加圧水型原子
炉）から発生する廃イオン交換樹脂を焼却した場合の１
日当りの照射線量率増加を求めた。焼却炉としては、次
の２つのものを用いた。1.08 = 0.26 x 3.7 x 10 10 x (1.17 + 1.33) x 1.764 x 10 -3
× A ∴A = 2.55 × 10 -8 When incinerating waste ion exchange resin generated from PWR (pressurized water reactor) using an incinerator of the same shape 1
The increase in irradiation dose rate per day was calculated. The following two incinerators were used.
従来型：SiO236％、Ａl2O355％のキャスタブル耐火物を
用いた。Conventional type: A castable refractory made of 36% SiO 2 and 55% Al 2 O 3 was used.
改良型：SiO2を５％以下としたキャスタブル耐火物を用
いた。Improved type: A castable refractory containing 5% or less of SiO 2 was used.
年間の焼却日数を200日とし、１年間に発生した廃樹脂
に含まれる放射能を1000Ciとする。前記と同じ位置（焼
却炉側面中央部で外面から1m離れた位置）における１日
当りの照射線量率増加ΔＤ（mR/h/日）は、次のように
表される。The number of incineration days per year is 200 days, and the radioactivity contained in the waste resin generated in one year is 1000 Ci. The irradiation dose rate increase ΔD (mR / h / day) per day at the same position as described above (at a position 1 m away from the outer surface at the center of the side surface of the incinerator) is expressed as follows.
r:廃棄物中の比率 R:焼却炉の残存係数 B:炉底灰として排出される割合 ΔＤを下記表−２に示す。本発明の改良型の焼却炉を用
いることにより、137Csおよび134Csの照射線量率増加が
著しく改善されていることが判る。したがって、従来型
では一日当り合計4.91mR/hの上昇があるのに対し、改良
型では１日当り合計3.52mR/hの上昇となり、線量率増加
を28％抑えることができる。 r: Ratio in waste R: Remaining coefficient of incinerator B: Ratio discharged as bottom ash ΔD is shown in Table 2 below. It can be seen that by using the improved incinerator of the present invention, the increase in irradiation dose rate of 137 Cs and 134 Cs is significantly improved. Therefore, while the conventional type has a total increase of 4.91 mR / h per day, the improved type has a total increase of 3.52 mR / h per day, and the dose rate increase can be suppressed by 28%.
発明の効果 本発明によれば、放射性廃棄物、特にイオン交換樹脂、
タービン廃油、有機溶剤等灰分中のSiO2が少ない廃棄物
を焼却炉で処理するに際し、焼却炉の炉材であるキャス
タブル耐火物または耐火レンガ中のSiO2含有率を５％以
下に低下させることにより、焼却炉内への放射能、特に
137Csの蓄積を低減化することができる。この結果、137
Csから発する放射線が減少し、焼却炉表面線量率が減少
して、運転、保守時の作業員の被曝量の低減化を図るこ
とができる。また本発明によれば、焼却炉を構成する耐
火物の材質そのものを変更して放射性核種Csの蓄積を低
減するものであるから、特別な構造物等を付加する必要
はなく、焼却炉が複雑な構造となるおそれもない。 EFFECTS OF THE INVENTION According to the present invention, radioactive wastes, especially ion exchange resins,
When treating waste such as turbine waste oil and organic solvents with low SiO 2 in ash, in the incinerator, reduce the SiO 2 content in the castable refractory or refractory brick, which is the furnace material of the incinerator, to 5% or less. Radioactivity into the incinerator, especially
The accumulation of 137 Cs can be reduced. As a result, 137
The radiation emitted from Cs is reduced, the incinerator surface dose rate is reduced, and the exposure dose of workers during operation and maintenance can be reduced. Further, according to the present invention, since the material itself of the refractory material constituting the incinerator is changed to reduce the accumulation of the radionuclide Cs, it is not necessary to add a special structure or the like, and the incinerator is complicated. There is no risk of a different structure.
第１図は、本発明で用いられる焼却炉の一例を示す概念
図である。 11……放射性廃棄物投入口 12……ガスバーナ口、13……排気口 14……炉材、15……排出口 16……保温材FIG. 1 is a conceptual diagram showing an example of an incinerator used in the present invention. 11 …… Radioactive waste input port 12 …… Gas burner port, 13 …… Exhaust port 14 …… Furnace material, 15 …… Discharge port 16 …… Heat insulating material
フロントページの続き (72)発明者 高奥 芳伸 東京都田無市谷戸町２丁目１番１号 住友 重機械工業株式会社田無製造所内 (72)発明者 永栄 圓 東京都田無市谷戸町２丁目１番１号 住友 重機械工業株式会社田無製造所内 (56)参考文献 特開 昭59−35199（ＪＰ，Ａ)Front page continuation (72) Inventor Yoshinobu Takaoku 2-1-1 Yatocho, Tanashi-shi, Tokyo Sumitomo Heavy Industries, Ltd. Tanashi Factory (72) Inventor Enei Ei 2-1-1 Taido-cho, Tanashi, Tokyo Sumitomo Heavy Industries Co., Ltd. Tanashi Factory (56) Reference JP-A-59-35199 (JP, A)
Claims (1)
るに際し、該焼却炉の炉材であるキャスタブル耐火物ま
たは耐火レンガ中のSiO2含有率を５％以下に減少させ、
該焼却炉内への放射性核種、特にCsの蓄積を低減するこ
とを特徴とする放射性廃棄物焼却炉における放射能の蓄
積低減化方法。Claims: 1. When incineration reduction treatment of radioactive waste is performed in an incinerator, the content of SiO 2 in castable refractory or refractory brick which is a furnace material of the incinerator is reduced to 5% or less,
A method for reducing the accumulation of radioactivity in a radioactive waste incinerator, which comprises reducing the accumulation of radionuclides, particularly Cs, in the incinerator.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62019940A JPH071319B2 (en) | 1987-01-30 | 1987-01-30 | Methods for reducing the accumulation of radioactivity in radioactive waste incinerators |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62019940A JPH071319B2 (en) | 1987-01-30 | 1987-01-30 | Methods for reducing the accumulation of radioactivity in radioactive waste incinerators |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS63187199A JPS63187199A (en) | 1988-08-02 |
| JPH071319B2 true JPH071319B2 (en) | 1995-01-11 |
Family
ID=12013204
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP62019940A Expired - Lifetime JPH071319B2 (en) | 1987-01-30 | 1987-01-30 | Methods for reducing the accumulation of radioactivity in radioactive waste incinerators |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH071319B2 (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2014068643A1 (en) * | 2012-10-29 | 2014-05-08 | 太平洋セメント株式会社 | Method for removing radioactive cesium, and method for producing fired material |
Family Cites Families (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5935199A (en) * | 1982-08-23 | 1984-02-25 | 株式会社日立製作所 | Radioactive waste combustion device |
-
1987
- 1987-01-30 JP JP62019940A patent/JPH071319B2/en not_active Expired - Lifetime
Also Published As
| Publication number | Publication date |
|---|---|
| JPS63187199A (en) | 1988-08-02 |
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| Schneider | Nuclear-fuel-cycle risk assessment: descriptions of representative non-reactor facilities, Sections 15-19 | |
| Höhlein | TREATMENT OF NUCLEAR WASTES | |
| TANG | EXPERIENCE IN THERMAL TREATMENT OF LOW-LEVEL RADIOACTIVE WASTES |