JPS6252277B2 - - Google Patents
Info
- Publication number
- JPS6252277B2 JPS6252277B2 JP122679A JP122679A JPS6252277B2 JP S6252277 B2 JPS6252277 B2 JP S6252277B2 JP 122679 A JP122679 A JP 122679A JP 122679 A JP122679 A JP 122679A JP S6252277 B2 JPS6252277 B2 JP S6252277B2
- Authority
- JP
- Japan
- Prior art keywords
- decomposition
- ammonium nitrate
- primary
- waste liquid
- 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
Links
- 238000000354 decomposition reaction Methods 0.000 claims description 51
- PAWQVTBBRAZDMG-UHFFFAOYSA-N 2-(3-bromo-2-fluorophenyl)acetic acid Chemical compound OC(=O)CC1=CC=CC(Br)=C1F PAWQVTBBRAZDMG-UHFFFAOYSA-N 0.000 claims description 32
- 239000002699 waste material Substances 0.000 claims description 32
- 239000007788 liquid Substances 0.000 claims description 25
- 230000002285 radioactive effect Effects 0.000 claims description 22
- 238000000034 method Methods 0.000 claims description 21
- 238000005979 thermal decomposition reaction Methods 0.000 claims description 17
- 238000012545 processing Methods 0.000 claims description 15
- 239000007789 gas Substances 0.000 claims description 13
- 238000006243 chemical reaction Methods 0.000 description 21
- 238000005336 cracking Methods 0.000 description 11
- MWUXSHHQAYIFBG-UHFFFAOYSA-N Nitric oxide Chemical compound O=[N] MWUXSHHQAYIFBG-UHFFFAOYSA-N 0.000 description 8
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 6
- MGWGWNFMUOTEHG-UHFFFAOYSA-N 4-(3,5-dimethylphenyl)-1,3-thiazol-2-amine Chemical compound CC1=CC(C)=CC(C=2N=C(N)SC=2)=C1 MGWGWNFMUOTEHG-UHFFFAOYSA-N 0.000 description 4
- GQPLMRYTRLFLPF-UHFFFAOYSA-N Nitrous Oxide Chemical compound [O-][N+]#N GQPLMRYTRLFLPF-UHFFFAOYSA-N 0.000 description 4
- JCXJVPUVTGWSNB-UHFFFAOYSA-N nitrogen dioxide Inorganic materials O=[N]=O JCXJVPUVTGWSNB-UHFFFAOYSA-N 0.000 description 4
- 238000000197 pyrolysis Methods 0.000 description 4
- 238000010586 diagram Methods 0.000 description 3
- DVARTQFDIMZBAA-UHFFFAOYSA-O ammonium nitrate Chemical compound [NH4+].[O-][N+]([O-])=O DVARTQFDIMZBAA-UHFFFAOYSA-O 0.000 description 2
- 238000004140 cleaning Methods 0.000 description 2
- 238000001816 cooling Methods 0.000 description 2
- 238000001704 evaporation Methods 0.000 description 2
- 230000008020 evaporation Effects 0.000 description 2
- 238000004880 explosion Methods 0.000 description 2
- 238000010438 heat treatment Methods 0.000 description 2
- 239000012857 radioactive material Substances 0.000 description 2
- 239000002901 radioactive waste Substances 0.000 description 2
- 238000005118 spray pyrolysis Methods 0.000 description 2
- 229910018626 Al(OH) Inorganic materials 0.000 description 1
- 239000012670 alkaline solution Substances 0.000 description 1
- 239000000956 alloy Substances 0.000 description 1
- 229910045601 alloy Inorganic materials 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 238000007796 conventional method Methods 0.000 description 1
- 230000007423 decrease Effects 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 238000002474 experimental method Methods 0.000 description 1
- 239000012530 fluid Substances 0.000 description 1
- 239000011810 insulating material Substances 0.000 description 1
- XEEYBQQBJWHFJM-UHFFFAOYSA-N iron Substances [Fe] XEEYBQQBJWHFJM-UHFFFAOYSA-N 0.000 description 1
- UGKDIUIOSMUOAW-UHFFFAOYSA-N iron nickel Chemical compound [Fe].[Ni] UGKDIUIOSMUOAW-UHFFFAOYSA-N 0.000 description 1
- 239000007769 metal material Substances 0.000 description 1
- 239000000203 mixture Substances 0.000 description 1
- 239000001272 nitrous oxide Substances 0.000 description 1
- 239000003758 nuclear fuel Substances 0.000 description 1
- 239000002245 particle Substances 0.000 description 1
- 238000003672 processing method Methods 0.000 description 1
- 238000011084 recovery Methods 0.000 description 1
- 238000012958 reprocessing Methods 0.000 description 1
- 230000000717 retained effect Effects 0.000 description 1
- 239000007787 solid Substances 0.000 description 1
- 239000007921 spray Substances 0.000 description 1
- 238000005507 spraying Methods 0.000 description 1
- 239000010935 stainless steel Substances 0.000 description 1
- 229910001220 stainless steel Inorganic materials 0.000 description 1
Landscapes
- Heat Treatment Of Water, Waste Water Or Sewage (AREA)
Description
【発明の詳細な説明】
本発明は、放射性残渣を含む硝酸アンモニウム
廃液の熱分解処理方法、さらに詳しくは、安全に
熱分解させると共に一酸化窒素NOと二酸化窒素
NO2の発生を極力少なくし、しかも熱分解後の放
射性残渣を最小限にし、その処理を簡単かつ容易
ならしめ得るようにした放射性残渣を含む硝酸ア
ンモニウム廃液の熱分解処理方法に関するもので
ある。DETAILED DESCRIPTION OF THE INVENTION The present invention provides a method for thermally decomposing waste ammonium nitrate containing radioactive residues, and more specifically, the present invention provides a method for thermally decomposing waste ammonium nitrate containing radioactive residues, and more specifically, a method for thermally decomposing waste liquid containing radioactive residues, and in particular for safely thermally decomposing it and converting it into nitrogen monoxide NO and nitrogen dioxide.
This invention relates to a thermal decomposition treatment method for ammonium nitrate waste liquid containing radioactive residue, which minimizes the generation of NO 2 and minimizes the radioactive residue after thermal decomposition, making the treatment simple and easy.
核燃料再処理過程から生ずる硝酸アンモニウム
廃液の成分は、水と硝酸アンモニウムと不溶性残
渣とからなり、その不溶性残渣の中に放射性物質
が含まれており、最近その量が多くなつているた
め、できうる限り減容して、安全に貯蔵できる処
理方法の出現が要請されている。一方硝酸アンモ
ニウム廃液中の硝酸アンモニウムを熱分解させ、
無害ガスとして放出することは公知であつて、こ
の熱分解方式を採用すれば、放射性残渣を含む硝
酸アンモニウム廃液中の硝酸アンモニウム塩をす
べて固体として貯蔵、保管するより有益なことは
当然考えられる。 The components of ammonium nitrate waste fluid generated from the nuclear fuel reprocessing process consist of water, ammonium nitrate, and insoluble residue.The insoluble residue contains radioactive materials, and the amount of radioactive materials has been increasing recently, so it should be reduced as much as possible. Therefore, there is a need for a processing method that allows safe storage. On the other hand, ammonium nitrate in the ammonium nitrate waste liquid is thermally decomposed,
It is known that the ammonium nitrate salt is released as a harmless gas, and if this thermal decomposition method is adopted, it is naturally thought that it is more beneficial than storing all the ammonium nitrate salts in the ammonium nitrate waste liquid containing radioactive residues as a solid.
ところで、従来の放射性残渣を含む硝酸アンモ
ニウム廃液の熱分解方法には、液膜分解法、噴霧
熱分解法、流動層熱分解法などがある。前記液膜
分解法は、廃液を反応管の内面に膜状として流下
させ、その反応管を外面よりヒーターで200℃〜
300℃に加熱することにより熱分解するもので、
廃液の流下速度により反応管内の滞留量を制御
し、安全性を確保することはできるが、熱分解し
ない放射性残渣が反応管の内面に付着するため、
反応管の内面を定期的に洗浄する必要があり、こ
のため廃棄物が多くなると共に洗浄水の処理が必
要となる。またこの方法は、再結合硝酸アンモニ
ウムの発生が多い欠点がある。 By the way, conventional methods for thermally decomposing ammonium nitrate waste liquid containing radioactive residues include liquid film decomposition, spray pyrolysis, and fluidized bed pyrolysis. In the liquid film decomposition method, the waste liquid flows down as a film on the inner surface of a reaction tube, and the reaction tube is heated from the outside to 200℃ using a heater.
It is thermally decomposed by heating to 300℃.
Although safety can be ensured by controlling the amount of waste liquid retained in the reaction tube by controlling the flow rate, radioactive residue that does not decompose will adhere to the inner surface of the reaction tube.
It is necessary to periodically clean the inner surface of the reaction tube, which increases the amount of waste and requires treatment of the cleaning water. This method also has the disadvantage that a large amount of recombined ammonium nitrate is generated.
噴霧熱分解法は、特公昭52−22751号公報に示
すように、180℃〜210℃に保つた一次分解炉中に
廃液を噴霧し、次いで熱分解ガス中の亜酸化窒素
N2Oを600℃〜1000℃に保つた二次分解炉中で熱
分解して無害化するもので、一次分解温度を低く
おさえているためNO,NO2などの発生量は少な
いが、前記液膜分解法と同様に、反応管の内面に
付着した放射性残渣の処理が必要であり、かつ廃
棄物処理が難しい問題がある。 In the spray pyrolysis method, as shown in Japanese Patent Publication No. 52-22751, waste liquid is sprayed into a primary decomposition furnace maintained at 180°C to 210°C, and then nitrous oxide in the pyrolysis gas is removed.
N 2 O is thermally decomposed and rendered harmless in a secondary decomposition furnace kept at 600℃ to 1000℃, and because the primary decomposition temperature is kept low, the amount of NO, NO 2, etc. generated is small; Similar to the liquid film decomposition method, it is necessary to dispose of radioactive residues attached to the inner surface of the reaction tube, and there is a problem that waste disposal is difficult.
流動熱分解法は、特開昭52−7369号公報に示す
ように、180℃〜290℃に保つた流動層中に廃液を
噴霧して熱分解するもので、NO,NO2などの発
生量は少ないが、流動層もガス処理系に流れるた
め装置が大型になるばかりでなく、流動粒子も放
射性廃棄物となり、廃棄物の量が多くなる欠点が
ある。すなわち、従来の硝酸アンモニウム廃液の
熱分解法は、放射性残渣を有する場合、放射能管
理、廃棄物処理の面からみて、好ましい熱分解方
法ではない。 As shown in Japanese Unexamined Patent Publication No. 52-7369, the fluidized pyrolysis method involves thermally decomposing waste liquid by spraying it into a fluidized bed maintained at 180℃ to 290℃, which reduces the amount of NO, NO 2 , etc. generated. However, since the fluidized bed also flows into the gas treatment system, it not only increases the size of the device, but also has the disadvantage that the fluidized particles also become radioactive waste, resulting in a large amount of waste. That is, the conventional thermal decomposition method of ammonium nitrate waste liquid is not a preferable thermal decomposition method from the viewpoint of radioactivity management and waste disposal when radioactive residue is present.
本発明は、前記の如き従来技術を改善し、熱分
解後の放射性残渣の管理、廃棄物処理などを容易
に行なうことができ、しかも一酸化窒素NO、二
酸化窒素NO2などの発生を極力少なくし、安全に
実施することができる放射性残渣を含む硝酸アン
モニウム廃液の熱分解処理方法を提供せんとする
ものである。 The present invention improves the conventional technology as described above, and makes it possible to easily manage radioactive residue after thermal decomposition and treat waste, while minimizing the generation of nitrogen monoxide NO, nitrogen dioxide NO 2 , etc. However, it is an object of the present invention to provide a thermal decomposition method for ammonium nitrate waste liquid containing radioactive residues that can be carried out safely.
本発明は、前記の如き目的を達成せんがため、
放射性残渣を含む硝酸アンモニウム廃液を処理容
器に入れ、これを一次分解炉中において分解温度
を250℃〜310℃に制御しつつ熱分解せしめ、かつ
該一次熱分解によつて発生する再結合硝酸アンモ
ニウムを350℃〜600℃に加熱された二次分解炉に
より再分解し、前記二段階分解により安全にかつ
有害ガスの発生を抑制しつつ分解せしめると共
に、熱分解後の放射性残渣を前記処理容器中にの
み残渣させて放射性廃棄物の処理を容易ならしめ
たことを特徴とする。 In order to achieve the above objects, the present invention has the following features:
The ammonium nitrate waste liquid containing radioactive residue is put into a processing container, and it is thermally decomposed in a primary decomposition furnace while controlling the decomposition temperature between 250℃ and 310℃, and the recombined ammonium nitrate generated by the primary thermal decomposition is heated to 350℃. Re-decomposition is carried out in a secondary decomposition furnace heated to 600 °C to 600 °C, and the two-stage decomposition allows the decomposition to occur safely and while suppressing the generation of harmful gases, and the radioactive residue after thermal decomposition is removed only into the processing container. It is characterized by making it easier to dispose of radioactive waste by leaving a residue.
以下本発明をさらに詳細に説明する。 The present invention will be explained in more detail below.
硝酸アンモニウムの代表的熱分解反応は下記反
応式(1)〜(4)に示すとおりである。 Typical thermal decomposition reactions of ammonium nitrate are shown in reaction formulas (1) to (4) below.
(1) NH4NO3NH3+HNO3
(2) NH4NO3→N2O+2H2O
(3) NH4NO3→N2+2H2O+1/2O2
(4) 2NH4NO3→N2+2NO+4H2O
分解模式は約310℃を境として大きく異なり、
310℃以下では反応(1),(2)が主反応であるが、そ
れ以上では反応(3),(4)が主反応となる。反応(1),
(2)に比べて反応(3),(4)は共に発熱反応であつて、
反応速度が速く、制御しにくいので爆発の危険性
があり、また分解生成ガスとして有害な一酸化窒
素NO、二酸化窒素NO2を生ずる。(1) NH 4 NO 3 NH 3 +HNO 3 (2) NH 4 NO 3 →N 2 O+2H 2 O (3) NH 4 NO 3 →N 2 +2H 2 O+1/2O 2 (4) 2NH 4 NO 3 →N 2 +2NO+4H 2 O The decomposition model differs greatly at about 310℃,
Below 310°C, reactions (1) and (2) are the main reactions, but above that, reactions (3) and (4) are the main reactions. reaction (1),
Compared to (2), reactions (3) and (4) are both exothermic reactions,
Because the reaction rate is fast and difficult to control, there is a risk of explosion, and the decomposition produces harmful nitrogen monoxide NO and nitrogen dioxide NO 2 as gases.
約310℃以下では、反応(1)の吸熱反応と反応(2)
の発熱反応とが同時に起るため、平衡温度が存在
し、暴走することなく、温度制御を容易に行なう
ことができる。しかし、310℃以下の熱分解で
は、反応(1)により分解(解離)した硝酸アンモニ
ウムが雰囲気中で再結合するため、分解を完全に
行なうことができる。 At temperatures below about 310℃, the endothermic reaction of reaction (1) and reaction (2) occur.
Since the exothermic reaction and the exothermic reaction occur simultaneously, an equilibrium temperature exists, and the temperature can be easily controlled without runaway. However, in thermal decomposition at 310° C. or lower, ammonium nitrate decomposed (dissociated) in reaction (1) recombines in the atmosphere, so decomposition can be completed completely.
ここにおいて本発明は、一次分解炉内では分解
温度を250℃〜310℃に押えることにより一次熱分
解反応を安全に行ない、前記一次分解炉で発生す
る再結合硝酸アンモニウムを350℃〜600℃で完全
に分解させる。 Here, the present invention safely performs the primary thermal decomposition reaction by suppressing the decomposition temperature within the primary decomposition furnace to 250°C to 310°C, and completely removes the recombined ammonium nitrate generated in the primary decomposition furnace at 350°C to 600°C. be decomposed into
そして、前記一次分解炉における分解は、放射
性残渣を含む硝酸アンモニウム廃液を処理容器中
に入れた状態のままで行ない、熱分解後の放射性
残渣がその処理容器中にのみ存在するようにし、
これにより、熱分解後の放射性残渣(廃棄物)を
最小限に減容すると共に、その回収並びに処理を
容易ならしめる。 The decomposition in the primary decomposition furnace is performed while the ammonium nitrate waste liquid containing radioactive residue is kept in the processing container, so that the radioactive residue after pyrolysis exists only in the processing container,
This reduces the volume of radioactive residue (waste) after thermal decomposition to a minimum, and facilitates its recovery and treatment.
本発明において、一次分解温度を250℃〜310
℃、二次分解温度を350℃〜600℃と定めたのは次
の理由による。 In the present invention, the primary decomposition temperature is set at 250°C to 310°C.
The reason why the secondary decomposition temperature was set at 350°C to 600°C is as follows.
すなわち、一次分解にて安全にかつ早く分解さ
せるには、前記(1),(2)式の分解温度(約210℃以
上)以上で、かつ、前記(3),(4)式の分解温度(約
310℃以下)以下あればよいが、低温(約210℃〜
250℃)では分解速度が遅く、かつ、未分解硝安
量が多くなるため、一次分解温度を250℃〜310℃
とした。 In other words, in order to decompose safely and quickly through primary decomposition, the decomposition temperature must be equal to or higher than the decomposition temperature of equations (1) and (2) above (approximately 210°C or higher), and the decomposition temperature of equations (3) and (4) above should be higher than (about
310℃ or below), but low temperature (approximately 210℃~
(250℃), the decomposition rate is slow and the amount of undecomposed ammonium nitrate increases, so the primary decomposition temperature is set at 250℃ to 310℃.
And so.
二次分解では、低温(350℃以下)では分解速
度が遅く、かつ、この種の装置(機器および配管
等)に使用する金属材料(例えば、熱間圧延ステ
ンレス鋼板、熱交換器用継目無ニツケル鉄合金
管)の強度は、常温に比べ高温で低下し特に600
℃以上で著しく低下するため、二次分解温度を
350℃〜600℃とした。 In secondary decomposition, the decomposition rate is slow at low temperatures (below 350°C), and the metal materials used in this type of equipment (equipment and piping, etc.) (e.g., hot-rolled stainless steel sheets, seamless nickel iron for heat exchangers) The strength of alloy pipes) decreases at high temperatures compared to room temperature, especially at 600°C.
℃ or higher, so the secondary decomposition temperature is
The temperature was 350°C to 600°C.
このような本発明の処理方法を用いると、一次
分解炉の分解温度が比較的低いため安全に一次分
解させることができ、一次分解炉で発生した再結
合残部硝酸アンモニウムのみを二次分解炉におい
て完全に分解させるので、一酸化窒素NO、二酸
化窒素NO2の発生は二次分解炉のみに押えられて
小量となり、さらに前述の如く熱分解後の放射性
残渣(廃棄物)は最小限に減容された状態で処理
容器中にのみ存在するので、その回収その他の処
理をきわめて簡単かつ容易に行なうことができ
る。 When the treatment method of the present invention is used, primary decomposition can be carried out safely because the decomposition temperature in the primary decomposition furnace is relatively low, and only the recombined residual ammonium nitrate generated in the primary decomposition furnace is completely removed in the secondary decomposition furnace. Since the generation of nitrogen monoxide NO and nitrogen dioxide NO 2 is suppressed to a small amount only by the secondary decomposition furnace, the volume of radioactive residue (waste) after thermal decomposition is reduced to a minimum as mentioned above. Since it exists only in the processing container in a processed state, its collection and other processing can be performed very simply and easily.
次に、添付図面を参照し乍ら本発明の実施の一
例を具体的に説明する。 Next, an example of the implementation of the present invention will be specifically described with reference to the accompanying drawings.
第1図は本発明に従う処理系統図である。1は
一次分解炉で、その内部に断熱材で囲んだ処理容
器の収容室を形成し、その中に廃液を入れた処理
容器7を入れる。また前記処理容器収容室の周囲
にはヒータ11が配設されている。さらにこの一
次分解炉は、前記収容室の上方に空間12を形成
させておく。2は二次分解炉、3は冷却空気取入
口、4は有害ガス捕集装置(例えばアルカリ溶液
スプレー洗浄装置)、5は除湿器、6は排気フア
ンである。 FIG. 1 is a processing system diagram according to the present invention. Reference numeral 1 denotes a primary decomposition furnace, in which a processing container housing chamber surrounded by a heat insulating material is formed, and a processing container 7 containing waste liquid is placed therein. Further, a heater 11 is arranged around the processing container storage chamber. Further, in this primary cracking furnace, a space 12 is formed above the storage chamber. 2 is a secondary cracking furnace, 3 is a cooling air intake, 4 is a harmful gas collection device (for example, an alkaline solution spray cleaning device), 5 is a dehumidifier, and 6 is an exhaust fan.
前記廃液処理容器7(φ100mm×H150mm)中に
試料(成分;水分80重量%、硝安12重量%、仮想
灰分Al(OH)3,Fe(OH)3各々4重量%)を入
れ、これを上部空間12の寸法をW300mm×L300
mm×H400mmとした一次分解炉1中に設置してヒ
ータ11により加熱し、処理容器内の温度を270
℃に制御した。加熱中の廃液処理容器内の温度は
第2図に示すように変化した。なお、第2図にお
いてAは水分蒸発過程、Bは硝安分解過程を示
し、その分解に約15分を要した。 A sample (components: water 80% by weight, ammonium nitrate 12% by weight, virtual ash content Al(OH) 3 and Fe(OH) 3 each 4% by weight) was placed in the waste liquid treatment container 7 (φ100mm x H150mm), and the sample was poured into the upper part. The dimensions of space 12 are W300mm x L300
It is installed in the primary decomposition furnace 1 with a size of mm
The temperature was controlled at ℃. The temperature inside the waste liquid treatment container during heating changed as shown in FIG. In Figure 2, A shows the water evaporation process and B shows the ammonium nitrate decomposition process, which took about 15 minutes.
廃液処理容器内から発生する分解生成ガスは、
一次分解炉の前記上部空間12を通つた後二次分
解炉2に導かれる。 The decomposition gas generated from inside the waste liquid treatment container is
After passing through the upper space 12 of the primary cracking furnace, it is led to the secondary cracking furnace 2.
二次分解炉(寸法;φ50mm×L300mm)は、設
定温度400℃〜420℃とし、一次分解炉1中で発生
する再結合硝安を分解させる。一次分解炉出口で
の再結合硝安の量は、30〜40重量%(処理量60g
硝安に対して、18g〜24g)であつたが、二次分
解炉の出口での未分解硝安の量は1〜2重量%に
低減された。また、硝安分解過程における二次分
解炉出口での分解ガス組成は、H2O:42.7%、
NO1+2:1.9%その他の分解ガス(N2,O2,
N2O):55.4%であつた。また、前記分解中、爆
発は全く起らなかつた。 The secondary cracking furnace (dimensions: φ50 mm x L 300 mm) has a set temperature of 400°C to 420°C, and decomposes the recombined ammonium nitrate generated in the primary cracking furnace 1. The amount of recombined ammonium nitrate at the outlet of the primary cracking furnace is 30 to 40% by weight (processing amount: 60 g).
The amount of undecomposed ammonium nitrate at the outlet of the secondary cracking furnace was reduced to 1 to 2% by weight. In addition, the cracked gas composition at the outlet of the secondary cracking furnace during the ammonium nitrate decomposition process is H 2 O: 42.7%,
NO 1+2 : 1.9% Other cracked gases (N 2 , O 2 ,
N2O ): 55.4%. Also, no explosion occurred during the decomposition.
二次分解炉2を出た分解ガスは、第1図に示す
ようにして外気で冷却した後、有害ガス捕集装置
4に導かれ、アルカリ水洗浄され、さらに除湿器
5で水分を除去した後大気中に排気させた。 The decomposed gas leaving the secondary decomposition furnace 2 was cooled with outside air as shown in Fig. 1, and then led to a harmful gas collection device 4 where it was washed with alkaline water, and further water was removed with a dehumidifier 5. It was then vented to atmosphere.
実験終了後、一次分解炉に設置した処理容器7
を取出し、残渣を分析したところ、残渣は仮想灰
分のみで、硝安は全く認められず、かつ、残渣の
廃液処理容器からの取出しも容易であつた。 After the experiment, processing container 7 installed in the primary decomposition furnace
When the sample was taken out and the residue was analyzed, it was found that the residue was only virtual ash and no ammonium nitrate was observed, and it was easy to remove the residue from the waste liquid treatment container.
第1図は本発明による放射性残渣を含む硝酸ア
ンモニウム廃液の熱分解処理方式を示す系統図、
第2図は処理容器内の温度変化を示す図である。
1……一次分解炉、2……二次分解炉、3……
冷却空気取入口、4……有害ガス捕集装置、5…
…除湿器、6……排気フアン、7……廃液処理容
器、11……ヒータ、A……水分蒸発過程、B…
…硝安分解過程。
FIG. 1 is a system diagram showing a thermal decomposition treatment method for ammonium nitrate waste liquid containing radioactive residues according to the present invention;
FIG. 2 is a diagram showing temperature changes inside the processing container. 1...Primary cracking furnace, 2...Secondary cracking furnace, 3...
Cooling air intake, 4... Harmful gas collection device, 5...
... Dehumidifier, 6 ... Exhaust fan, 7 ... Waste liquid processing container, 11 ... Heater, A ... Moisture evaporation process, B ...
...Ammonium nitrate decomposition process.
Claims (1)
理容器に入れ、これを一次分解炉中において分解
温度を250℃〜310℃に制御しつつ熱分解せしめ、
かつ該一次分解炉において発生する再結合硝酸ア
ンモニウムを350℃〜600℃に加熱された二次分解
炉により再分解し、前記二段階分解により安全に
かつ有害ガスの発生を抑制しつつ分解せしめると
共に、熱分解後の放射性残渣を前記処理容器中に
のみ残存させることを特徴とする放射性残渣を含
む硝酸アンモニウム廃液の熱分解処理方法。1. Put ammonium nitrate waste liquid containing radioactive residue into a processing container, and thermally decompose it in a primary decomposition furnace while controlling the decomposition temperature between 250°C and 310°C.
The recombined ammonium nitrate generated in the primary decomposition furnace is re-decomposed in a secondary decomposition furnace heated to 350°C to 600°C, and the two-stage decomposition is used to decompose safely and while suppressing the generation of harmful gases, A method for thermal decomposition treatment of ammonium nitrate waste liquid containing radioactive residues, characterized in that the radioactive residues after thermal decomposition are left only in the treatment container.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP122679A JPS5594199A (en) | 1979-01-12 | 1979-01-12 | Method of processing and pyrolyzing radioactive ammonium nitrate liquid waste |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP122679A JPS5594199A (en) | 1979-01-12 | 1979-01-12 | Method of processing and pyrolyzing radioactive ammonium nitrate liquid waste |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS5594199A JPS5594199A (en) | 1980-07-17 |
| JPS6252277B2 true JPS6252277B2 (en) | 1987-11-04 |
Family
ID=11495545
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP122679A Granted JPS5594199A (en) | 1979-01-12 | 1979-01-12 | Method of processing and pyrolyzing radioactive ammonium nitrate liquid waste |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS5594199A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO1998057894A1 (en) * | 1997-06-18 | 1998-12-23 | Anan Kasei Co., Ltd. | Method for treating waste water containing nitrate ions |
Families Citing this family (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS59107300A (en) * | 1982-12-10 | 1984-06-21 | 株式会社日立製作所 | Radioactive waste resin processing method and equipment |
| JPS59220696A (en) * | 1983-05-30 | 1984-12-12 | 株式会社日立製作所 | Method and device for processing radioactive resin waste |
| JPS6140596A (en) * | 1984-07-10 | 1986-02-26 | 東洋エンジニアリング株式会社 | Batch treatment method for radioactive organic waste |
| US4636336A (en) * | 1984-11-02 | 1987-01-13 | Rockwell International Corporation | Process for drying a chelating agent |
-
1979
- 1979-01-12 JP JP122679A patent/JPS5594199A/en active Granted
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO1998057894A1 (en) * | 1997-06-18 | 1998-12-23 | Anan Kasei Co., Ltd. | Method for treating waste water containing nitrate ions |
Also Published As
| Publication number | Publication date |
|---|---|
| JPS5594199A (en) | 1980-07-17 |
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