JP2500408B2 - Continuous melting device for nuclear fuel - Google Patents

Continuous melting device for nuclear fuel

Info

Publication number
JP2500408B2
JP2500408B2 JP9593692A JP9593692A JP2500408B2 JP 2500408 B2 JP2500408 B2 JP 2500408B2 JP 9593692 A JP9593692 A JP 9593692A JP 9593692 A JP9593692 A JP 9593692A JP 2500408 B2 JP2500408 B2 JP 2500408B2
Authority
JP
Japan
Prior art keywords
nuclear fuel
reaction chamber
nitric acid
reaction
gas
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 - Fee Related
Application number
JP9593692A
Other languages
Japanese (ja)
Other versions
JPH05264780A (en
Inventor
洋一 高島
伸一 長谷川
建二 西村
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.)
Mitsubishi Materials Corp
Original Assignee
Mitsubishi Materials Corp
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 Mitsubishi Materials Corp filed Critical Mitsubishi Materials Corp
Priority to JP9593692A priority Critical patent/JP2500408B2/en
Publication of JPH05264780A publication Critical patent/JPH05264780A/en
Application granted granted Critical
Publication of JP2500408B2 publication Critical patent/JP2500408B2/en
Anticipated expiration legal-status Critical
Expired - Fee Related legal-status Critical Current

Links

Classifications

    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors
    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02WCLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
    • Y02W30/00Technologies for solid waste management
    • Y02W30/50Reuse, recycling or recovery technologies

Landscapes

  • Processing Of Solid Wastes (AREA)

Description

【発明の詳細な説明】Detailed Description of the Invention

【0001】[0001]

【産業上の利用分野】本発明は、核燃料の製造工程で発
生する核燃料スクラップ粉末又は使用済み核燃料の再処
理工程における核燃料粉末を連続的に溶解する装置に関
するものである。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to an apparatus for continuously melting nuclear fuel scrap powder generated in a nuclear fuel manufacturing process or nuclear fuel powder in a spent nuclear fuel reprocessing process.

【0002】[0002]

【従来の技術】核燃料の製造工程で発生する核燃料スク
ラップ粉末は精製されてリサイクルされる。この精製の
ためにスクラップ粉末は円筒状のバッチ式の溶解槽によ
り溶解されている。また使用済み核燃料の再処理では未
燃焼の核分裂性物質や新しく生成した核分裂性物質を分
離回収するために、再処理の前処理工程においていわゆ
る「剪断リーチ法」が一般的に行われている。この剪断
リーチ法は剪断刃により使用済み核燃料棒を燃料集合体
の状態でその直径方向に被覆管ごと数cmの長さに切断
してそのまま硝酸水溶液中に入れ、核燃料を浸出溶解さ
せる方法である。剪断リーチ法で処理された核燃料は円
筒状の溶解槽で溶解されるか、或いはスクリュー型の連
続溶解槽(例えば特開昭58−176107,同64−
65497)又は水車バケット型の連続溶解槽(例えば
特公昭60−41318,実開昭64−52533)で
溶解される。また別の連続溶解処理装置として、円環状
の槽内を隔壁で仕切り、仕切られた一端から溶解処理液
を前記槽内へ供給し他端から排出する溶解槽の中に、使
用済原子燃料の剪断片を装荷した複数の燃料装荷かごを
配置し、前記燃料装荷かごの下部を前記溶解処理液に浸
漬することによって使用済原子燃料を溶解処理する使用
済原子燃料の連続溶解処理装置が開示されている(特開
平1−141399)更に半連続溶解装置として、金
属材により被覆された核燃料を細かく切断した細片の収
納バスケットを受入れる複数個のバレルを高さ位置を変
えて並設するとともに、同各バレルの底部をパルセータ
ーに接続し、貯液槽を溶解液供給管を介して最高位のバ
レルに、最低位のバレルを溶解液排出管を介して同貯液
槽に、それぞれ接続することにより上記細片を溶解液に
より溶解する核燃料溶解装置が開示されている(特開昭
61−270695)。
2. Description of the Related Art Nuclear fuel scrap powder generated in a nuclear fuel manufacturing process is refined and recycled. For this refining, the scrap powder is dissolved in a cylindrical batch type dissolution tank. In the reprocessing of spent nuclear fuel, a so-called “shear reach method” is generally performed in the pretreatment step of the reprocessing in order to separate and recover unburned fissile material and newly generated fissile material. The shear reach method is a method in which a spent nuclear fuel rod is cut into a length of several cm along with a cladding tube in the diameter direction of a fuel assembly by a shear blade and put into an aqueous nitric acid solution as it is to leach and dissolve the nuclear fuel. . The nuclear fuel processed by the shear reach method is melted in a cylindrical melting tank, or is a screw type continuous melting tank (for example, JP-A-58-176107, 64-64).
65497) or a water turbine bucket type continuous melting tank (for example, Japanese Examined Patent Publication No. 60-41318, Japanese Utility Model Publication No. 64-52533). As another continuous dissolution treatment device,
The inside of the tank is partitioned by a partition wall, and the dissolution treatment liquid starts from one end of the partition.
In a dissolution tank that supplies the above into the tank and discharges from the other end.
Multiple fuel-loaded cages loaded with spent nuclear fuel shear fragments
And place the lower part of the fuel-loaded cage in the dissolution treatment liquid.
Use to dissolve and process spent nuclear fuel by dipping
A continuous dissolution processing apparatus for spent nuclear fuel is disclosed
(1-141399) . Furthermore, as a semi-continuous melting device, gold
Collection of finely cut strips of nuclear fuel coated with metal
Change the height position of the barrels that receive the baskets.
Side by side, and the bottom of each barrel is pulsated.
To the top of the reservoir via the dissolution liquid supply pipe.
Store the lowest barrel in the barrel via the dissolution liquid discharge pipe.
The above strips can be used as a solution by connecting them to the tank respectively.
A nuclear fuel melting device that dissolves more is disclosed (Japanese Patent Laid-Open No. Sho 61-135).
61-270695).

【0003】[0003]

【発明が解決しようとする課題】しかしながら、円筒状
の溶解槽はバッチ処理を前提としており、これを連続処
理装置として使用するためにはバッチ式の溶解槽を最低
2基設け、これらを交互に切換えて使用するか、或いは
円筒状溶解槽と溶解液の貯槽を大容量にして1回の処理
量を増大させる必要がある。前者の場合には切換え操作
が煩雑になり、後者の場合には溶解装置が大型化するな
どの問題点がある。またスクリュー型の連続溶解槽及び
水車バケット型の連続溶解槽ではいずれもスクリュー又
は水車バケットを駆動する軸が溶解槽を貫通して設けら
れるため、駆動軸の貫通部分には溶解液が槽外に漏洩し
ないようにシール性が要求される。この駆動軸のシール
性を維持するために上記連続溶解槽では定期的な保全作
業を必要とする。また特開平1−141399号公報に
示される複数の燃料装荷かごを使用する連続溶解処理装
置では、使用済原子燃料の剪断片を装荷した複数の燃料
装荷かごを移動させる必要がある。この移動を実施する
ために、燃料装荷かご支持板、回転昇降装置、反転装置
等の装置を設けなければならず、処理に際しては溶解処
理の終了した未溶解残渣の入った燃料装荷かごを溶解槽
内から上昇させ、次いで反転させて内部の剪断片を排出
させた後、再び下降させて溶解槽内に戻すという複雑な
作業が必要となる。 また特開昭61−270695号公
報に示される溶解装置でも溶解反応が終了したと判断さ
れるバレルでは未溶解残渣を除去するためにバスケット
を抜出して交換を行うための装置を要し、これに伴う煩
わしい作業が必要となる。更に核燃料を取扱う装置は核
燃料の溶解槽を含めて、臨界安全管理上、核燃料の取扱
量や装置の直径、厚み、幅等の寸法や形状に制限があ
り、従来のバッチ式又は連続溶解槽ではいずれも処理能
力に限界がある。
However, the cylindrical melting tank is premised on batch processing, and in order to use this as a continuous processing apparatus, at least two batch type melting tanks are provided and these are alternately arranged. It is necessary to switch and use, or to increase the capacity of the one-time processing by increasing the capacity of the cylindrical dissolution tank and the storage tank of the dissolution liquid. In the former case, the switching operation becomes complicated, and in the latter case, there is a problem that the melting apparatus becomes large. Further, in both the screw type continuous dissolution tank and the water turbine bucket type continuous dissolution tank, the shaft for driving the screw or the water turbine bucket is provided so as to penetrate the dissolution tank. Sealing property is required to prevent leakage. In order to maintain the sealing property of the drive shaft, the continuous melting tank requires regular maintenance work. Also, in Japanese Patent Laid-Open No. 1-141399.
Continuous melt processing equipment using multiple fuel-loaded cages shown
In the installation, multiple fuels loaded with spent nuclear fuel shear fragments
You need to move the loading basket. Carry out this move
In order to support the fuel loading cage support plate, rotary lifting device, reversing device
It is necessary to install equipment such as
Dissolving tank with fuel loaded basket containing undissolved residue
Elevate from inside and then invert to expel internal shear fragments
After that, it is lowered again and returned to the dissolution tank.
Work is required. Also, JP-A-61-270695
The dissolution device indicated in the report also determined that the dissolution reaction was completed.
In the barrel is a basket to remove undissolved residue
Requires a device to remove and replace the
A little work is needed. Furthermore, the equipment that handles nuclear fuel, including the dissolution tank for nuclear fuel, is limited in terms of critical safety management in terms of the amount of nuclear fuel handled and the size and shape of the equipment such as diameter, thickness, width, etc. Both have a limited processing capacity.

【0004】本発明の目的は、コンパクトな形状で、か
つ臨界安全管理上問題を生じることなく、処理能力を任
意に設定でき、保全が容易な核燃料の連続溶解装置を提
供することにある。本発明の別の目的は、核燃料の未溶
解残渣を容易に除去し得る核燃料の連続溶解装置を提供
することにある。
An object of the present invention is to provide a continuous melting apparatus for nuclear fuel which has a compact shape, can be arbitrarily set with a processing capacity without causing a problem in criticality safety management, and is easy to maintain. Another object of the present invention is the unmelted nuclear fuel.
Providing a continuous melting device for nuclear fuel that can easily remove solution residues
To do.

【0005】[0005]

【課題を解決するための手段】上記目的を達成するため
に、本発明の構成を実施例に対応する図1及び図2に基
づいて説明する。本発明の核燃料の連続溶解装置は、
燃料の硝酸溶解液を貯溜可能な溶解槽11と、この記溶
解槽11の内部に複数の反応室15a〜15eを形成
し、かつ上位の反応室から下位の反応室に硝酸溶解液が
流れるように溶解槽11の底面に上方に向けて設けられ
た下部仕切板12と、最上位に位置する反応室15aに
設けられた核燃料の供給口13と、最下位に位置する反
応室15eに設けられた溶解液の排出口14と、反応室
15a〜15eに硝酸を供給する硝酸供給手段16と、
反応室15a〜15eに設けられ、反応室にガスを導入
してその硝酸溶解液を撹拌するガス導入手段19と、反
応室15a〜15eの温度を制御する温度制御手段22
を備えた核燃料の溶解装置である。 その特徴ある構成
は、溶解槽11が傾斜した底面11aを有し、貯えた前
記核燃料が臨界にならない厚さを有する平板状にかつ密
閉して形成され、溶解槽11の複数の反応室15a〜1
5eのそれぞれの底面11aに反応室15a〜15eの
底部に沈降した核燃料の未溶解残渣を取出す残渣取出管
17がバルブ24を介して接続され、最下位の反応室1
5eを除く反応室15a〜15e内に上方から下方に向
けて上位の反応室から下位の反応室への硝酸溶解液のシ
ョートパスを防止する上部仕切板18が設けられ、反応
室15a〜15eから廃ガスを排出する廃ガス排出手段
21が設けられたところにある。
In order to achieve the above object, the structure of the present invention will be described with reference to FIGS. 1 and 2 corresponding to the embodiments. Continuous melting apparatus of the nuclear fuel of the present invention, nuclear
A dissolution tank 11 capable of storing a nitric acid solution of fuel and a plurality of reaction chambers 15a to 15e are formed in the dissolution tank 11, and the nitric acid solution flows from the upper reaction chamber to the lower reaction chamber. A lower partition plate 12 provided on the bottom surface of the dissolution tank 11 facing upward, a nuclear fuel supply port 13 provided in the uppermost reaction chamber 15a, and a lowermost reaction chamber 15e. And a nitric acid supply means 16 for supplying nitric acid to the reaction chambers 15a to 15e.
Gas introducing means 19 provided in the reaction chambers 15a to 15e for introducing gas into the reaction chambers and stirring the nitric acid solution, and temperature control means 22 for controlling the temperature of the reaction chambers 15a to 15e.
And a melting device for nuclear fuel. Its characteristic structure
Has a bottom surface 11a where the dissolution tank 11 is inclined and
Nuclear fuel is flat and has a thickness that does not make it critical.
A plurality of reaction chambers 15 a to 1 of the dissolution tank 11 formed by being closed.
5e on the bottom surface 11a of each of the reaction chambers 15a-15e
Residue removal pipe for removing undissolved residue of nuclear fuel that has settled to the bottom
17 is connected via a valve 24, and the lowest reaction chamber 1
From the upper side to the lower side in the reaction chambers 15a to 15e except 5e.
The nitric acid solution from the upper reaction chamber to the lower reaction chamber.
An upper partition plate 18 is installed to prevent gating and
Waste gas discharge means for discharging waste gas from the chambers 15a to 15e
21 is provided.

【0006】なお、供給口13に供給される核燃料を核
燃料粉末と水とを混練したスラリーにすると、反応室1
5aで粉塵が発生せず、核燃料の供給口13での閉塞等
によるトラブルが減少するため、好ましい。また、反応
室の硝酸溶解液を撹拌するガスとして、空気の代わりに
NOxガスを各反応室に導入すると、撹拌効果に加えて
溶解反応を促進させ、かつヨウ素を追出す効果も生じる
ため、好ましい。
When the nuclear fuel supplied to the supply port 13 is made into a slurry in which nuclear fuel powder and water are kneaded, the reaction chamber 1
5a is preferable because no dust is generated and troubles due to blockage of the nuclear fuel supply port 13 are reduced. In addition, when NOx gas is introduced into each reaction chamber instead of air as a gas for stirring the nitric acid solution in the reaction chamber, the dissolution reaction is promoted in addition to the stirring effect, and iodine is expelled, which is preferable. .

【0007】[0007]

【作用】供給口13から供給された核燃料は溶解槽11
の反応室15a〜15eに貯えられた硝酸に溶解する。
硝酸溶解液は上部仕切板18によりショートパスするこ
となく、また下部仕切板12により十分な核燃料との反
応時間を与えられて上位の反応室から下位の反応室に流
動し、排出口14から排出される。反応室15a〜15
eの硝酸溶解液は硝酸供給手段16から供給される硝酸
によりその硝酸濃度が調整され、ガス導入手段19から
導入されるガスにより撹拌される。また温度制御手段2
2により反応温度が制御される。反応により生成した不
溶解残渣は残渣取出管17により取出され、廃ガスは廃
ガス排出手段21により排出される。
[Operation] The nuclear fuel supplied from the supply port 13 is the melting tank 11
Dissolved in nitric acid stored in the reaction chambers 15a to 15e.
The nitric acid-dissolved liquid flows from the upper reaction chamber to the lower reaction chamber without being short-passed by the upper partition plate 18 and given sufficient reaction time with the lower partition plate 12 to be discharged from the discharge port 14. To be done. Reaction chambers 15a-15
The nitric acid solution of e has its nitric acid concentration adjusted by the nitric acid supplied from the nitric acid supply means 16, and is stirred by the gas introduced from the gas introduction means 19. Also, the temperature control means 2
The reaction temperature is controlled by 2. The insoluble residue produced by the reaction is taken out by the residue take-out pipe 17, and the waste gas is discharged by the waste gas discharge means 21.

【0008】[0008]

【実施例】次に本発明の一実施例を図面に基づいて詳し
く説明する。図1及び図2に示すように、連続処理装置
の溶解槽11は傾斜した底面11aを有する。溶解槽1
1は核燃料の硝酸溶解液を貯溜可能であって、貯えた核
燃料が臨界にならない厚さを有する平板状に形成され
る。この例では厚さA(図2)は約23cmである。ま
た溶解層11の高さBは約3m、長さCは約2mである
(図1)。この溶解層11の内部にこの例では5つの反
応室15a,15b,15c,15d及び15eを形成
する4枚の下部仕切板12が溶解槽11の底面11aに
間隔をあけて鉛直方向に設けられる。これらの仕切板1
2は核燃料の硝酸溶解液が上位の反応室から下位の反応
室に流れるようにほぼ同一の高さを有する。最上位に位
置する反応室15aの上方には核燃料のシュート13a
が取付けられ、シュート上端には供給口13が設けられ
る。この例では供給口13に供給される核燃料は核燃料
粉末と水とを混練したスラリーである。最下位に位置す
る反応室15eの上部には硝酸溶解液の排出管14aが
取付けられる。排出管14aは排出口14を有する。
An embodiment of the present invention will be described in detail with reference to the drawings. As shown in FIGS. 1 and 2, the dissolution tank 11 of the continuous processing apparatus has an inclined bottom surface 11a. Dissolution tank 1
1 is capable of storing a nitric acid solution of nuclear fuel and is formed in a flat plate shape having a thickness such that the stored nuclear fuel does not become critical. In this example, the thickness A (FIG. 2) is about 23 cm. The height B of the dissolution layer 11 is about 3 m and the length C is about 2 m (FIG. 1). In this example, four lower partition plates 12 forming five reaction chambers 15a, 15b, 15c, 15d and 15e are provided in the dissolution layer 11 vertically on the bottom surface 11a of the dissolution tank 11 at intervals. . These partition plates 1
2 has approximately the same height so that the nitric acid solution of nuclear fuel flows from the upper reaction chamber to the lower reaction chamber. A nuclear fuel chute 13a is provided above the uppermost reaction chamber 15a.
Is attached, and a supply port 13 is provided at the upper end of the chute. In this example, the nuclear fuel supplied to the supply port 13 is a slurry obtained by kneading nuclear fuel powder and water. A discharge pipe 14a for the nitric acid solution is attached to the upper part of the reaction chamber 15e located at the lowest position. The discharge pipe 14a has a discharge port 14.

【0009】溶解層11の外側には硝酸の供給管16が
配管される。供給管16はバルブ23を介して5つの反
応室15a〜15eの上部に導入される。反応室15a
〜15eの各底部には核燃料の未溶解残渣を反応室から
取出す残渣取出管17がバルブ24を介して接続され、
溶解槽11の底面に沿って配管される。最下位の反応室
15eを除く4つの反応室15a〜15d内には上方か
ら下方に向けて4枚の上部仕切板18が溶解槽11の頂
面に間隔をあけて設けられる。これらの仕切板18の下
端は下部仕切板12の上端より低い位置まで延び、上位
の反応室から下位の反応室への硝酸溶解液のショートパ
スを防止するようになっている。また反応室15a〜1
5eの各底部にガス導入管19が貫通して設けられ、各
反応室内に突出するその導入管端部にはガス噴出部26
が接続される。このガス導入管19にはこの例ではNO
xガスが図示しないコンプレッサにより圧送される。反
応室15a〜15eの上方の溶解層11の頂部には反応
により生じた廃ガスを排出する廃ガス排出管21が接続
される。更に溶解槽11の外側面には各反応室の温度を
上昇させるヒータ22aが設けられる。ヒータ22aは
コントローラ22により硝酸溶解液の温度が一定となる
ように制御される。
A supply pipe 16 for nitric acid is provided outside the dissolution layer 11. The supply pipe 16 is introduced into the upper portions of the five reaction chambers 15a to 15e via the valve 23. Reaction chamber 15a
A residue extraction pipe 17 for extracting the undissolved residue of the nuclear fuel from the reaction chamber is connected to each bottom of each of ~ 15e via a valve 24,
It is arranged along the bottom surface of the dissolution tank 11. In the four reaction chambers 15a to 15d except the lowest reaction chamber 15e, four upper partition plates 18 are provided from the upper side to the lower side at intervals on the top surface of the dissolution tank 11. The lower ends of these partition plates 18 extend to a position lower than the upper ends of the lower partition plates 12 to prevent a short path of the nitric acid solution from the upper reaction chamber to the lower reaction chamber. Also, the reaction chambers 15a-1
5e is provided with a gas introducing pipe 19 penetrating each bottom thereof, and a gas ejecting portion 26 is provided at the end of the introducing pipe protruding into each reaction chamber.
Is connected. This gas introduction pipe 19 has NO in this example.
The x gas is pumped by a compressor (not shown). A waste gas discharge pipe 21 for discharging the waste gas generated by the reaction is connected to the top of the dissolution layer 11 above the reaction chambers 15a to 15e. Further, a heater 22a for raising the temperature of each reaction chamber is provided on the outer surface of the melting tank 11. The heater 22a is controlled by the controller 22 so that the temperature of the nitric acid solution is constant.

【0010】このように構成された装置の動作を説明す
る。先ず、所定の硝酸濃度に調整された硝酸水溶液を硝
酸供給管16を介して反応室15a〜15eに供給し、
図示する水位まで貯溜しておく。またコントローラ22
はヒータ22aを制御して反応室15a〜15eの温度
を硝酸水溶液の沸点近傍に維持する。次いで、核燃料粉
末を水と混練してスラリーにし、供給口13から反応室
15aに供給する。この核燃料粉末は核燃料の製造工程
で発生する核燃料スクラップ粉末でもよいし、或いは使
用済み核燃料の再処理工程で発生する核燃料粉末でもよ
い。核燃料粉末をスラリー化することにより、反応室1
5aで粉塵が発生せず、シュート13aが核燃料粉末で
詰まることがなくなる。
The operation of the apparatus thus configured will be described. First, an aqueous nitric acid solution adjusted to a predetermined nitric acid concentration is supplied to the reaction chambers 15a to 15e through the nitric acid supply pipe 16,
Store up to the water level shown. Also the controller 22
Controls the heater 22a to maintain the temperature of the reaction chambers 15a to 15e near the boiling point of the nitric acid aqueous solution. Next, the nuclear fuel powder is kneaded with water to form a slurry, which is supplied from the supply port 13 to the reaction chamber 15a. The nuclear fuel powder may be nuclear fuel scrap powder generated in the nuclear fuel manufacturing process, or nuclear fuel powder generated in the spent nuclear fuel reprocessing process. By converting the nuclear fuel powder into a slurry, the reaction chamber 1
No dust is generated at 5a, and the chute 13a is not clogged with the nuclear fuel powder.

【0011】ガス導入管19に圧送されたNOxガスが
ガス噴出部26から反応室15aに導入され、核燃料ス
ラリーと硝酸水溶液は撹拌されて核燃料粉末の溶解が始
まる。このNOxガスの導入により使用済み核燃料に含
まれていたヨウ素を追出すことができる。放射性を有す
るヨウ素がこの溶解工程後で抽出されるウラニウムやプ
ロトニウムに紛れ込むとウラニウムやプロトニウムの取
扱いを困難にし、また再処理の最終仮焼時に好ましくな
いガス状化合物に転換するため、溶解装置の次にヨウ素
追出し槽を従来設けていたが、このNOxガスの導入に
よりヨウ素追出し槽は不要になる。
The NOx gas pressure-fed to the gas introduction pipe 19 is introduced into the reaction chamber 15a from the gas injection portion 26, the nuclear fuel slurry and the nitric acid aqueous solution are agitated, and the nuclear fuel powder starts to dissolve. By introducing this NOx gas, iodine contained in the spent nuclear fuel can be expelled. If radioactive iodine is mixed with uranium or protonium extracted after this dissolution step, it will be difficult to handle uranium or protonium, and it will be converted into an undesired gaseous compound at the time of final calcination of reprocessing. Conventionally, an iodine purging tank was conventionally provided, but the introduction of this NOx gas makes the iodine purging tank unnecessary.

【0012】また核燃料粉末の溶解により、硝酸溶解液
の硝酸濃度が変化すると、バルブ23を開いて硝酸を硝
酸溶解液に加えてその濃度を調整する。反応室15aか
ら下部仕切板12を越えて硝酸溶解液が反応室15bに
流入する。ここで上部仕切板18によって、硝酸溶解液
は上位の反応室15aから下位の反応室15bにショー
トパスすることなく、十分に時間をかけて反応が行われ
る。続いて上位の反応室からオーバーフローの状態の硝
酸溶解液は順次下部仕切板12を越えて下位の反応室に
流れ落ちる。この下位の反応室においても、上位の反応
室の場合と同様に、NOxガスがガス噴出部26から導
入され、かつ供給管16から供給される硝酸により濃度
調整される。最下位の反応室15eで完全に核燃料粉末
は硝酸に溶解され、排出管14aから排出される。この
装置では1日当り4トンの核燃料を連続して溶解するこ
とができる。反応室15a〜15eで沈降した未溶解残
渣は傾斜した底面に沿って自重により残渣取出管17の
取出し口に集まり、バルブ24を間欠的に開くことによ
り取出管17を通って溶解槽11外に排出される。反応
室15a〜15eで生成した廃ガスは排出管21を通し
て排出される。
When the nitric acid concentration of the nitric acid solution changes due to the dissolution of the nuclear fuel powder, the valve 23 is opened and nitric acid is added to the nitric acid solution to adjust the concentration. The nitric acid solution flows from the reaction chamber 15a through the lower partition plate 12 into the reaction chamber 15b. Here, by the upper partition plate 18, the nitric acid solution does not short-pass from the upper reaction chamber 15a to the lower reaction chamber 15b, and the reaction is carried out for a sufficient time. Then, the nitric acid solution in an overflow state from the upper reaction chamber sequentially flows over the lower partition plate 12 and flows down to the lower reaction chamber. In this lower reaction chamber as well, as in the case of the upper reaction chamber, the NOx gas is introduced from the gas ejection portion 26 and the concentration thereof is adjusted by the nitric acid supplied from the supply pipe 16. The nuclear fuel powder is completely dissolved in nitric acid in the lowest reaction chamber 15e, and is discharged from the discharge pipe 14a. This device can continuously dissolve 4 tons of nuclear fuel per day. The undissolved residue settled in the reaction chambers 15a to 15e gathers at the outlet of the residue outlet pipe 17 by its own weight along the inclined bottom surface, and is intermittently opened through the outlet pipe 17 to the outside of the dissolution tank 11 by opening the valve 24 intermittently. Is discharged. The waste gas generated in the reaction chambers 15a to 15e is discharged through the discharge pipe 21.

【0013】なお、上記例では核燃料粉末を予め水と混
練して、スラリーにしたが、溶解処理量が少なければ、
特別にスラリーにせずに、粉末のまま供給口から供給す
ることもできる。また、硝酸溶解液を撹拌するガスとし
て、NOxガスを挙げたが、撹拌のためだけであれば、
空気でもよい。更に、温度制御手段としてヒータとコン
トローラを例示したが、ヒータに加えて過熱状態を回避
するために硝酸溶解液の冷却手段を設けてもよい。
In the above example, the nuclear fuel powder was previously kneaded with water to form a slurry, but if the dissolution treatment amount is small,
It is also possible to supply the powder as it is from the supply port without making it into a slurry. Moreover, although NOx gas was mentioned as a gas for stirring the nitric acid solution, if only for stirring,
It may be air. Further, although the heater and the controller are illustrated as the temperature control means, a cooling means for the nitric acid solution may be provided in addition to the heater in order to avoid an overheated state.

【0014】[0014]

【発明の効果】以上述べたように、本発明は次の多くの
優れた効果を奏する。 供給した核燃料が上位の反応室から下位の反応室に
順次溶解度を高めながら移動して排出されるため、核燃
料を連続して溶解処理することができる。 溶解層が貯溜する核燃料の臨界にならない平板状で
あるため、臨界安全管理上問題を生じない。 溶解槽の長さC(図1)を延長してもその厚さA
(図2)を変えなければ臨界安全性は保たれるため、溶
解槽の長さを変えて反応室を増減することにより、溶解
反応に必要な滞留時間や処理能力に合致した連続処理装
置を容易に製作できる。 上部仕切板により、未溶解の核燃料粉末を含む硝酸
溶解液はショートパスすることなく、下位の反応室に流
れ落ちるまでの間に各反応室内で十分な反応時間が与え
られる。 反応室毎に硝酸濃度、空気又はNOxガスの濃度や
量、或いは核燃料の硝酸溶解液の温度を制御可能なた
め、各反応室における溶解反応を正確に制御できる。 溶解槽は傾斜した底面を有するため、各反応室の底
部から沈降性の未溶解残渣を間欠的に容易に取出すこと
ができる。 従来の連続溶解装置におけるような駆動部がないた
め、装置の保全が容易である。 核燃料を核燃料粉末を水と混練したスラリーの形態
で反応室に供給すれば、粉塵の発生がなく、供給口を閉
塞するなどのトラブルが減少する。 従来の再処理工程では核燃料の溶解装置の次にヨウ
素追出し槽を設けていたものが、反応室の硝酸溶解液に
NOxガスを吹込めば、核燃料に含まれるヨウ素を追出
すことができ、従来のヨウ素追出し槽が不要となる。
As described above, the present invention has the following many excellent effects. Since the supplied nuclear fuel moves and is discharged from the upper reaction chamber to the lower reaction chamber in order of increasing solubility, the nuclear fuel can be continuously dissolved. Since the dissolved layer is a flat plate shape that does not make the stored nuclear fuel critical, there is no problem in criticality safety management. Even if the length C (Fig. 1) of the melting tank is extended, its thickness A
Since the criticality safety is maintained unless (Fig. 2) is changed, the length of the dissolution tank is changed and the number of reaction chambers is increased or decreased to create a continuous processing device that matches the residence time and processing capacity required for the dissolution reaction. Easy to make. The upper partition plate gives a sufficient reaction time in each reaction chamber until the nitric acid solution containing undissolved nuclear fuel powder flows into the lower reaction chamber without short-passing. Since the nitric acid concentration, the concentration or amount of air or NOx gas, or the temperature of the nitric acid solution of nuclear fuel can be controlled for each reaction chamber, the dissolution reaction in each reaction chamber can be accurately controlled. Since the dissolution tank has a sloping bottom surface, it is possible to easily and intermittently take out the settling undissolved residue from the bottom of each reaction chamber. The maintenance of the device is easy because there is no driving part as in the conventional continuous melting device. When the nuclear fuel is supplied to the reaction chamber in the form of a slurry in which nuclear fuel powder is kneaded with water, no dust is generated and troubles such as blocking the supply port are reduced. In the conventional reprocessing process, an iodine purging tank was installed next to the nuclear fuel dissolving device. However, if NOx gas is blown into the nitric acid dissolving liquid in the reaction chamber, iodine contained in the nuclear fuel can be expelled. It eliminates the need for iodine discharge tank.

【図面の簡単な説明】[Brief description of drawings]

【図1】本発明実施例の核燃料の連続溶解装置の構成
図。
FIG. 1 is a configuration diagram of a continuous melting apparatus for nuclear fuel according to an embodiment of the present invention.

【図2】そのD−D線断面図。FIG. 2 is a sectional view taken along the line DD.

【符号の説明】[Explanation of symbols]

11 溶解槽 11a 溶解槽の底面 12 下部仕切板 13 核燃料の供給口 14 硝酸溶解液の排出口 15a〜15e 反応室 16 硝酸供給管(硝酸供給手段) 17 残渣取出管(残渣取出手段) 18 上部仕切板 19 ガス導入管(ガス導入手段) 21 廃ガス排出管(廃ガス排出手段) 22 コントローラ(温度制御手段) 22a ヒータ 11 dissolution tank 11a bottom surface of dissolution tank 12 lower partition plate 13 supply port for nuclear fuel 14 discharge port for nitric acid dissolved solution 15a to 15e reaction chamber 16 nitric acid supply pipe (nitric acid supply means) 17 residue extraction pipe (residue extraction means) 18 upper partition Plate 19 Gas introduction pipe (gas introduction means) 21 Waste gas discharge pipe (waste gas discharge means) 22 Controller (temperature control means) 22a Heater

───────────────────────────────────────────────────── フロントページの続き (56)参考文献 特開 昭63−61194(JP,A) 特開 平1−141399(JP,A) ─────────────────────────────────────────────────── ─── Continuation of the front page (56) References JP-A-63-61194 (JP, A) JP-A-1-141399 (JP, A)

Claims (3)

(57)【特許請求の範囲】(57) [Claims] 【請求項1】核燃料の硝酸溶解液を貯溜可能な溶解槽(1
1)と、 前記溶解槽(11)の内部に複数の反応室(15a,15b,15c,15
d,15e)を形成し、かつ上位の反応室から下位の反応室に
前記硝酸溶解液が流れるように前記溶解槽(11)の底面に
上方に向けて設けられた下部仕切板(12)と、 最上位に位置する反応室(15a)に設けられた核燃料の供
給口(13)と、 最下位に位置する反応室(15e)に設けられた前記溶解液
の排出口(14)と、 前記反応室(15a,15b,15c,15d,15e)に硝酸を供給する硝
酸供給手段(16)と、 前記反応室(15a,15b,15c,15d,15e)に設けられ、前記反
応室にガスを導入してその硝酸溶解液を撹拌するガス導
入手段(19)と、 前記反応室(15a,15b,15c,15d,15e)の温度を制御する温
度制御手段(22)とを備えた核燃料の溶解装置において、 前記溶解槽(11)が傾斜した底面(11a)を有し、貯えた前
記核燃料が臨界にならない厚さを有する平板状にかつ密
閉して形成され、 前記溶解槽(11)の複数の反応室(15a,15b,15c,15d,15e)
のそれぞれの底面(11a)に前記反応室(15a,15b,15c,15d,
15e)の底部に沈降した前記核燃料の未溶解残渣を取出す
残渣取出管(17)がバルブ(24)を介して接続され、 最下位の反応室(15e)を除く前記反応室(15a,15b,15c,15
d)内に上方から下方に向けて上位の反応室から下位の反
応室への前記硝酸溶解液のショートパスを防止する上部
仕切板(18)が設けられ、 前記反応室(15a,15b,15c,15d,15e)から廃ガスを排出す
る廃ガス排出手段(21)が 設けられたことを特徴とする核燃料の連続溶解装置。
1. A dissolution tank capable of storing a nitric acid solution of nuclear fuel (1
1) and a plurality of reaction chambers (15a, 15b, 15c, 15) inside the dissolution tank (11).
d, 15e), and a lower partition plate (12) provided upward on the bottom of the dissolution tank (11) so that the nitric acid solution flows from the upper reaction chamber to the lower reaction chamber. A supply port (13) for the nuclear fuel provided in the reaction chamber (15a) located at the top, and a discharge port (14) for the solution provided in the reaction chamber (15e) located at the bottom, Nitric acid supply means (16) for supplying nitric acid to the reaction chamber (15a, 15b, 15c, 15d, 15e), and the reaction chamber (15a, 15b, 15c, 15d, 15e) is provided, the reaction chamber is a gas Dissolution of nuclear fuel provided with gas introduction means (19) for introducing and stirring the nitric acid solution, and temperature control means (22) for controlling the temperature of the reaction chambers (15a, 15b, 15c, 15d, 15e) In the device, the melting tank (11) has an inclined bottom surface (11a) and
Nuclear fuel is flat and has a thickness that does not make it critical.
A plurality of reaction chambers (15a, 15b, 15c, 15d, 15e) of the dissolution tank (11) that are formed by being closed.
On the bottom surface (11a) of each of the reaction chambers (15a, 15b, 15c, 15d,
Take out the undissolved residue of the nuclear fuel settled at the bottom of 15e)
The residue extraction pipe (17) is connected through a valve (24), and the reaction chambers (15a, 15b, 15c, 15) except the lowest reaction chamber (15e) are connected.
d) Inside the upper reaction chamber from the upper reaction chamber to the lower reaction chamber
The upper part that prevents the short path of the nitric acid solution to the reaction chamber
A partition plate (18) is provided to discharge waste gas from the reaction chambers (15a, 15b, 15c, 15d, 15e).
An apparatus for continuously melting nuclear fuel, characterized in that a waste gas discharge means (21) is provided.
【請求項2】供給口(13)に供給される核燃料は核燃料粉
末と水とを混練したスラリーである請求項1記載の核燃
料の連続溶解装置。
2. The continuous melting apparatus for nuclear fuel according to claim 1, wherein the nuclear fuel supplied to the supply port (13) is a slurry prepared by kneading nuclear fuel powder and water.
【請求項3】ガス導入手段(19)で反応室内に導入される
ガスは空気又はNOxガスである請求項1記載の核燃料
の連続溶解装置。
3. The continuous melting apparatus for nuclear fuel according to claim 1, wherein the gas introduced into the reaction chamber by the gas introducing means (19) is air or NOx gas.
JP9593692A 1992-03-23 1992-03-23 Continuous melting device for nuclear fuel Expired - Fee Related JP2500408B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP9593692A JP2500408B2 (en) 1992-03-23 1992-03-23 Continuous melting device for nuclear fuel

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP9593692A JP2500408B2 (en) 1992-03-23 1992-03-23 Continuous melting device for nuclear fuel

Publications (2)

Publication Number Publication Date
JPH05264780A JPH05264780A (en) 1993-10-12
JP2500408B2 true JP2500408B2 (en) 1996-05-29

Family

ID=14151159

Family Applications (1)

Application Number Title Priority Date Filing Date
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Country Link
JP (1) JP2500408B2 (en)

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* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP4940114B2 (en) * 2007-11-30 2012-05-30 株式会社東芝 Criticality safety management method for continuous dissolution tank in reprocessing facility
JP5422688B2 (en) * 2012-02-24 2014-02-19 株式会社東芝 Criticality safety management method for continuous dissolution tank in reprocessing facility

Family Cites Families (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS61270695A (en) * 1985-05-27 1986-11-29 三菱重工業株式会社 Nulcear fuel melter

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