JPH0467639B2 - - Google Patents
Info
- Publication number
- JPH0467639B2 JPH0467639B2 JP59129001A JP12900184A JPH0467639B2 JP H0467639 B2 JPH0467639 B2 JP H0467639B2 JP 59129001 A JP59129001 A JP 59129001A JP 12900184 A JP12900184 A JP 12900184A JP H0467639 B2 JPH0467639 B2 JP H0467639B2
- Authority
- JP
- Japan
- Prior art keywords
- tube
- melting
- slab
- pipe
- nuclear fuel
- 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
Classifications
-
- Y—GENERAL 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
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
-
- Y—GENERAL 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
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02W—CLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
- Y02W30/00—Technologies for solid waste management
- Y02W30/50—Reuse, recycling or recovery technologies
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- Manufacture And Refinement Of Metals (AREA)
Description
【発明の詳細な説明】
[産業上の利用分野]
本発明は使用済核燃料の溶解装置に係り、特に
使用済核燃料の溶解が迅速に行なえるよう改良さ
れた使用済核燃料の溶解装置に関する。DETAILED DESCRIPTION OF THE INVENTION [Industrial Application Field] The present invention relates to a spent nuclear fuel melting device, and more particularly to a spent nuclear fuel melting device that has been improved so that spent nuclear fuel can be melted quickly.
[従来技術]
従来、使用済の酸化ウラニウム等の核燃料を溶
解処理する場合、使用済核燃料を短く切断し、こ
れを硝酸等の酸溶液中に浸漬して溶解させてい
る。[Prior Art] Conventionally, when dissolving spent nuclear fuel such as uranium oxide, the spent nuclear fuel is cut into short pieces and immersed in an acid solution such as nitric acid to dissolve the spent nuclear fuel.
第2図は従来の使用済核燃料の溶解装置を示す
概略的な断面図である。 FIG. 2 is a schematic cross-sectional view showing a conventional spent nuclear fuel melting device.
この使用済核燃料の溶解装置は、筒状の溶解管
12と、溶解管12中に装入された篭体14とか
らなる。篭体14は多孔性であり、通常、ステン
レス等の金網製筒状体、あるいは、多数の孔が穿
設された金属製筒状体等が用いられる。なお各図
において、篭体14が多孔性であることを示すた
めに、この篭体14は破線で示されている。 This spent nuclear fuel melting device consists of a cylindrical melting tube 12 and a casing 14 inserted into the melting tube 12. The casing 14 is porous, and is usually a cylindrical body made of wire mesh such as stainless steel, or a cylindrical body made of metal with a large number of holes. In each figure, the casing 14 is shown with a broken line to indicate that the casing 14 is porous.
溶解管12の側面の複数箇所は、スラブと称さ
れる液槽16に連通管18,20,22,24で
接続されている。また、溶解管12の下部には、
酸素ガス吹込管26が設置されている。そして、
溶解管12及びスラブ16中には硝酸等の酸溶液
が充填されている。 A plurality of locations on the side surface of the melting tube 12 are connected to a liquid tank 16 called a slab through communication tubes 18, 20, 22, and 24. In addition, at the bottom of the dissolution tube 12,
An oxygen gas blowing pipe 26 is installed. and,
The melting tube 12 and the slab 16 are filled with an acid solution such as nitric acid.
吹込管26から酸素ガスを吹き込むと、このガ
スは溶解管12中を上昇し、これに伴つて溶解管
12中の液も上昇して連通管22からスラブ16
内に入り、連通管18から再び溶解管12中に戻
り、循環する。 When oxygen gas is blown from the blowing pipe 26, this gas rises in the melting pipe 12, and along with this, the liquid in the melting pipe 12 also rises and flows from the communicating pipe 22 to the slab 16.
It returns to the melting tube 12 through the communication tube 18 and circulates.
なお液の一部は、中間のレベルの設置された連
通管20を通つてスラブ16と溶解管12とを往
来する。連通管24はガス流通用のものであり、
吹込管26から溶解管12内に吹き込まれた酸素
ガスが、この連通管24を通り、スラブ16内に
入る。 A portion of the liquid passes between the slab 16 and the melting tube 12 through a communication tube 20 installed at an intermediate level. The communication pipe 24 is for gas distribution,
Oxygen gas blown into the melting tube 12 from the blowing pipe 26 passes through the communication pipe 24 and enters the slab 16.
篭体14中には、短く切断された使用済核燃料
が装入されており、次のような化学反応式に従い
次第に酸溶液に溶解してゆく。 Spent nuclear fuel cut into short pieces is charged in the casing 14, and is gradually dissolved in an acid solution according to the following chemical reaction formula.
UO3+2HNO3+1/2O2→
UO2(NO3)2+H2O
なおスラブ16には、図示はされていないが、
核燃料が溶け込んだ酸溶液の抜出手段、新しい酸
溶液の供給手段、不溶解性のスラツジの抜出手段
等が設置されている。酸化ウラニウム核燃料は、
通常、ステンレス等のパイプに挿入されている
が、この切断屑や酸化ウラニウム棒中の不溶解分
等がスラツジとなつて、酸溶液中に含まれるので
ある。 UO 3 +2HNO 3 +1/2O 2 → UO 2 (NO 3 ) 2 +H 2 O Although not shown in the slab 16,
A means for extracting an acid solution in which nuclear fuel has been dissolved, a means for supplying a new acid solution, a means for extracting insoluble sludge, etc. are installed. Uranium oxide nuclear fuel is
Usually, it is inserted into a pipe made of stainless steel or the like, but the cutting waste and undissolved matter in the uranium oxide rod become sludge and are included in the acid solution.
また酸化ウラニウム棒が挿入されたパイプそれ
自体は酸溶液には溶けず、酸化ウラニウムが溶け
出した後でも篭体14中に残留するので、溶解終
了後、篭体14を引き上げ、残つたパイプを取り
出す。 Furthermore, the pipe itself into which the uranium oxide rod is inserted does not dissolve in the acid solution and remains in the case 14 even after the uranium oxide has dissolved, so after the melting is finished, the case 14 is pulled up and the remaining pipe is removed. Take it out.
[発明が解決しようとする問題点]
上記従来の使用済核燃料の溶解管においては、
連通管18から溶解管12中に入り、その中を上
昇する酸溶液は、篭体14の底面を通り、更に篭
体14内を上昇しようとする。[Problems to be solved by the invention] In the above-mentioned conventional spent nuclear fuel melting tube,
The acid solution entering the dissolution tube 12 from the communication tube 18 and rising therein passes through the bottom surface of the casing 14 and tries to rise further inside the casing 14 .
ところが、篭体14内には、短く切断された使
用済核燃料が多数装入されているので、酸素ガス
吹込量を増加し液の上昇速度を大きくしようとし
ても、気泡の上昇量に上限があり、所定量以上の
酸素ガスを吹き込むことができなかつた。 However, since a large amount of spent nuclear fuel that has been cut into short pieces is charged into the casing 14, even if an attempt is made to increase the rate of rise of the liquid by increasing the amount of oxygen gas blown, there is an upper limit to the amount of bubbles that can rise. However, it was not possible to inject more than a predetermined amount of oxygen gas.
そのため、溶解管12中を流れて使用済核燃料
と接触する酸溶液の流通量に上限があり、使用済
核燃料の溶解にかなり長い時間を要するという問
題があつた。 Therefore, there is an upper limit to the flow rate of the acid solution that flows through the melting tube 12 and comes into contact with the spent nuclear fuel, resulting in the problem that it takes a considerably long time to melt the spent nuclear fuel.
また、上記従来例においては、溶解管12とス
ラブ16の下部との連通管18が湾曲して、部分
的に勾配が無いか又は極めて小さい部分があり、
そのため、スラツジが貯まり易いという問題があ
つた。 In addition, in the above conventional example, the communication pipe 18 between the melting pipe 12 and the lower part of the slab 16 is curved, and there are parts where there is no slope or where the slope is extremely small.
Therefore, there was a problem that sludge was likely to accumulate.
[問題点を解決するための手段]
上記従来の問題点を解決するために、本発明
は、第1図、第3図等に示す如く、溶解される使
用済核燃料保持用の篭体が内部に装入された溶解
管12と、この溶解管12に対して複数本の連通
管18,22,24で連結されたスラブ16とを
有する使用済核燃料の溶解装置において、スラブ
16を筒状とし、このスラブ16の底部から酸素
ガス又は酸素を含む気体を吹き込んで、酸溶液を
スラブ16内では上向流となり溶解管12内では
下向流となるように循環させる。また溶解管12
からスラブ16へ液を流す連通管18を、直管又
は直管状とし、かつこの連通管18を傾斜させて
設置する。そして、溶解管12の下部に接続して
スラツジ捕集部28を設ける。[Means for Solving the Problems] In order to solve the above-mentioned conventional problems, the present invention provides that, as shown in FIGS. 1 and 3, the spent nuclear fuel casing to be melted is In a spent nuclear fuel melting device having a melting tube 12 charged into the melting tube 12 and a slab 16 connected to the melting tube 12 by a plurality of communication tubes 18, 22, 24, the slab 16 is cylindrical. Oxygen gas or a gas containing oxygen is blown into the bottom of the slab 16 to circulate the acid solution so that it flows upward within the slab 16 and flows downward within the melting tube 12. Also, the melting tube 12
A communication pipe 18 through which the liquid flows from the to the slab 16 is a straight pipe or a straight pipe shape, and the communication pipe 18 is installed at an angle. A sludge collection section 28 is provided connected to the lower part of the melting tube 12.
溶解管12の底部は開口部とされ、この開口部
分を覆う様に、スラツジ捕集部28としての筒形
の容器状部材34が固着されている。容器状部材
34は太径部34a、細径部34b及びテーパ部
34cからなり、テーパ部34cと溶解管12の
開口縁との間に間〓が形成されている。また太径
部34aの上端は溶解管の下部外周面に固着され
ている。そして前記の連通管18はこの太径部3
4aに接続されている。 The bottom of the melting tube 12 is an opening, and a cylindrical container-like member 34 serving as a sludge collecting section 28 is fixed so as to cover this opening. The container-shaped member 34 consists of a large diameter part 34a, a small diameter part 34b, and a tapered part 34c, and a gap is formed between the tapered part 34c and the opening edge of the melting tube 12. Further, the upper end of the large diameter portion 34a is fixed to the lower outer peripheral surface of the melting tube. The communication pipe 18 is connected to this large diameter portion 3.
4a.
[作用]
スラブ16の底部から吹き込まれた気体がスラ
ブ16中を上昇すると、これに伴つてスラブ16
内の酸溶液が上向きに流れ、連通管22を経て溶
解管12内に入る。溶解管12内では酸溶液は下
向きに流れ、その途中で使用済核燃料の酸化ウラ
ニウムを溶解し、スラツジ捕集部28でスラツジ
が分離された後、連通管18からスラブ16内に
戻る。[Function] When the gas blown from the bottom of the slab 16 rises in the slab 16, the slab 16
The acid solution inside flows upward and enters the dissolution tube 12 through the communication tube 22. The acid solution flows downward in the melting tube 12, dissolves the uranium oxide of the spent nuclear fuel along the way, and after the sludge is separated in the sludge collection section 28, it returns into the slab 16 through the communication tube 18.
このような本発明の使用済核燃料の溶解装置に
おいては、スラブ16内に気体が吹き込まれるの
で、多量の気体を吹き込んで酸溶液の循環量を増
大させることができる。そのため、使用済核燃料
に多量の酸溶液が接触するようになり、使用済核
燃料の溶解速度が大きくなる。また、多量の気体
を吹き込むので、酸素ガスの替わりに空気を吹き
込んでも、酸化ウラニウムの溶解に必要な酸素を
十分に供給でき、高価な酸素ガスの使用の必要が
ない。 In the spent nuclear fuel melting apparatus of the present invention, gas is blown into the slab 16, so that a large amount of gas can be blown to increase the amount of acid solution circulated. Therefore, a large amount of acid solution comes into contact with the spent nuclear fuel, increasing the rate of dissolution of the spent nuclear fuel. Furthermore, since a large amount of gas is blown into the system, even if air is blown in instead of oxygen gas, the oxygen necessary for dissolving uranium oxide can be sufficiently supplied, and there is no need to use expensive oxygen gas.
また、使用済核燃料との接触により液中に含ま
れるようになつたスラツジは、溶解管12の下部
に位置する捕集部ですぐに捕集されるので、液中
のスラツジ含有量が小さくなる。そして、連通管
18が傾斜して設置されており、従来の如く勾配
の小さい部分が無いので、連通管18にスラツジ
が貯まることが無い。 In addition, the sludge that has come into contact with the spent nuclear fuel and is included in the liquid is immediately collected in the collection section located at the bottom of the melting tube 12, so the sludge content in the liquid is reduced. . Furthermore, since the communication pipe 18 is installed at an angle and there is no part with a small slope unlike the conventional system, sludge does not accumulate in the communication pipe 18.
[実施例] 以下図面を参照して実施例について説明する。[Example] Examples will be described below with reference to the drawings.
第1図は本発明の第1の実施例を示す使用済核
燃料の溶解装置の概略的な縦断面図である。 FIG. 1 is a schematic vertical sectional view of a spent nuclear fuel melting apparatus showing a first embodiment of the present invention.
第1図において、溶解管12の内周面の中間レ
ベルの部分にリング13が設けられ、篭体14が
このリング13に掛止されている。 In FIG. 1, a ring 13 is provided at an intermediate level on the inner circumferential surface of the melting tube 12, and a housing 14 is hooked onto this ring 13.
溶解管12は、連通管18,22,24によ
り、その側面部がスラブ16に接続されている。
連通管18は、本実施例では直管が用いられ、ス
ラブ16から溶解管12に向つて下り勾配となる
よう設置されている。連通管24は溶解管12の
上部のレベルの部分に、また連通管22は篭体1
4の頂部よりも若干上方のレベルの部分に、それ
ぞれ設けられている。 The melting tube 12 has its side surface connected to the slab 16 through communication tubes 18 , 22 , and 24 .
In this embodiment, the communication pipe 18 is a straight pipe, and is installed so as to have a downward slope from the slab 16 toward the melting pipe 12. The communication tube 24 is located at the upper level of the melting tube 12, and the communication tube 22 is connected to the housing 1.
4, respectively, at a level slightly above the top.
本実施例では、溶解管12の側周面にはジヤケ
ツト30,32が設けられ、酸溶液を必要に応じ
冷却し又は加熱するために、冷却水又は加熱水が
流通される。 In this embodiment, jackets 30 and 32 are provided on the side circumferential surface of the dissolution tube 12, through which cooling water or heated water flows to cool or heat the acid solution as required.
また、溶解管12の下部にはスラツジ捕集部2
8が設けられている。この捕集部28の構成を次
に説明すると、溶解管12の底部が開口部とさ
れ、この開口部分を覆う様に筒形の容器状部材3
4が固着されている。容器状部材34は太径部3
4a、細径部34b及びテーパ部34cからな
り、テーパ部34cと溶解管12の開口縁との間
に間隙が形成されている。また太径部34aの上
端は溶解管の下部外周面に固着されている。そし
て前記の連通管18はこの太径部34aに接続さ
れている。 In addition, a sludge collection section 2 is provided at the bottom of the melting tube 12.
8 is provided. The configuration of this collection section 28 will be explained next. The bottom of the dissolution tube 12 is an opening, and a cylindrical container-like member 3 is arranged to cover this opening.
4 is fixed. The container-shaped member 34 has a large diameter portion 3
4a, a narrow diameter portion 34b, and a tapered portion 34c, and a gap is formed between the tapered portion 34c and the opening edge of the melting tube 12. Further, the upper end of the large diameter portion 34a is fixed to the lower outer peripheral surface of the melting tube. The communication pipe 18 is connected to this large diameter portion 34a.
溶解管12内を下向きに流れてきた酸溶液は、
その下端開口縁を回り込んで太径部34aの内側
部に入り、スラツジは、酸溶液の回り込みに際し
分離され、容器状部材34の底部に沈殿する。 The acid solution flowing downward in the dissolution tube 12 is
The sludge goes around the opening edge of the lower end and enters the inside of the large diameter part 34a, and is separated when the acid solution goes around and settles at the bottom of the container-like member 34.
容器状部材34の底部には、沈殿したスラツジ
を取り出し易くするために、カツプ状スラツジ受
36が装入されている。 A cup-shaped sludge receiver 36 is inserted into the bottom of the container-shaped member 34 in order to facilitate taking out the settled sludge.
篭体14としては、ステンレス等、耐酸性の金
網の有底筒状体、あるいは、周壁面と底面とに多
数の孔を穿設した有底筒状体等、要するに液がそ
の周壁面と底面とを通過でき、かつ使用済核燃料
の切断体をその内部に保持できる構造のものが用
いられる。 The housing 14 may be a bottomed cylindrical body made of acid-resistant wire mesh made of stainless steel or the like, or a bottomed cylindrical body with a number of holes bored in the peripheral wall surface and the bottom surface. A structure that can pass through and hold the cut pieces of spent nuclear fuel inside is used.
また、スラブ16は筒状であり、その下部はテ
ーパ状に絞られ、気体の吹込管26はこのスラブ
16の底部に設けられている。このスラブ16に
もジヤケツト42,44が設けられ、必要に応じ
冷却水又は加熱水が供給され、酸溶液の冷却又は
加熱が行なわれる。なお、スラブ16には排液管
46と排ガス管48とが設けられている。 Further, the slab 16 is cylindrical, the lower part thereof is tapered, and the gas blowing pipe 26 is provided at the bottom of the slab 16. This slab 16 is also provided with jackets 42 and 44, and cooling or heating water is supplied as necessary to cool or heat the acid solution. Note that the slab 16 is provided with a drain pipe 46 and an exhaust gas pipe 48.
このように構成された実施例に係る使用済核燃
料の溶解装置において、吹込管26から吹き込ま
れた気体のスラブ16内の上昇に伴つて、酸溶液
はスラブ16内を上昇し、連通管22から溶解管
12内に入つて下向きに流れ、篭体14内に流入
し、篭体14内の使用済核燃料と接触し、核燃料
が溶解される。またこの際、スラツジが酸溶液に
含有されるようになる。この酸溶液は捕集部28
を通つてスラツジが分離された後、酸溶液18か
らスラブ16に入り、循環される。(なお、スラ
ブ16内に入つた酸溶液の一部は排液管46によ
りスラブ16から排出され、替わりに新しい酸溶
液が供給される。)
また溶解管12内で酸溶液から脱離した気体
は、連通管24を通つてスラブ16内に入り、ス
ラブ16内に吹き込まれた気体と共に、排ガス管
48から排出される。 In the spent nuclear fuel melting apparatus according to the embodiment configured as described above, as the gas blown from the blowing pipe 26 rises inside the slab 16, the acid solution rises inside the slab 16 and flows from the communication pipe 22. It enters the melting tube 12, flows downward, flows into the casing 14, contacts the spent nuclear fuel in the casing 14, and the nuclear fuel is melted. Also, at this time, the sludge comes to be contained in the acid solution. This acid solution is collected in the collecting section 28.
After the sludge has been separated through the acid solution 18, it enters the slab 16 and is recycled. (Note that part of the acid solution that has entered the slab 16 is discharged from the slab 16 through the drain pipe 46, and new acid solution is supplied instead.) In addition, gas desorbed from the acid solution in the dissolution pipe 12 enters the slab 16 through the communication pipe 24 and is discharged from the exhaust gas pipe 48 together with the gas blown into the slab 16.
この第1の実施例では、直管状の連通管18が
示されているが、本発明においては、直管状のも
の、例えば、複数本の直管をく字形に接続した屈
曲管を用いても良い。この場合でも、勾配の小さ
い部分が生じない様に、管の全長に渡つて傾斜を
つける。 In this first embodiment, a straight communicating pipe 18 is shown, but in the present invention, a straight pipe, for example, a bent pipe in which a plurality of straight pipes are connected in a dogleg shape, may also be used. good. Even in this case, the pipe should be sloped along its entire length so that there are no areas with a small slope.
また、本発明においては、溶解管12からスラ
ブ16へ向つて下り勾配となるように連通管18
を設けても良い。 Further, in the present invention, the communication pipe 18 is arranged so that it has a downward slope from the melting pipe 12 toward the slab 16.
may be provided.
第3図は本発明の第2の実施例に係る使用済核
燃料の溶解装置の要部を示すものである。 FIG. 3 shows the main parts of a spent nuclear fuel melting apparatus according to a second embodiment of the present invention.
この実施例においては、溶解管12中に装入さ
れる篭体14内に多孔管38を立設し、この多孔
管38の上端を篭体14の上部に開口させると共
に、多孔管38の下端をプラグ40で封塞してい
る。また篭体14は、溶解管12に形成されたテ
ーパ部12aに掛止されている。 In this embodiment, a perforated tube 38 is set upright in the casing 14 inserted into the dissolving tube 12, the upper end of the perforated tube 38 is opened at the upper part of the casing 14, and the lower end of the perforated tube 38 is opened at the upper part of the casing 14. is sealed with a plug 40. Further, the housing 14 is hooked onto a tapered portion 12a formed in the dissolving tube 12.
この実施例に係る使用済核燃料の溶解管におい
て、溶解管12内を下向きに流れる酸溶液の一部
は、篭体14の上部から篭体14内に入る。また
酸溶液の残部は、多孔管38の上端開口から多孔
管38内に入り下向きに流れる。そしてその途中
で、少しずつ、多孔管38の周壁の孔を通過して
篭体14内に入る。このようにして篭体14内の
使用済核燃料は酸溶液と満遍なく接触し、核燃料
が速やかに溶解される。 In the spent nuclear fuel melting tube according to this embodiment, a part of the acid solution flowing downward in the melting tube 12 enters the housing 14 from the upper part of the housing 14. The remainder of the acid solution enters the porous tube 38 from the upper end opening of the porous tube 38 and flows downward. On the way, it passes through holes in the peripheral wall of the perforated tube 38 and enters the housing 14 little by little. In this way, the spent nuclear fuel within the casing 14 comes into contact with the acid solution evenly, and the nuclear fuel is quickly dissolved.
篭体14を通過し、核燃料を溶かし込んだ酸溶
液は第1の実施例と同様に捕集部28でスラツジ
が分離された後、連通管18を通つてスラブ16
に循環される。 The acid solution that has passed through the casing 14 and dissolved the nuclear fuel is separated into sludge in the collecting section 28 as in the first embodiment, and then passes through the communication pipe 18 to the slab 16.
is circulated.
第4図は、本発明の第3の実施例に係る使用済
核燃料の溶解装置の要部を示すものである。 FIG. 4 shows the main parts of a spent nuclear fuel melting apparatus according to a third embodiment of the present invention.
この実施例は、篭体14の底面外周部にコーン
状にテーパを付け、このテーパ部を溶解管のテー
パ部12aと係合させるようにしたものである。
このようにすれば、篭体14が安定して溶解管1
2内に保持される。 In this embodiment, the outer circumferential portion of the bottom surface of the housing 14 is tapered into a cone shape, and this tapered portion is engaged with the tapered portion 12a of the dissolving tube.
In this way, the housing 14 is stabilized and the melting tube 1
2.
第5図は本発明の第4の実施例に係る使用済核
燃料の溶解装置の要部を示すものである。 FIG. 5 shows the main parts of a spent nuclear fuel melting apparatus according to a fourth embodiment of the present invention.
この実施例においては、篭体14の下部が細径
部14aとなつており、上方の太径部14bとの
境目に段部14dが形成されている。そして溶解
管12の内周面にはリング13が設けられてお
り、このリング13に篭体段部14dが封止さ
れ、篭体14を溶解管12内に保持するようにし
ている。 In this embodiment, the lower part of the housing 14 is a narrow diameter part 14a, and a stepped part 14d is formed at the boundary with the upper large diameter part 14b. A ring 13 is provided on the inner circumferential surface of the melting tube 12 , and a housing stepped portion 14 d is sealed in the ring 13 to hold the housing 14 inside the melting tube 12 .
なお段部14dの上面側に傾斜部14cを設け
てコーン状とすれば、細径部14a内に使用済核
燃料を容易に挿入できる。 Note that if the sloped portion 14c is provided on the upper surface side of the step portion 14d to form a cone shape, the spent nuclear fuel can be easily inserted into the narrow diameter portion 14a.
第5図の実施例では太径部14bが設けられて
いるが、この太径部14bを設けず、即ち、段部
14dより上部の部分を無くし、替わりに多孔管
28の上端部にワイヤ、細棒等を連結し、このワ
イヤ、細棒等を引張つて篭体14を溶解管12内
に出し入れするようにしても良い。 In the embodiment shown in FIG. 5, a large diameter portion 14b is provided, but this large diameter portion 14b is not provided, that is, the portion above the stepped portion 14d is eliminated, and instead, a wire is attached to the upper end of the porous tube 28. The housing 14 may be moved in and out of the melting tube 12 by connecting a thin rod or the like and pulling the wire or thin rod.
[効果]
以上の通り、本発明によれば、酸溶液の循環量
を増加させ、酸溶液と使用済核燃料との接触を良
好なものとし、核燃料を迅速に溶解することが可
能となる。また溶解管とスラブの下部との連通管
にスラツジが堆積しない。更に、高価な酸素ガス
の代わりに空気を用いることもできる。[Effects] As described above, according to the present invention, it is possible to increase the circulation amount of the acid solution, improve the contact between the acid solution and the spent nuclear fuel, and quickly dissolve the nuclear fuel. Moreover, sludge does not accumulate in the communication pipe between the melting pipe and the lower part of the slab. Furthermore, air can be used instead of the expensive oxygen gas.
第1図及び第3図は本発明の実施例に係る使用
済核燃料の溶解装置を示す縦断面図、第2図は従
来例を示す縦断面図、第4図及び第5図はそれぞ
れ本発明の異なる実施例に係る要部断面図であ
る。
12……溶解管、14……篭体、16……スラ
ブ、18,20,22,24……連通管、26…
…気体吹込管、28……スラツジ捕集部、30,
32,42,44……ジヤケツト、38……多孔
管、40……プラグ。
1 and 3 are longitudinal sectional views showing a spent nuclear fuel melting apparatus according to an embodiment of the present invention, FIG. 2 is a longitudinal sectional view showing a conventional example, and FIGS. 4 and 5 are respectively in accordance with the present invention. FIG. 3 is a sectional view of a main part according to a different embodiment. 12...Dissolution tube, 14...Casing, 16...Slab, 18, 20, 22, 24...Communication tube, 26...
...Gas blowing pipe, 28...Sludge collection section, 30,
32, 42, 44... Jacket, 38... Porous pipe, 40... Plug.
Claims (1)
料保持用の篭体が内部に装入された溶解管と、該
溶解管に隣接して上下方向に設置された筒状のス
ラブと、該溶解管の下部とスラブの下部とを連通
し、該溶解管からスラブへ液を流す下部連通管
と、該下部連通管よりも上方のレベルで溶解管と
スラブとを連通する少くとも1本の連通管と、該
スラブの底部に接続された気体吹込管と、該溶解
管の下部に接続して設けられたスラツジ捕集部
と、を備えてなる使用済核燃料の溶解装置であつ
て、 前記下部連通管は直管又はほぼ直管状であり、
かつ傾斜して設置されてなり、 前記スラツジ捕集部は、筒軸方向を上下方向と
した略筒形状のものであつて、前記溶解管の下部
の外周を囲む太径部と、該太径部の下端に連なり
下方に向かつて縮径するテーパ部と、該テーパ部
の下端に連なる細径部とを備えてなり、 前記溶解管の下端の開口縁と該テーパ部とが同
一高さとなつており、該テーパ部と該溶解管の下
端の開口縁との間には間〓が形成されており、太
径部の上端は溶解管の下部外周面に固着されてお
り、 前記下部連通管は該太径部に接続されているこ
とを特徴とする使用済核燃料の溶解装置。[Scope of Claims] 1. A melting tube that is installed vertically and has a casing for holding spent nuclear fuel to be melted inserted therein, and a cylindrical tube that is installed vertically adjacent to the melting tube. A lower communicating pipe that communicates the lower part of the melting tube with the lower part of the slab and allows liquid to flow from the melting tube to the slab, and communicates the melting tube and the slab at a level above the lower communicating pipe. A spent nuclear fuel melting device comprising at least one communication pipe, a gas blowing pipe connected to the bottom of the slab, and a sludge collection section connected to the bottom of the melting pipe. The lower communicating pipe is straight or almost straight,
The sludge collecting section has a substantially cylindrical shape with the cylindrical axis direction as the vertical direction, and has a large diameter part surrounding the outer periphery of the lower part of the melting tube, and a large diameter part surrounding the outer periphery of the lower part of the melting tube. a tapered part that continues to the lower end of the melting tube and whose diameter decreases downward; and a narrow diameter part that continues to the lower end of the tapered part, and the opening edge of the lower end of the melting tube and the tapered part are at the same height. A gap is formed between the tapered part and the opening edge at the lower end of the melting tube, and the upper end of the large diameter part is fixed to the outer peripheral surface of the lower part of the melting tube, and the lower communicating tube is connected to the large-diameter portion, a spent nuclear fuel melting device.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP59129001A JPS617496A (en) | 1984-06-21 | 1984-06-21 | Spent nuclear fuel melting equipment |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP59129001A JPS617496A (en) | 1984-06-21 | 1984-06-21 | Spent nuclear fuel melting equipment |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS617496A JPS617496A (en) | 1986-01-14 |
| JPH0467639B2 true JPH0467639B2 (en) | 1992-10-28 |
Family
ID=14998687
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP59129001A Granted JPS617496A (en) | 1984-06-21 | 1984-06-21 | Spent nuclear fuel melting equipment |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS617496A (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS6361194A (en) * | 1986-09-01 | 1988-03-17 | 株式会社日立製作所 | Continuous melting device for spent nuclear fuel |
Family Cites Families (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE3274719D1 (en) * | 1981-09-29 | 1987-01-29 | Atomic Energy Authority Uk | Agitator apparatus |
| DE3147199A1 (en) * | 1981-11-27 | 1983-06-01 | Alkem Gmbh, 6450 Hanau | METHOD FOR SOLVING SOLIDS, ESPECIALLY SOLID CORE REACTOR FUELS, AND SOLUTION VESSEL, ESPECIALLY FOR THIS METHOD |
-
1984
- 1984-06-21 JP JP59129001A patent/JPS617496A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS617496A (en) | 1986-01-14 |
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| LAPS | Cancellation because of no payment of annual fees |