JPH0439638B2 - - Google Patents
Info
- Publication number
- JPH0439638B2 JPH0439638B2 JP12664284A JP12664284A JPH0439638B2 JP H0439638 B2 JPH0439638 B2 JP H0439638B2 JP 12664284 A JP12664284 A JP 12664284A JP 12664284 A JP12664284 A JP 12664284A JP H0439638 B2 JPH0439638 B2 JP H0439638B2
- Authority
- JP
- Japan
- Prior art keywords
- nuclear fuel
- tube
- melting
- melting tube
- spent nuclear
- 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
- 238000002844 melting Methods 0.000 claims description 54
- 230000008018 melting Effects 0.000 claims description 54
- 239000002915 spent fuel radioactive waste Substances 0.000 claims description 30
- 239000002253 acid Substances 0.000 description 22
- 239000007788 liquid Substances 0.000 description 10
- 239000003758 nuclear fuel Substances 0.000 description 6
- 230000002093 peripheral effect Effects 0.000 description 6
- MYMOFIZGZYHOMD-UHFFFAOYSA-N Dioxygen Chemical compound O=O MYMOFIZGZYHOMD-UHFFFAOYSA-N 0.000 description 5
- 229910001882 dioxygen Inorganic materials 0.000 description 5
- GRYLNZFGIOXLOG-UHFFFAOYSA-N Nitric acid Chemical compound O[N+]([O-])=O GRYLNZFGIOXLOG-UHFFFAOYSA-N 0.000 description 4
- 229910017604 nitric acid Inorganic materials 0.000 description 4
- WZECUPJJEIXUKY-UHFFFAOYSA-N [O-2].[O-2].[O-2].[U+6] Chemical compound [O-2].[O-2].[O-2].[U+6] WZECUPJJEIXUKY-UHFFFAOYSA-N 0.000 description 3
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 description 3
- 238000004090 dissolution Methods 0.000 description 3
- 239000001301 oxygen Substances 0.000 description 3
- 229910052760 oxygen Inorganic materials 0.000 description 3
- 229910001220 stainless steel Inorganic materials 0.000 description 3
- 239000010935 stainless steel Substances 0.000 description 3
- 229910000439 uranium oxide Inorganic materials 0.000 description 3
- 238000006243 chemical reaction Methods 0.000 description 2
- 239000007789 gas Substances 0.000 description 2
- 230000000630 rising effect Effects 0.000 description 2
- 239000010802 sludge Substances 0.000 description 2
- 238000007664 blowing Methods 0.000 description 1
- 238000001816 cooling Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 229910052751 metal Inorganic materials 0.000 description 1
- 239000002184 metal Substances 0.000 description 1
- 239000002893 slag Substances 0.000 description 1
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
Landscapes
- Solid Fuels And Fuel-Associated Substances (AREA)
- Manufacture And Refinement Of Metals (AREA)
Description
【発明の詳細な説明】
［産業上の利用分野］
本発明は溶解管中に使用済核燃料保持用の篭体
が装入された使用済核燃料の溶解管に係り、特に
この篭体の形状を改良して、使用済核燃料の溶解
効率を向上させるようにした使用済核燃料の溶解
管に関する。[Detailed Description of the Invention] [Industrial Application Field] The present invention relates to a spent nuclear fuel melting tube in which a casing for holding spent nuclear fuel is charged, and in particular, the present invention relates to a spent nuclear fuel melting tube in which a casing for holding spent nuclear fuel is charged. The present invention relates to a spent nuclear fuel melting tube that has been improved to improve the spent nuclear fuel melting efficiency.
［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 the pieces are immersed in nitric acid to be dissolved.
第２図は従来の使用済核燃料の溶解管１０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 tube 10. As shown in FIG.
この使用済核燃料の溶解管１０は、筒状の溶解
管本体１２と、溶解管本体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 tube 10 consists of a cylindrical melting tube main body 12 and a casing 14 inserted into the melting tube main body 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 addition, in each figure, in order to show that the casing 14 is porous, this casing 14 is shown with a broken line.
溶解管本体１２の側面の複数箇所は、スラブと
称される液槽１６に短管１８，２０，２２，２４
で接続されている。また、溶解管本体１２の下部
には、酸素ガス吹込口２６が設置されている。そ
して、溶解管本体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。 At multiple locations on the side surface of the melting tube body 12, short tubes 18, 20, 22, 24 are connected to a liquid tank 16 called a slab.
connected with. Furthermore, an oxygen gas inlet 26 is installed at the bottom of the melting tube main body 12. The melting tube main body 12 and the slab 16 are filled with an acid solution such as nitric acid.
吹込口２６から酸素ガスを吹き込むと、このガ
スは溶解管本体１２中を上昇し、これに伴つて溶
解管本体１２中の液も上昇して短管２２からスラ
ブ１６内に入り、短管１８から再び溶解管本体１
２中に戻り、循環する。 When oxygen gas is blown in from the blowing port 26, this gas rises in the melting tube body 12, and the liquid in the melting tube body 12 also rises and enters the slab 16 from the short tube 22, and flows into the short tube 18. From the melting tube body 1 again
Return to 2 and cycle.
なお液の一部は、短管１８と２２との中間のレ
ベルに設置された短管２０を通つてスラブ１６と
溶解管本体１２とを従来する。短管２４はガス流
通用のものであり、吹込口２６から溶解管本体１
２内に吹き込まれた酸素ガスが、この短管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 body 12 through the short tube 20 installed at a level intermediate between the short tubes 18 and 22. The short pipe 24 is for gas distribution, and is connected to the melting pipe main body 1 from the inlet 26.
Oxygen gas blown into the slab 16 passes through this short 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
次第に該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 the acid solution according to the following chemical reaction formula.
UO2＋2HNO3＋1/2O2→UO2（NO3）2＋H2O
なおスラブ１６には、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。
（但しいずれも図示しない。）また酸化ウラニウム
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１
４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。UO 2 +2HNO 3 +1/2O 2 →UO 2 (NO 3 ) 2 +H 2 O The slab 16 includes a means for extracting an acid solution in which nuclear fuel is dissolved, a means for supplying a new acid solution, and a means for extracting insoluble sludge. Egress means etc. are installed.
(None of these are shown, however.)Although uranium oxide nuclear fuel is usually inserted into a pipe made of stainless steel or the like, this pipe itself does not dissolve in acid solution, and even after the uranium oxide has melted out, the casing remains intact.
After the melting is completed, the housing 14 is pulled up and the remaining pipe is taken out.
［発明が解決しようとする問題点］
上記状来の使用済核燃料の溶解管においては、
短管１８からの溶解管本体１２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 spent nuclear fuel melting tube,
The acid solution entering the dissolution tube body 12 from the short tube 18 and rising therein passes through the bottom surface of the housing 14 and tries to further rise inside the housing 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、液流通抵
抗が大きく、そのため液のかなりの部分が篭体１
４から出て、篭体１４と溶解管本体１２内周面と
の間の部分を通り、いわば篭体１４を素通りする
様に流れる。 However, since a large amount of spent nuclear fuel that has been cut into short pieces is charged into the casing 14, the liquid flow resistance is large, and therefore a considerable portion of the liquid flows into the casing 1.
4 and flows through the portion between the housing 14 and the inner peripheral surface of the melting tube main body 12, so to speak, passing through the housing 14 without passing through.
そのため溶解管本体１２中を流れて使用済核燃
料と接触する酸溶液の量が少なくなり、使用済核
燃料の溶解に長時間を要するという問題があつ
た。 Therefore, the amount of acid solution flowing through the melting tube main body 12 and coming into contact with the spent nuclear fuel is reduced, resulting in a problem that it takes a long time to melt the spent nuclear fuel.
［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、第４図等に示す如く、溶解
管本体１２中に装入される篭体１４内に多孔管２
８を立設し、この多孔管２８の下端を篭体１４の
底面に開口させると共に、多孔管２８の上端を封
塞するか、又は、多孔管２８の他の部分よりも小
さい開口面積としたものである。[Means for Solving the Problems] In order to solve the above-mentioned problems of the conventional art, the present invention provides a melting tube that is inserted into the melting tube main body 12 as shown in FIGS. 1, 3, 4, etc. The perforated pipe 2 is placed inside the housing 14.
8 is set upright, and the lower end of this porous tube 28 is opened to the bottom surface of the casing 14, and the upper end of the porous tube 28 is sealed or has an opening area smaller than other parts of the porous tube 28. It is something.
［作用］
短管１８から溶解管本体１２中に入つた酸溶液
の一部は、篭体１４の底面から直に篭体１４内に
入る。酸溶液の残部は、多孔管２８内から入り、
該多孔管２８内を上昇するが、多孔管２８の上端
が封塞されているか、又は、開口面積が小さくと
られているので、漸次、多孔管２８の周壁面の孔
を通つて篭体１４内に入り、使用済核燃料と接触
する。[Function] A portion of the acid solution that has entered the dissolution tube main body 12 from the short pipe 18 enters the casing 14 directly from the bottom surface of the casing 14. The remainder of the acid solution enters from within the perforated tube 28;
It ascends inside the porous tube 28, but since the upper end of the porous tube 28 is closed or the opening area is set small, the casing 14 gradually passes through the holes in the peripheral wall of the porous tube 28. inside and come into contact with spent nuclear fuel.
そのため篭体１４内の使用済核燃料に満遍なく
多量の酸溶液が接触するようになり、溶解速度が
大きくなる。 Therefore, a large amount of the acid solution evenly contacts the spent nuclear fuel in the casing 14, increasing the dissolution rate.
［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
燃料の溶解管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 tube showing a first embodiment of the present invention.
第１図において、溶解管１０は溶解管本体１２
と、該溶解管本体１２に装入された篭体１４から
なる。 In FIG. 1, the melting tube 10 is the melting tube main body 12.
and a housing 14 inserted into the melting tube main body 12.
溶解管本体１２の中の下部は若干細径となつて
おり、それよりも上方の太径の部分とはテーパ部
１２ａを介して連絡されている。細径部の下部に
は酸素の吹込口２６が設けられている。（なお、
図示はしないが、溶解管本体１２の外周面にジヤ
ケツトが取り付けられ溶解管内部の液の冷却や加
熱が可能とされている。）
篭体１４は、この太径部と細径部との中間の径
を有しており、太径部の上部から溶解管本体１２
内に装入され、テーパ部１２ａに掛止されてい
る。 The lower part of the melting tube main body 12 has a slightly smaller diameter, and is connected to the larger diameter part above it via a tapered part 12a. An oxygen inlet 26 is provided at the bottom of the narrow diameter portion. (In addition,
Although not shown, a jacket is attached to the outer peripheral surface of the melting tube main body 12 to enable cooling and heating of the liquid inside the melting tube. ) The housing 14 has a diameter intermediate between the large diameter part and the small diameter part, and the melting tube main body 12 is inserted from the top of the large diameter part.
It is inserted into the inside and is hooked to the tapered portion 12a.
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.
この篭体１４の内部には、多孔管２８が上下方
向に篭体１４と同軸的に設置され、その下端は篭
体１４の底面に開口し、上端はプラグ３０で封塞
されている。 Inside this housing 14, a porous tube 28 is installed vertically coaxially with the housing 14, its lower end is open to the bottom surface of the housing 14, and its upper end is sealed with a plug 30.
なお溶解管本体１２は、短管１８，２２，２４
によりその側面部がスラブ１６に接続されてい
る。なお短管１８は、本実施例では直径が用いら
れ、スラブ１６から溶解管本体１２に向つて下り
勾配となるよう設置されている。短管２４は篭体
１４の上部のレベルの部分に、短管２２は多孔管
２８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。 Note that the melting tube main body 12 includes short tubes 18, 22, 24.
Its side portion is connected to the slab 16 by. In this embodiment, the diameter of the short pipe 18 is used, and the short pipe 18 is installed so as to have a downward slope from the slab 16 toward the melting pipe main body 12. The short pipe 24 is provided at a level above the casing 14, and the short pipe 22 is provided at a level slightly above the top of the porous pipe 28.
このように構成された実施例に係る使用済核燃
料の溶解管においては、溶解管本体１２及びスラ
ブ１６の内部には硝酸等の酸溶液が充填されてお
り、吹込口２６から吹き込まれた酸素ガスの溶解
管本体１２内の上昇に伴つて、酸素液は溶解管本
体１２内を上昇する。 In the spent nuclear fuel melting tube according to the embodiment configured as described above, the inside of the melting tube main body 12 and the slab 16 are filled with an acid solution such as nitric acid, and the oxygen gas blown from the inlet 26 is filled with an acid solution such as nitric acid. As the oxygen liquid rises within the melting tube main body 12, the oxygen liquid rises within the melting tube main body 12.
この際、酸溶液の一部は、篭体１４の底面を通
つて篭体１４内に入る。また酸溶液の残部は、多
孔管２８の下端開口から多孔管２８内に入り上昇
する。そしてその途中で、少しずつ、多孔管２８
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。 At this time, a portion of the acid solution enters the housing 14 through the bottom surface of the housing 14. The remainder of the acid solution enters the porous tube 28 from the lower end opening of the porous tube 28 and rises. And along the way, little by little, the porous pipe 28
It passes through a hole in the peripheral wall of the housing 14 and enters the housing 14. 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、短管２２を通つてスラブ１６に入り、再度
短管１８を通つて溶解管本体１２内に循環され
る。（なお、スラブ１６内に入つた酸溶液の一部
はスラブ１６から排出され、代わりに新しい酸溶
液が供給される。）
また溶解管本体１２内の酸素ガスの一部は、核
燃料の溶解反応に消費され、残部は短管２４を通
りスラブ１６に入り、次いでスラブ１６から排出
される。 The acid solution that has passed through the housing 14 and dissolved the nuclear fuel enters the slab 16 through the short pipe 22 and is circulated into the melting tube main body 12 through the short pipe 18 again. (Note that part of the acid solution that has entered the slab 16 is discharged from the slab 16, and a new acid solution is supplied instead.) Also, part of the oxygen gas in the melting tube body 12 is absorbed by the nuclear fuel melting reaction. The remainder passes through the short pipe 24 into the slab 16 and is then discharged from the slab 16.
第３図は本発明の第２の実施例に係る使用済核
燃料の溶解管の要部を示すものである。 FIG. 3 shows the main parts of a spent nuclear fuel melting tube according to a second 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本体の
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
管本体１２内に保持される。 In this embodiment, the bottom outer circumferential portion of the housing 14 is tapered into a cone shape, and this tapered portion is engaged with the tapered portion 12a of the melting tube main body. In this way, the housing 14 is stably held within the melting tube main body 12.
第４図は本発明の第３の実施例に係る使用済核
燃料の溶解管の要部を示すものである。 FIG. 4 shows the main parts of a spent nuclear fuel melting tube according to a third 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
管本体１２の内周面にはリング３２が設けられて
おり、このリング３２に篭体段部１４ｄが掛止さ
れ、篭体１４を溶解管体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 32 is provided on the inner circumferential surface of the melting tube main body 12, and the casing stepped portion 14d is hooked onto this ring 32 to hold the casing 14 within 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４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
４ｄより上部の部分を無くし、替わりに多孔管２
８の上端部にワイヤ、細等棒を連結し、このワイ
ヤ、細棒等を引張つて篭体１４を溶解管本体１２
内に出し入れするようにしても良い。 Although the embodiment shown in FIG. 4 is provided with a large-diameter portion 14b, this large-diameter portion 14b is not provided, that is, the portion above the step portion 4d is eliminated, and instead, the porous pipe 2
A wire or a thin rod is connected to the upper end of the casing 14 and the melting tube main body 12 is pulled by pulling the wire or thin rod.
It may be put in and out.
上記の各実施例において、多孔管２８の上端は
プラグ３０で封塞されている。これは、多孔管２
８内を上昇する酸溶液を、多孔管２８の周壁の孔
を通過して篭体１４内に満遍なく流入させるため
であるが、このような流入が確保される限り、小
さな孔をプラグ３０に開けて、多孔管２８内の酸
溶液の一部がプラグ３０の孔を通つてその上部に
流れるようにしても良い。即ち多孔管２８の上端
は封塞しても良く、また多孔管２８の他の部分よ
りも小なる開口面積となるようにしても良い。 In each of the above embodiments, the upper end of the porous tube 28 is sealed with a plug 30. This is porous pipe 2
This is to allow the acid solution rising inside the plug 30 to pass through the holes in the peripheral wall of the porous tube 28 and evenly flow into the housing 14. As long as such an inflow is ensured, small holes are made in the plug 30. A portion of the acid solution in the perforated tube 28 may then flow through the holes in the plug 30 to the top thereof. That is, the upper end of the porous tube 28 may be sealed, or the opening area may be smaller than that of other portions of the porous tube 28.
また上記の実施例では、スラグ１６と溶解管本
体１２の下部を接続する短管１８が直管であり、
かつ液流れ方向に向つて下り勾配となるように設
置されているので、この短管１８内にスラツジが
堆積せず、液流通が良好になるという効果が奏さ
れる。 Further, in the above embodiment, the short pipe 18 connecting the slag 16 and the lower part of the melting tube main body 12 is a straight pipe,
In addition, since it is installed so as to have a downward slope in the direction of liquid flow, sludge does not accumulate in the short pipe 18, and the liquid flow is improved.
［効果］
以上の通り、本発明によれば、酸溶液と使用済
核燃料との接触が良好となり、核燃料が満遍なく
かつ迅速に溶解する。[Effects] As described above, according to the present invention, the contact between the acid solution and the spent nuclear fuel becomes good, and the nuclear fuel is evenly and quickly dissolved.
第１図は本発明の実施例に係る使用済核燃料の
溶解管を示す縦断面図、第２図は従来例を示す縦
断面図、第３図及び第４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。
１０……使用済核燃料の溶解管、１２……溶解
管本体、１４……篭体、１６……スラブ、１８，
２０，２２，２４……短管、２８……多孔管、３
０……プラグ。
FIG. 1 is a vertical cross-sectional view showing a spent nuclear fuel melting tube according to an embodiment of the present invention, FIG. 2 is a vertical cross-sectional view showing a conventional example, and FIGS. 3 and 4 are respectively different embodiments of the present invention. FIG. 2 is a sectional view of main parts. 10... Spent nuclear fuel melting tube, 12... Melting tube body, 14... Casing, 16... Slab, 18,
20, 22, 24... short pipe, 28... porous pipe, 3
0...Plug.
Claims (1)
管本体中に装入された、使用済核燃料保持用の篭
体とを有する使用済核燃料の溶解管において、 周壁面が多孔性である多孔管を該篭体中に立設
し、該多孔管の下端を篭体底面に開口せしめると
共に、該多孔管の上端を封塞するか、又は、該多
孔管のその他の部分よりも小なる開口面積とした
ことを特徴とする使用済核燃料の溶解管。[Scope of Claims] 1. A spent nuclear fuel melting tube having a melting tube body installed in the vertical direction and a spent nuclear fuel holding casing inserted into the melting tube body, including: A porous tube having a porous structure is erected in the housing, and the lower end of the porous tube is opened to the bottom surface of the housing, and the upper end of the porous tube is sealed, or other A spent nuclear fuel melting tube characterized by having an opening area smaller than the opening area.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP59126642A JPS614998A (en) | 1984-06-20 | 1984-06-20 | Dissolving pipe for spent nuclear fuel |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP59126642A JPS614998A (en) | 1984-06-20 | 1984-06-20 | Dissolving pipe for spent nuclear fuel |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS614998A JPS614998A (en) | 1986-01-10 |
| JPH0439638B2 true JPH0439638B2 (en) | 1992-06-30 |
Family
ID=14940250
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP59126642A Granted JPS614998A (en) | 1984-06-20 | 1984-06-20 | Dissolving pipe for spent nuclear fuel |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS614998A (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS6078990U (en) * | 1983-11-07 | 1985-06-01 | 株式会社イワキ | Diaphragm structure |
-
1984
- 1984-06-20 JP JP59126642A patent/JPS614998A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS614998A (en) | 1986-01-10 |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| EXPY | Cancellation because of completion of term |