JPS60132630A - Dissolving apparatus - Google Patents

Dissolving apparatus

Info

Publication number
JPS60132630A
JPS60132630A JP23994383A JP23994383A JPS60132630A JP S60132630 A JPS60132630 A JP S60132630A JP 23994383 A JP23994383 A JP 23994383A JP 23994383 A JP23994383 A JP 23994383A JP S60132630 A JPS60132630 A JP S60132630A
Authority
JP
Japan
Prior art keywords
nitric acid
barrel
concentrated nitric
nuclear fuel
inner shell
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.)
Pending
Application number
JP23994383A
Other languages
Japanese (ja)
Inventor
Akira Shimizu
明 清水
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 Heavy Industries Ltd
Original Assignee
Mitsubishi Heavy Industries Ltd
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 Heavy Industries Ltd filed Critical Mitsubishi Heavy Industries Ltd
Priority to JP23994383A priority Critical patent/JPS60132630A/en
Publication of JPS60132630A publication Critical patent/JPS60132630A/en
Pending legal-status Critical Current

Links

Abstract

PURPOSE:To prevent corrosion caused by conc. nitric acid, by forming a dissolving apparatus of used nuclear fuel from a double structure consisting of an inner barrel and an outer barrel while filling the ring shaped space between both barrels with a heating medium. CONSTITUTION:The lower part of a barrel 2 is formed of a double structure consisting of an inner barrel 2a for receiving used nuclear fuel and conc. nitric acid and an outer barrel 2b to which a heating jacket 9 for receiving steam 10 used in heating is welded and the ring shaped space 8 between both inner and outer barrels 2a, 2b is filled with a heating medium such as water or oil. By this structure, there is no contact with concentrated nitric acid and a heat affected part is prevented from corrosion due to concentrated nitric acid.

Description

【発明の詳細な説明】 本発明は使用済核燃料を溶解するのに用いられる溶解装
置に関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a melting device used to melt spent nuclear fuel.

酸化物はレット中のウラン268が部分的にプルトニウ
ム269に変わった形で持つ。
The oxide has uranium-268 in lett partially converted to plutonium-269.

この種溶解装置は、原子炉の使用4料を再処他の核分裂
生成物と部分離し易くする為にこれを高温の濃硝酸を用
いて溶解させる機能を持つ。
This type of melting device has the function of melting the four materials used in a nuclear reactor using high-temperature concentrated nitric acid in order to easily separate them from nuclear fission products for reprocessing.

従来の溶解装置の1例が第1図に示され、矩形断面ケし
たスラブ(1)と円筒形のバレル(2)が連結管(3)
で接続されている。細断された使用済核燃料はバレル(
2)内のバスケット(4)内に投入される。その後、ス
ラブ(1)内に濃硝酸を充たし、バレル(2)の外側に
溶接されたジャケット(5)内に加熱用蒸気を流すこと
により装置内の濃硝酸を加熱すると同時にその循環を行
わせるようになっている。
An example of a conventional melting device is shown in Figure 1, in which a slab (1) with a rectangular cross section and a cylindrical barrel (2) are connected to a connecting pipe (3).
connected with. Shredded spent nuclear fuel is stored in barrels (
2) into the basket (4). After that, the slab (1) is filled with concentrated nitric acid, and heating steam is flowed into the jacket (5) welded to the outside of the barrel (2) to heat the concentrated nitric acid inside the device and simultaneously circulate it. It looks like this.

この溶解装置はその内部に高温の濃硝酸が充填されてい
る為、腐食してピンホールが発生するおそれがある。又
、ジャケット(5)をバレル(2)に溶接して取り付け
ている為、熱影響部からの腐食の可能性が太き(、ジャ
ケット(5)内の接液部が腐食した場合には補修の方法
がなく、装置全体を交換せざるをえないという欠点があ
った。
Because this melting device is filled with high-temperature concentrated nitric acid, there is a risk of corrosion and pinholes. Also, since the jacket (5) is attached to the barrel (2) by welding, there is a high possibility of corrosion from the heat-affected zone (and if the wetted parts inside the jacket (5) corrode, it must be repaired. There was no way to do this, and the entire device had to be replaced.

本発明は上記欠点を解消するために発明されたもので、
その要旨とするところは、濃硝酸が充填されるスラブと
使用済核燃料が投入されろ円筒形のバレルと、上記スラ
ブとバレルとを接続する連結管からなる使用済核燃料の
溶解装置において、上記バレルの全体又は部分を使用済
核燃料及び濃硝酸を受け入れる内胴と、加熱用蒸気欠受
は入れる加熱用ジャケットを具えた外胴かもなる2重構
造とし、上記内胴と外胴との間の環状空間内に熱媒体を
充填したことを特徴とする溶解装置にある。
The present invention was invented to solve the above-mentioned drawbacks.
The gist is that in a spent nuclear fuel melting device consisting of a slab filled with concentrated nitric acid, a cylindrical barrel into which spent nuclear fuel is charged, and a connecting pipe connecting the slab and barrel, the barrel The whole or part of the shell has a double structure consisting of an inner shell that receives spent nuclear fuel and concentrated nitric acid, and an outer shell that is equipped with a heating jacket that receives the heating steam. A melting device characterized in that a space is filled with a heat medium.

本発明においては、上記構成を具えているので、加熱用
ジャケラl具えた外胴は内胴内の高温の濃硝酸と内胴及
び環状空間内の熱媒体によって隔離されていて、濃硝酸
に接するこ乏はなく、従って、加熱用ジャケットを溶接
にまり外胴に取り付けた場合にもその熱影響部が濃硝酸
により腐食されろことはかい。そして、濃硝酸を受け入
れる内胴は溶接することなく一体構造としりるので、こ
れが濃硝酸によって腐食されるおそれは少くなる。
In the present invention, since the above structure is provided, the outer shell equipped with the heating jacket is isolated from the high-temperature concentrated nitric acid in the inner shell by the heat medium in the inner shell and the annular space, and is in contact with the concentrated nitric acid. Therefore, even if the heating jacket is welded and attached to the outer shell, its heat-affected zone will not be corroded by concentrated nitric acid. Furthermore, since the inner shell that receives concentrated nitric acid has an integral structure without being welded, there is less risk that the inner shell will be corroded by concentrated nitric acid.

更に、内胴及び外胴はその機能に応じ別個の材質、構造
とすることができ、万一いずれかが損傷しても一方だけ
を取り換えれば巨い。
Furthermore, the inner and outer shells can be made of different materials and have different structures depending on their functions, so even if one of them is damaged, it will be a hassle to replace just one.

本発明の1実施例が第2図に示され、第2図はノ2レル
の部分的断面図である。第2図に示されるようにバレル
(2)の下部は使用済核燃料及び濃硝酸を受け入れる内
胴(2α)と加熱用蒸気(101’4受は入れる加熱用
ジャケット(9)が溶接された外胴(2h)とからなる
2重構造とされ、内胴(2α)と外胴(2h)との間の
環状空間(8)には水又は油等の熱媒体が充填されてい
る。内胴(2αルエステンレス製で、その本体は溶接部
分を減ら1−ため一体構造とされ、ノズル01)との接
合部分のみが溶接されている。なお、図示されていない
が、バレルの内胴(2α片工連結管を介してスラブと接
続されている。
One embodiment of the invention is shown in FIG. 2, which is a partial cross-sectional view of the nozzle barrel. As shown in Figure 2, the lower part of the barrel (2) consists of an inner shell (2α) that receives spent nuclear fuel and concentrated nitric acid, and an outer shell (101'4) that is welded with a heating jacket (9) that contains heating steam (101'4). It has a double structure consisting of a shell (2h), and the annular space (8) between the inner shell (2α) and the outer shell (2h) is filled with a heat medium such as water or oil.Inner shell (It is made of 2α stainless steel, and its main body has an integrated structure to reduce the number of welded parts, and only the joint part with nozzle 01) is welded.Although not shown, the inner body of the barrel (2α It is connected to the slab via a one-piece connecting pipe.

しかして、加熱用ジャケット(9)向火通過する蒸気に
より外胴(2b)が加熱され、次いで環状空間(8)を
満たしている熱媒体を通じての熱伝導にまり内胴(2α
)が加熱され、次いで内胴(2α)の内部の濃硝酸が加
熱される。環状空間(8)内を大気圧にすれば、100
C以上に濃硝酸乞加熱するためには、熱媒体として沸点
の高い油を充填するのが望ましい。濃硝酸は、ステンレ
ス製の内胴(2α)の結晶粒界を通り極(少量ではある
が内胴(2α)の外面に浸み出すことも考えられるが、
その場合においても、環状空間(8)乞満たす熱媒体に
より希釈され濃硝酸が直接外胴(2h)の溶接部に達す
ることはない。なお、環状空間(8)内に充填された熱
媒体のPHを計測し、異常のある場合は直ちに内胴(2
α)を取り換えることもできろ。
The outer shell (2b) is heated by the steam passing through the heating jacket (9), and then the inner shell (2α) is heated by heat conduction through the heat medium filling the annular space (8).
) is heated, and then the concentrated nitric acid inside the inner shell (2α) is heated. If the inside of the annular space (8) is brought to atmospheric pressure, 100
In order to heat concentrated nitric acid to a temperature above C, it is desirable to fill the tank with oil having a high boiling point as a heat medium. Concentrated nitric acid may pass through the grain boundaries of the stainless steel inner shell (2α) and seep into the outer surface of the inner shell (2α), albeit in a small amount.
Even in that case, the concentrated nitric acid is diluted by the heat medium filling the annular space (8) and does not directly reach the welded part of the outer shell (2h). In addition, the PH of the heat medium filled in the annular space (8) is measured, and if there is any abnormality, immediately remove the inner shell (2).
It would also be possible to replace α).

【図面の簡単な説明】[Brief explanation of the drawing]

第1図は従来の溶解装置の正面図、第2図は本発明の1
実施例におけるバレルの部分的縦断面図である。 スラブ・・・m バレル・・・(2) 連結管・・・(
3)内胴・・・(2α) 外胴・・・(2h)加熱用ジ
ャケット・・・(9) 環状空間・・・(8)復代理人
 弁理士 岡 本 重 文 第1図 第2図
FIG. 1 is a front view of a conventional melting device, and FIG. 2 is a front view of a conventional melting device.
FIG. 3 is a partial vertical cross-sectional view of the barrel in the example. Slab...m Barrel...(2) Connecting pipe...(
3) Inner shell...(2α) Outer shell...(2h) Heating jacket...(9) Annular space...(8) Sub-Agent Patent Attorney Shige Okamoto Figure 1 Figure 2

Claims (1)

【特許請求の範囲】[Claims] 濃硝酸が充填されるスラブと使用済核燃料が投入される
円筒形のバレルと、上記スラブとノZレルと乞接続する
連結管からなる使用済核燃料の溶解装置において、上記
バレルの全体又は部分を使用済核燃料及び濃硝酸を受け
入れる内胴と、加熱用蒸気を受け入れる加熱用ジャケラ
トラ具えた外胴からなる2重構造とし、上記内胴と外胴
との間の環状空間内に熱媒体を充填したことを特徴とす
る溶解装置。
In a spent nuclear fuel melting device consisting of a slab filled with concentrated nitric acid, a cylindrical barrel into which spent nuclear fuel is charged, and a connecting pipe that connects the slab and the nozzle, the whole or part of the barrel is It has a double structure consisting of an inner shell that receives spent nuclear fuel and concentrated nitric acid, and an outer shell that is equipped with a heating jacket that receives heating steam, and a heat medium is filled in the annular space between the inner shell and the outer shell. A dissolving device characterized by:
JP23994383A 1983-12-21 1983-12-21 Dissolving apparatus Pending JPS60132630A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP23994383A JPS60132630A (en) 1983-12-21 1983-12-21 Dissolving apparatus

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP23994383A JPS60132630A (en) 1983-12-21 1983-12-21 Dissolving apparatus

Publications (1)

Publication Number Publication Date
JPS60132630A true JPS60132630A (en) 1985-07-15

Family

ID=17052123

Family Applications (1)

Application Number Title Priority Date Filing Date
JP23994383A Pending JPS60132630A (en) 1983-12-21 1983-12-21 Dissolving apparatus

Country Status (1)

Country Link
JP (1) JPS60132630A (en)

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