JPH081485Y2 - Equipment for measuring the amount of corrosion of radioactive waste - Google Patents
Equipment for measuring the amount of corrosion of radioactive wasteInfo
- Publication number
- JPH081485Y2 JPH081485Y2 JP1990073614U JP7361490U JPH081485Y2 JP H081485 Y2 JPH081485 Y2 JP H081485Y2 JP 1990073614 U JP1990073614 U JP 1990073614U JP 7361490 U JP7361490 U JP 7361490U JP H081485 Y2 JPH081485 Y2 JP H081485Y2
- Authority
- JP
- Japan
- Prior art keywords
- corrosion
- radioactive waste
- package
- amount
- solidified
- 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
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- Testing Resistance To Weather, Investigating Materials By Mechanical Methods (AREA)
- Investigating Or Analyzing Materials By The Use Of Electric Means (AREA)
Description
【考案の詳細な説明】 「産業上の利用分野」 本考案は放射性廃棄物の腐食量測定装置に関する。DETAILED DESCRIPTION OF THE INVENTION "Industrial field of application" The present invention relates to a device for measuring the amount of corrosion of radioactive waste.
「従来の技術」 一般に、原子炉発電プラント等で発生する高レベル放
射性廃棄物は、例えばガラス固化処理することによっ
て、取り扱い性を向上させることができる。“Prior Art” Generally, high-level radioactive waste generated in a nuclear power plant or the like can be improved in handleability by vitrification treatment, for example.
そして、ガラス固化等の処理がなされたいわゆる固化
パッケージは、第3図に示すような放射性廃棄物用貯蔵
庫で長期間保管される計画である。The so-called solidified package that has been subjected to a process such as vitrification is planned to be stored for a long time in a radioactive waste storage as shown in FIG.
第3図において、符号Pは高レベル放射性廃棄物をガ
ラス固化する等の処理を施してなる固化パッケージ等の
放射性廃棄物、1は放射性廃棄物Pを多数収納保管する
ためのセル室、2はセル室1を囲んでいるコンクリート
壁、3はセル室1の上方に設けられる搬送室、4はセル
室1と搬送室3を仕切っているコンクリート壁からなる
天井スラブ、5は天井スラブ4から吊持されて放射性廃
棄物Pを縦積み状態に複数収納するための鋼管等の収納
管、6はセル室1の中に水平に架設されている支持構造
物(支持架構)、7は支持構造物6に支持されかつた収
納管5を囲んでいる外管、8は外気入口、9は空気出
口、10は冷却空気挿通路、11は収納管5の上部を密閉す
る閉塞蓋である。In FIG. 3, reference symbol P indicates radioactive waste such as a solidified package obtained by subjecting high-level radioactive waste to vitrification, etc., 1 is a cell chamber for storing a large number of radioactive waste P, and 2 is a cell chamber. A concrete wall surrounding the cell chamber 1, 3 is a transfer chamber provided above the cell chamber 1, 4 is a ceiling slab made of a concrete wall separating the cell chamber 1 and the transfer chamber 3, and 5 is a ceiling slab 4. A storage pipe such as a steel pipe for holding a plurality of radioactive wastes P in a vertically stacked state, 6 is a support structure (support frame) horizontally installed in the cell chamber 1, and 7 is a support structure. An outer pipe which is supported by 6 and surrounds the housing pipe 5, 8 is an outside air inlet, 9 is an air outlet, 10 is a cooling air insertion passage, and 11 is a closing lid for sealing the upper part of the housing pipe 5.
このような構造の貯蔵庫では、放射性物質の崩壊熱に
よって、収納管5の温度が高くなると、固化パッケージ
収納管5と外管7との間の筒状空間12の空気が上昇する
対流が生じて、第3図に矢印で示すように、冷却空気挿
通路10から取り入れた空気によって冷却が行なわれ、加
熱された空気が空気出口9から排出される。したがっ
て、動力源を必要とせず崩壊熱が生じている期間、自然
の対流による冷却が行なわれ、停電等に左右されず高い
安全性を有するものとなる。In the storage having such a structure, when the temperature of the storage tube 5 rises due to the decay heat of the radioactive material, convection occurs in which the air in the cylindrical space 12 between the solidified package storage tube 5 and the outer tube 7 rises. As shown by the arrow in FIG. 3, cooling is performed by the air taken in from the cooling air insertion passage 10, and the heated air is discharged from the air outlet 9. Therefore, cooling is performed by natural convection during a period in which decay heat is generated without requiring a power source, and high safety is ensured without being affected by a power failure or the like.
「考案が解決しようとする課題」 しかしながら、前記従来の貯蔵庫においては、ガラス
固化体を長期に貯蔵する施設において、貯蔵設備構造材
の寿命(腐食量)を推定しておくことは肝要である。[Problems to be Solved by the Invention] However, in the conventional storage, it is important to estimate the life (corrosion amount) of the storage facility structural material in a facility that stores the vitrified material for a long time.
本考案は前記事情に鑑みてなされたものであって、貯
蔵設備構造材等の寿命を直接的、かつ確実に把握するこ
とのできる放射性廃棄物の腐食量測定装置を提供するこ
とを目的としている。The present invention has been made in view of the above circumstances, and it is an object of the present invention to provide a device for measuring the amount of corrosion of radioactive waste, which can directly and reliably grasp the life of a storage facility structural material or the like. .
「課題を解決するための手段」 本考案の腐食量測定装置は、放射性廃棄物用貯蔵庫に
複数配される固化パッケージ収納管の一部に、内部に冷
却空気を挿通させるための導入口及び排気口が下部及び
上部に形成され、導入口及び排気口が形成された状態の
固化パッケージ収納管の内部に固化パッケージに代えて
収納され、パッケージの腐食量を測定するための腐食量
測定装置であって、前記パッケージに類似させた形状に
形成されるとともに冷却空気を流通させるための流通孔
が上下に形成されている容器と、この容器内に支持具に
より吊持状態に支持された供試体とを具備する技術を採
用している。[Means for Solving the Problem] The corrosion amount measuring device of the present invention is provided with an inlet and an exhaust for inserting cooling air into a part of a solidified package storage pipe arranged in a plurality of radioactive waste storages. It is a corrosion amount measuring device for measuring the corrosion amount of the package, which is stored in the solidified package storage pipe with the inlet and the exhaust port formed in the lower part and the upper part in place of the solidified package. A container having a shape similar to that of the package and having vertically formed through holes for circulating cooling air, and a sample supported in a suspended state by a support in the container. It adopts the technology equipped with.
「作用」 収納管に腐食量測定装置を収納した状態とすると、貯
蔵されている固化パッケージの発熱に基づいてセル室の
収納管に上昇空気流が生じ、この上昇空気流の一部が、
導入口及び排気口が形成された状態の固化パッケージ収
納管の内部を挿通することにより、空気流が容器の流通
孔を経由して内部に導入されて供試体に接触する。そし
て、前記供試体を随時取り出すことによって腐食量の測
定がなされる。[Operation] When the corrosion amount measuring device is stored in the storage pipe, an ascending air flow is generated in the storage pipe of the cell chamber based on the heat generated by the stored solidification package.
By inserting the inside of the solidified package storage tube in which the introduction port and the exhaust port are formed, the air flow is introduced into the interior through the circulation hole of the container and comes into contact with the sample. Then, the amount of corrosion is measured by taking out the specimen at any time.
「実施例」 以下、本考案の一実施例について、図面を参照して説
明する。[Embodiment] An embodiment of the present invention will be described below with reference to the drawings.
本実施例の放射性廃棄物の腐食量測定装置20は、第1
図に示すように、固化パッケージ(放射性廃棄物)Pに
類似させた形状(固化パッケージPをモデル化した形
状)に形成された容器21と、この容器21の中に上下に間
隔を空けて水平に架設された複数の支持具22と、該支持
具22に吊持された供試体23とを備えた構成となってい
る。前記供試体23は、固化パッケージPの外壁より腐食
が早い材質等によって形成される。The radioactive waste corrosion amount measuring device 20 of the present embodiment is the first
As shown in the figure, a container 21 formed in a shape similar to the solidified package (radioactive waste) P (a modeled shape of the solidified package P) and a horizontal space in the container 21 with a vertical space between them. It is configured to include a plurality of supports 22 erected on the base and a sample 23 suspended from the supports 22. The sample 23 is formed of a material that corrodes faster than the outer wall of the solidified package P.
容器21の上部及び下部には、収納管5を通過する外気
を流通させるための流通孔21a,21bが形成されている。Circulation holes 21a, 21b for circulating the outside air passing through the storage tube 5 are formed in the upper part and the lower part of the container 21.
次に、本実施例の放射性廃棄物の腐食量測定装置20の
一使用例について第2図を参照して説明する。前記腐食
量測定装置20は、放射性廃棄物の貯蔵庫の収納管内に収
納されて使用に供される。この貯蔵庫は、高レベル廃棄
物を固化させた固化パッケージPを収納する複数の固化
パッケージ収納管5と、これら固化パッケージ収納管5
を配置したセル室2と、このセル室2の下部へ外気を導
入する外気入口8を備えた概略構成とされている。そし
て、前記固化パッケージ収納管5のうち図中左側の固化
パッケージ収納管5には、その下部に前記冷却空気挿通
路10に対して開口する導入口15aが形成され、この導入
口15aから導入した外気を固化パッケージ収納管5の内
部に挿通させた後に排出するための排気口15bが上部に
形成されている。Next, an example of use of the radioactive waste corrosion amount measuring apparatus 20 of the present embodiment will be described with reference to FIG. The corrosion amount measuring device 20 is stored in a storage pipe of a radioactive waste storage for use. This storage contains a plurality of solidified package storage pipes 5 for storing a solidified package P obtained by solidifying high-level waste, and these solidified package storage pipes 5.
The cell chamber 2 in which is arranged, and the outside air inlet 8 for introducing outside air to the lower portion of the cell chamber 2 are provided as a schematic configuration. In the solidified package storage pipe 5 on the left side of the figure among the solidified package storage pipes 5, an introduction port 15a that opens to the cooling air insertion passage 10 is formed in the lower portion, and the solidification package storage pipe 5 is introduced from this introduction port 15a. An exhaust port 15b is formed in the upper part for discharging outside air after it has been inserted into the solidified package housing pipe 5.
そして、前記固化パッケージ収納管5内には、前記腐
食量測定装置20が収納されている。The corrosion amount measuring device 20 is housed in the solidified package housing pipe 5.
本実施例の放射性廃棄物の腐食量測定装置は、前記収
納管5に供試体23を備えた腐食量測定装置20を収納した
状態で使用に供される。このとき、腐食量測定装置20の
容器21には、その下部に形成された流通孔22bから外気
が導入され、上部に形成された流通孔22aから排出され
る。The apparatus for measuring the amount of corrosion of radioactive waste according to the present embodiment is used in a state in which the apparatus for measuring the amount of corrosion 20 provided with the sample 23 is housed in the housing pipe 5. At this time, the outside air is introduced into the container 21 of the corrosion amount measuring device 20 through the flow hole 22b formed in the lower part thereof and discharged from the flow hole 22a formed in the upper part.
そして、貯蔵庫内において他の固化パッケージPと同
一条件下に供試体23を配置してその腐食量を随時測定す
る。Then, the specimen 23 is placed in the storage under the same conditions as the other solidified packages P, and the amount of corrosion thereof is measured at any time.
本実施例の腐食量測定装置20を使用すれば、貯蔵設備
の長期に亘る腐食量を実際の環境下での条件で測定可能
となるため、直接的かつ確実な腐食量測定を可能とする
ことができる。そして、常に貯蔵設備機器の腐食量が明
確になり、その長期健全性が確認できる。If the corrosion amount measuring device 20 of the present embodiment is used, the long-term corrosion amount of the storage facility can be measured under the conditions of the actual environment, so that it is possible to directly and reliably measure the corrosion amount. You can Then, the amount of corrosion of the storage equipment is always clear, and its long-term soundness can be confirmed.
また、本実施例の腐食量測定装置20は、他の固化パッ
ケージPと同様の取り扱いができるため、使い勝手がよ
い。また、貯蔵設備内において、他の固化パッケージP
と同一条件を与えることができる。Further, the corrosion amount measuring device 20 of the present embodiment can be handled in the same manner as other solidified packages P, and is therefore easy to use. Also, in the storage facility, another solidified package P
Can be given the same conditions as.
なお、本考案の実施例は、前記実施例のみに限られる
ことはなく、他の変形例も可能である。It should be noted that the embodiment of the present invention is not limited to the above-mentioned embodiment, and other modifications are possible.
「考案の効果」 以上説明したように、本考案に係る放射性廃棄物の腐
食量測定装置によれば、貯蔵設備の長期に亙る腐食量を
実際の環境下での条件で測定可能となるため、直接的か
つ確実な腐食量測定を行うことができる。そして、常に
貯蔵設備機器の腐食量が明確になり、その長期健全性が
確認できる。“Effect of device” As described above, the radioactive waste corrosion amount measuring device according to the present invention makes it possible to measure a long-term corrosion amount of a storage facility under actual environment conditions. A direct and reliable corrosion amount measurement can be performed. Then, the amount of corrosion of the storage equipment is always clear, and its long-term soundness can be confirmed.
また、パッケージと同様の取り扱いができるため、使
い勝手がよい等の優れた効果を奏する。Further, since it can be handled in the same manner as a package, it has excellent effects such as ease of use.
第1図および第2図は本考案に係る放射性廃棄物の腐食
量測定装置の一実施例を示すもので、第1図は腐食量測
定装置の正断面図、第2図は第1図の腐食量測定装置を
収納した放射性廃棄物貯蔵庫の要部の正断面図、第3図
は放射性廃棄物貯蔵庫の従来例を示す正断面図である。 P……固化パッケージ、1……セル室、2……コンクリ
ート壁、3……搬送室、4……天井スラブ、5……固化
パッケージ収納管、6……支持構造物、7……外管、8
……外気入口、9……空気出口、10……冷却空気挿通
路、11……閉塞蓋、12……筒状空間、20……腐食量測定
装置、21……容器、21a、21b……流通孔、22……支持
具、23……供試体。1 and 2 show one embodiment of the apparatus for measuring the amount of radioactive waste according to the present invention. FIG. 1 is a front sectional view of the apparatus for measuring the amount of corrosion, and FIG. FIG. 3 is a front cross-sectional view of a main part of a radioactive waste storage containing the corrosion amount measuring device, and FIG. 3 is a front cross-sectional view showing a conventional example of the radioactive waste storage. P ... Solidified package, 1 ... Cell room, 2 ... Concrete wall, 3 ... Transport room, 4 ... Ceiling slab, 5 ... Solidified package storage tube, 6 ... Support structure, 7 ... Outer tube , 8
…… Outside air inlet, 9 …… Air outlet, 10 …… Cooling air insertion passage, 11 …… Closing lid, 12 …… Cylinder space, 20 …… Corrosion amount measuring device, 21 …… Container, 21a, 21b …… Circulation hole, 22 ... Supporting tool, 23 ... Specimen
Claims (1)
パッケージ収納管(5)の一部に、内部に冷却空気を挿
通させるための導入口(15a)及び排気口(15b)が下部
及び上部に形成され、導入口及び排気口が形成された状
態の固化パッケージ収納管の内部に固化パッケージ
(P)に代えて収納され、パッケージの腐食量を測定す
るための腐食量測定装置(20)であって、前記パッケー
ジに類似させた形状に形成されるとともに冷却空気を流
通させるための流通孔(21a,21b)が上下に形成さてい
る容器(21)と、この容器内に支持具(22)により吊持
状態に支持された供試体(23)とを具備することを特徴
とする放射性廃棄物の腐食量測定装置。1. An inlet (15a) and an outlet (15b) for inserting cooling air into a lower part of a part of a solidified package storage pipe (5) arranged in a radioactive waste storage, and a lower part of the solidified package storage pipe (5). Corrosion amount measuring device (20) for measuring the corrosion amount of the package, which is housed in the solidified package storage pipe formed in the upper part with the introduction port and the exhaust port formed in place of the solidified package (P). A container (21) having a shape similar to that of the package and having vertically formed through holes (21a, 21b) for circulating cooling air, and a support (22) inside the container (21). ) A test piece (23) supported in a suspended state by (1), and a device for measuring the amount of corrosion of radioactive waste.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1990073614U JPH081485Y2 (en) | 1990-07-11 | 1990-07-11 | Equipment for measuring the amount of corrosion of radioactive waste |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1990073614U JPH081485Y2 (en) | 1990-07-11 | 1990-07-11 | Equipment for measuring the amount of corrosion of radioactive waste |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH0432063U JPH0432063U (en) | 1992-03-16 |
| JPH081485Y2 true JPH081485Y2 (en) | 1996-01-17 |
Family
ID=31612588
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP1990073614U Expired - Lifetime JPH081485Y2 (en) | 1990-07-11 | 1990-07-11 | Equipment for measuring the amount of corrosion of radioactive waste |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH081485Y2 (en) |
Family Cites Families (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS566927Y2 (en) * | 1980-01-16 | 1981-02-16 | ||
| JPS6442439U (en) * | 1987-09-08 | 1989-03-14 |
-
1990
- 1990-07-11 JP JP1990073614U patent/JPH081485Y2/en not_active Expired - Lifetime
Also Published As
| Publication number | Publication date |
|---|---|
| JPH0432063U (en) | 1992-03-16 |
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