JPS59176642A - Method for inspecting leakage of vessel for transporting spent nuclear fuel - Google Patents
Method for inspecting leakage of vessel for transporting spent nuclear fuelInfo
- Publication number
- JPS59176642A JPS59176642A JP58051236A JP5123683A JPS59176642A JP S59176642 A JPS59176642 A JP S59176642A JP 58051236 A JP58051236 A JP 58051236A JP 5123683 A JP5123683 A JP 5123683A JP S59176642 A JPS59176642 A JP S59176642A
- Authority
- JP
- Japan
- Prior art keywords
- inspection
- pipe
- helium
- leakage
- valve
- 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
Links
Classifications
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01M—TESTING STATIC OR DYNAMIC BALANCE OF MACHINES OR STRUCTURES; TESTING OF STRUCTURES OR APPARATUS, NOT OTHERWISE PROVIDED FOR
- G01M3/00—Investigating fluid-tightness of structures
- G01M3/02—Investigating fluid-tightness of structures by using fluid or vacuum
- G01M3/04—Investigating fluid-tightness of structures by using fluid or vacuum by detecting the presence of fluid at the leakage point
- G01M3/20—Investigating fluid-tightness of structures by using fluid or vacuum by detecting the presence of fluid at the leakage point using special tracer materials, e.g. dye, fluorescent material, radioactive material
- G01M3/202—Investigating fluid-tightness of structures by using fluid or vacuum by detecting the presence of fluid at the leakage point using special tracer materials, e.g. dye, fluorescent material, radioactive material using mass spectrometer detection systems
Landscapes
- Physics & Mathematics (AREA)
- General Physics & Mathematics (AREA)
- Examining Or Testing Airtightness (AREA)
Abstract
Description
【発明の詳細な説明】
本発明は使用済核燃料輸送容器の漏洩検査方法に関する
。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a method for inspecting spent nuclear fuel transportation containers for leakage.
使用済核燃料輸送容器（以下、＋ヤスクと称す）は、密
封性が要求されるため、輸送前において漏洩検査か義務
づけられている。従来、上記漏洩検査方法として、その
検査箇所手前内方部を加圧してその減圧を調べていたが
、＋セスク自体の温度が高いため正確な漏洩検査を行な
うこ々ができなかったし、また検査箇所外方部を真空に
して内方部からの漏れを検出する方法が考えられるが、
通常、士セスク内には水が封入されるため、その検査箇
所に水が付着し、従って真空時に、付着した水が蒸発し
て所定の真空度に達するのに時間を要するという問題か
ある。Spent nuclear fuel transport containers (hereinafter referred to as +Yasks) must be airtight, so leakage testing is required before transport. Conventionally, the leakage test method described above was to pressurize the inner part in front of the inspection point and check for depressurization, but because the temperature of the sesquish itself was high, it was not possible to perform an accurate leakage test, and One possible method is to vacuum the outside of the inspection area and detect leakage from the inside.
Normally, water is sealed inside the chamber, so water adheres to the inspection area.Therefore, when a vacuum is applied, there is a problem in that it takes time for the adhering water to evaporate and reach a predetermined degree of vacuum.
そこで、本発明は上記問題を解消し得る使用済核燃料輸
送容器の漏洩検査方法を提供することを目的とする。SUMMARY OF THE INVENTION An object of the present invention is to provide a leakage inspection method for a spent nuclear fuel transport container that can solve the above-mentioned problems.
即ち、本発明は漏洩検査箇所における容器本体側の内方
部にヘリウムガスを供給加圧し、次に漏洩検査箇所にお
ける外方部を真空ポンプで吸引した後、該外方部に漏洩
するヘリウムガス量を検出することを特徴とする使用済
核燃料輸送容器の漏洩検査方法でかかる方法によると、
ヘリウムガスを使用しているので、従来のように、ただ
容器本体側内方部の空気を加圧する場合に比べて温度の
影響を受けないので、検査精度が向上し、また従来のよ
うに空気洩れを検出する場合とは異なり、ヘリウムガス
を検出するので、外方部の真空達成度Ｆｉ少々悪くても
あまシ検査精度に影響を与えることがなく、従って検査
時間の短縮化を図ることができる。That is, the present invention supplies and pressurizes helium gas to the inside part of the container body at the leakage inspection location, then sucks the exterior part of the leakage inspection location with a vacuum pump, and then removes the helium gas leaking into the exterior part. According to this method of leakage inspection method for spent nuclear fuel transportation containers, which is characterized by detecting the amount of
Since helium gas is used, it is not affected by temperature compared to the conventional method of simply pressurizing the air inside the container body, improving inspection accuracy. Unlike the case of detecting leaks, since helium gas is detected, even if the degree of vacuum achievement Fi in the outer part is slightly poor, it does not affect the inspection accuracy, and therefore the inspection time can be shortened. can.
以ｒ１本発明の第１Ａ実施例を第１図に基づき脱すノす
る。（１ンは使用済核燃料輸送容器（以下、単に＋セス
ク七称す）（２）の容器本体で、その途中には例えば容
器本体（１）内の水位を調節するための第１パルプ（３
）が設けられると共に、この第１バルブ（３）には短管
（内方部）（４）を介して第２バルブ（５）が取付けら
れている。（６）は漏洩検査装置で、ヘリウムボンベ（
７）と、真空ポンプ（８）と、ヘリウムガス検出器（９
）と、これら各機器（７） （８） （９）と第２バル
ブ（５）とを第１枝管四、第２技管αυ、第３枝管（６
）を介して連通ずる連通管（外方部）ａ３と、各枝管α
（０１υ＠にそれぞれ設けられた第３、第４、第５パル
づ０４１（１５（ｌｆ９と、連通管Ｑ３途中に取付けら
れた圧力計Ｑ７）とから構成されている。Hereinafter, the 1A embodiment of the present invention will be explained based on FIG. (1) is the container body of the spent nuclear fuel transport container (hereinafter simply referred to as +Sesku 7) (2), and in the middle there is a first pulp (3) for adjusting the water level in the container body (1).
), and a second valve (5) is attached to the first valve (3) via a short pipe (inner part) (4). (6) is a leak detection device, which is used for helium cylinders (
7), a vacuum pump (8), and a helium gas detector (9).
), these devices (7) (8) (9) and the second valve (5) are connected to the first branch pipe 4, the second technical pipe αυ, and the third branch pipe (6
) and each branch pipe α.
(It is composed of the third, fourth, and fifth pulses 041 (15 (lf9) and a pressure gauge Q7 installed in the middle of the communication pipe Q3) provided at the 01υ@, respectively.
次に、上記構成において、外界との遮断を図る第２バル
ブ（漏洩検査箇所）（５）からの漏洩を検出する手順に
ついて説明する。まず、すべてのパルづ（３）（５）
ｔ１４） Ｑｆ９ （１・を閉じると共に、真空ポンプ
（８）及びヘリウムガス検出器（９）を作動させる。次
に、第２パルづ（５）及び第４パルづＱ５１を開いて、
短管（４）及び連通管ＣＩ罎内を真空引きし、所定の負
圧になったら第４パルプαＱを閉じる。次に、第３パル
づσ４を開き、短管（４）及び連通管α１内にヘリウム
ガスを供給して所定圧力まで加圧した後、第２及び第３
バルブ（５） （１４を閉じる。次に、第４パルづＱＱ
を開き、連通管＠内のヘリウムガスを吸引し、所定の負
圧になったら第４パルプ（へ）を閉じる。次に、第５パ
ル″ｊｕＱを開いて連通管Ｑ３内のヘリウムガス量（Ｖ
＋）を検出した後、第５バルブα・を閉じる。そして、
所定時間経過後、再び第５バルブｑ・を開いてヘリウム
カス量（Ｖりを検出して、第５パル″ｊ１．ＩＱを閉じ
る。Next, in the above configuration, a procedure for detecting leakage from the second valve (leakage inspection location) (5) that is intended to be isolated from the outside world will be described. First of all, all pals (3) (5)
t14) Close Qf9 (1) and operate the vacuum pump (8) and helium gas detector (9). Next, open the second pulse (5) and the fourth pulse Q51,
The short pipe (4) and the communication pipe CI are evacuated, and when a predetermined negative pressure is reached, the fourth pulp αQ is closed. Next, the third pulse σ4 is opened and helium gas is supplied into the short pipe (4) and the communication pipe α1 to pressurize it to a predetermined pressure.
Valve (5) (Close 14. Next, 4th pulse QQ
is opened, the helium gas inside the communicating tube is sucked out, and when the predetermined negative pressure is reached, the fourth pulp is closed. Next, open the fifth pulse "juQ" to open the helium gas amount (V
+), the fifth valve α・ is closed. and,
After a predetermined time has elapsed, the fifth valve q is opened again to detect the amount of helium scum (V), and the fifth pulse ``j1.IQ'' is closed.
従って、上記最初の検出ヘリウムガス量（Ｖ、）と所定
時間経過後の検出ヘリウムガス量（ｖｚ）＜！：の差が
漏洩した量である。Therefore, the first detected helium gas amount (V,) and the detected helium gas amount after a predetermined time (vz)<! : The difference is the amount of leakage.
次に、第２の実施例として、士Ｐスクの各部例えば水位
調整バルブ部（ロ）、ベントバルブ部（イ）、シール部
（ハ）及びドレンパルづ部（ハ）における漏洩検出方法
を第２図に基づき説明する。なお、第２図中、（ハ）ｅ
ま士セスク（４）の蓋に）に取付けられた水位調整管に
）の上端に設けられた第１水位調整パルプ、（イ）は第
１水位調整パルプに）に第１短管曽を介して接続された
第２水位調整バルブ、０◇は蓋に）に設けられたベシト
バルプ、に）け蓋に）と容器本体−とのシール（ロ）■
間の漏洩を検査するための検査穴、（７）は容器本体に
）下部に穿設されたドレシ穴に）端部に設けられた第１
ドレンパルづ、＠は第１ドレンパルづ（至）に第２短管
（至）を介して接続された第２ドレンパルづである。（
至）は漏洩検査装置で、ヘリウムボンベｈｃ＞と、真空
ポンプθ復と、ヘリウムガス検出器（６）と、これら各
機器−（ロ）■と第２水位調整バルー＞翰とを第１１枝
管−１第１２技管（財）、第１３枝管に）、第１４技管
四を介して連通ずる第１連通管値力と、ベントパル″ｊ
６υと第１２技管−とを連通ずる第２連通管（ト）と、
検査穴に）と第１２杖管■とを連通ずる第３連通管（ト
）と、第２ドレンパルづ（ロ）と第１２杖管（財）とを
連通ずる第４連通管−と、第４連通管（４）と第１１枝
管（財）とを連通ずる第５連通管６υと、各枝管−〜■
及び各連通管１７１−ｆ！ｉυ途中に設けられた第１１
〜第１９パルプ６→〜…と、第１１技管−に設けられた
圧力計ゆ１）し、第１３技管に）に設けられた真空計−
とから構成されている。Next, as a second example, a leakage detection method in each part of the water level adjustment valve part (b), vent valve part (a), seal part (c), and drain valve part (c) of the water level adjustment valve part (c) will be described. This will be explained based on the diagram. In addition, in Figure 2, (c) e
The first water level adjusting pulp installed at the upper end of the water level adjusting pipe attached to the water level adjusting pipe attached to the lid of the water tank (4), and the first water level adjusting pulp attached to the first water level adjusting pulp in The second water level adjustment valve connected to
An inspection hole (7) is a drain hole drilled at the bottom of the container body, and a first hole at the end.
The drain pulse @ is the second drain pulse connected to the first drain pulse via the second short pipe. (
(to) is a leakage inspection device, which includes a helium cylinder hc>, a vacuum pump θ, a helium gas detector (6), each of these devices (b)■, and a second water level adjustment balloon>to the 11th branch. Pipe-1 12th Technical Pipe (Incorporated), 13th Branch Pipe), 14th Technical Pipe 4 which communicates with the first connecting pipe, and vent pal "j"
A second communication pipe (G) that communicates 6υ with the 12th technical pipe,
A third communication pipe (G) that communicates with the inspection hole) and the 12th cane pipe (G), a fourth communication pipe that communicates the second drain pal (B) with the 12th cane pipe (G), The 5th communicating pipe 6υ that connects the 4th communicating pipe (4) and the 11th branch pipe (goods), and each branch pipe - ~■
and each communication pipe 171-f! No. 11 established on the way to iυ
〜19th pulp 6→〜..., the pressure gauge installed in the 11th technical tube 1), and the vacuum gauge installed in the 13th technical tube 1)
It is composed of.
次に、各部分の漏洩検査手順について説明する。Next, the leakage inspection procedure for each part will be explained.
まず、すべてのパルプ帽１ル（７）＠＠〜−を閉じると
共に、真空ポンプ（ロ）及びヘリウムガス検出器（６）
を作動させる。次に、第１及び第２水位調整パルづ帽転
第１１バルブに）、第１２パルづ鏝を開いて、容器本体
に）内にヘリウムガスを供給すると共に所定圧力に加圧
した後、第１水位調整パルプに）、第１１バルブ（財）
、第１２パルづ輪を閉じる。First, close all the pulp caps (7) @@~-, and also close the vacuum pump (b) and helium gas detector (6).
Activate. Next, the first and second water level adjustment pulses are opened (to the 11th valve) and the 12th pulse is opened to supply helium gas into the container body (to the container body) and pressurize it to a predetermined pressure. 1 water level adjustment pulp), 11th valve (goods)
, close the 12th pulse ring.
次に、第１３及び第１４バルブ軸曽、第１６〜第１８パ
ルプ＠−輪を関き、各管内を所定の負圧まで真空引きす
る。次に、第１３パルプ−１第１４パルづ■、第１７バ
ルプ岐、第１８パルプ−を閉じ、そして第１５パルプ卿
を開き、ベントバルブ６ルより漏洩するヘリウムカス量
を検出した後、第１６バルプｑを閉じる。次に、第１７
バルブ□□□を開き、シール（ロ）［有］間から漏洩す
るヘリウムガス量を検出する。次に、曲記第１の実施例
と同様の手順で第２水位調整バルブ（支）及び第２ドレ
ンパルプ（ロ）からの漏洩を検出する。Next, the 13th and 14th valve shafts and the 16th to 18th pulp rings are connected to evacuate the inside of each pipe to a predetermined negative pressure. Next, close the 13th pulp-1 14th pulp, the 17th valve branch, and the 18th pulp, open the 15th pulp, and after detecting the amount of helium scum leaking from the vent valve 6, 16 Close valve q. Next, the 17th
Open the valve □□□ and detect the amount of helium gas leaking between the seals (B) and [Yes]. Next, leakage from the second water level adjustment valve (support) and the second drain pulp (b) is detected using the same procedure as in the first embodiment.
ｈ ａｗ方法によると、ヘリウムガスを使用しているの
で、従来のように、ただ容器本体側内方部の空気を加圧
する場合に比べて温度の影響を受けないので、検査精度
が向Ｅし、また従来のように空気洩れを検出する場合と
け異なり、ヘリウムガス検出器
てもあまり検査精度に影響を与えることがなく、従って
検査時間の短縮化を図ることができる。According to the h aw method, since helium gas is used, it is not affected by temperature compared to the conventional method of simply pressurizing the air inside the container body, so the inspection accuracy is improved. Also, unlike the conventional method for detecting air leaks, the use of a helium gas detector does not significantly affect the inspection accuracy, and therefore the inspection time can be shortened.
第１図は本発明のｇｇｌ実施例の概略構成図、第２図は
第２実施例の概略構成図である。
（１）・・容器本体、（２）・・・使用済核燃料輸送容
器（十セスク）（３）・・第１バルブ、（４）・・短管
（内方部）、（５）・・・第２パルプ、（６）・・漏洩
検査装置、（７）・・・ヘリウムボンベ、（８）・・真
空ポンプ、（９）・ヘリウムガス検出器、曹・・・連通
管（外方＃）（ロ）−・・水位調整バルブ部、（イ）・
・・ベントバルブ部、（ト）・・・シール部、■・・ド
レンバルブ部、に）・・・第１水位ｍ整パルプ、（ハ）
・・・＋セスタ、（２）・・・第２水位調整バルブ、（
至）・・・第１短管、０η・・・ベントバルブ、（イ）
・・・検査穴、曽・・・容器本体、（至）・・・シール
、μｓ・・・第１ドレンバルブ、（ロ）・・・第２ドレ
ンパルプ、（至）・・・第２短管、■・・・漏洩検査装
置、−・・・ヘリウムボンベ、（ロ）・・真空ポンプ、
（６）・・・ヘリウムガス検出器、１′ｉ）・・・第１
連通管、（財）・・・第２連通管、（６）・−・第３連
通管、■・・・第４連通管代理人 森 木 義
弘FIG. 1 is a schematic diagram of a ggl embodiment of the present invention, and FIG. 2 is a schematic diagram of a second embodiment. (1)... Container body, (2)... Spent nuclear fuel transport container (10 sescs) (3)... First valve, (4)... Short pipe (inner part), (5)...・Second pulp, (6)・Leak inspection device, (7)・Helium cylinder, (8)・Vacuum pump, (9)・Helium gas detector, Soda・Communication pipe (outer # ) (B) - Water level adjustment valve section, (A) -
... Vent valve part, (g)... Seal part, ■... Drain valve part, )... First water level adjustment pulp, (c)
...+Cesta, (2)...Second water level adjustment valve, (
To)...1st short pipe, 0η...Vent valve, (A)
...Inspection hole, So...Container body, (To)...Seal, μs...First drain valve, (B)...Second drain pulp, (To)...Second short pipe , ■...Leakage inspection device, -...Helium cylinder, (B)...Vacuum pump,
(6)...Helium gas detector, 1'i)...1st
Communication pipe, (foundation)...Second communication pipe, (6)...Third communication pipe,■...Fourth communication pipe Agent Yoshi Moriki
Hiroshi
Claims (1)
ウムガスを供給加圧し、次に漏洩検査箇所における外方
部を真空ポンプで吸引した後、該外方部に漏洩するヘリ
ウムガス量を検出することを特徴とする使用済核燃料輸
送容器の漏洩検査方法。l. Supply and pressurize helium gas to the inside part of the container body side at the leakage inspection point, then suck the outside part of the leakage inspection point with a vacuum pump, and then detect the amount of helium gas leaking to the outside part. A leakage inspection method for a spent nuclear fuel transport container.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58051236A JPS59176642A (en) | 1983-03-25 | 1983-03-25 | Method for inspecting leakage of vessel for transporting spent nuclear fuel |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58051236A JPS59176642A (en) | 1983-03-25 | 1983-03-25 | Method for inspecting leakage of vessel for transporting spent nuclear fuel |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS59176642A true JPS59176642A (en) | 1984-10-06 |
Family
ID=12881309
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP58051236A Pending JPS59176642A (en) | 1983-03-25 | 1983-03-25 | Method for inspecting leakage of vessel for transporting spent nuclear fuel |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS59176642A (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH01182731A (en) * | 1988-01-14 | 1989-07-20 | Nippon Atom Ind Group Co Ltd | Testing airtight performance of sealed container |
| JP2010509579A (en) * | 2006-11-08 | 2010-03-25 | コミッサリヤ ア レネルジ アトミック | Apparatus for transporting nuclear fuel and method for loading / unloading said apparatus |
-
1983
- 1983-03-25 JP JP58051236A patent/JPS59176642A/en active Pending
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH01182731A (en) * | 1988-01-14 | 1989-07-20 | Nippon Atom Ind Group Co Ltd | Testing airtight performance of sealed container |
| JP2010509579A (en) * | 2006-11-08 | 2010-03-25 | コミッサリヤ ア レネルジ アトミック | Apparatus for transporting nuclear fuel and method for loading / unloading said apparatus |
| JP2013242322A (en) * | 2006-11-08 | 2013-12-05 | Commissariat A L'energie Atomique | Device for transportation of nuclear fuel and method for loading/unloading the device |
| US8855260B2 (en) | 2006-11-08 | 2014-10-07 | Commissariat A L'energie Atomique | Device for the transportation of nuclear fuel and method for loading/unloading of the said device |
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