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JPH0316636B2 - - Google Patents
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JPH0316636B2 - - Google Patents

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Publication number
JPH0316636B2
JPH0316636B2 JP57065771A JP6577182A JPH0316636B2 JP H0316636 B2 JPH0316636 B2 JP H0316636B2 JP 57065771 A JP57065771 A JP 57065771A JP 6577182 A JP6577182 A JP 6577182A JP H0316636 B2 JPH0316636 B2 JP H0316636B2
Authority
JP
Japan
Prior art keywords
nuclear fuel
shipping
cap
caps
cylinders
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
Application number
JP57065771A
Other languages
Japanese (ja)
Other versions
JPS58182593A (en
Inventor
Shigeo Iida
Kaoru Kita
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 JP57065771A priority Critical patent/JPS58182593A/en
Publication of JPS58182593A publication Critical patent/JPS58182593A/en
Publication of JPH0316636B2 publication Critical patent/JPH0316636B2/ja
Granted legal-status Critical Current

Links

Classifications

    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Monitoring And Testing Of Nuclear Reactors (AREA)

Description

【発明の詳細な説明】 本発明は核燃料の漏洩検査装置に関する。[Detailed description of the invention] The present invention relates to a nuclear fuel leakage inspection device.

原子力発電プラントの核燃料はプラントの定期
検査時に所定の検査が実施され、その健全性が確
認されて燃焼率の小さいものは次回に再び使用さ
れる。ここで、核燃料の検査は主として破損等の
欠陥の有無、外観上の異常の有無について実施さ
れる。このうち核燃料の欠陥の有無の検査方法は
一般にシツピング検査と呼ばれており、現在、ガ
ス循環法、水サンプル法の2種が実施されてい
る。これらはいずれも被検査燃料を他の燃料等の
周囲条件より隔離してガスサンプルあるいは水サ
ンプルを分析し、バツクグラウンド(通常状態の
レベル)から放射性核種が増加しているか否かに
より核燃料の漏洩の有無を判定するものである。
Nuclear fuel in nuclear power plants is subjected to predetermined inspections during regular plant inspections, and if its soundness is confirmed, fuel with a low combustion rate is used again next time. Here, the nuclear fuel is inspected mainly for the presence of defects such as damage, and for the presence or absence of abnormalities in appearance. Among these methods, the method for testing the presence or absence of defects in nuclear fuel is generally called a shipping test, and two methods are currently in use: the gas circulation method and the water sample method. In both of these methods, the fuel to be inspected is isolated from the surrounding conditions of other fuels, etc., and a gas or water sample is analyzed, and whether radionuclides have increased from the background (normal state level) or not, the leakage of nuclear fuel is determined. This is to determine the presence or absence of.

従来、例えばガス循環法は第1図及び第2図に
示す如き検査装置を用いて行われている。
Conventionally, for example, the gas circulation method has been carried out using an inspection apparatus as shown in FIGS. 1 and 2.

第1図中1は原子炉容器であり、その炉心2に
は核燃料3…が装荷されている。一方、図中11
は内部に水が満たされた核燃料貯蔵ピツトであ
り、この貯蔵ピツト11内には核燃料3を収容し
てシツピング検査を行うためのシツピングキヤン
12が設けられている。また、前記貯蔵ピツト1
1上にはクレーン13がレール14,14上に移
動自在に設けられている。前記シツピングキヤン
12の上部開口には第2図に示す如くシツピング
キヤツプ15が着脱自在に嵌装されている。この
シツピングキヤツプ15にはサンプル管16が挿
入され、前記シツピングキヤツプ15によつて隔
離状態となつた前記シツピングキヤン12の上部
開口と連通している。前記サンプル管16には分
析部17が連結している。この分析部17には循
環ポンプ18が連結しており、更にこの循環ポン
プ18には前記シツピングキヤン12の下部と連
通する配管19が連結している。
1 in FIG. 1 is a nuclear reactor vessel, and the reactor core 2 is loaded with nuclear fuel 3. On the other hand, 11 in the figure
1 is a nuclear fuel storage pit filled with water, and within this storage pit 11 is provided a shipping can 12 for storing nuclear fuel 3 and carrying out a shipping inspection. In addition, the storage pit 1
A crane 13 is movably provided on rails 14, 14. A shipping cap 15 is detachably fitted into the upper opening of the shipping can 12, as shown in FIG. A sample tube 16 is inserted into the shipping cap 15 and communicates with the upper opening of the shipping can 12 isolated by the shipping cap 15. An analysis section 17 is connected to the sample tube 16. A circulation pump 18 is connected to the analysis section 17, and a pipe 19 communicating with the lower part of the shipping can 12 is connected to the circulation pump 18.

上述した検査装置によるシツピング検査は以下
のようにして行われる。
Shipping inspection by the above-mentioned inspection device is performed as follows.

まず、炉心2に装荷されていた核燃料3…は炉
心2より取り出され、一旦核燃料貯蔵ピツト11
内の例えばアングル材で構成された核燃料貯蔵ラ
ツクに収納される。次に、核燃料3はシツピング
検査を実施するため、クレーン13によりシツピ
ングキヤン12内へ1体づつ移される。この後、
循環ポンプ18を作動し、所定流量のガス(通常
高純度のN2ガス)を配管19を通して前記シツ
ピングキヤン12下部に供給し、順次サンプル管
16、分析部17、循環ポンプ18、配管19を
循環させる。この際、核燃料3に欠陥があれば、
前記ガス中に放射性ガス核種が放散蓄積される。
したがつて、分析部17においてガスを連続的に
分析することにより核燃料3の漏洩を検出でき
る。
First, the nuclear fuel 3... loaded in the reactor core 2 is taken out from the reactor core 2, and is temporarily transferred to the nuclear fuel storage pit 11.
The fuel is stored in a nuclear fuel storage rack made of, for example, angle material. Next, the nuclear fuels 3 are moved one by one into the shipping can 12 by the crane 13 in order to carry out a shipping inspection. After this,
The circulation pump 18 is operated and a predetermined flow rate of gas (usually high-purity N 2 gas) is supplied to the lower part of the shipping can 12 through the pipe 19, and the sample pipe 16, analysis section 17, circulation pump 18, and pipe 19 are sequentially connected. Circulate. At this time, if there is a defect in nuclear fuel 3,
Radioactive gas nuclides are diffused and accumulated in the gas.
Therefore, leakage of the nuclear fuel 3 can be detected by continuously analyzing the gas in the analysis section 17.

水サンプル法の場合は上述したガス循環法と同
様にシツピングキヤン12内に核燃料3を収容し
て隔離状態とし、所定時間経過後シツピングキヤ
ン12内の水をサンプリングして水中の放射線核
種を分析し、バツクグラウンドと比較することに
より核燃料3の漏洩を検出する。
In the case of the water sample method, similar to the gas circulation method described above, the nuclear fuel 3 is stored in the shipping can 12 and isolated, and after a predetermined period of time, the water in the shipping can 12 is sampled to detect radionuclides in the water. The leakage of the nuclear fuel 3 is detected by analyzing and comparing it with the background.

しかしながら、上述した従来のシツピング検査
においては第1図に示す如く、一旦核燃料貯蔵ピ
ツト11内に収納された200体近くの核燃料3…
を1体づつあらためてシツピングキヤン12内に
移送し、再び返却する必要があるため、操作が繁
雑となり核燃料取扱いの信頼性上不利であるう
え、定期検査時の検査作業時間が長くなるという
欠点がある。また、シツピングキヤン12を核燃
料貯蔵ピツト11内に設けるために該貯蔵ピツト
11が大型化し設備面でも不利である。
However, in the conventional shipping inspection described above, as shown in FIG.
Since it is necessary to transfer the nuclear fuel to the shipping can 12 one by one and return it again, the operation becomes complicated, which is disadvantageous in terms of the reliability of handling nuclear fuel, and the inspection work time during periodic inspections is lengthened. be. Furthermore, since the shipping can 12 is provided within the nuclear fuel storage pit 11, the storage pit 11 becomes larger, which is disadvantageous in terms of equipment.

本発明は上記事情に鑑みてなされたものであ
り、設備面の制約を減少し、核燃料の取扱い上の
信頼性向上及び検査の作業時間の短縮を達成し得
る核燃料の漏洩検査装置を提供しようとするもの
である。
The present invention has been made in view of the above circumstances, and it is an object of the present invention to provide a nuclear fuel leakage inspection device that can reduce restrictions on equipment, improve reliability in handling nuclear fuel, and shorten inspection work time. It is something to do.

以下、本発明を水サンプル法による核燃料の漏
洩検査装置に適用した実施例を第3図を参照して
説明する。
Hereinafter, an embodiment in which the present invention is applied to a nuclear fuel leakage inspection device using a water sample method will be described with reference to FIG.

図中21は水が満たされ選択的に原子炉容器に
連絡された核燃料貯蔵ピツトである。この貯蔵ピ
ツト21内には核燃料が個別に収容される多数本
の筒体(キヤン)22…が縦横に規則的に碁盤目
状に立設され、キヤン型核燃料貯蔵ラツクを構成
している。これら筒体22…の各々は収容された
核燃料の底部及び側面を包囲しうる構造を有して
いる。これら筒体22…のうちの十数本の上部開
口には各筒体22…に対応した複数の封冠部23
a…を有するシツピングキヤツプ23が同時に着
脱自在に嵌装され、各封冠部23a…は対応する
十数本の各筒体22…と協働して個別の隔離空間
を画成するようになつている。このキヤツプ23
は前記貯蔵ピツト21上に設けられたレール24
上に移動自在に取付けられたクレーン25からワ
イヤ26によつて引上げられ、貯蔵ラツクを構成
する他の筒体22…の上部開口にも同時に着脱自
在に嵌装されるようになつている。前記キヤツプ
23にはその封冠部23a…と協働して隔離され
た各々の貯蔵ラツク22…の上部開口に連通する
十数本のフレキシブルなサンプル管27…が挿入
されている。これらサンプル管27…は前記貯蔵
ピツト21全域をカバーできる長さを有する。ま
た、これらサンプル管27…はサンプリング装置
28と連結しており、更にサンプリング装置28
は分析器29と連結している。
In the figure, 21 is a nuclear fuel storage pit filled with water and selectively connected to the reactor vessel. Inside this storage pit 21, a large number of cylinders (cans) 22 in which nuclear fuel is individually housed are arranged vertically and horizontally in a regular grid pattern, forming a can-type nuclear fuel storage rack. Each of these cylindrical bodies 22 has a structure capable of surrounding the bottom and side surfaces of the nuclear fuel contained therein. A plurality of sealing parts 23 corresponding to each cylinder 22 are provided in the upper openings of more than ten of these cylinders 22.
The shipping caps 23 having a... are removably fitted at the same time, and each sealing portion 23a... cooperates with each of the corresponding ten or more cylinders 22... so as to define an individual isolated space. It's summery. This cap 23
is a rail 24 provided on the storage pit 21.
It is pulled up by a wire 26 from a crane 25 movably mounted above, and is simultaneously removably fitted into the upper openings of other cylindrical bodies 22 constituting the storage rack. More than ten flexible sample tubes 27 are inserted into the cap 23 and communicate with the upper openings of the respective isolated storage racks 22 in cooperation with the caps 23a. These sample tubes 27 have a length that can cover the entire area of the storage pit 21. Further, these sample tubes 27... are connected to a sampling device 28, and furthermore, the sampling device 28 is connected to a sampling device 28.
is connected to the analyzer 29.

上述した装置を用いた水サンプル法による核燃
料の漏洩検査は以下のようにして行われる。
A nuclear fuel leak test using the water sample method using the above-mentioned apparatus is carried out as follows.

まず、原子炉の炉心から核燃料30…をキヤン
型核燃料貯蔵ラツクを構成する各筒体22…に収
容した後、筒体22…のうちの十数本の上部開口
にシツピングキヤツプ23を同時に嵌装し該キヤ
ツプ23の封冠部23a…と協働して十数本の筒
体22…を個別に隔離する。次に、サンプリング
装置28によりサンプル管27…を通して前記キ
ヤツプ23を構成する各封冠部23a…で隔離さ
れた各々の筒体22…ごとに順次水をサンプリン
グし、分析器29により分析する。そして、バツ
クグラウンドより放射性核種が増加していれば、
核燃料30…の漏洩を検出できる。最初の十数本
の核燃料30…についてシツピング検査が終了す
れば、クレーン25により前記キヤツプ23を移
動させ、貯蔵ラツクを構成する他の十数本の筒体
22…の上部開口にキヤツプ23を同時に嵌装し
てそれら筒体22…をキヤツプ23の封冠部23
a…で隔離して同様にシツピング検査を行う。
First, after storing the nuclear fuel 30 from the core of the reactor into each cylinder 22 constituting the can-type nuclear fuel storage rack, the shipping caps 23 are simultaneously fitted into the upper openings of more than ten of the cylinders 22. In cooperation with the sealing portions 23a of the caps 23, the ten or more cylindrical bodies 22 are individually isolated. Next, water is sequentially sampled by the sampling device 28 through the sample tubes 27 from each of the cylindrical bodies 22 separated by the caps 23a constituting the cap 23, and analyzed by the analyzer 29. And if the radionuclides increase compared to the background,
Leakage of nuclear fuel 30... can be detected. When the shipping inspection for the first ten or more nuclear fuels 30 is completed, the crane 25 moves the cap 23 and simultaneously inserts the cap 23 into the upper opening of the other ten or so cylinders 22 that make up the storage rack. The cylindrical bodies 22 are fitted into the cap 23 and attached to the cap 23.
Isolate in a... and conduct a shipping inspection in the same way.

しかして上記検査装置によれば、キヤン型核燃
料貯蔵ラツクを構成する十数本の筒体22…の上
部開口に各筒体22…に対応した複数の封冠部2
3a…を有するシツピングキヤツプ23を同時に
嵌装することにより各筒体22…を個々に隔離状
態にして核燃料30…のシツピング検査を行うこ
とができる。したがつて、従来のように核燃料貯
蔵ピツト内に別途シツピングキヤンを設ける必要
がなく、貯蔵ピツトの小型化が可能となり設備面
で有利となる。また、一旦核燃料貯蔵ラツクに収
納された核燃料を1体づつシツピングキヤンに移
送する作業がなくなるので、核燃料取扱い上の信
頼性向上に大きく寄与するばかりでなく、核燃料
の漏洩検査の作業時間の大幅な低減、ひいてはプ
ラント定期検査の作業時間短縮にも大きく寄与す
る。
However, according to the above-mentioned inspection apparatus, a plurality of sealing parts 2 corresponding to each cylinder 22 are formed in the upper openings of more than ten cylinders 22 constituting the can-type nuclear fuel storage rack.
By simultaneously fitting the shipping caps 23 having the cylinders 3a, it is possible to conduct a shipping inspection of the nuclear fuel 30 while keeping each cylinder body 22 individually isolated. Therefore, there is no need to provide a separate shipping can inside the nuclear fuel storage pit as in the past, and the storage pit can be made smaller, which is advantageous in terms of equipment. In addition, since the work of transporting nuclear fuel stored in the nuclear fuel storage rack one by one to the shipping can is eliminated, it not only greatly contributes to improving the reliability of handling nuclear fuel, but also significantly reduces the time required for nuclear fuel leakage inspection. It also greatly contributes to reducing the amount of time required for periodic plant inspections.

なお、上記検査装置においてサンプル水の分析
を自動化し、シーケンシヤルに十数本分の水をサ
ンプル分析できるようにすれば、作業時間をより
一層短縮することができる。
In addition, if the analysis of sample water is automated in the above-mentioned inspection device, and ten or more bottles of water can be analyzed sequentially, the working time can be further shortened.

また、ガスを循環する制循ポンプ及びこの循環
ポンプに連結し、キヤン型核燃料貯蔵ラツクの下
部に連通するガス配管を設けることによりガス循
環法による核燃料の漏洩検査にも同様に適用でき
る。
Furthermore, by providing a circulation control pump that circulates gas and a gas pipe connected to the circulation pump and communicating with the lower part of the can-type nuclear fuel storage rack, the present invention can be similarly applied to nuclear fuel leakage inspection using the gas circulation method.

また、シツピングキヤツプは上記実施例の如く
十数本分を検査できるものに限らず、クレーンに
よる操作性、サンプリング装置等に応じて検査し
得る本数を増減できる。
Further, the shipping cap is not limited to one capable of inspecting ten or more vessels as in the above embodiment, but the number of vessels that can be inspected can be increased or decreased depending on the operability of the crane, the sampling device, etc.

以上詳述した如く本発明によれば、設備面の制
約を受けることなく、核燃料の取扱い上の信頼性
を向上できるとともに検査の作業時間を大幅に短
縮し得る核燃料の漏洩検査装置を提供できるもの
である。
As detailed above, according to the present invention, it is possible to provide a nuclear fuel leakage inspection device that can improve reliability in handling nuclear fuel and significantly shorten inspection work time without being subject to equipment restrictions. It is.

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

第1図は従来の核燃料の漏洩検査装置の概略を
示す平面図、第2図は同装置の側面図、第3図は
本発明の実施例における核燃料の欠陥検査装置を
示す側面図である。 21……核燃料貯蔵ピツト、22……筒体、2
3……シツピングキヤツプ、23a……封冠部、
24……レール、25……クレーン、26……ワ
イヤ、27……サンプル管、28……サンプリン
グ装置、29……分析器、30……核燃料。
FIG. 1 is a plan view schematically showing a conventional nuclear fuel leakage inspection device, FIG. 2 is a side view of the same device, and FIG. 3 is a side view showing a nuclear fuel defect inspection device in an embodiment of the present invention. 21...Nuclear fuel storage pit, 22...Cylinder body, 2
3... Shipping cap, 23a... Crowning section,
24...Rail, 25...Crane, 26...Wire, 27...Sample tube, 28...Sampling device, 29...Analyzer, 30...Nuclear fuel.

Claims (1)

【特許請求の範囲】[Claims] 1 水が満たされ選択的に原子炉容器に連絡され
る格納室と、該格納室内に設けられ、核燃料を個
別に収容して核燃料の底部及び側面を包囲する筒
体を縦横に規則的に多数本立設させた核燃料貯蔵
ラツクと、前記筒体のうち複数本の筒体の上部開
口に同時に着脱自在に嵌装され、各筒体に対応し
各筒体と協働して個別の隔離空間を画成する複数
の封冠部を有するキヤツプと、該キヤツプの封冠
部によつて隔離された各々の筒体の上部開口に連
通する複数のサンプル管と、これらサンプル管と
連結する分析器とを具備したことを特徴とする核
燃料の漏洩検査装置。
1. A containment chamber filled with water and selectively connected to the reactor vessel, and a large number of regularly spaced cylinders vertically and horizontally provided within the containment chamber, individually containing nuclear fuel, and surrounding the bottom and sides of the nuclear fuel. The nuclear fuel storage rack is installed vertically and the upper openings of a plurality of cylinders are removably fitted at the same time, corresponding to each cylinder and working together to create individual isolated spaces. A cap having a plurality of caps defining a plurality of caps, a plurality of sample tubes communicating with an upper opening of each cylinder isolated by the cap of the cap, and an analyzer coupled to the sample tubes. A nuclear fuel leakage inspection device characterized by comprising:
JP57065771A 1982-04-20 1982-04-20 Nuclear fuel failure inspecting device Granted JPS58182593A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP57065771A JPS58182593A (en) 1982-04-20 1982-04-20 Nuclear fuel failure inspecting device

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP57065771A JPS58182593A (en) 1982-04-20 1982-04-20 Nuclear fuel failure inspecting device

Publications (2)

Publication Number Publication Date
JPS58182593A JPS58182593A (en) 1983-10-25
JPH0316636B2 true JPH0316636B2 (en) 1991-03-06

Family

ID=13296617

Family Applications (1)

Application Number Title Priority Date Filing Date
JP57065771A Granted JPS58182593A (en) 1982-04-20 1982-04-20 Nuclear fuel failure inspecting device

Country Status (1)

Country Link
JP (1) JPS58182593A (en)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5994098A (en) * 1982-11-19 1984-05-30 原子燃料工業株式会社 Method and device for inspecting leakage of nuclear fuel assembly

Also Published As

Publication number Publication date
JPS58182593A (en) 1983-10-25

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