JPS603590A - Detector for position of breakage of fuel - Google Patents
Detector for position of breakage of fuelInfo
- Publication number
- JPS603590A JPS603590A JP58110815A JP11081583A JPS603590A JP S603590 A JPS603590 A JP S603590A JP 58110815 A JP58110815 A JP 58110815A JP 11081583 A JP11081583 A JP 11081583A JP S603590 A JPS603590 A JP S603590A
- Authority
- JP
- Japan
- Prior art keywords
- water
- fuel
- damage
- sampling
- fuel assembly
- 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
-
- 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
Landscapes
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.
Description
【発明の詳細な説明】
〔発明の利用分野〕
本発明は、破損燃料検出装置に係シ、特に、冷却水槽内
で、燃料集合体を容器で密封し、容器内の水を採取する
破損燃料検出装置に関するものである。DETAILED DESCRIPTION OF THE INVENTION [Field of Application of the Invention] The present invention relates to a device for detecting damaged fuel, and in particular, a device for detecting damaged fuel in which a fuel assembly is sealed in a container in a cooling water tank and water in the container is collected. This invention relates to a detection device.
原子炉内に設置された燃料果合体が、破損しだ場合、そ
の原因を究明することは、燃料破損防止対策上、重要で
あシ、そのためには、燃料集合体の破損発生位置を把握
することが、有効な手段となる。When a fuel assembly installed in a nuclear reactor begins to break, it is important to investigate the cause in order to prevent fuel damage.To do this, it is necessary to understand the location of damage in the fuel assembly. This is an effective method.
つまり、破損発生位置の把握によって、破損発生位置の
出力履歴と破損との相関が明確にできるなど、破損原因
の推定に有効な手がかシを得て、以後の原子炉運転に反
映させるという観点から、破損位置の把握は非常に有用
なことである。In other words, by understanding the location of damage, it is possible to clearly correlate the output history of the location of damage with the damage, providing an effective basis for estimating the cause of damage, which can be reflected in future reactor operations. From this point of view, understanding the location of damage is very useful.
従来の燃料破損検出技術は１シヨツピング（Ｓ ｉｒ）
ｐｉｎｇ ）” として知られている。第１図をもとに
、この技術及び装置について以下に述べる。Conventional fuel failure detection technology is one-shotting (Sir)
This technique and apparatus will be described below with reference to FIG.
燃料集合体２は、まわシの冷却水と隔離するだめの容器
（ジッパカン１）の中に置かれ、給水管′３より純水が
供給さ扛、冷却水と置換される。その後、リサイクルポ
ンプ５による強制循環により、燃料から放出された放射
性物質が均一に純水中に拡散した状態になるまで、放置
した後、サンプリング管４よシ、ジッパカン１の中の水
をサンプリングする。このサンプリング水中の放射性物
質を測定することにより、燃料破損を検出する。The fuel assembly 2 is placed in a container (zipper can 1) that is isolated from the cooling water of the tank, and purified water is supplied from the water supply pipe '3 to replace the cooling water. Thereafter, the water in the zipper can 1 is sampled through the sampling tube 4 after being allowed to stand until the radioactive substances released from the fuel are uniformly diffused into the pure water through forced circulation by the recycle pump 5. . Fuel damage is detected by measuring radioactive substances in this sampled water.
このため、従来のシツピングでは、ジッパカン１の中の
水は、均一の放射能を持つことになり、燃料集合体長手
方向のどの位置で、破損が生じているか検出できなかっ
た。For this reason, in conventional shipping, the water in the zipper can 1 has uniform radioactivity, making it impossible to detect where damage has occurred in the longitudinal direction of the fuel assembly.
また、燃料破損位置を検出するための技術としては、燃
料集合体を解体し、個々の燃料棒の目視検査、渦電流探
傷試験等の方法がある。しかし、これらの方法は、非常
に時間を要する作業であり、よシ簡単な方法の実用化が
望まれている。Techniques for detecting the location of fuel damage include methods such as disassembling the fuel assembly, visual inspection of individual fuel rods, and eddy current testing. However, these methods are extremely time-consuming, and it is desired to put simpler methods into practical use.
本発明の目的は、燃料集合体の破損位置を容易に、かつ
安全に、検出できる装置を提供することにある。An object of the present invention is to provide a device that can easily and safely detect the location of damage to a fuel assembly.
本発明の特徴は、シンパ管１内の水を気体を供給するこ
とによシ押下げ、燃料が水中に没する部分を限定した場
合の水中に含まれる放射性物質の濃度を測定することに
よシ、破損位置を検出することにある。A feature of the present invention is that the water in the sympathizer tube 1 is pushed down by supplying gas, and the concentration of radioactive substances contained in the water is measured when the portion where the fuel is submerged in the water is limited. The main purpose is to detect the location of damage.
以下、本発明の実施例を第２図にもとづき説明する。 Hereinafter, embodiments of the present invention will be described based on FIG.
まず、ジッパカン１の中に、燃料集合体２を密閉する。First, the fuel assembly 2 is sealed inside the zipper can 1.
次に（１）から（＼りの手順によシ、水に浸る燃料集合
体２の高さを限定した時の水中に含まれる放射性物質の
濃度を測定する。Next, according to steps (1) to (\), the concentration of radioactive substances contained in the water is measured when the height of the fuel assembly 2 immersed in the water is limited.
＜＋＞ 弁１２と１５を開き、弁１３と１４を閉じ、気
体供給装置を駆動して、気体供給管６より気体を供給す
ることによシ、サンプリング管４からジッパカン１内の
水を燃料集合体２の下部まで抜く。<+> Open the valves 12 and 15, close the valves 13 and 14, drive the gas supply device, and supply gas from the gas supply pipe 6 to fuel the water in the zipper can 1 from the sampling pipe 4. Pull it out to the bottom of assembly 2.
（１１）弁１２を閉じ、１４を開いて、給水管３より純
水を供給し、ジッパカン１及びサンプリング管４内に残
っている水をサンプリング管４よシ排出てせ純水と置換
させる。(11) Close the valve 12, open the valve 14, supply pure water from the water supply pipe 3, and drain the water remaining in the zipper can 1 and the sampling pipe 4 through the sampling pipe 4 to replace it with pure water.
ＧＯＤ 弁１５を閉じ、１３を開いて、給水管３より
入純水を供給しながら、排気管７よシス体を徐々に抜き
、燃料集合体が浸る液面８の高さく水位）を水位計９に
よシ水中ペリスコープ等を用いて観察し、所定の高さに
調節する。GOD Close valve 15, open 13, and from water supply pipe 3
While supplying pure water, gradually remove the cis body through the exhaust pipe 7, and observe the water level (at the height of the liquid level 8 where the fuel assembly is immersed) using an underwater periscope etc. to the specified level. Adjust to height.
１１ＶＩ 液面８の高さが定寸ったら、すべての弁を閉
じ、一定時間その壕まで放置する。11VI When the height of the liquid level 8 is determined, close all the valves and leave it in the trench for a certain period of time.
Ｍ 一定時間放置した後、弁１２と１５を開き、気体供
給￥ｆ３から気体を供給し、サンプリング管４よシシツ
パカン１内の水をサンプリングタンク１０内に導く。M After leaving it for a certain period of time, open the valves 12 and 15, supply gas from the gas supply f3, and guide the water in the sampling tube 4 into the sampling tank 10.
付９ サンプリングタンク１０内でサンプリング水をか
く拌し、サンプリング水内の放射性物質濃度が均一にな
ったところで、少量のサンプリング水を抽出し、その放
射性物質の濃度を測定する。Appendix 9 The sampling water is stirred in the sampling tank 10, and when the radioactive material concentration in the sampling water becomes uniform, a small amount of the sampling water is extracted and the radioactive material concentration is measured.
以上の（１）からｑ）の手順をｅ、シ返し、水位を燃料
集合体２の下方から上方へ、一定間隔あるいは任意に変
化させて、放射性物質の濃度を測定する。The above steps (1) to q) are repeated e, and the water level is changed from below to above the fuel assembly 2 at regular intervals or arbitrarily, and the concentration of radioactive substances is measured.
このようにして得られたサンプリング水において、水位
が燃料の破損している箇所（破損位置）より下の場合の
サンプリング水中には、燃料よシ放出された放射性物質
が含ま扛ておらず、放射性物質の濃度は低い。一方、水
位が破損位置よシ上の場合のサンプリング水には、燃料
から放出された放射性物質が含まれているので、水位が
破損位置より下の場合に比べ、その放射性物質の濃度が
高くなる。In the sampling water obtained in this way, if the water level is below the damaged part of the fuel (damage position), the sampling water does not contain radioactive substances released from the fuel, and is radioactive. The concentration of the substance is low. On the other hand, since the sampled water when the water level is above the damage location contains radioactive materials released from the fuel, the concentration of radioactive materials will be higher than when the water level is below the damage location. .
このことより、水位を変化させた場合のサンプリング水
中の放射性物質の濃度を比較することにより破損位置が
容易に検出できる。Therefore, the location of the damage can be easily detected by comparing the concentration of radioactive substances in the sampled water when the water level is changed.
本発明によれば、燃料集合体の任意の長手方向位置まで
水に浸した場合の水中に含まれる放射性物質の濃度を測
定することが可能であシ、燃料集合体の解体を実施する
ことなく容易に破損位置が検出できる。According to the present invention, it is possible to measure the concentration of radioactive substances contained in water when a fuel assembly is immersed in water up to any longitudinal position, and without dismantling the fuel assembly. Damage position can be easily detected.
【図面の簡単な説明】
第１図は従来の破損検出装置の概略図、第２図は本発明
の一実施例を示すジッパカンの断面図である。
１・・・ジッパカン、２・・・燃料集合体、３・・・給
水管、４・・・サンプリング管、５・・・リサイクルモ
ータ、６・・・気体供給管、７・・・排気管、８・・・
液面、９・・・水位計、１０・・・サンプリングタンク
、１１・・・気体供給系 １ 目BRIEF DESCRIPTION OF THE DRAWINGS FIG. 1 is a schematic diagram of a conventional damage detection device, and FIG. 2 is a sectional view of a zipper can showing an embodiment of the present invention. DESCRIPTION OF SYMBOLS 1... Zipper can, 2... Fuel assembly, 3... Water supply pipe, 4... Sampling pipe, 5... Recycle motor, 6... Gas supply pipe, 7... Exhaust pipe, 8...
Liquid level, 9... Water level gauge, 10... Sampling tank, 11... Gas supply system 1st
Claims (1)
の水を採取し、この水の中に含まれている放射性物質を
測定することによシ、破損燃料の検出を行う装置におい
て、当該密封容器の下端部に純水注入管と排水管を、上
部に気体供給管と排気管を具備し、当該密封容器内の液
面を任意の高１位置まで押し下げることができるよう気
体を供給する装置と、液面の高さを検知する装置を具備
することを特徴とした燃料破損位置検出装置。1. A device that detects damaged fuel by sealing the fuel assembly in a container in a cooling water tank, sampling the water in the container, and measuring the radioactive substances contained in this water. , a pure water injection pipe and a drain pipe are provided at the lower end of the sealed container, and a gas supply pipe and an exhaust pipe are provided at the upper end. A fuel damage position detection device characterized by comprising a device for supplying liquid and a device for detecting the height of the liquid level.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58110815A JPS603590A (en) | 1983-06-22 | 1983-06-22 | Detector for position of breakage of fuel |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58110815A JPS603590A (en) | 1983-06-22 | 1983-06-22 | Detector for position of breakage of fuel |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS603590A true JPS603590A (en) | 1985-01-09 |
Family
ID=14545356
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP58110815A Pending JPS603590A (en) | 1983-06-22 | 1983-06-22 | Detector for position of breakage of fuel |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS603590A (en) |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2006029930A (en) * | 2004-07-15 | 2006-02-02 | Hitachi Ltd | Out-pile shipping device and method for nuclear fuel |
| JP2014232075A (en) * | 2013-05-30 | 2014-12-11 | 原子燃料工業株式会社 | Damage determination device for nuclear fuel |
| JP2015017877A (en) * | 2013-07-10 | 2015-01-29 | 原子燃料工業株式会社 | Damage determination device of fuel assembly |
-
1983
- 1983-06-22 JP JP58110815A patent/JPS603590A/en active Pending
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2006029930A (en) * | 2004-07-15 | 2006-02-02 | Hitachi Ltd | Out-pile shipping device and method for nuclear fuel |
| JP2014232075A (en) * | 2013-05-30 | 2014-12-11 | 原子燃料工業株式会社 | Damage determination device for nuclear fuel |
| JP2015017877A (en) * | 2013-07-10 | 2015-01-29 | 原子燃料工業株式会社 | Damage determination device of fuel assembly |
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