JPS6139999Y2 - - Google Patents
Info
- Publication number
- JPS6139999Y2 JPS6139999Y2 JP1979075925U JP7592579U JPS6139999Y2 JP S6139999 Y2 JPS6139999 Y2 JP S6139999Y2 JP 1979075925 U JP1979075925 U JP 1979075925U JP 7592579 U JP7592579 U JP 7592579U JP S6139999 Y2 JPS6139999 Y2 JP S6139999Y2
- Authority
- JP
- Japan
- Prior art keywords
- measuring
- measuring tank
- tank
- filter
- pipe
- 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
Links
- 239000000446 fuel Substances 0.000 claims description 23
- 238000001514 detection method Methods 0.000 claims description 13
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 19
- 238000001914 filtration Methods 0.000 description 9
- 230000000712 assembly Effects 0.000 description 7
- 238000000429 assembly Methods 0.000 description 7
- 238000005070 sampling Methods 0.000 description 7
- 238000004140 cleaning Methods 0.000 description 3
- 238000004891 communication Methods 0.000 description 3
- 238000010586 diagram Methods 0.000 description 3
- 238000005259 measurement Methods 0.000 description 3
- NWUYHJFMYQTDRP-UHFFFAOYSA-N 1,2-bis(ethenyl)benzene;1-ethenyl-2-ethylbenzene;styrene Chemical compound C=CC1=CC=CC=C1.CCC1=CC=CC=C1C=C.C=CC1=CC=CC=C1C=C NWUYHJFMYQTDRP-UHFFFAOYSA-N 0.000 description 2
- 239000000498 cooling water Substances 0.000 description 2
- 238000005202 decontamination Methods 0.000 description 2
- 238000005342 ion exchange Methods 0.000 description 2
- 239000003456 ion exchange resin Substances 0.000 description 2
- 229920003303 ion-exchange polymer Polymers 0.000 description 2
- 230000005855 radiation Effects 0.000 description 2
- 230000002411 adverse Effects 0.000 description 1
- 238000005341 cation exchange Methods 0.000 description 1
- 238000005253 cladding Methods 0.000 description 1
- 230000008878 coupling Effects 0.000 description 1
- 238000010168 coupling process Methods 0.000 description 1
- 238000005859 coupling reaction Methods 0.000 description 1
- 230000003588 decontaminative effect Effects 0.000 description 1
- 238000003113 dilution method Methods 0.000 description 1
- 230000005251 gamma ray Effects 0.000 description 1
- 231100001261 hazardous Toxicity 0.000 description 1
- 238000007689 inspection Methods 0.000 description 1
- 239000007788 liquid Substances 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 230000000737 periodic effect Effects 0.000 description 1
- 239000000941 radioactive substance Substances 0.000 description 1
- 239000002699 waste material Substances 0.000 description 1
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)
Description
【考案の詳細な説明】
本考案は原子炉の炉心に装荷された燃料集合体
の破損燃料検出装置に関する。[Detailed Description of the Invention] The present invention relates to a device for detecting damaged fuel in a fuel assembly loaded in the core of a nuclear reactor.
一般に原子炉の炉心に装荷される燃料集合体は
運転中、何らかの原因で被覆管に亀裂を生じる可
能性があり、これに起因して放射線漏れ等の事故
が生じるおそれがある関係上、炉心に装荷された
燃料集合体の健全性を図るために、定期検査が義
務付けられており、燃料破損事故の早期発見を図
つている。特に、軽水型原子炉における燃料集合
体では“シツピング装置”と称する破損燃料検出
装置が採用されている。 In general, during operation of the fuel assemblies loaded into the core of a nuclear reactor, cracks may occur in the cladding for some reason, and this may cause accidents such as radiation leakage. Periodic inspections are required to ensure the integrity of loaded fuel assemblies, and the aim is to detect fuel damage accidents early. In particular, a fuel assembly in a light water reactor employs a damaged fuel detection device called a "shipping device."
従来技術のシツピング装置を第１図を参照して
説明する。 A prior art shipping device will be described with reference to FIG.
原子炉に装荷された燃料集合体はその上端を支
持している上部格子板１により４個の燃料集合体
２が１組とされて取付けられている。この格子板
１を通じて各燃料集合体２の冷却水を採取るため
のカツプリング配管４を接続し、弁２３を介して
計量槽５に接続する。計量槽５にはオーバフロー
配管１１が設けてあり、溢流した試料水は弁２４
を通つてドレイン配管１９に捨てられる。計量槽
５は配管１２に連結され、弁２７を介してイオン
交換樹脂槽７に接続している。真空ポンプ１０を
作動させ、弁２３，２６，３４，３５を開き試料
水を配管４を通じて計量槽５に導く。計量槽５で
計量された試料水は弁２７を開けると配管１２を
通つてイオン交換樹脂槽７に入つてくる。イオン
分離し陽イオン交換脂中に捕捉された放射性核種
は、ガンマ線検出器２１によつて検出され、波高
分析器２２で信号分離される。 The fuel assemblies loaded in the nuclear reactor are attached as a set of four fuel assemblies 2 by an upper grid plate 1 that supports the upper ends of the fuel assemblies. A coupling pipe 4 for collecting cooling water for each fuel assembly 2 is connected through the grid plate 1, and connected to a metering tank 5 via a valve 23. The measuring tank 5 is provided with an overflow pipe 11, and overflowing sample water is passed through a valve 24.
The water is discharged through the drain pipe 19. Measuring tank 5 is connected to piping 12 and connected to ion exchange resin tank 7 via valve 27 . The vacuum pump 10 is activated, the valves 23, 26, 34, and 35 are opened, and the sample water is introduced into the measuring tank 5 through the piping 4. When the valve 27 is opened, the sample water measured in the measuring tank 5 enters the ion exchange resin tank 7 through the pipe 12. The radionuclides ion-separated and captured in the cation-exchange fat are detected by a gamma ray detector 21, and signals are separated by a pulse height analyzer 22.
しかし、上記方法においては次のような問題点
がある。一度サンプリングすると、サンプリング
配管４及び計量槽５内が汚染する可能性があり、
それに対する除染方法が不充分である。そのため
次のサンプルに前のサンプルの放射化物が混入し
測定結果に悪影響を及ぼす恐れがある。 However, the above method has the following problems. Once sampled, there is a possibility that the inside of the sampling pipe 4 and measuring tank 5 will become contaminated.
Decontamination methods for this are insufficient. Therefore, the next sample may be contaminated with radioactive substances from the previous sample, which may adversely affect the measurement results.
本考案は上述の事情を考慮してなされたもの
で、検出精度の高い破損燃料検出装置を得ること
を目的としている。 The present invention has been made in consideration of the above-mentioned circumstances, and an object thereof is to obtain a damaged fuel detection device with high detection accuracy.
以下図面を参照して本考案の一実施例を説明す
る。 An embodiment of the present invention will be described below with reference to the drawings.
本考案の破損燃料検出装置は試料水を採取する
サンプリング系と採取した試料を化学処理するフ
イルタリング系とフイルタ供給系と対象放射性核
種を吸着したフイルタを測定する検出系と、サン
プリングライン及びフイルタリングラインを洗浄
する洗浄系とから構成される。 The damaged fuel detection device of the present invention includes a sampling system for collecting sample water, a filtering system for chemically processing the collected sample, a filter supply system, a detection system for measuring the filter adsorbing the target radionuclide, and a sampling line and filtering system. It consists of a cleaning system that cleans the line.
本考案の系統図を第２図に示す。 A system diagram of the present invention is shown in Figure 2.
複数体の燃料集合体２上部を包含するように炉
心格子板１上に設置されたシツパーキヤツプ３を
通して燃料集合体内の冷却水を採取する採取管４
が弁５１，５３を介して計量槽５ａに連結されて
いる。計量槽５ａは中に計量カツプ５ｂを持つ２
重構造となつており、その上部には滴よけのテー
パー付屋根５ｃがついている。計量カツプ５ｂか
ら試料水があふれた事を検知するために、連通管
４５とフオトセンサ４０を組み合わせた検知機構
が計量槽５ａの横に設けてある。計量カツプ５ａ
はフイルタリング部３８に弁５５を介した配管４
７により連結され、フイルタリング終了後の廃液
は配管４８を通つてドレンに流れる。計量槽５ａ
は弁５６を介して配管４３により真空ポンプ１０
とつながつている。 A collection pipe 4 for collecting cooling water in the fuel assemblies through a shipper cap 3 installed on the core grid plate 1 so as to cover the upper parts of the plurality of fuel assemblies 2.
is connected to the measuring tank 5a via valves 51 and 53. The measuring tank 5a has a measuring cup 5b inside.
It is a heavy structure, and a tapered roof 5c is attached to the top to prevent drips. In order to detect overflow of sample water from the measuring cup 5b, a detection mechanism combining a communication tube 45 and a photo sensor 40 is provided next to the measuring tank 5a. Measuring cup 5a
The pipe 4 is connected to the filter ring 38 via the valve 55.
7, and the waste liquid after filtering flows through the pipe 48 to the drain. Measuring tank 5a
is connected to the vacuum pump 10 by the piping 43 via the valve 56.
connected with.
フイルタ供給部３７は防害核種除去用フイルタ
とイオン交換フイルタが保管されており、適時、
フイルタリング部３８に移送され、試料水のろ過
後は鉛でシールドされた検出部に送られる。検出
部は検出器２１と計測システム２２からなつてい
る。 The filter supply unit 37 stores a filter for removing hazardous nuclide and an ion exchange filter, and is supplied with the filter at the appropriate time.
The sample water is transferred to the filtering section 38, and after being filtered, it is sent to the detection section shielded with lead. The detection section consists of a detector 21 and a measurement system 22.
一方、試料水のサンプリングごとにサンプリン
グラインとフイルタリングラインの洗浄を行うた
め、純水源４１からでた配管４２が弁５２を介し
て採取管４と計量槽５ａにつながつている。 On the other hand, in order to clean the sampling line and filtering line every time sample water is sampled, a pipe 42 from a pure water source 41 is connected to the sampling pipe 4 and the measuring tank 5a via a valve 52.
真空ポンプにより計量槽５ａ内を減圧した状態
で弁５１，５３を開にすると、試料水が配管４を
通つて計量カツプ５ｂに注がれる。計量カツプ５
ｂよりあふれた試料水は連通管４５に流れ込みフ
オトセンサ４０により、一定量の試料が採取でき
た事を検知できる。その後、三方弁５６を大気開
放にして、弁５５を開にする事により、採取試料
がフイルタリング部３８に流れ込み、試料中に含
まれる対象放射性核種がイオン交換される。フイ
ルタリング後イオン交換フイルタ３９は検出部に
移送され、放射線計測される。 When the valves 51 and 53 are opened while the pressure inside the measuring tank 5a is reduced by the vacuum pump, sample water is poured into the measuring cup 5b through the pipe 4. Measuring cup 5
The sample water overflowing from b flows into the communication pipe 45, and the photo sensor 40 can detect that a certain amount of sample has been collected. Thereafter, by opening the three-way valve 56 to the atmosphere and opening the valve 55, the collected sample flows into the filtering section 38, and the target radionuclide contained in the sample is ion-exchanged. After filtering, the ion exchange filter 39 is transferred to a detection section and radiation is measured.
一工程終了ごとに、弁５１，５２，５３が開と
なり、採取管４と計量カツプ５ｂに純水が注がれ
る。この場合もサンプリングと同様にして純水の
オーバーフローを検知して、計量カツプ５ｂ内の
純水を配管４７を通してドレンに廃棄する。洗浄
時はこの操作を複数回繰り返す事により十分にサ
ンプリングラインとフイルタリングラインの除染
を行う。 After each step, the valves 51, 52, and 53 are opened, and pure water is poured into the collection tube 4 and measuring cup 5b. In this case as well, an overflow of pure water is detected in the same manner as sampling, and the pure water in the measuring cup 5b is disposed of through the pipe 47 to the drain. During cleaning, repeat this operation multiple times to thoroughly decontaminate the sampling line and filtering line.
上述したように本考案の破損燃料検出装置にお
いては、試料水の計量を計量カツプで行う事によ
り、非常に精度よく定量でき、定量精度が向上
し、ひいては試料ごとの破損燃料検出精度が向上
する。 As mentioned above, in the damaged fuel detection device of the present invention, by measuring the sample water with a measuring cup, it is possible to quantify the sample water with high precision, improving the quantitative accuracy and, in turn, improving the accuracy of detecting damaged fuel for each sample. .
また、計量槽が二重構造になつており、洗浄時
には純水を計量カツプ５ｂからオーバーフローさ
せるため、計量カツプの上端まで洗浄でき、しか
も希釈方式による繰り返し洗浄のため除染能力が
すぐれており、破損燃料の検出精度が向上する。 In addition, the measuring tank has a double structure, and during cleaning, pure water overflows from the measuring cup 5b, so it is possible to wash up to the upper end of the measuring cup. Moreover, it has excellent decontamination ability because it is repeatedly washed by dilution method. The accuracy of detecting damaged fuel is improved.
第１図は従来の破損燃料検出装置の系統図、第
２図は本考案の一実施例の系統図である。
１……炉心格子板、２……燃料集合体、３……
シツパーキヤツプ、４……採取管、５ａ……計量
槽、５ｂ……計量カツプ、１０……真空ポンプ、
２１……検出器、２２……計測システム、３７…
…フイルタ供給、３８……フイルタリング部、４
０……フオトセンサ、４１……純水源、４３……
配管、４５……連通管、４７……配管、４８……
配管、５１……弁、５３……弁、５６……弁。
FIG. 1 is a system diagram of a conventional damaged fuel detection device, and FIG. 2 is a system diagram of an embodiment of the present invention. 1... Core lattice plate, 2... Fuel assembly, 3...
Shipper cap, 4... Collection tube, 5a... Measuring tank, 5b... Measuring cup, 10... Vacuum pump,
21...Detector, 22...Measurement system, 37...
...Filter supply, 38...Filtering section, 4
0...Photo sensor, 41...Pure water source, 43...
Piping, 45...Communication pipe, 47...Piping, 48...
Piping, 51... valve, 53... valve, 56... valve.
Claims (1)
に被冠し得るように設けられたシツパーキヤツプ
とこのシツパーキヤツプに接続された給気管およ
び採取管とこの採取管に接続して設けられた計量
槽と、この計量槽に配管により接続する真空ポン
プと、計量槽に配管により接続するフイルタ挿脱
自在のろ過器と、使用済フイルタの放射能を測定
する検出器よりなる破損燃料検出装置において、
計量槽内に計量カツプを設けて、計量槽を２重構
造にしたことを特徴とする破損燃料検出装置。 A shipper cap provided so as to be able to be detachably attached to the head of a fuel assembly loaded in the reactor core, an air supply pipe and a collection pipe connected to the shipper cap, and a metering tank provided connected to the collection pipe. and a damaged fuel detection device consisting of a vacuum pump connected to the measuring tank by piping, a filter with a removable filter connected to the measuring tank by piping, and a detector for measuring the radioactivity of the used filter.
A damaged fuel detection device characterized in that a measuring cup is provided in the measuring tank, and the measuring tank has a double structure.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1979075925U JPS6139999Y2 (en) | 1979-06-06 | 1979-06-06 |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1979075925U JPS6139999Y2 (en) | 1979-06-06 | 1979-06-06 |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS55177697U JPS55177697U (en) | 1980-12-19 |
| JPS6139999Y2 true JPS6139999Y2 (en) | 1986-11-15 |
Family
ID=29309447
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP1979075925U Expired JPS6139999Y2 (en) | 1979-06-06 | 1979-06-06 |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS6139999Y2 (en) |
-
1979
- 1979-06-06 JP JP1979075925U patent/JPS6139999Y2/ja not_active Expired
Also Published As
| Publication number | Publication date |
|---|---|
| JPS55177697U (en) | 1980-12-19 |
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