JP2000162372A - Failed fuel assembly detector - Google Patents
Failed fuel assembly detectorInfo
- Publication number
- JP2000162372A JP2000162372A JP10335275A JP33527598A JP2000162372A JP 2000162372 A JP2000162372 A JP 2000162372A JP 10335275 A JP10335275 A JP 10335275A JP 33527598 A JP33527598 A JP 33527598A JP 2000162372 A JP2000162372 A JP 2000162372A
- Authority
- JP
- Japan
- Prior art keywords
- fuel assembly
- damaged
- reactor
- shield
- radionuclide
- 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
Description
【０００１】[0001]
【発明の属する技術分野】本発明は、原子炉内における
破損燃料集合体の検出に係わり、原子炉炉心内の破損燃
料集合体より放出される放射性核種を検出する検出器を
水中に吊り下ろすことにより、短時間にて破損燃料集合
体を検出するのに好適な破損燃料集合体検出装置に関す
る。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to the detection of a damaged fuel assembly in a nuclear reactor, and a method of hanging a detector for detecting radionuclides released from the damaged fuel assembly in a reactor core in water. Accordingly, the present invention relates to a damaged fuel assembly detection device suitable for detecting a damaged fuel assembly in a short time.
【０００２】[0002]
【従来の技術】一般に、軽水型原子炉の一例である沸騰
水型原子炉では、破損燃料集合体の検出は、主にシッピ
ング法により原子炉炉心内の燃料集合体上部にシッパー
キャップを装着し、燃料集合体内の原子炉水を隔離後、
破損燃料棒内より隔離水中への放射性核種の溶出を待
ち、これを採水し、放射性核種分析装置により採水中の
放射性核種濃度測定を実施し、破損燃料集合体のみより
放出される放射性核種濃度量より破損燃料集合体の特定
を実施する。2. Description of the Related Art In general, in a boiling water reactor, which is an example of a light water reactor, a broken fuel assembly is detected mainly by installing a shipper cap on the upper part of the fuel assembly in the reactor core by a shipping method. After isolating the reactor water in the fuel assembly,
Waiting for elution of radionuclides from the damaged fuel rod into the sequestration water, sampling the water, measuring the radionuclide concentration in the water sample using a radionuclide analyzer, and measuring the radionuclide concentration released only from the damaged fuel assembly Identify the damaged fuel assembly from the quantity.
【０００３】あるいは、原子炉炉心内燃料集合体を１体
毎に原子炉炉心より取り出し、他の燃料集合体と隔離す
るための機器内まで移動後採水し、破損燃料集合体より
放出される放射性核種の含有の有無を放射線量の測定、
あるいは、放射性核種分析を実施し、破損燃料集合体の
特定を実施する。[0003] Alternatively, the fuel assemblies in the reactor core are taken out of the reactor core one by one, moved to a device for isolating the fuel assemblies from other fuel assemblies, and then water is collected and released from the damaged fuel assemblies. Measurement of radiation dose to determine the presence or absence of radionuclides,
Alternatively, a radionuclide analysis is performed to identify a damaged fuel assembly.
【０００４】従来の破損燃料集合体検出装置は、燃料集
合体内の原子炉水の隔離，破損燃料棒よりの放射性核種
溶出待ち、燃料集合体内の原子炉水の採取および放射性
核種分析を実施している。あるいは、燃料集合体を１体
毎に取り出し、破損燃料集合体を隔離する機器内への移
動を実施している。[0004] The conventional damaged fuel assembly detection device carries out isolation of reactor water in the fuel assembly, waiting for elution of radionuclides from the damaged fuel rods, collection of reactor water in the fuel assembly, and analysis of radionuclides. I have. Alternatively, the fuel assemblies are taken out one by one, and the damaged fuel assemblies are moved into a device for isolating them.
【０００５】このことより、原子炉内に装荷されている
全燃料集合体の測定に膨大な時間を要する必要がある。
また、採水装置および燃料集合体を隔離する機器は大型
である。[0005] For this reason, it is necessary to take an enormous amount of time to measure all the fuel assemblies loaded in the nuclear reactor.
Also, the water sampling device and the equipment for isolating the fuel assembly are large.
【０００６】[0006]
【発明が解決しようとする課題】本発明の目的は、原子
炉内に装荷されている全燃料集合体について破損の有無
を短時間にて特定することができる破損燃料集合体検出
装置を提供することにある。SUMMARY OF THE INVENTION It is an object of the present invention to provide a damaged fuel assembly detection device capable of identifying in a short time the presence or absence of damage for all fuel assemblies loaded in a nuclear reactor. It is in.
【０００７】あるいは、従来の技術により破損燃料集合
体を特定する場合の早期検出のために、事前に破損燃料
集合体の原子炉内における概略位置を特定することがで
きる破損燃料集合体検出装置を提供することにある。[0007] Alternatively, a damaged fuel assembly detection device capable of specifying in advance the approximate position of a damaged fuel assembly in a nuclear reactor for early detection when a damaged fuel assembly is identified by a conventional technique. To provide.
【０００８】さらに、装置各部の小型化を図り、作業性
の良い破損燃料集合体検出装置を提供することにある。It is still another object of the present invention to provide a damaged fuel assembly detection device which can reduce the size of each part of the device and has good workability.
【０００９】[0009]
【課題を解決するための手段】上記目的を達成するため
に、本発明は、燃料集合体の破損事象発生後の原子炉解
放後に、原子炉内に全燃料集合体が収納されている状態
にて、原子炉炉心内に装荷された燃料集合体上に気中よ
り遠隔にて吊り下ろされた遮蔽体内に収納された放射性
核種検出器を順次連続して移動させることにより、燃料
集合体内より上昇する原子炉水を効率よく捕獲および排
出することにより、破損燃料集合体より放出される放射
性核種の有無を連続的に原子炉水中にて直接測定できる
ので、破損燃料集合体の検出を短時間で実施することが
できる。SUMMARY OF THE INVENTION To achieve the above object, the present invention provides a method for storing all fuel assemblies in a reactor after the reactor is released after a failure event of the fuel assemblies has occurred. As a result, the radionuclide detectors housed in shields suspended remotely from the air are moved sequentially above the fuel assemblies loaded in the reactor core, By efficiently capturing and discharging the reactor water, the presence or absence of radionuclides released from the damaged fuel assembly can be continuously measured directly in the reactor water, making it possible to detect damaged fuel assemblies in a short time. Can be implemented.
【００１０】また、破損燃料集合体検出装置を燃料集合
体上部に装着することにより、個々の燃料集合体につい
てより精度良く測定することができる。Further, by mounting the damaged fuel assembly detection device on the upper part of the fuel assembly, it is possible to measure each fuel assembly more accurately.
【００１１】さらに、燃料集合体内の原子炉水を採取す
るための装置、および、燃料集合体を隔離するための機
器が不要であるため、装置の設定が容易となり作業性を
向上させることができる。Further, since a device for collecting the reactor water in the fuel assembly and a device for isolating the fuel assembly are not required, the setting of the device is easy and the workability can be improved. .
【００１２】[0012]
【発明の実施の形態】以下、本発明の一実施例を図１〜
図４を用いて説明する。DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS One embodiment of the present invention will now be described with reference to FIGS.
This will be described with reference to FIG.
【００１３】図１は、原子力発電用の原子炉炉心内水中
において、燃料集合体１の上部に位置した遮蔽体２の構
造図を示す。FIG. 1 is a structural view of a shield 2 located above a fuel assembly 1 in water in a nuclear reactor core for nuclear power generation.
【００１４】遮蔽体２の上部には、吊り手３が取り付け
てあり気中からの吊り具４に装着され、遮蔽体２の内部
には、破損した燃料集合体１から放出する放射性核種を
検出する検出器５を設置している。On the upper part of the shield 2, a suspender 3 is attached and attached to a suspender 4 from the air, and inside the shield 2, a radionuclide released from the damaged fuel assembly 1 is detected. Detector 5 is installed.
【００１５】遮蔽体２は燃料集合体１内部より上昇する
原子炉水を捕獲口６より捕獲し、排出口７より排出する
ものであり、遮蔽体２内部に原子炉水を有効に捕獲、及
び排出される構造を備える。The shield 2 captures reactor water rising from the inside of the fuel assembly 1 through the capture port 6 and discharges the reactor water through the discharge port 7. The shield 2 effectively captures reactor water inside the shield 2, and Equipped with a structure to be discharged.
【００１６】さらに、遮蔽体２は周囲の原子炉水中に存
在する放射性核種からの放射線を遮蔽するためのもので
あり、遮蔽体２内部に捕獲された放射性核種を有効に検
出できるものを選定する。検出器５よりの信号は、ケー
ブル１０により伝達される。図２は、原子炉炉心の模式
図を示す。Further, the shield 2 is for shielding radiation from radioactive nuclides present in the surrounding reactor water, and a shield capable of effectively detecting the radionuclide captured inside the shield 2 is selected. . The signal from the detector 5 is transmitted by a cable 10. FIG. 2 shows a schematic diagram of the reactor core.
【００１７】遮蔽体２を図１に示すように、燃料集合体
１に接触しない高さに位置させ、図２に示す遮蔽体移動
ルート８のように燃料集合体１の上部を連続して移動さ
せ、破損した燃料集合体１から放出される放射性核種の
有無を検出する。As shown in FIG. 1, the shield 2 is positioned at a height not in contact with the fuel assembly 1, and the upper portion of the fuel assembly 1 is continuously moved as shown in a shield moving route 8 shown in FIG. Then, the presence or absence of radionuclides released from the damaged fuel assembly 1 is detected.
【００１８】この場合、連続して放射性核種の検出を行
うことから、破損した燃料集合体１の近傍において当該
燃料集合体１からの放射性核種を検出することになる。
この方法により、短時間にて原子炉炉心内の破損した燃
料集合体１のおおよその位置を検出可能となる。In this case, since the radionuclide is continuously detected, the radionuclide from the fuel assembly 1 is detected near the damaged fuel assembly 1.
According to this method, the approximate position of the damaged fuel assembly 1 in the reactor core can be detected in a short time.
【００１９】また、図３に示すように、燃料集合体１の
上部に装着させ燃料集合体１の内部より上昇する原子炉
水を捕獲することにより、燃料集合体１より放出される
放射性核種の有無の検出がより精度良く実施することが
可能である。Further, as shown in FIG. 3, by mounting on the upper part of the fuel assembly 1 and capturing the reactor water rising from the inside of the fuel assembly 1, the radionuclide released from the fuel assembly 1 is removed. The presence / absence detection can be performed with higher accuracy.
【００２０】図４に、破損燃料集合体検出装置の全体構
成を示す。FIG. 4 shows the entire configuration of the damaged fuel assembly detection device.
【００２１】遮蔽体２は、原子炉炉心上の燃料取替機９
などに取り付けた吊り具４により水中に保持される。遮
蔽体２の内部に設置された検出器５からのケーブル１０
が燃料取替機９などの上に設置された計測器１１に接続
され、検出器５からの信号を処理する。計測器１１に
は、計測した情報を表示，保存及び表示方法を各種処理
するための計測データ表示器１２に接続されている。The shield 2 is provided with a refueling machine 9 on the reactor core.
It is held in the water by a hanging tool 4 attached to the like. Cable 10 from detector 5 installed inside shield 2
Is connected to a measuring instrument 11 installed on the refueling machine 9 or the like, and processes a signal from the detector 5. The measurement device 11 is connected to a measurement data display device 12 for displaying, storing, and variously processing the display method of the measured information.
【００２２】計測データ表示器１２には、計測器１１か
らの情報以外に燃料取替機９の座標信号を入力し、計測
器１１からの情報を原子炉炉心内のマップとして展開で
きる。また、その他必要に応じ外部より情報を入力する
ことも可能である。また、プリンタ１３を接続すること
により、各種情報を出力することも可能である。In addition to the information from the measuring device 11, a coordinate signal of the refueling machine 9 is input to the measurement data display 12, and the information from the measuring device 11 can be developed as a map in the reactor core. In addition, it is also possible to input information from outside as needed. Further, by connecting the printer 13, various information can be output.
【００２３】[0023]
【発明の効果】本発明によれば、原子炉炉心内水中にお
いて、比較的単純な構造の破損燃料集合体検出装置で、
短時間に破損した燃料集合体の検出を実施することがで
きる。According to the present invention, a device for detecting a damaged fuel assembly having a relatively simple structure in water in a reactor core is provided.
It is possible to detect a damaged fuel assembly in a short time.
【図１】本発明による破損燃料集合体検出装置の遮蔽体
の概略構造図。FIG. 1 is a schematic structural view of a shield of a damaged fuel assembly detection device according to the present invention.
【図２】原子炉炉心の模式図と遮蔽体移動ルート例を示
す平面図。FIG. 2 is a plan view showing a schematic diagram of a reactor core and an example of a shield moving route.
【図３】本発明による破損燃料集合体検出装置の遮蔽体
を燃料集合体上部に装着した場合の概念図。FIG. 3 is a conceptual diagram when a shield of the damaged fuel assembly detection device according to the present invention is mounted on the upper part of the fuel assembly.
【図４】破損燃料集合体検出装置の機器構成図。FIG. 4 is a device configuration diagram of a damaged fuel assembly detection device.
１…燃料集合体、２…遮蔽体、３…吊り手、４…吊り
具、５…検出器、６…捕獲口、７…排出口、８…遮蔽体
移動ルート、９…燃料取替機、１０…ケーブル、１１…
計測器、１２…計測データ表示器、１３…プリンタ。DESCRIPTION OF SYMBOLS 1 ... Fuel assembly, 2 ... Shield, 3 ... Hanger, 4 ... Hanging tool, 5 ... Detector, 6 ... Capture port, 7 ... Discharge port, 8 ... Shield moving route, 9 ... Refueling machine, 10 ... cable, 11 ...
Measuring device, 12: Measurement data display device, 13: Printer.
───────────────────────────────────────────────────── フロントページの続き (72)発明者 飯田 耕司 茨城県日立市幸町三丁目２番２号 株式会 社日立エンジニアリングサービス内 Ｆターム(参考） 2G075 CA08 CA38 CA40 CA50 DA08 DA16 EA01 FA05 FA18 FB07 FB08 FB09 GA15 ────────────────────────────────────────────────── ─── Continuing from the front page (72) Inventor Koji Iida 3-2-2, Sachimachi, Hitachi-shi, Ibaraki F-term in Hitachi Engineering Services Co., Ltd. (Reference) 2G075 CA08 CA38 CA40 CA50 DA08 DA16 EA01 FA05 FA18 FB07 FB08 FB09 GA15
Claims (4)
放後における破損燃料集合体の検出装置において、原子
炉内に全燃料集合体が収納されている状態にて、破損燃
料集合体より放出される放射性核種を検出する放射性核
種検出器を有することを特徴とする破損燃料集合体検出
装置。An apparatus for detecting a damaged fuel assembly after a reactor is released after a failure event of the fuel assembly has occurred, wherein the damaged fuel assembly is stored in a state where all the fuel assemblies are stored in the reactor. A damaged fuel assembly detection device, comprising a radionuclide detector for detecting radionuclide emitted from the fuel assembly.
出される放射性核種を測定する放射性核種検出器を遮蔽
体内に有し、原子炉内に装荷された燃料集合体上を容易
に移動測定し、燃料集合体の破損の有無が検出可能であ
ることを特徴とする破損燃料集合体検出装置。2. A fuel cell according to claim 1, further comprising a radionuclide detector for measuring radionuclide released from the damaged fuel assembly in a shield, and easily moving and measuring on the fuel assembly loaded in the reactor. A damaged fuel assembly detection device capable of detecting whether or not the fuel assembly is damaged.
燃料集合体内よりの上昇原子炉水を効率よく捕獲及び排
出できる機能を有し、測定対象燃料集合体より放出され
るそれ以外の原子炉水中に含まれる放射性核種からの遮
蔽機能を有することを特徴とする破損燃料集合体検出装
置。3. The shield according to claim 2, wherein the shield has a function of efficiently capturing and discharging ascending reactor water from the fuel assembly to be measured, and other atoms released from the fuel assembly to be measured. A damaged fuel assembly detection device having a function of shielding radioactive nuclides contained in reactor water.
原子炉内炉水中の破損燃料集合体より放出される放射性
核種の測定値を測定座標と相関させ、その濃度分布が表
示できることを特徴とする破損燃料集合体検出装置。4. The method according to claim 1, wherein
A damaged fuel assembly detection device, wherein a measured value of a radionuclide released from a damaged fuel assembly in reactor water is correlated with a measurement coordinate and a concentration distribution thereof can be displayed.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP10335275A JP2000162372A (en) | 1998-11-26 | 1998-11-26 | Failed fuel assembly detector |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP10335275A JP2000162372A (en) | 1998-11-26 | 1998-11-26 | Failed fuel assembly detector |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JP2000162372A true JP2000162372A (en) | 2000-06-16 |
Family
ID=18286706
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP10335275A Pending JP2000162372A (en) | 1998-11-26 | 1998-11-26 | Failed fuel assembly detector |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JP2000162372A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR3053516A1 (en) * | 2016-06-29 | 2018-01-05 | Commissariat A L'energie Atomique Et Aux Energies Alternatives | METHOD FOR IDENTIFYING A NUCLEAR FUEL ASSEMBLY, IDENTIFICATION SYSTEM AND NUCLEAR INSTALLATION COMPRISING SUCH AN IDENTIFICATION SYSTEM |
-
1998
- 1998-11-26 JP JP10335275A patent/JP2000162372A/en active Pending
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR3053516A1 (en) * | 2016-06-29 | 2018-01-05 | Commissariat A L'energie Atomique Et Aux Energies Alternatives | METHOD FOR IDENTIFYING A NUCLEAR FUEL ASSEMBLY, IDENTIFICATION SYSTEM AND NUCLEAR INSTALLATION COMPRISING SUCH AN IDENTIFICATION SYSTEM |
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