JPH06148380A - Inspection method of reactor core internal structure - Google Patents

Inspection method of reactor core internal structure

Info

Publication number
JPH06148380A
JPH06148380A JP4296916A JP29691692A JPH06148380A JP H06148380 A JPH06148380 A JP H06148380A JP 4296916 A JP4296916 A JP 4296916A JP 29691692 A JP29691692 A JP 29691692A JP H06148380 A JPH06148380 A JP H06148380A
Authority
JP
Japan
Prior art keywords
displacement
core
core support
support plate
connecting 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.)
Pending
Application number
JP4296916A
Other languages
Japanese (ja)
Inventor
Shigeru Adachi
茂 足立
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.)
Toshiba Corp
Original Assignee
Toshiba Corp
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 Toshiba Corp filed Critical Toshiba Corp
Priority to JP4296916A priority Critical patent/JPH06148380A/en
Publication of JPH06148380A publication Critical patent/JPH06148380A/en
Pending 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)

Abstract

PURPOSE:To enable inspection of displacement and deformation of core support plates and a connecting tube part. CONSTITUTION:A fuel assembly is pulled out from a connecting tube 4 supported by core support plates 3 and a jig 7 for inspection is inserted in place of it. The top part of the jig 7 for inspection is provided with a marking or a target. With this marking or the target used as a mark, displacement and a tilt of the jig 7 for inspection are observed and measured by an ultrasonic transducer 14 fitted to an inspection device through sodium 13 and displacement and deformation of the core support plates 3 and the connecting tube 4 are detected therefor.

Description

【発明の詳細な説明】Detailed Description of the Invention

【0001】[0001]

【産業上の利用分野】本発明は高速増殖炉の炉心燃料を
支持するための炉内構造物の検査方法に関する。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a method for inspecting core internals for supporting core fuel of a fast breeder reactor.

【0002】[0002]

【従来の技術】高速増殖炉の炉心燃料を支持するための
炉内構造物の検査方法としては、原子炉停止時において
も 200℃以上と高温であること、液体ナトリウム雰囲気
であること、高放射線環境下であることから、原子炉停
止時において炉心頂部レベルの変位,変形をナトリウム
中透視装置で観察,測定する方法、炉心頂部レベルと治
具を用いて炉上部プラグから測定する接触スキャニング
方法などが考えられてきた。
2. Description of the Related Art As a method of inspecting the internal structure for supporting the core fuel of a fast breeder reactor, a high temperature of 200 ° C. or higher, a liquid sodium atmosphere, a high radiation Since it is in an environment, a method of observing and measuring the displacement and deformation of the reactor core top level with a sodium see-through device when the reactor is shut down, a contact scanning method of measuring from the reactor top plug using the reactor core top level and jig, etc. Has been considered.

【0003】次に、図3によりナトリウム中透視装置に
より炉心支持構造物の変位,変形を検査する方法につい
て説明する。
Next, a method of inspecting the displacement and deformation of the core support structure by the sodium see-through device will be described with reference to FIG.

【0004】図3において図中符号1は原子炉容器で、
この原子炉容器1内には炉内構造支持構造物2が設置さ
れている。この炉内構造支持構造物2には炉心支持板3
が設けられ、この炉心支持板3に連結管4が立設され、
連結管4内に燃料集合体6のエントランスノズル部が挿
入されている。燃料集合体6の外側には炉心槽5が設け
られている。
In FIG. 3, reference numeral 1 is a reactor vessel,
Inside the reactor vessel 1, a reactor internal structural support structure 2 is installed. The core support plate 3 is attached to the core structure support structure 2.
And a connecting pipe 4 is erected on the core support plate 3,
The entrance nozzle portion of the fuel assembly 6 is inserted into the connecting pipe 4. The reactor core 5 is provided outside the fuel assembly 6.

【0005】原子炉容器1の上端開口にはしゃへいプラ
グ11および回転プラグ12が設けられて閉塞されている。
回転プラグ12には超音波トランスジューサ14を有するナ
トリウム中透視装置13が垂設され、原子炉容器1内に冷
却材としてのナトリウム10が収容されている。
A shield plug 11 and a rotary plug 12 are provided and closed at the upper end opening of the reactor vessel 1.
A sodium see-through device 13 having an ultrasonic transducer 14 is vertically installed in the rotary plug 12, and sodium 10 as a coolant is contained in the reactor vessel 1.

【0006】図3は炉心支持構造物のうち炉内構造支持
構造物2の変形が炉心槽5の頂部に現れることを利用し
て、ナトリウム中透視装置13により炉心槽5頂部に設け
たマーキングまたはターゲットを観察,測定し、水平方
向変位、垂直方向変位を90°おきに4方向のデータを測
定,整理することにより、炉内構造支持構造物2の変
位,変形を測定する方法を示したものである。
FIG. 3 shows that the deformation of the in-core structural support structure 2 of the core support structure appears at the top of the core cistern 5 so that markings provided on the top of the core cistern 5 by the sodium see-through device 13 or A method for measuring the displacement and deformation of the in-core structural support structure 2 by observing and measuring the target, and measuring and organizing data in four directions at 90 ° horizontal displacement and vertical displacement. Is.

【0007】[0007]

【発明が解決しようとする課題】従来の検査方法は炉心
支持構造物全体の変形を測定する上では非常に有効であ
る。しかしながら、炉心支持構造物の各構成部品の変
位,変形を観察する上では有効でなく、特に炉心支持構
造物のうち最も厳しい中性子照射を受け、熱過渡にもさ
らされる炉心支持板3や連結管4部についてはどのよう
な情報も得ることができない。
The conventional inspection method is very effective in measuring the deformation of the entire core supporting structure. However, it is not effective in observing the displacement and deformation of each component of the core support structure, and in particular, the core support plate 3 and the connecting pipe that are exposed to thermal transients due to the most severe neutron irradiation of the core support structure. No information is available on the four copies.

【0008】このように、従来の技術では、炉心支持構
造物のうち最も厳しい中性子照射を受け、また熱過渡に
もさらされる炉心支持板や連結管部については、検査で
きないという課題があった。
As described above, the conventional technique has a problem that the core support plate and the connecting pipe portion that are subjected to the most severe neutron irradiation among the core support structures and are also exposed to the thermal transient cannot be inspected.

【0009】本発明は上記課題を解決するためになされ
たもので、炉心支持板および連結管部の変位,変形を検
査できる炉内構造物の検査方法を提供することにある。
The present invention has been made to solve the above problems, and it is an object of the present invention to provide a method for inspecting internal structures capable of inspecting the displacement and deformation of the core support plate and the connecting pipe portion.

【0010】[0010]

【課題を解決するための手段】本発明は炉心槽内に装荷
された燃料集合体の代りに連結管部に緊密に装着可能な
下部エントランスノズルを備えた検査用治具を連結管に
挿入して、この検査用治具の働きにより炉心支持板およ
び連結管部の変位,変形がこの検査用治具の頂部に変位
や傾きとして増幅して表わされることを利用して、頂部
の変位や傾きをナトリウム中透視装置で観察,測定する
ことによって炉心支持板および連結管部の変位,変形を
検査することを特徴とする。
According to the present invention, an inspection jig having a lower entrance nozzle which can be tightly mounted on a connecting pipe portion is inserted into the connecting pipe instead of the fuel assembly loaded in the reactor core. By utilizing the fact that the displacement and deformation of the core support plate and the connecting pipe part are amplified and displayed as displacement and inclination on the top of this inspection jig by the function of this inspection jig, the displacement and inclination of the top can be utilized. Is characterized by inspecting and measuring with a fluoroscope in sodium to inspect displacement and deformation of the core support plate and the connecting pipe part.

【0011】[0011]

【作用】炉心支持板に変位,変形がある場合、炉心支持
板3、連結管4にある変位,変形が検査用治具7により
増幅されて検査用治具頂部に現れるので、この頂部に施
したマーキングまたはターゲットをナトリウム中透視装
置13の超音波トランスジューサで観察,測定する。
When the core support plate is displaced or deformed, the displacement and deformation of the core support plate 3 and the connecting pipe 4 are amplified by the inspection jig 7 and appear on the inspection jig top. The marking or the target is observed and measured by the ultrasonic transducer of the fluoroscope 13 in sodium.

【0012】これにより炉心支持板および連結管部分で
の変位,変形を検査することができる。
Thus, the displacement and deformation of the core support plate and the connecting pipe can be inspected.

【0013】[0013]

【実施例】図1および図2を参照しながら本発明に係る
炉内構造物の検査方法の一実施例を説明する。
DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS An embodiment of the method for inspecting a reactor internal structure according to the present invention will be described with reference to FIGS.

【0014】図1において、原子炉容器1内には炉内構
造支持構造物2が設置されている。この炉内構造支持構
造物2には炉心支持板3が設けられ、この炉心支持板3
に連結管4が立設され、連結管4内に検査用治具7が挿
入されている。検査用治具7の外側には炉心槽5が設け
られている。
In FIG. 1, a reactor internal structure support structure 2 is installed in a reactor vessel 1. A core support plate 3 is provided on the in-core structure support structure 2, and the core support plate 3
A connecting pipe 4 is erected on the inside of the connecting pipe 4, and an inspection jig 7 is inserted into the connecting pipe 4. The reactor core 5 is provided outside the inspection jig 7.

【0015】原子炉容器1の上端開口にはしゃへいプラ
グ11および回転プラグ12が設けられている。回転プラグ
12には超音波トランスジューサ14を有するナトリウム中
透視装置13が垂設され、原子炉容器1内には冷却材とし
てのナトリウム10が収容されている。図中15はアーム
で、超音波トランスジューサ14の角度調整を行う。
A shield plug 11 and a rotary plug 12 are provided at the upper end opening of the reactor vessel 1. Rotating plug
A sodium see-through device 13 having an ultrasonic transducer 14 is vertically provided at 12, and sodium 10 as a coolant is contained in the reactor vessel 1. In the figure, reference numeral 15 is an arm for adjusting the angle of the ultrasonic transducer 14.

【0016】ここで、炉心支持板3、連結管4部の変
位,変形を調べるために図3で示した炉心槽5内の燃料
集合体6を引き抜き、その代りに検査用治具7を連結管
4部に挿入する。
Here, in order to examine the displacement and deformation of the core support plate 3 and the connecting pipe 4, the fuel assembly 6 in the core tank 5 shown in FIG. 3 is pulled out, and the inspection jig 7 is connected instead. Insert in 4 tubes.

【0017】検査用治具7は、下部は連結管4に緊密に
装着可能なエントランスノズル部を備え、上部は燃料交
換装置で取り扱えるようにハンドリングヘッド9部を備
え、また図2(d)で示したようにハンドリングヘッド
9の頂部には超音波トランスジューサ14で観察,測定し
やすいようにそれぞれの番地によって異なるマーキング
またはターゲット8を施している。
The inspection jig 7 has an entrance nozzle portion which can be tightly attached to the connecting pipe 4 at the lower portion, and a handling head 9 portion which can be handled by the fuel exchange device at the upper portion, and in FIG. 2 (d). As shown, a different marking or target 8 is provided on the top of the handling head 9 for each address so that it can be easily observed and measured by the ultrasonic transducer 14.

【0018】また、検査用治具7は燃料集合体6のラッ
パ管相当位置の直径を燃料集合体より細くすることによ
り、炉心支持板3、連結管4部での変位,変形が周りの
集合体の影響を受けずに検査用治具7頂部に現れるよう
にしている。
Further, in the inspection jig 7, the diameter of the fuel assembly 6 at the position corresponding to the trumpet pipe is made smaller than that of the fuel assembly, so that the displacement and deformation in the core support plate 3 and the connecting pipe 4 are gathered around. It is designed to appear on the top of the inspection jig 7 without being affected by the body.

【0019】このようにして現れた検査用治具7頂部の
変位、傾きを図2(c)に示す炉心槽5内の燃料集合体
について径方向、周方向の番地をマーキングまたはター
ゲット8を目印にして複数箇所についてナトリウム中透
視装置13の超音波トランスジューサ14で調べることによ
り炉心支持板3全体の変位,変形を検査することができ
る。
The displacement and inclination of the apex of the inspection jig 7 thus appearing are shown in FIG. 2 (c). For the fuel assembly in the reactor core 5, radial and circumferential addresses are marked or targets 8 are marked. Then, the displacement and deformation of the whole core support plate 3 can be inspected by examining the ultrasonic transducer 14 of the sodium see-through device 13 at a plurality of locations.

【0020】図2(a)は炉心支持板3に変位,変形が
生じてない場合で、図2(b)は炉心支持板3に変位,
変形が生じている場合である。
FIG. 2A shows the case where the core support plate 3 is not displaced or deformed, and FIG. 2B is the case where the core support plate 3 is displaced or deformed.
This is the case when deformation has occurred.

【0021】図2(a),(b)中(A),(B)の位
置は図2(c)に示すように炉心中心との延長上にあっ
て、径方向番地が異なる位置である。したがって、例え
ば(A),(B)の燃料集合体の位置について検査した
場合、図2(b)のように傾きが認められると炉心支持
板3に何らかの異常が生じていることがわかる。
The positions (A) and (B) in FIGS. 2A and 2B are on the extension of the core center as shown in FIG. 2C, and the radial addresses are different. . Therefore, for example, when the positions of the fuel assemblies of (A) and (B) are inspected, if inclination is recognized as shown in FIG. 2B, it is understood that some abnormality has occurred in the core support plate 3.

【0022】[0022]

【発明の効果】本発明によれば、従来検査できなかった
炉心支持板および連結管部等の炉内構造物の変位,変形
検査をナトリウム中透視装置と検査用治具との組合せに
より容易に行うことができる。
According to the present invention, it is possible to easily perform displacement and deformation inspection of core internals such as the core support plate and the connecting pipe portion, which could not be inspected in the past, by the combination of the sodium see-through device and the inspection jig. It can be carried out.

【0023】また、検査用治具を燃料集合体とほぼ同じ
外形形状,寸法にすることで燃料交換装置や燃料出入機
により炉内での移送や炉内外への出入れ作業が容易とな
る。さらに、炉内構造物等の永久構造物は検査のために
何ら改造する必要がないため、既設の高速炉プラントに
も適用可能である。
Further, by making the inspection jig to have substantially the same outer shape and dimensions as the fuel assembly, it becomes easy to carry out the work in and out of the furnace by the fuel exchange device and the fuel in / out machine. Furthermore, since permanent structures such as reactor internal structures do not need to be modified for inspection, they can be applied to existing fast reactor plants.

【図面の簡単な説明】[Brief description of drawings]

【図1】本発明に係る炉内構造物の検査方法の一実施例
を説明するための縦断面図。
FIG. 1 is a vertical cross-sectional view for explaining an embodiment of a method for inspecting an internal structure according to the present invention.

【図2】(a)は図1における炉心支持板に変位,変形
が生じてない場合の立面図、(b)は同じく炉心支持板
に変位,変形を生じている場合の立面図、(c)は
(a)を説明するための図1における炉心を示す平面
図、(d)は(a)におけるd部を拡大して示す立面
図。
2 (a) is an elevation view when the core support plate in FIG. 1 is not displaced or deformed, and (b) is an elevation view when the core support plate is similarly displaced or deformed, (C) is a plan view showing the core in FIG. 1 for explaining (a), and (d) is an enlarged elevational view showing a d portion in (a).

【図3】従来の炉内構造物の検査方法を説明するための
縦断面図。
FIG. 3 is a vertical cross-sectional view for explaining a conventional method for inspecting a reactor internal structure.

【符号の説明】[Explanation of symbols]

1…原子炉容器、2…炉内構造支持構造物、3…炉心支
持板、4…連結管、5…炉心槽、6…燃料集合体、7…
検査用治具、8…マーキングまたはターゲット、9…ハ
ンドリングヘッド、10…ナトリウム、11…しゃへいプラ
グ、12…回転プラグ、13…ナトリウム中透視装置、14…
超音波トランスジューサ、15…アーム。
DESCRIPTION OF SYMBOLS 1 ... Reactor vessel, 2 ... Reactor internal structure support structure, 3 ... Core support plate, 4 ... Connection pipe, 5 ... Reactor tank, 6 ... Fuel assembly, 7 ...
Inspection jig, 8 ... Marking or target, 9 ... Handling head, 10 ... Sodium, 11 ... Shield plug, 12 ... Rotating plug, 13 ... Sodium see-through device, 14 ...
Ultrasonic transducer, 15 ... arm.

Claims (1)

【特許請求の範囲】[Claims] 【請求項1】 炉心支持板で支持された連結管から燃料
集合体を引き抜き、この燃料集合体が引き抜かれた連結
管に緊密に装着可能な下部エントランスノズルを備えか
つその頂部にターゲットまたはマーキングを施した検査
用治具を挿入し、この挿入後の検査用治具の頂部の変
位,傾きをナトリウム中透視装置により観察,測定し
て、前記炉心支持板および連結管の変位,変形を検出す
ることを特徴とする炉内構造物検査方法。
1. A fuel assembly is drawn out from a connecting pipe supported by a core support plate, and a lower entrance nozzle that can be tightly mounted on the connecting pipe from which the fuel assembly is drawn is provided, and a target or marking is provided on the top thereof. The inspection jig is inserted, and the displacement and inclination of the top of the inspection jig after insertion are observed and measured by a sodium see-through device to detect the displacement and deformation of the core support plate and connecting pipe. A method for inspecting a structure inside a furnace, which is characterized by the above.
JP4296916A 1992-11-06 1992-11-06 Inspection method of reactor core internal structure Pending JPH06148380A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP4296916A JPH06148380A (en) 1992-11-06 1992-11-06 Inspection method of reactor core internal structure

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP4296916A JPH06148380A (en) 1992-11-06 1992-11-06 Inspection method of reactor core internal structure

Publications (1)

Publication Number Publication Date
JPH06148380A true JPH06148380A (en) 1994-05-27

Family

ID=17839836

Family Applications (1)

Application Number Title Priority Date Filing Date
JP4296916A Pending JPH06148380A (en) 1992-11-06 1992-11-06 Inspection method of reactor core internal structure

Country Status (1)

Country Link
JP (1) JPH06148380A (en)

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