JPS632326B2 - - Google Patents

Info

Publication number
JPS632326B2
JPS632326B2 JP56039400A JP3940081A JPS632326B2 JP S632326 B2 JPS632326 B2 JP S632326B2 JP 56039400 A JP56039400 A JP 56039400A JP 3940081 A JP3940081 A JP 3940081A JP S632326 B2 JPS632326 B2 JP S632326B2
Authority
JP
Japan
Prior art keywords
signal
transducer
reactor
processing device
drive mechanism
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
Application number
JP56039400A
Other languages
Japanese (ja)
Other versions
JPS57154006A (en
Inventor
Fumio Kadohata
Junzo Taguchi
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
Nippon Genshiryoku Jigyo KK
Original Assignee
Toshiba Corp
Nippon Genshiryoku Jigyo KK
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, Nippon Genshiryoku Jigyo KK filed Critical Toshiba Corp
Priority to JP56039400A priority Critical patent/JPS57154006A/en
Publication of JPS57154006A publication Critical patent/JPS57154006A/en
Publication of JPS632326B2 publication Critical patent/JPS632326B2/ja
Granted legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C17/00Monitoring; Testing ; Maintaining
    • G21C17/08Structural combination of reactor core or moderator structure with viewing means, e.g. with television camera, periscope, window
    • 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

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Indication And Recording Devices For Special Purposes And Tariff Metering Devices (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Length Measuring Devices Characterised By Use Of Acoustic Means (AREA)

Description

【発明の詳細な説明】 本発明は炉心の異常、特に燃料集合体の装荷状
態の異常を速やかに検出できる原子炉内検査シス
テムに関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to an in-reactor inspection system that can quickly detect abnormalities in a reactor core, particularly abnormalities in the loading state of fuel assemblies.

たとえば高速増殖炉等の原子炉において、炉心
に装荷された核燃料集合体は、交換の容易化、熱
変形の吸収化などの観点から炉容器内に強固に固
定されてはおらず、単に植立されたままの状態に
なつている。このため、植立形態が何らかの原因
でずれると冷却材の圧力によつて浮上力が生じ、
浮上り現象が発生する。このように核燃料集合体
が浮上ると反応度に影響が表われる。又、炉上部
機構を炉心上から移動させる場合、核燃料集合体
が正しく装荷されているか、あるいは制御棒の切
り離しが完全であるか確認しないと核燃料集合体
や制御棒と衝突する可能性がある。
For example, in nuclear reactors such as fast breeder reactors, the nuclear fuel assemblies loaded in the reactor core are not firmly fixed in the reactor vessel in order to facilitate replacement and absorb thermal deformation, but are simply planted. It has become a state of being. For this reason, if the planting configuration shifts for some reason, a levitation force will be generated due to the pressure of the coolant.
A floating phenomenon occurs. When the nuclear fuel assembly floats in this way, the reactivity is affected. Furthermore, when moving the upper reactor mechanism from above the reactor core, there is a possibility of collision with the nuclear fuel assembly or control rods unless it is confirmed that the nuclear fuel assemblies are correctly loaded and that the control rods are completely separated.

したがつて、このような不具合を解消するため
には何らかの手段で核燃料集合体や制御棒の装荷
状態を検出し、これに基いて正常の位置にセツト
し直す必要がある。しかし、冷却材の多くはナト
リウムなどの不透明物質であるので検出が困難で
ある。したがつてこの種の検出系を備えた原子炉
の出現が要望されている。
Therefore, in order to eliminate such problems, it is necessary to detect the loading status of the nuclear fuel assembly and control rods by some means, and then reset them to their normal positions based on this. However, many coolants are opaque substances such as sodium, making them difficult to detect. Therefore, there is a demand for a nuclear reactor equipped with this type of detection system.

本発明はこのような要望を満たすためになされ
たもので、その目的とするところは、炉心に装荷
されている核燃料集合体や制御棒が異常状態を生
じたり、あるいは炉心上方に異物が漂つたような
場合には、直ちにこの異常状態および位置を検出
でき、これに基いて適切な処置を講じることがで
きる安全性に富んだ原子炉内検査システムを提供
することにある。
The present invention was made to meet these demands, and its purpose is to prevent abnormal conditions in the nuclear fuel assemblies and control rods loaded in the reactor core, or in the event that foreign objects float above the reactor core. In such a case, it is an object of the present invention to provide a highly safe nuclear reactor inspection system that can immediately detect the abnormal state and position and take appropriate measures based on this.

従来、この種の検査システムとして使用されて
いるナトリウム透視装置は第1図に示されるよう
に、トランスジユーサ1が約300℃〜600℃程度の
高温度で溶解しているナトリウム2中に浸漬さ
れ、炉心3をはさむように対向して設置された反
射板4とトランスジユーサを水平面内で扇状に走
査し、その位置や角度を調整し、トランスジユー
サの位置を検出する駆動機構5および駆動機構制
御部6と信号処理装置8および画像表示装置9か
ら構成されている。なお符号7は発受信制御部で
ある。
Conventionally, a sodium fluoroscopy device used as this type of inspection system has a transducer 1 immersed in molten sodium 2 at a high temperature of about 300°C to 600°C, as shown in Figure 1. and a drive mechanism 5 that scans the transducer and the reflector plate 4, which are installed opposite to each other so as to sandwich the reactor core 3, in a fan shape in a horizontal plane, adjusts the position and angle, and detects the position of the transducer. It is composed of a drive mechanism control section 6, a signal processing device 8, and an image display device 9. Note that the reference numeral 7 is a transmission/reception control section.

このような構成において超音波パルスがトラン
スジユーサから発信される。超音波はCore
Gap10を通つて反射板で反射され、同じトランス
ジユーサで受信される。この時、核燃料集合体や
制御棒が超音波の伝播路中に存在すると、超音波
がさえぎられるため反射板からのエコーレベルが
減少する。したがつてトランスジユーサで受信さ
れるエコー信号の大小を検出し、適切な信号処理
を受けてギヤツプに比例した信号として画像表示
できるようになつている。
In such a configuration, ultrasonic pulses are emitted from the transducer. Ultrasonic is Core
It passes through Gap10, is reflected by a reflector, and is received by the same transducer. At this time, if a nuclear fuel assembly or control rod exists in the propagation path of the ultrasonic waves, the ultrasonic waves will be blocked and the echo level from the reflector will decrease. Therefore, it is possible to detect the magnitude of the echo signal received by the transducer, undergo appropriate signal processing, and display an image as a signal proportional to the gap.

しかしながら、上述した炉内検査システムでは
下記のような欠点がある。
However, the above-mentioned in-core inspection system has the following drawbacks.

トランスジユーサより発射された超音波は反射
板で反射され受信する構成になつているため、検
査システムが大型化し、又複雑になつている。
Since the ultrasonic waves emitted from the transducer are reflected by a reflector and received, the inspection system becomes larger and more complex.

そのため炉容器内における検査システムの占有
面積が大きく、保守点検が大変である。また反射
板の製作・据付等コスト高になるなどの問題点が
あつた。
Therefore, the inspection system occupies a large area within the reactor vessel, making maintenance and inspection difficult. In addition, there were other problems such as high costs for manufacturing and installing the reflector.

本発明はこのような従来の欠点を除去するため
になされたもので占有面積が少さく保守の容易な
原子炉内検査システムを提供することを目的とす
る。
The present invention was made to eliminate such conventional drawbacks, and an object of the present invention is to provide an in-reactor inspection system that occupies a small area and is easy to maintain.

すなわち本発明は原子炉内に設置された超音波
のトランスジユーサと、このトランスジユーサを
駆動する駆動機構と、この駆動機構を制御すると
ともにこの駆動機構から信号を受けて前記トラン
スジユーサの超音波発受信方向を示す信号を画像
処理装置に送る制御部と、前記トランスジユーサ
に超音波発信信号を送るとともに前記トランスジ
ユーサから送られた超音波受信信号を受ける発受
信制御部と、この発受信制御部から超音波受信信
号を受けてこれを加算処理する信号選別装置と、
この信号選別装置から加算処理後の信号を受けて
原子炉内障害物の有無を示す信号に変換する信号
処理装置と、この信号処理装置および前記制御部
から信号を受けてこれを画像処理する画像処理装
置とを具備してなる原子炉内検査システムであ
る。
That is, the present invention includes an ultrasonic transducer installed in a nuclear reactor, a drive mechanism that drives this transducer, and a system that controls this drive mechanism and receives signals from this drive mechanism to operate the transducer. a control unit that sends a signal indicating an ultrasound transmission/reception direction to an image processing device; a transmission/reception control unit that sends an ultrasound transmission signal to the transducer and receives an ultrasound reception signal sent from the transducer; a signal selection device that receives an ultrasonic reception signal from the transmission/reception control unit and performs addition processing on the received ultrasonic signal;
a signal processing device that receives a signal after addition processing from the signal sorting device and converts it into a signal indicating the presence or absence of an obstacle in the reactor; and an image processing device that receives signals from the signal processing device and the control section and processes the signals into images. This is an in-reactor inspection system comprising a processing device.

以下、添付図面を参照して本発明の一実施例に
ついて説明する。
Hereinafter, one embodiment of the present invention will be described with reference to the accompanying drawings.

第2図において炉容器11の上部開口部は回転
プラグ12によつて密閉されている。上記、炉容
器11内には複数本の核燃料集合体を植立させて
構成された炉心部3と制御棒を操作したりする時
に供された炉上部機構12と燃料を交換する時に
用いられる燃料交換機14等がそれぞれ設けられ
ている。なお炉心部3は炉心3aとそれを取りま
くブランケツト部3bとから構成されている。
In FIG. 2, the upper opening of the furnace vessel 11 is sealed by a rotating plug 12. In FIG. In the reactor vessel 11, a plurality of nuclear fuel assemblies are planted in the reactor core section 3, and the reactor upper mechanism 12 is used to operate the control rods, and the fuel is used when exchanging fuel. A switch 14 etc. are provided respectively. The reactor core section 3 is composed of a reactor core 3a and a blanket section 3b surrounding it.

また炉容器11内には液体ナトリウムで代表さ
れる冷却材2が炉容器11の下部の流入口15か
ら流入し流出口16から流出する。一方、前記炉
上部機構12の側方部には、駆動機構5によつて
回転および上下方向移動を可能とした操作軸18
が回転プラグから吊設されており、その操作軸1
8にはトランスジユーサ1が装置されている。
Furthermore, a coolant 2 typified by liquid sodium flows into the furnace vessel 11 from an inlet 15 at the bottom of the furnace vessel 11 and flows out from an outlet 16 . On the other hand, an operating shaft 18 that can be rotated and moved in the vertical direction by the drive mechanism 5 is provided on the side of the furnace upper mechanism 12.
is suspended from the rotating plug, and its operating shaft 1
A transducer 1 is installed at 8.

上記トランスジユーサ1は第3図に示すように
例えばステンレス鋼製のパイプ19に同じくステ
ンレス鋼製で厚肉に形成された容器20を固定
し、この容器20を固定してこの容器20内に絶
縁筒21、絶縁板22、金属板23、スプリング
24、金属板25、音響結合材26、LiNbo3
どで形成された圧電素子27および音響結合材2
8を図示のように収納し、この状態で容器20の
開口部に上記音響結合材28に接触する部分だけ
が薄肉に形成されたステンレス鋼製キヤツプ29
を装着し互いに溶接によつて固着したものから構
成されており、金属板23はパイプ19内に挿入
されているケーブル30の芯線31に電気的に接
続されている。
As shown in FIG. 3, the transducer 1 is constructed by fixing a container 20, which is also made of stainless steel and having a thick wall, to a pipe 19 made of, for example, stainless steel. An insulating tube 21, an insulating plate 22, a metal plate 23, a spring 24, a metal plate 25, an acoustic coupling material 26, a piezoelectric element 27 formed of LiNbo 3 , etc., and an acoustic coupling material 2
8 is housed as shown in the figure, and in this state, a stainless steel cap 29 is attached to the opening of the container 20, which has a thin wall only at the part that contacts the acoustic coupling material 28.
The metal plate 23 is electrically connected to the core wire 31 of the cable 30 inserted into the pipe 19.

また、上記トランスジユーサ1を走査せしめる
駆動機構5は次のように構成されている。すなわ
ち、一つの駆動源、伝達機構、リバーシブルモー
タ、減速ギヤ、回転反転機構等からなつており、
回転プラグ12の上部にフランジを介して固定さ
れている。しかして図示していないが減速ギヤが
トランスジユーサ1を装着した操作軸18に連結
されておりトランスジユーサが所用の速度でリバ
ーシブルモータによつて水平扇形状に走査され
る。一方、トランスジユーサ1の縦方向の走査は
リバーシブルモータ、反転機構、回転一直線運動
変換機構(例えばピニオン・ラツク)からなる装
置によつて行なわれる。これらの操作は駆動機構
制御部6で行なわれ出力として画像処理装置9に
トランスジユーサ1の位置および角度の信号が入
力される。
Further, the drive mechanism 5 that causes the transducer 1 to scan is configured as follows. In other words, it consists of one drive source, transmission mechanism, reversible motor, reduction gear, rotation reversal mechanism, etc.
It is fixed to the upper part of the rotating plug 12 via a flange. Although not shown, a reduction gear is connected to the operating shaft 18 on which the transducer 1 is mounted, and the transducer is scanned in a horizontal fan shape at a desired speed by a reversible motor. On the other hand, the longitudinal scanning of the transducer 1 is performed by a device consisting of a reversible motor, a reversing mechanism, and a rotary linear motion conversion mechanism (for example, a pinion rack). These operations are performed by the drive mechanism control section 6, and signals representing the position and angle of the transducer 1 are input to the image processing device 9 as outputs.

第2図および第4図において、トランスジユー
サ1で発信される超音波は炉上部機構13と核燃
料集合体3の間のコアギヤツプ10を通つて炉容
器の内壁11aに進み、そこで反射される。反射
したエコー信号は再びトランスジユーサで受信さ
れ、信号選別装置17に入力される。印加したエ
コー信号は従来の反射板を用いた方式に比べS/
N比が悪くそのままでは画像表示できない。
In FIGS. 2 and 4, the ultrasonic waves emitted by the transducer 1 pass through the core gap 10 between the upper reactor mechanism 13 and the nuclear fuel assembly 3 to the inner wall 11a of the reactor vessel, where they are reflected. The reflected echo signal is received by the transducer again and input to the signal selection device 17. The applied echo signal has an S/
The N ratio is poor and images cannot be displayed as is.

従つて上記した信号選別装置17でS/Nの改
善をし、信号処理装置18に送信する。すなわち
トランスジユーサ1で発信された超音波は、炉容
器の内壁11aの表面状態および位置・角度等に
より常に上記トランスジユーサ1に向けて反射さ
れるとは限らない。そのため、ノイズが多く真の
信号との見分けがつかない。そこで信号選別装置
17によりS/N<1の信号をS/N>1にし信
号処理装置18に送信するのである。つまり、ト
ランスジユーサ1で発信された超音波は炉容器の
内壁11aで反射したエコー信号は色々な方向に
分散し、極くわずかな真の信号を残しノイズとな
つてトランスジユーサに受信される。しかしノイ
ズの信号は常に一定周期ではないため、トランス
ジユーサ1で受信した信号を何回も加算すること
により、雑音に埋れた信号を抽出することができ
る。この抽出する装置を信号選別装置17と称
し、抽出した信号をDA変換して、信号処理装置
18に出力する。信号処理装置18に入力した信
号は適切な信号処理を受け、ギヤツプに比例した
信号として画像処理装置9に加えられる。
Therefore, the signal selection device 17 described above improves the S/N and transmits the signal to the signal processing device 18. That is, the ultrasonic waves emitted by the transducer 1 are not always reflected toward the transducer 1 due to the surface condition, position, angle, etc. of the inner wall 11a of the furnace vessel. Therefore, there is a lot of noise and it is difficult to distinguish it from the real signal. Therefore, the signal selection device 17 converts the signal with S/N<1 to S/N>1 and transmits it to the signal processing device 18. In other words, the ultrasonic waves emitted by the transducer 1 are reflected by the inner wall 11a of the reactor vessel, and the echo signals are dispersed in various directions, leaving a very small amount of true signals as noise that is received by the transducer. Ru. However, since the noise signal does not always have a constant period, by adding the signals received by the transducer 1 many times, it is possible to extract the signal buried in the noise. This extraction device is called a signal selection device 17, and the extracted signal is subjected to DA conversion and outputted to a signal processing device 18. The signal input to the signal processing device 18 undergoes appropriate signal processing and is applied to the image processing device 9 as a signal proportional to the gap.

したがつて駆動機構5および駆動機構制御部6
によつて前述のように上下方向および水平扇形方
向にトランスジユーサ1を移動させ炉上部機構1
3および燃料交換機14を横切るように超音波を
走査させれば、画像処理装置には第5図に示すよ
うに、炉上部機構、燃料交換機および核燃料集合
体3等の輪郭が表示され、両者の現在位置や正常
に作動しているか否か等を目によつて確認するこ
とができる。
Therefore, the drive mechanism 5 and the drive mechanism control section 6
As described above, the transducer 1 is moved in the vertical direction and the horizontal sector direction, and the furnace upper mechanism 1 is moved.
3 and the fuel exchanger 14, the image processing device displays the outlines of the upper reactor mechanism, the fuel exchanger, the nuclear fuel assembly 3, etc., as shown in FIG. You can visually check the current location and whether or not it is working properly.

本発明は上述のように構成したので、炉容器に
おける検査システムの占有面積が小さく、保守・
点検が容易になり、また反射板の製作、据付等が
ないため安価なものとなる。
Since the present invention is configured as described above, the area occupied by the inspection system in the reactor vessel is small, and maintenance and
Inspection is easier, and since there is no need to manufacture or install a reflector, it is inexpensive.

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

第1図は従来の検査システムの概略を示す縦断
面図、第2図は本発明の検査システムの概略を示
す縦断面図、第3図はトランスジユーサの断面
図、第4図はトランスジユーサと炉容器の超音波
送受信関係を示す線図、第5図は本発明に係る画
像表示装置の画像表示例を示す線図である。 1……トランスジユーサ、3……核燃料集合
体、5……駆動機構、6……制御部、7……発受
信制御部、9……画像処理装置、11……炉容
器、12……回転プラグ、13……炉上部機構、
14……燃料交換機、17……信号選別装置、1
8……信号処理装置。
FIG. 1 is a longitudinal sectional view schematically showing a conventional inspection system, FIG. 2 is a longitudinal sectional view schematically showing the inspection system of the present invention, FIG. 3 is a sectional view of a transducer, and FIG. 4 is a longitudinal sectional view schematically showing a conventional inspection system. A diagram showing the ultrasonic transmission/reception relationship between the user and the furnace vessel, and FIG. 5 is a diagram showing an example of image display by the image display device according to the present invention. DESCRIPTION OF SYMBOLS 1... Transducer, 3... Nuclear fuel assembly, 5... Drive mechanism, 6... Control unit, 7... Transmission/reception control unit, 9... Image processing device, 11... Reactor vessel, 12... Rotating plug, 13...Furnace upper mechanism,
14...Fuel exchange machine, 17...Signal selection device, 1
8...Signal processing device.

Claims (1)

【特許請求の範囲】[Claims] 1 原子炉内に設置された超音波のトランスジユ
ーサと、このトランスジユーサを駆動する駆動機
構と、この駆動機構を制御するとともにこの駆動
機構から信号を受けて前記トランスジユーサの超
音波発受信方向を示す信号を画像処理装置に送る
制御部と、前記トランスジユーサに超音波発信信
号を送るとともに前記トランスジユーサから送ら
れた超音波受信信号を受ける発受信制御部と、こ
の発受信制御部から超音波受信信号を受けてこれ
を加算処理する信号選別装置と、この信号選別装
置から加算処理後の信号を受けて原子炉内障害物
の有無を示す信号に変換する信号処理装置と、こ
の信号処理装置および前記制御部から信号を受け
てこれを画像処理する画像処理装置とを具備して
なる原子炉内検査システム。
1 An ultrasonic transducer installed in a nuclear reactor, a drive mechanism that drives this transducer, and a system that controls this drive mechanism and receives signals from this drive mechanism to generate ultrasonic waves from the transducer. a control unit that sends a signal indicating a reception direction to the image processing device; a transmission/reception control unit that sends an ultrasound transmission signal to the transducer and receives an ultrasound reception signal sent from the transducer; A signal selection device that receives an ultrasonic reception signal from a control unit and performs addition processing on the received signal, and a signal processing device that receives a signal after addition processing from the signal selection device and converts it into a signal indicating the presence or absence of an obstruction in the reactor. An in-reactor inspection system comprising: this signal processing device; and an image processing device that receives signals from the control section and processes the signals.
JP56039400A 1981-03-20 1981-03-20 Inspection system for interior of nuclear reactor Granted JPS57154006A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP56039400A JPS57154006A (en) 1981-03-20 1981-03-20 Inspection system for interior of nuclear reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP56039400A JPS57154006A (en) 1981-03-20 1981-03-20 Inspection system for interior of nuclear reactor

Publications (2)

Publication Number Publication Date
JPS57154006A JPS57154006A (en) 1982-09-22
JPS632326B2 true JPS632326B2 (en) 1988-01-18

Family

ID=12551934

Family Applications (1)

Application Number Title Priority Date Filing Date
JP56039400A Granted JPS57154006A (en) 1981-03-20 1981-03-20 Inspection system for interior of nuclear reactor

Country Status (1)

Country Link
JP (1) JPS57154006A (en)

Also Published As

Publication number Publication date
JPS57154006A (en) 1982-09-22

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