JPS59163595A - Control rod position detecting device - Google Patents

Control rod position detecting device

Info

Publication number
JPS59163595A
JPS59163595A JP58037442A JP3744283A JPS59163595A JP S59163595 A JPS59163595 A JP S59163595A JP 58037442 A JP58037442 A JP 58037442A JP 3744283 A JP3744283 A JP 3744283A JP S59163595 A JPS59163595 A JP S59163595A
Authority
JP
Japan
Prior art keywords
control rod
core
reactor
control
rod position
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
JP58037442A
Other languages
Japanese (ja)
Inventor
孝雄 伊藤
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 JP58037442A priority Critical patent/JPS59163595A/en
Publication of JPS59163595A publication Critical patent/JPS59163595A/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

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】 〔発明の技術分野〕 本発明は、原子炉の制御棒駆動愼侮、特に、スクラム時
に駆動機構から切離して落下させたili制御棒が炉心
の案内管内(二挿入したことを確認する原子炉用’1B
IJ御棒位置検出装置(二関する。
[Detailed Description of the Invention] [Technical Field of the Invention] The present invention relates to the control rod drive mechanism of a nuclear reactor, and in particular, to the control rod drive mechanism of a nuclear reactor, in which an ili control rod that is separated from a drive mechanism and dropped during a scram is inserted into a guide tube of a reactor core. '1B for nuclear reactor to confirm that
IJ rod position detection device (2 related)

〔発明の技術的背景とその問題点〕[Technical background of the invention and its problems]

原子炉の制御棒駆@機構は、原子炉の起動、停止及び出
力制御を行なうものであるが、中でも異常時(二原子炉
を緊急停止させるスクラム機能は原子炉の安全確保土産
も厘安な機能ておる。このため、原子炉の起動前(二は
、必ず1ljiJ 4ihil偉品鯛機構のスクラム機
能を確認することが義務づけられている。
The control rod drive mechanism of a nuclear reactor is used to start, stop, and control the output of a nuclear reactor, but in the event of an abnormality (the scram function that makes an emergency shutdown of two reactors), it is also a cheap souvenir to ensure the safety of a nuclear reactor. It is functioning.For this reason, it is mandatory to check the scram function of the Ippin Tai Mechanism before starting up the reactor.

このような制御棒駆動、機構(二は、スクラム時(1制
検出が駆動軸と一体(二基下する方法と、制御棒を、駆
動軸と切離して単体で落下させる方法とがあり、原子炉
の運転上の信頼性を高めるために、両方法を併用するこ
とが一般的(二考えられている。
There are two methods for such a control rod drive mechanism (the second is a method in which the first detection is integrated with the drive shaft (lowering two units), and a method in which the control rod is separated from the drive shaft and dropped alone. In order to improve the operational reliability of the furnace, it is common to use both methods in combination.

ところが、後者の方法では、スクラム愼北tm認する上
で1.駆動軸から離れて落下した制御棒が、元金(二炉
心の案内管内(二挿入されたか否かを検出することが困
難であり、この点が従来からM女な仮相課題であった。
However, in the latter method, 1. It is difficult to detect whether a control rod that has fallen away from the drive shaft has been inserted into the guide tube of the two cores, and this point has traditionally been a problem for masochistic women.

ところで、切離し落下型制御棒のヌクラム後の従来の位
置検出方法を第1図(二ついて説明する。
By the way, a conventional method for detecting the position of a detachable drop-type control rod after it has been removed is illustrated in FIG.

同図(二おいて、上部案内・計5内を落下する制御棒1
は、制御棒1の落下を確実にするための加速機構2と一
体となって落下し、加速機構2の太径部3に取付けられ
た磁石4が、上部系内宮5の外周に巻回された検出コイ
ル6中を通過する1県起′−力を測定することにより検
出される。
The same figure (2, control rod 1 falling inside the upper guide, total 5)
The control rod 1 falls together with the acceleration mechanism 2 to ensure that the control rod 1 falls, and the magnet 4 attached to the large diameter part 3 of the acceleration mechanism 2 is wound around the outer periphery of the inner chamber 5 of the upper system. It is detected by measuring the single predetermined force passing through the detection coil 6.

しかし、この従来の位置検出方法では、その構造上検出
コイル6や磁石4の大きさが副1奴されるため、十分な
大きさの信号が得られない、μだ加速愼構は制#俸1が
完全(二炉心の下部某内官7内に挿入される以前(二停
止させる盛装があるため、制御棒1の完全挿入位置は、
検出できない寺の問題があった。
However, in this conventional position detection method, the size of the detection coil 6 and magnet 4 is limited due to its structure, so it is difficult to obtain a signal of sufficient size, and the acceleration mechanism is limited. The complete insertion position of control rod 1 is
There was a problem with undetectable temples.

、〔発明の目的〕 本発明は、前記の如き問題点を解決するため(二なされ
たもので、その目的は、原子炉の起動前点検(二おいて
、各制御棒駆動機構(二ついて、それぞれ制御棒の完全
挿入を確認し、スクラム戦北を確実に点検できる制御棒
位置検出装置を提供する(1必る。
, [Object of the Invention] The present invention has been made in order to solve the above-mentioned problems. Provides a control rod position detection device that can confirm complete insertion of control rods and reliably inspect scram Senhoku (1 required).

〔発明の概要〕[Summary of the invention]

本発明は、上記目的を達成するため(二、原子炉容器内
に配設された炉心及び炉心上部機構と前記炉心の中心上
で前記炉心上部伝構な貫通してなる回転自在な制御棒位
置検出器と、前記炉心の上端外周囲に配設した反射体と
から構成された原子炉用制御棒位置検出装置である。F
jil記?IjlJ御俸位置検出器は長尺円面形状でそ
の下部に超音波トランスデユーサが取付けられておシ、
丑だ、前記反射体は円筒形状をなすものが用いられる。
The present invention has been made to achieve the above objects (2. A core and a core upper structure disposed in a reactor vessel, and a rotatable control rod position formed by penetrating the core upper structure over the center of the reactor core. This is a control rod position detection device for a nuclear reactor, which is composed of a detector and a reflector disposed around the upper end of the reactor core.
Jil record? The IjlJ position detector has an elongated circular shape with an ultrasonic transducer attached to the bottom.
Unfortunately, the reflector used has a cylindrical shape.

〔発明の実施例〕[Embodiments of the invention]

不発明の一笑施タリを第2図および第3図を参照して説
明する。
The uninvented joke will be explained with reference to FIGS. 2 and 3.

第2図は、本発明に係る制御棒位置検出装置を据付けた
原子炉容器内の概略断面図である。同図口おいて、原子
炉容器8の上端開口を閉塞したしゃへいプラグ9を貫通
じて炉心16の中心位置に設置された制御棒位置検出器
10は長尺円筒形でその円筒形の下端には超音波を水平
方向(−送信しかつ受信する超音波トランスデユーサ1
3が取付けられている。この超音波トランスデユーサ1
3から送信された超音波を反射体14が炉心16を囲む
よう(二炉心取付機構上(二配設されている。また、制
御棒駆動機構11も原子炉容器8のじやへいプラグ9を
貫通しており、その駆動軸12(−よって制#伜の炉心
16内への挿入が行なわれる。第2図(二おいて、炉心
16内の制御4$1ba 、 15bは、′I!jlJ
御(1g mr ja構11の駆動軸12よp切離され
たスクラム後の状態を示してお)、制御棒15aは落下
途中の状態、市制御梓15bは完全(二賂下した状態を
示している。なお・、符号19は原子炉容器8内(二光
填された成体金属ナトリウムの冷却材である。
FIG. 2 is a schematic cross-sectional view of the interior of a reactor vessel in which a control rod position detection device according to the present invention is installed. As shown in the figure, a control rod position detector 10 is installed at the center of the reactor core 16 through a shielding plug 9 that closes the upper end opening of the reactor vessel 8. is an ultrasonic transducer 1 that transmits and receives ultrasound waves horizontally (-
3 is installed. This ultrasonic transducer 1
The ultrasonic waves transmitted from the reactor vessel 8 are reflected by the reflectors 14 so that they surround the reactor core 16 (two are placed on the core attachment mechanism). The drive shaft 12 (-) is inserted into the reactor core 16. In FIG.
The control rod 15a is in the middle of falling, and the city control rod 15b is complete (showing the state after being separated from the drive shaft 12 of the 1g mr ja structure 11). Note that the reference numeral 19 is a solid metal sodium coolant filled in the reactor vessel 8.

第3図は、第2図(二おける炉心上部の1 1  +鵬
に沿う概略断面図である。炉心16には詳細(二図示し
ていないが、多数の燃料集合体が一ヘニカム状(二櫃設
されておp、その燃料集合体の1−」には逸尚な間隔ケ
おいて澗イ卸棒下部案内管が植設されており、その中に
制傾1棒が挿入される構造となっている。
FIG. 3 is a schematic cross-sectional view of the upper part of the core in FIG. The lower guide pipe of the fuel assembly is installed at a special interval in the lower part of the fuel assembly, and the control rod 1 is inserted into it. It becomes.

次(二、本発明による制御棒の位置検出方法(二ついて
説明する。
Next (2) Control rod position detection method according to the present invention (two methods will be explained).

先ず、直接反射方式では、トランスデユーサ13による
超音波の発振・受信径路は、第3図中符号17で示すよ
う(二、制御棒15aが完全(二洛下し終るlでは、I
・ランヌデューサ13から発振される超音波は制御棒1
5aの外表面で反射、つ註り直接反射してトランスデユ
ーサ13i二受信される。そして、制御稈15aが完全
に炉心16の案内管内に挿入されると、この反射波は受
信されなくなるので、副1卸偉の完全挿入が検出できる
。従って、スクラム開始より7!制御棒からの反射波が
受信されなくなる時点までの時間を測定すオLば、制御
#1駆動機構のスクラム時間が測定できる。
First, in the direct reflection method, the ultrasonic oscillation/reception path by the transducer 13 is as shown by reference numeral 17 in FIG.
・Ultrasonic waves emitted from the runnuducer 13 are sent to the control rod 1
It is reflected by the outer surface of the transducer 5a, directly reflected, and received by the transducer 13i. Then, when the control culm 15a is completely inserted into the guide tube of the reactor core 16, this reflected wave is no longer received, so that complete insertion of the first sub-tube can be detected. Therefore, 7 from the start of the scrum! By measuring the time until the reflected wave from the control rod is no longer received, the scram time of the control #1 drive mechanism can be measured.

一方、反射体方式では、トランスデユーサ13(=よる
超音波の発信・受信径路は、第3図中符号18で示すよ
う(二1b1」検出15bが完全に挿入されるまでは円
筒形状の反射体14で反射される超音波は1tilJ 
#棒15b(=さえぎられてトランスジューサ13(−
は到達しないが、匍]検出15bが完全(二炉心16の
案内管内(二挿入されると、反射体14からの超音波の
反射波がトランスデユーサ13に受信され、制御棒の完
全挿人を検出することができる。従って、スクラム開始
より反射体からの反射波が受信される時点丑ての時間を
測定すれば制御棒秘励俄栴のスクラム時間が迎]足でき
る。
On the other hand, in the reflector method, the transmission/reception path of the ultrasonic waves by the transducer 13 is a cylindrical reflection path until the detection 15b is completely inserted (21b1), as shown by the reference numeral 18 in FIG. The ultrasonic wave reflected by the body 14 is 1tilJ
# Rod 15b (= obstructed transducer 13 (-
When the detection 15b is completely inserted into the guide tube of the core 16, the reflected wave of the ultrasonic wave from the reflector 14 is received by the transducer 13, and the control rod is fully inserted. Therefore, by measuring the time from the start of the scram to the time when the reflected wave from the reflector is received, the scram time of the control rod discharge can be added.

なお、前り己直接反射方式葦たは戊躬俸方式の説明では
、′1I51制御作の位置を第3図中符号15aまたは
15b(二ついて説明しているが、制御)l全恒匣恢出
表〔位13を水平に回転する構造としているので、刊(
凱偉位置検出装置13次所望の制御偉方同に回転でせる
ことによp尚該’i[ilJ御棒検出心系内看内への完
全挿入を確認することができる。
In addition, in the explanation of the front self-direct reflection type reed or the boman-yaku type, the position of the control operation '1I51 is indicated by the reference numeral 15a or 15b (although there are two in the explanation, the control) l all constant position. The structure of the display (position 13) is to rotate horizontally, so the publication (
By rotating the position detection device 13 in the same direction as the desired control direction, complete insertion of the rod into the detection heart system can be confirmed.

〔発明の効果〕〔Effect of the invention〕

、+発明(二よれは、原子炉運転前の制御棒1駆動磯猶
の点検において、全ての制御俸駆動厳栴のスクラム性能
を確央に検出することがてさ、そのため(二!ti制検
出駆鯛礪構を特(二改造する盛装もない。なた、必要な
場合は、運転中においても、任意(二辿択された制御棒
のスクラム性能を検出することができる。
, + Invention (Secondly, it is necessary to accurately detect the scram performance of all control rod drives in the inspection of the control rod 1 drive system before reactor operation. Therefore, (2!ti control) There is no special modification of the detection drive structure.If necessary, the scram performance of the selected control rod can be detected even during operation.

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

第1区は従来の切離落下型1tj1.制御棒1駆励機構
の部分即[面図、第2図は不発明(1係る装置の一実施
例に示す戒!4硯[面図、第3図は坐2図のI−1戯(
二沿う概略断面図である。 8・・・原子炉    9・・しやへいグラブ10・・
・制御鼻位は検出器 11・・・市1j御(単駆動 1辰構     12・
・・、・駆動軸」13・・・超音波トランスデユーサ 
14・・・反射坏15a 、 15b・・・制御浄  
  16・・・炉心代理人 升埋士 則 近 急 佑(
ほか1名)第1図 第2図 第3図
The first section is the conventional separation drop type 1tj1. Parts of the control rod 1 driving mechanism [front view, Figure 2 is an uninvented figure (1) The command shown in one embodiment of such a device!
FIG. 8... Nuclear reactor 9... Shiyahei grab 10...
・The control nose position is the detector 11... City 1j control (single drive 1 arm configuration 12
・・・Drive shaft" 13... Ultrasonic transducer
14...Reflector 15a, 15b...Control cleaning
16...Reactor agent Masu filler Noriyuki Chika (
1 other person) Figure 1 Figure 2 Figure 3

Claims (2)

【特許請求の範囲】[Claims] (1)原子炉容器内(二配設された炉心及び炉心上部機
構と、前記炉心の中心上で前記炉心上部機構を貝辿して
なる回転自在な制呻桿位置検出器と、前6己炉心の上端
外周囲に配設した反射体とからなり、FjiJ記1lf
lJ岬俸位!a検出器は、長尺円筒形状でその下−都(
二組音波を発受信する超音波トランスデユーサを取付け
てなることン特徴と一9−る原子炉用制(i111+拳
位i6検出装置。
(1) Inside the reactor vessel (2) A reactor core and a core upper mechanism arranged, a rotatable control rod position detector that traces the core upper mechanism over the center of the core, and a front 6 cylinder. It consists of a reflector placed around the upper edge of the core, and
LJ Misaki salary rank! The a detector has a long cylindrical shape with a
It is equipped with an ultrasonic transducer that emits and receives two sets of sound waves, and has the following features: 19-1 nuclear reactor system (i111 + fist position i6 detection device).
(2)  反則体は短尺円筒形(二形成された府訂開水
の郵囲第1項記載の原子炉用制御悸位lfi、俣出装置
(2) The offending body has a short cylindrical shape (2), and is a control pulse lfi for a nuclear reactor, as described in Section 1 of the Kaisui Post Office, Matade device.
JP58037442A 1983-03-09 1983-03-09 Control rod position detecting device Pending JPS59163595A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP58037442A JPS59163595A (en) 1983-03-09 1983-03-09 Control rod position detecting device

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP58037442A JPS59163595A (en) 1983-03-09 1983-03-09 Control rod position detecting device

Publications (1)

Publication Number Publication Date
JPS59163595A true JPS59163595A (en) 1984-09-14

Family

ID=12497621

Family Applications (1)

Application Number Title Priority Date Filing Date
JP58037442A Pending JPS59163595A (en) 1983-03-09 1983-03-09 Control rod position detecting device

Country Status (1)

Country Link
JP (1) JPS59163595A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0410580A2 (en) * 1989-07-24 1991-01-30 The Babcock & Wilcox Company Scanning outer profiles of control rods
JP2012078259A (en) * 2010-10-04 2012-04-19 Mitsubishi Heavy Ind Ltd Reactor core top part monitor

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0410580A2 (en) * 1989-07-24 1991-01-30 The Babcock & Wilcox Company Scanning outer profiles of control rods
EP0410580A3 (en) * 1989-07-24 1991-11-27 The Babcock & Wilcox Company Scanning outer profiles of control rods
JP2012078259A (en) * 2010-10-04 2012-04-19 Mitsubishi Heavy Ind Ltd Reactor core top part monitor

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