JPH03200095A - Device for holding fuel assembly with measuring line - Google Patents
Device for holding fuel assembly with measuring lineInfo
- Publication number
- JPH03200095A JPH03200095A JP1338235A JP33823589A JPH03200095A JP H03200095 A JPH03200095 A JP H03200095A JP 1338235 A JP1338235 A JP 1338235A JP 33823589 A JP33823589 A JP 33823589A JP H03200095 A JPH03200095 A JP H03200095A
- Authority
- JP
- Japan
- Prior art keywords
- extension tube
- tube
- fuel assembly
- pipe
- outer extension
- 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.)
- Granted
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
【発明の詳細な説明】
[発明の目的]
(産業上の利用分野)
本発明は計測ケーブルを備えた燃料集合体を保持し、上
記計測ケーブルを炉外へ導くための計測線材燃料集合体
保持装置に関するものである。[Detailed Description of the Invention] [Object of the Invention] (Industrial Application Field) The present invention provides a measurement wire fuel assembly holding method for holding a fuel assembly equipped with a measurement cable, and for guiding the measurement cable out of the reactor. It is related to the device.
(従来の技術)
高速増殖炉の炉心を設計する際には、中性子照射により
炉心燃料から発生する核分裂生成ガス量や、炉心内を流
れる冷却材流量および燃料各部の温度を知る必要がある
。このような炉心燃料の挙動を連続的に測定するために
は、内部に各種センサ(例えば熱電対、電磁流量計、中
性子検出器等)を装備した計測線材燃料集合体と、この
計測線材燃料集合体の計測ケーブルを炉外へ導くための
装置が必要となる。(Prior Art) When designing the core of a fast breeder reactor, it is necessary to know the amount of fission product gas generated from the core fuel by neutron irradiation, the flow rate of coolant flowing in the core, and the temperature of each part of the fuel. In order to continuously measure the behavior of the core fuel, it is necessary to use a measurement wire fuel assembly equipped with various sensors (e.g. thermocouples, electromagnetic flowmeters, neutron detectors, etc.) A device is required to guide the body measurement cable out of the furnace.
従来、計測線材燃料集合体の計測ケーブルを炉外へ導く
装置としては、特公昭59−25200号に開示されて
いる計測線材燃料集合体保持装置がある。この計測線材
燃料集合体保持装置は第3図〜第5図に示すように、遮
蔽プラグ1を貫通して原子炉容器2内に挿入されたガイ
ド管4と、このガイド管4内に昇降可能に設けられた外
側延長管5と、この外側延長管5の内側に設けられた内
側延長管6とを有し、内側延長管6の下部には原子炉容
器2内の炉心3に装荷された計測線材燃料集合体8を保
持するラッチ機構7が開閉自在に設けられている。Conventionally, as a device for guiding a measurement cable of a measurement wire fuel assembly out of the reactor, there is a measurement wire fuel assembly holding device disclosed in Japanese Patent Publication No. 59-25200. As shown in FIGS. 3 to 5, this measurement wire fuel assembly holding device has a guide tube 4 inserted into the reactor vessel 2 through the shielding plug 1, and can be moved up and down into the guide tube 4. It has an outer extension tube 5 provided at A latch mechanism 7 that holds the measurement wire fuel assembly 8 is provided so as to be openable and closable.
上記計測線材燃料集合体8の内部には、複数本の燃料ビ
ンが収納されているとともに熱電対、電磁流量計、中性
子検出器等の各種センサが設けられ、これら各種センサ
と接続した計測ケーブル9は内側延長管6内を通って炉
外に設置された測定器10に接続されている。そして、
外側延長管5の下部には上記計測ケーブル9を切断する
カッター11が設けられている。Inside the measurement wire fuel assembly 8, a plurality of fuel bottles are housed, and various sensors such as thermocouples, electromagnetic flow meters, and neutron detectors are provided.Measurement cables 9 are connected to these various sensors. passes through the inner extension tube 6 and is connected to a measuring device 10 installed outside the furnace. and,
A cutter 11 for cutting the measurement cable 9 is provided at the lower part of the outer extension tube 5.
また、前記ガイド管4の上部には外側延長管5を昇降駆
動する駆動部12が設けられている。この駆動部12の
上部にはハンドル13が設けられており、このハンドル
13でリードねじ14を回転させて外側延長管5を昇降
させる構成となっている。なお、前記ガイド管4と外側
延長管5および外側延長管5と内側延長管6は、原子炉
容器2内の圧力バウンダリを確保するためにベローズ1
5.16で連結されている。Further, a drive section 12 is provided at the upper part of the guide tube 4 to drive the outer extension tube 5 up and down. A handle 13 is provided at the top of the drive unit 12, and the handle 13 rotates a lead screw 14 to move the outer extension tube 5 up and down. Note that the guide pipe 4 and the outer extension pipe 5 and the outer extension pipe 5 and the inner extension pipe 6 are connected to the bellows 1 in order to secure the pressure boundary inside the reactor vessel 2.
5.16 is connected.
このように構成される計#III付燃料集合体保持装置
は、駆動部12の上部に設けられたハンドル13を操作
して外側延長管5を下降させると、外側延長管5の下部
に設けられたカッター11が計測線材燃料集合体8の計
測ケーブル9を切断するとともに、外側延長管5の下部
に設けられたガイド17(第5図参照)が下降し、ラッ
チ機構7に当接してラッチ機構7を閉成させるので、計
測ケーブル9の切断と計測線材燃料集合体8の切り離し
を1つの動作で行なうことができる。The fuel assembly holding device with gauge #III configured as described above is configured so that when the handle 13 provided at the upper part of the drive unit 12 is operated to lower the outer extension pipe 5, the device is attached to the lower part of the outer extension pipe 5. At the same time, the cutter 11 cuts the measurement cable 9 of the measurement wire fuel assembly 8, and the guide 17 (see FIG. 5) provided at the lower part of the outer extension tube 5 descends, contacts the latch mechanism 7, and closes the latch mechanism. 7 is closed, cutting of the measurement cable 9 and separation of the measurement wire fuel assembly 8 can be performed in one operation.
ところで、従来の計測線材燃料集合体保持装置は計測線
材燃料集合体8の計測ケーブル9をカッター11で切断
し、内側延長管6の下端から計測線材燃料集合体8を切
り離した後、新しい計測線材燃料集合体8を内側延長管
6の下端に取付ける場合、前述したようにガイド管4と
外側延長管5および外側延長管5と内側延長管6がベロ
ーズ15.16で連結されているため、ガイド管4およ
び駆動部12を含めた装置全体を取り外す必要がある。By the way, the conventional measurement wire fuel assembly holding device cuts the measurement cable 9 of the measurement wire fuel assembly 8 with a cutter 11, separates the measurement wire fuel assembly 8 from the lower end of the inner extension tube 6, and then creates a new measurement wire fuel assembly. When attaching the fuel assembly 8 to the lower end of the inner extension pipe 6, the guide pipe 4 and the outer extension pipe 5 and the outer extension pipe 5 and the inner extension pipe 6 are connected by the bellows 15, 16 as described above, so the guide The entire device including tube 4 and drive 12 must be removed.
しかし、装置全体を取り外すためには駆動部周辺の制御
棒駆動装置も取り外さなければならないため、計測線材
燃料集合体8の取替え作業に多大の労力と時間を要して
いた。However, in order to remove the entire device, it is also necessary to remove the control rod drive device around the drive section, which requires a great deal of effort and time to replace the measurement wire fuel assembly 8.
(発明が解決しようとする課題)
上述の如く、従来の計測線材燃料集合体保持装置は原子
炉圧力容器2内の圧力バウンダリを確保するために、ガ
イド管4と外側延長管5および外側延長管5と内側延長
管6がベローズ15゜16で連結されていたため、計測
線材燃料集合体の取替えを行なう場合に装置全体を取り
外す必要があり、計測線材燃料集合体8の取替え作業に
多大の労力と時間を要するという問題があった。(Problems to be Solved by the Invention) As described above, the conventional measurement wire fuel assembly holding device uses the guide pipe 4, the outer extension pipe 5, and the outer extension pipe to ensure the pressure boundary within the reactor pressure vessel 2. 5 and the inner extension pipe 6 were connected by bellows 15° and 16, it was necessary to remove the entire device when replacing the measuring wire fuel assembly 8, and it took a lot of effort to replace the measuring wire fuel assembly 8. The problem was that it took time.
本発明はこのような問題点に着目してなされたもので、
その目的とするところはガイド管と外側延長管および外
側延長管と内側延長管をベローズで連結しなくても原子
炉圧力容器内の圧力バウンダリを確保でき、計測線材燃
料集合体の取替え作業を容易に行なうことのできる計測
線材燃料集合体保持装置を提供することにある。The present invention was made by focusing on these problems.
The purpose of this is to ensure the pressure boundary inside the reactor pressure vessel without connecting the guide tube and the outer extension tube and the outer extension tube and the inner extension tube with bellows, and to facilitate the replacement work of the measurement wire fuel assembly. The object of the present invention is to provide a measuring wire fuel assembly holding device that can perform measurements.
[発明の構成]
(課題を解決するための手段)
上記目的を達成するために第1の発明は、遮蔽プラグを
貫通して原子炉容器内に挿入されたガイド管と、このガ
イド管の内側に設けられた外側延長管と、この外側延長
管の内側に設けられた内側延長管と、前記ガイド管の上
部に設けられ前記外側延長管及び内側延長管のうちどち
らか一方を昇降駆動する駆動部と、前記外側延長管及び
内側延長管のうち前記駆動部により昇降駆動されない側
の延長管に設けられ計測線材燃料集合体を保持するラッ
チ機構と、前記外側延長管及び内側延長管のうち前記駆
動部により昇降駆動される側の延長管に設けられ前記計
測線材燃料集合体の計測ケーブルを切断するカッターと
を具備してなる計測線材燃料集合体保持装置において、
前記ガイド管と外側延長管との間および前記外側延長管
と内側延長管との間に、0リングを上下に配置した二重
シール部を設けると共に、これら二重シール部の上部シ
ール部と下部シール部との間にバックアップ用のガスシ
ール部を設けたことを特徴とするものである。[Structure of the Invention] (Means for Solving the Problems) In order to achieve the above object, a first invention provides a guide tube inserted into a reactor vessel through a shielding plug, and an inner side of the guide tube. an outer extension tube provided on the outer extension tube; an inner extension tube provided on the inner side of the outer extension tube; and a drive provided on the upper part of the guide tube that drives either the outer extension tube or the inner extension tube up and down. a latch mechanism provided on the extension tube on the side of the outer extension tube and the inner extension tube that is not driven up and down by the driving section and holds the measurement wire fuel assembly; A measurement wire fuel assembly holding device comprising: a cutter that is provided on an extension tube on the side that is driven up and down by a drive unit and cuts the measurement cable of the measurement wire fuel assembly;
A double seal portion in which O-rings are arranged above and below is provided between the guide tube and the outer extension tube and between the outer extension tube and the inner extension tube, and an upper seal portion and a lower portion of the double seal portion are provided. It is characterized by providing a backup gas seal part between the seal part and the seal part.
また、第2の発明は遮蔽プラグを貫通して原子炉容器内
に挿入されたガイド管と1、このガイド管内に設けられ
た外側延長管と、この外側延長管の内側に設けられた内
側延長管と、前記ガイド管の上部に設けられ前記外側延
長管及び内側延長管のうちどちらか一方を昇降駆動する
駆動部と、前記外側延長、管及び内側延長管のうち前記
駆動部により昇降駆動されない側の延長管に設けられ計
測ケーブルを備えた燃料集合体を保持するラッチ機構と
、前記外側延長管及び内側延長管のうち前記駆動部によ
り昇降駆動される側の延長管に設けられ前記計測ケーブ
ルを切断するカッターとを具備してなる計測線材燃料集
合体保持装置において、前記ガイド管と外側延長管との
間および前記外側延長管と内側延長管との間に、0リン
グを上下に配置した二重シール部をそれぞれ設けると共
に、これら二重シール部の上部シール部と下部シール部
との間にバックアップ用のガスシール部を設け、かつ前
記ガイド管と外側延長管との間に前記外側延長管に付着
したナトリウムを除去するナトリウムスフレバを設けた
ことを特徴とするものである。The second invention also includes a guide tube inserted into the reactor vessel through a shielding plug, an outer extension tube provided inside the guide tube, and an inner extension provided inside the outer extension tube. a tube, a driving section provided at the upper part of the guide tube and driving one of the outer extension tube and the inner extension tube up and down; and one of the outer extension, tube, and inner extension tube that is not driven up and down by the drive section. a latch mechanism provided on a side extension tube to hold a fuel assembly having a measurement cable; and a latch mechanism provided on the extension tube on the side of the outer extension tube and the inner extension tube that is driven up and down by the driving section and equipped with the measurement cable. In the measurement wire fuel assembly holding device, the O-rings are arranged vertically between the guide tube and the outer extension tube and between the outer extension tube and the inner extension tube. A double seal portion is provided, a backup gas seal portion is provided between the upper seal portion and the lower seal portion of these double seal portions, and the outer extension tube is provided between the guide tube and the outer extension tube. It is characterized by the provision of a sodium souffle valve that removes sodium adhering to the tube.
(作 用)
第1の本発明においては、原子炉容器内の圧力バウンダ
リを、ガイド管と外側延長管との間および外側延長管と
内側延長管との間に設けられた二重シール部によって確
保できるため、外側延長管および内側延長管のみを原子
炉容器内から引き抜くことができ、計測線材燃料集合体
の取替え作業を容易に行なうことができる。また、二重
シル部の上部シール部と下部シール部との間には、バッ
クアップ用のガスシール部が設けられているため、0リ
ングの破損等により二重シール部のシール機能が喪失し
た場合でも原子炉圧力容器内の圧力バウンダリを確保で
きる。(Function) In the first invention, the pressure boundary inside the reactor vessel is controlled by the double seal portion provided between the guide pipe and the outer extension pipe and between the outer extension pipe and the inner extension pipe. Therefore, only the outer extension tube and the inner extension tube can be pulled out from inside the reactor vessel, and the measurement wire fuel assembly can be easily replaced. Additionally, a backup gas seal is provided between the upper and lower seals of the double sill, so if the sealing function of the double seal is lost due to damage to the O-ring, etc. However, the pressure boundary inside the reactor pressure vessel can be secured.
第2の本発明はガイド管と外側延長管との間にナトリウ
ムスフレバが設けであるので、第1の発明と同様に計測
線材燃料集合体の取替え作業を容易に行なうことができ
ると共に、外側延長管に付着したナトリウムをナトリウ
ムスフレバで除去することができる。In the second aspect of the present invention, since a sodium souffle valve is provided between the guide tube and the outer extension tube, the measurement wire fuel assembly can be easily replaced as in the first aspect, and the outer extension tube can be replaced easily. Sodium adhering to the extension tube can be removed with a sodium souffle valve.
(実施例)
以下、本発明の一実施例を第1図及び第2図を参照して
説明する。なお、第3図〜第5図に示したものと同一部
分には同一符号を付し、その部分の説明は省略する。(Example) An example of the present invention will be described below with reference to FIGS. 1 and 2. Note that the same parts as shown in FIGS. 3 to 5 are given the same reference numerals, and explanations of those parts will be omitted.
第1図において、ガイド管4と外側延長管5との間およ
び外側延長管5と内側延長管6との間には、二重シール
部18.19が設けられている。In FIG. 1, double seals 18, 19 are provided between the guide tube 4 and the outer extension tube 5 and between the outer extension tube 5 and the inner extension tube 6.
これらの二重シール部18.19は第2図に示すように
、それぞれ0リング20.21を上下に配置して構成さ
れており、上側に配置されたOリング(上部シール部)
20と下側に配置されたOリング(下部シール部)21
との間には、環状溝からなるガスシール部22.23が
設けられている。As shown in Fig. 2, these double seal parts 18 and 19 are each composed of O rings 20 and 21 arranged above and below, and the O ring (upper seal part) arranged on the upper side
20 and O-ring (lower seal part) 21 placed on the lower side
A gas seal portion 22.23 consisting of an annular groove is provided between the two.
これらのガスシール部22.23には窒素ガス等のシー
ルガスが原子炉容器内の圧力より高い圧力で供給されて
おり、二重シール部18.19のバックアップ用として
設けられている。Seal gas such as nitrogen gas is supplied to these gas seal sections 22, 23 at a pressure higher than the pressure inside the reactor vessel, and is provided as a backup for the double seal sections 18, 19.
また、前記ガイド管4と外側延長管5との間の下部位置
にはナトリウムスフレバ24が設けられている。このナ
トリウムスフレバ24は連結管25を介してガイド管4
に固定されており、外側延長管5の外面にナトリウムが
蒸若するのを防止すると共に外側延長管5の外面に付む
したナトリウムを外側延長管5の昇降時に除去する機能
を有している。Further, a sodium souffle valve 24 is provided at a lower position between the guide tube 4 and the outer extension tube 5. This sodium souffle valve 24 is connected to the guide pipe 4 via a connecting pipe 25.
It has the function of preventing sodium from evaporating on the outer surface of the outer extension tube 5 and removing the sodium attached to the outer surface of the outer extension tube 5 when the outer extension tube 5 is raised and lowered. .
このように構成される計測線材燃料集合体保持装置は、
ガイド管4と外側延長管5との間および外側延長管5と
内側延長管6との間にOリング20.21を上下に配置
した二重シール部18゜19が設けられているため、こ
れらの二重シール部18.19によって原子炉圧力容器
内の圧力バウンダリを確保できる。したがって、従来の
ようにガイド管4と外側延長管5および外側延長管5と
内側延長管6をベローズで連結しなくても原子炉圧力容
器内の圧力バウンダリを確保でき、外側延長管5および
内側延長管6のみを原子炉圧力容器内から引き抜くこと
ができるので、計測線材燃料集合体8の取替え作業を容
易に行なうことができる。また、二重シール部18.1
9の上部シール部20と下部シール部21との間には、
バックアップ用のガスシール部22.23が設けられて
いるので、0リングの劣化、破損等により二重シール部
18.19のシール機能が低下した場合でもガスシール
部22.23によって原子炉圧力容器内の圧力バウンダ
リを確保でき、原子炉の安全性及び健全性向上を図るこ
とができる。The measurement wire fuel assembly holding device configured in this way is
Double seal parts 18 and 19 are provided between the guide tube 4 and the outer extension tube 5 and between the outer extension tube 5 and the inner extension tube 6, with O-rings 20 and 21 arranged above and below. The pressure boundary within the reactor pressure vessel can be secured by the double seal portions 18 and 19. Therefore, the pressure boundary inside the reactor pressure vessel can be secured without connecting the guide tube 4 and the outer extension tube 5 and the outer extension tube 5 and the inner extension tube 6 with bellows as in the past. Since only the extension tube 6 can be pulled out from inside the reactor pressure vessel, the measurement wire fuel assembly 8 can be easily replaced. In addition, the double seal part 18.1
Between the upper seal part 20 and the lower seal part 21 of 9,
Since the backup gas seal part 22.23 is provided, even if the sealing function of the double seal part 18.19 deteriorates due to deterioration or damage of the O-ring, the gas seal part 22.23 will protect the reactor pressure vessel. The pressure boundary within the reactor can be secured, and the safety and soundness of the reactor can be improved.
さらに、本実施例ではガイド管4と外側延長管5との間
にナトリウムスフレバ24が設けられているため、外側
延長管5に付着したナトリウムをナトリウムスフレバ2
4によって除去することができる。したがって、外側延
長管5および内側延長管6を原子炉容器内から引抜く際
に、ナトリウムによって外側延長管5がガイド管4に固
着するようなことがなく、外側延長管5および内側延長
管6を原子炉容器内から容易に引き抜くことができる。Furthermore, in this embodiment, since the sodium souffle bar 24 is provided between the guide tube 4 and the outer extension tube 5, the sodium adhering to the outer extension tube 5 is removed by the sodium souffle bar 24.
4 can be removed. Therefore, when pulling out the outer extension tube 5 and the inner extension tube 6 from inside the reactor vessel, the outer extension tube 5 does not stick to the guide tube 4 due to sodium, and the outer extension tube 5 and the inner extension tube 6 can be easily pulled out from inside the reactor vessel.
なお、上記実施例では計測線材燃料集合体8の計測ケー
ブル9を切断するカッター11を外側延長管5に設けて
いるが、カッター11を内側延長管6に設け、計測線材
燃料集合体8を保持するラッチ機構7を外側延長管5に
取り付けてもよい。In the above embodiment, the cutter 11 for cutting the measurement cable 9 of the measurement wire fuel assembly 8 is provided on the outer extension tube 5, but the cutter 11 is provided on the inner extension tube 6 to hold the measurement wire fuel assembly 8. A latch mechanism 7 may be attached to the outer extension tube 5.
ただし、その場合には内側延長管6が昇降駆動される構
成となる。However, in that case, the inner extension tube 6 will be driven up and down.
[発明の効果]
以上説明したように第1の本発明は、ガイド管と外側延
長管および外側延長管と内側延長管をベローズで連結し
なくても原子炉圧力容器内の圧力バウンダリを確保でき
、計測線材燃料集合体の取替え作業を容易に行なうこと
ができる。しかも、二重シール部のシール機能が低下し
た場合でもガスシール部によって原子炉圧力容器内の圧
力バウンダリを確保でき、原子炉の安全性及び健全性向
上を図ることができる。[Effects of the Invention] As explained above, the first invention makes it possible to secure the pressure boundary in the reactor pressure vessel without connecting the guide tube and the outer extension tube and the outer extension tube and the inner extension tube with bellows. , the measurement wire fuel assembly can be easily replaced. Furthermore, even if the sealing function of the double seal section is degraded, the pressure boundary within the reactor pressure vessel can be secured by the gas seal section, and the safety and soundness of the nuclear reactor can be improved.
また、第2の本発明は第1の発明と同様に計測線材燃料
集合体の取替え作業を容易に行なう、ことができるとと
もに、外側延長管に付着したナトリウムをナトリウムス
フレバによって除去することができる。Further, the second invention allows the measurement wire fuel assembly to be easily replaced in the same manner as the first invention, and the sodium adhering to the outer extension tube can be removed by the sodium souffle bar. .
第1図は本発明の一実施例を示す計測線材燃料集合体保
持装置の断面図、第2図はその要部を示す図、第3図〜
第5図は従来の計測線材燃料集合体保持装置を示す図で
ある。
1・・・遮蔽プラグ、2・・・原子炉容器、3・・・炉
心、4・・・ガイド管、5・・・外側延長管、6・・・
内側延長管、7・・・ラッチ機構、8・・・計7IIl
線材燃料集合体、9・・・計測ケーブル、11・・・カ
ッター 12・・・駆動部、18.19・・・二重シー
ル部、20・・・0リング(上部シール部)
2
1 ・・・0
リング
(下部シール部)
22゜
3・・・ガスシール部、
24・・・ナト
リウムス
ク
レバ。Fig. 1 is a sectional view of a measurement wire fuel assembly holding device showing an embodiment of the present invention, Fig. 2 is a view showing the main parts thereof, and Figs.
FIG. 5 is a diagram showing a conventional measurement wire fuel assembly holding device. DESCRIPTION OF SYMBOLS 1... Shielding plug, 2... Reactor vessel, 3... Reactor core, 4... Guide tube, 5... Outer extension tube, 6...
Inner extension tube, 7...Latch mechanism, 8...Total 7IIl
Wire fuel assembly, 9...Measuring cable, 11...Cutter 12...Drive part, 18.19...Double seal part, 20...0 ring (upper seal part) 2 1...・0 ring (lower seal part) 22° 3...Gas seal part, 24...Sodium scraper.
Claims (2)
ガイド管と、このガイド管の内側に設けられた外側延長
管と、この外側延長管の内側に設けられた内側延長管と
、前記ガイド管の上部に設けられ前記外側延長管及び内
側延長管のうちどちらか一方を昇降駆動する駆動部と、
前記外側延長管及び内側延長管のうち前記駆動部により
昇降駆動されない側の延長管に設けられ計測線材燃料集
合体を保持するラッチ機構と、前記外側延長管及び内側
延長管のうち前記駆動部により昇降駆動される側の延長
管に設けられ前記計測線材燃料集合体の計測ケーブルを
切断するカッターとを有する計測線付燃料集合体保持装
置において、前記ガイド管と外側延長管との間および前
記外側延長管と内側延長管との間に、Oリングを上下に
配置した二重シール部を設けると共に、これら二重シー
ル部の上部シール部と下部シール部との間にバックアッ
プ用のガスシール部を設けたことを特徴とする計測線付
燃料集合体保持装置。(1) A guide tube inserted into the reactor vessel through a shielding plug, an outer extension tube provided inside this guide tube, and an inner extension tube provided inside this outer extension tube, a drive unit provided at the upper part of the guide tube and driving one of the outer extension tube and the inner extension tube up and down;
A latch mechanism that is provided on the side of the extension tube that is not driven up and down by the drive section among the outer extension tube and the inner extension tube and holds the measurement wire fuel assembly; In the fuel assembly holding device with a measurement wire, the cutter is provided on the extension pipe on the side that is driven up and down and cuts the measurement cable of the measurement wire fuel assembly, and the cutter is provided between the guide pipe and the outer extension pipe and on the outer side. A double seal part with O-rings arranged above and below is provided between the extension pipe and the inner extension pipe, and a backup gas seal part is provided between the upper seal part and the lower seal part of these double seal parts. A fuel assembly holding device with a measurement line.
ガイド管と、このガイド管の内側に設けられた外側延長
管と、この外側延長管の内側に設けられた内側延長管と
、前記ガイド管の上部に設けられ前記外側延長管及び内
側延長管のうちどちらか一方を昇降駆動する駆動部と、
前記外側延長管及び内側延長管のうち前記駆動部により
昇降駆動されない側の延長管に設けられ計測線材燃料集
合体を保持するラッチ機構と、前記外側延長管及び内側
延長管のうち前記駆動部により昇降駆動される側の延長
管に設けられ前記計測線材燃料集合体の計測ケーブルを
切断するカッターとを有する計測線付燃料集合体保持装
置において、前記ガイド管と外側延長管との間および前
記外側延長管と内側延長管との間に、Oリングを上下に
配置した二重シール部を設けると共に、これら二重シー
ル部の上部シール部と下部シール部との間にバックアッ
プ用のガスシール部を設け、かつ前記ガイド管と外側延
長管との間に前記外側延長管に付着したナトリウムを除
去するナトリウムスクレパを設けたことを特徴とする計
測線材燃料集合体保持装置。(2) a guide tube inserted into the reactor vessel through the shielding plug; an outer extension tube provided inside the guide tube; and an inner extension tube provided inside the outer extension tube; a drive unit provided at the upper part of the guide tube and driving one of the outer extension tube and the inner extension tube up and down;
A latch mechanism that is provided on the side of the extension tube that is not driven up and down by the drive section among the outer extension tube and the inner extension tube and holds the measurement wire fuel assembly; In the fuel assembly holding device with a measurement wire, the cutter is provided on the extension pipe on the side that is driven up and down and cuts the measurement cable of the measurement wire fuel assembly, and the cutter is provided between the guide pipe and the outer extension pipe and on the outer side. A double seal part with O-rings arranged above and below is provided between the extension pipe and the inner extension pipe, and a backup gas seal part is provided between the upper seal part and the lower seal part of these double seal parts. A measurement wire fuel assembly holding device characterized in that a sodium scraper is provided between the guide tube and the outer extension tube to remove sodium adhering to the outer extension tube.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP1338235A JPH07104429B2 (en) | 1989-12-28 | 1989-12-28 | Fuel assembly holding device with measuring line |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP1338235A JPH07104429B2 (en) | 1989-12-28 | 1989-12-28 | Fuel assembly holding device with measuring line |
Publications (2)
Publication Number | Publication Date |
---|---|
JPH03200095A true JPH03200095A (en) | 1991-09-02 |
JPH07104429B2 JPH07104429B2 (en) | 1995-11-13 |
Family
ID=18316203
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP1338235A Expired - Lifetime JPH07104429B2 (en) | 1989-12-28 | 1989-12-28 | Fuel assembly holding device with measuring line |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPH07104429B2 (en) |
Cited By (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2013503335A (en) * | 2009-08-28 | 2013-01-31 | シーレイト リミテッド ライアビリティー カンパニー | Fission reactor, vented fission fuel module, method thereof, and vented fission fuel module system |
US8929505B2 (en) | 2009-08-28 | 2015-01-06 | Terrapower, Llc | Nuclear fission reactor, vented nuclear fission fuel module, methods therefor and a vented nuclear fission fuel module system |
US9259690B2 (en) | 2006-06-27 | 2016-02-16 | Toray Industries, Inc. | Polymer separation membrane and process for producing the same |
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-
1989
- 1989-12-28 JP JP1338235A patent/JPH07104429B2/en not_active Expired - Lifetime
Cited By (9)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US9259690B2 (en) | 2006-06-27 | 2016-02-16 | Toray Industries, Inc. | Polymer separation membrane and process for producing the same |
JP2013503335A (en) * | 2009-08-28 | 2013-01-31 | シーレイト リミテッド ライアビリティー カンパニー | Fission reactor, vented fission fuel module, method thereof, and vented fission fuel module system |
JP2013503338A (en) * | 2009-08-28 | 2013-01-31 | シーレイト リミテッド ライアビリティー カンパニー | Fission reactor, vented fission fuel module, method thereof, and vented fission fuel module system |
JP2013503336A (en) * | 2009-08-28 | 2013-01-31 | シーレイト リミテッド ライアビリティー カンパニー | Vented fission fuel module |
JP2013503334A (en) * | 2009-08-28 | 2013-01-31 | シーレイト リミテッド ライアビリティー カンパニー | Fission reactor, vented fission fuel module, method thereof, and vented fission fuel module system |
JP2013503337A (en) * | 2009-08-28 | 2013-01-31 | シーレイト リミテッド ライアビリティー カンパニー | Fission reactor, vented fission fuel module, method thereof, and vented fission fuel module system |
US8929505B2 (en) | 2009-08-28 | 2015-01-06 | Terrapower, Llc | Nuclear fission reactor, vented nuclear fission fuel module, methods therefor and a vented nuclear fission fuel module system |
US9269462B2 (en) | 2009-08-28 | 2016-02-23 | Terrapower, Llc | Nuclear fission reactor, a vented nuclear fission fuel module, methods therefor and a vented nuclear fission fuel module system |
US9721677B2 (en) | 2009-08-28 | 2017-08-01 | Terrapower, Llc | Nuclear fission reactor, a vented nuclear fission fuel module, methods therefor, and a vented nuclear fission fuel module system |
Also Published As
Publication number | Publication date |
---|---|
JPH07104429B2 (en) | 1995-11-13 |
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