JPH0651080A - Fuel assembly fixing device - Google Patents

Fuel assembly fixing device

Info

Publication number
JPH0651080A
JPH0651080A JP4202763A JP20276392A JPH0651080A JP H0651080 A JPH0651080 A JP H0651080A JP 4202763 A JP4202763 A JP 4202763A JP 20276392 A JP20276392 A JP 20276392A JP H0651080 A JPH0651080 A JP H0651080A
Authority
JP
Japan
Prior art keywords
fuel assembly
rod
fixing device
insertion hole
support plate
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.)
Withdrawn
Application number
JP4202763A
Other languages
Japanese (ja)
Inventor
Kiyoshi Kato
潔 加藤
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.)
IHI Corp
Original Assignee
IHI 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 IHI Corp filed Critical IHI Corp
Priority to JP4202763A priority Critical patent/JPH0651080A/en
Publication of JPH0651080A publication Critical patent/JPH0651080A/en
Withdrawn legal-status Critical Current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

PURPOSE:To enhance the adaptability to a nuclear reactor in which the upper opening of a riser pipe is throated, enhance the effectiveness in works of replacing fuel assembly, reduce the labor therein, and enhance the fixation strength in high temp. condition. CONSTITUTION:A fuel assembly fixing device concerned includes a dint-shaped detention part 20b formed in a fuel assembly insertion hole 20a, a detaining cylinder 14a located at the bottom of a fuel assembly 14, a restraining rod 23 to be supported movably by the detaining cylinder 14a, a thermally actuated element which is deformed into the stored shape and detains the rod 23 with the detention part 20b, and a resilient member which is installed on the thermally actuated element and moves the rod 23 inward.

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、燃料集合体固定装置に
係り、特に、炉心から蒸気発生器への上昇一次冷却水を
導くためのライザ管が狭められている場合に、燃料集合
体の炉心部分への設置や交換時の作業性を向上させるも
のである。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a fuel assembly fixing device, and more particularly to a fuel assembly fixing device for narrowing a riser pipe for guiding rising primary cooling water from a core to a steam generator. The workability at the time of installation or replacement in the core part is improved.

【0002】[0002]

【従来技術】従来、燃料集合体の交換に関連する技術例
として、特開平3−252593号公報(燃料集合体の
交換装置)、特開平3−252594号公報(燃料集合
体の交換装置)、特開平3−252595号公報(燃料
集合体の交換装置)が提案されている。
2. Description of the Related Art Conventionally, as a technical example related to the replacement of a fuel assembly, Japanese Patent Application Laid-Open No. 3-252599 (fuel assembly replacement device), Japanese Patent Application Laid-Open No. 3-252594 (fuel assembly replacement device), JP-A-3-252595 (fuel assembly exchange device) is proposed.

【0003】また、これらの公報には、図4ないし図6
に示す技術が記載されている。各図において、符号1は
原子炉圧力容器、2は炉心、3は蒸気発生器、4は上
蓋、5は制御棒駆動装置、6は一次冷却水ポンプ、7は
制御棒支持構造物、8はライザ部、9は仕切壁、10は
テレスコープ部、11は燃料棒グリッパ、12は搬送台
車、13は横行台車、14は燃料集合体、15はライザ
管、16ポイズンタンク、17は冷却水入口、18は水
圧作動弁、19はポイズン流通器、20は炉心支持板、
Pはほう酸水(炉内プール水)、作業用空間Y、燃料交
換装置Xである。
Further, in these publications, FIGS.
The technique shown in is described. In each drawing, reference numeral 1 is a reactor pressure vessel, 2 is a core, 3 is a steam generator, 4 is an upper lid, 5 is a control rod driving device, 6 is a primary cooling water pump, 7 is a control rod support structure, and 8 is Riser part, 9 partition wall, 10 telescope part, 11 fuel rod gripper, 12 carrier car, 13 traverse car, 14 fuel assembly, 15 riser pipe, 16 poison tank, 17 cooling water inlet , 18 is a hydraulically operated valve, 19 is a poison distributor, 20 is a core support plate,
P is a boric acid water (pool water in the furnace), a working space Y, and a fuel exchange device X.

【0004】図4例の原子炉にあっては、炉心2の上部
に位置している構造物を撤去して図5に示す状態にし、
テレスコープ部10及び燃料棒グリッパ11をライザ部
8の中に挿入することにより、燃料集合体14の引き出
しや装填が実施される。
In the nuclear reactor shown in FIG. 4, the structure located above the core 2 is removed to obtain the state shown in FIG.
By inserting the telescope unit 10 and the fuel rod gripper 11 into the riser unit 8, the fuel assembly 14 is pulled out and loaded.

【0005】図6例の原子炉にあっても、炉心2の上部
に位置する一次冷却水ポンプ6等を撤去した状態とし
て、テレスコープ部10及び燃料棒グリッパ11をライ
ザ管15の中に挿入し、さらに、各公報に記載されてい
る交換装置を駆使することにより燃料集合体14の引き
出しや装填が可能となる。
Even in the reactor shown in FIG. 6, the telescope section 10 and the fuel rod gripper 11 are inserted into the riser pipe 15 with the primary cooling water pump 6 and the like located above the reactor core 2 removed. Further, by making full use of the exchange device described in each publication, the fuel assembly 14 can be pulled out and loaded.

【0006】一方、原子炉の運転時には、各燃料集合体
14を固定した状態とする必要がある。図4例及び図5
例では、炉心2と制御棒支持構造物7との間に燃料集合
体固定装置21を配して、各燃料集合体14を固定する
ようにしている。図6例では、制御棒がないため、例え
ば炉心支持板20の部分に燃料集合体固定装置21を配
して、各燃料集合体14を固定する計画がなされてい
る。
On the other hand, during operation of the nuclear reactor, it is necessary to fix each fuel assembly 14. FIG. 4 example and FIG.
In the example, the fuel assembly fixing device 21 is arranged between the core 2 and the control rod support structure 7 to fix each fuel assembly 14. In the example of FIG. 6, since there are no control rods, it is planned to fix each fuel assembly 14 by disposing the fuel assembly fixing device 21 in the portion of the core support plate 20, for example.

【0007】[0007]

【発明が解決しようとする課題】しかし、図4例及び図
6例いずれの場合にあっても、各燃料集合体14の固定
及び解除作業性や労力の点で解決すべき課題が残されて
いる。つまり、図4例及び図5例にあっては、燃料集合
体14を引き抜く際に、燃料集合体固定装置21を原子
炉の外に撤去する必要があって、その労力が多大なもの
となり、図6例にあっては、燃料集合体固定装置21が
ライザ管15の上部開口より大きいと、単純な引き出し
ができなくなり、分割して撤去する場合には、取り外
し、撤去、再取り付け作業の労力が大きくなる。
However, in both cases of FIG. 4 and FIG. 6, there remains a problem to be solved in terms of workability and labor for fixing and releasing each fuel assembly 14. There is. That is, in the example of FIG. 4 and the example of FIG. 5, when withdrawing the fuel assembly 14, it is necessary to remove the fuel assembly fixing device 21 to the outside of the nuclear reactor, and the labor becomes great. In the example of FIG. 6, if the fuel assembly fixing device 21 is larger than the upper opening of the riser pipe 15, simple withdrawal becomes impossible, and in the case of dividing and removing, labor of removal, removal, and reattachment work is performed. Grows larger.

【0008】本発明は、かかる事情に鑑みてなされたも
ので、 原子炉運転時等の高温状態における固定強度を向上さ
せること、 燃料集合体の交換時に燃料集合体固定装置の解体撤去
等を不要とすること、 ライザ管の直径を小さくして蒸気発生器の設置スペー
スを増大させる原子炉への適用性を高めること、 燃料集合体の固定時または解除時に要する労力を低減
すること等を目的としている。
The present invention has been made in view of the above circumstances, and it is necessary to improve the fixing strength in a high temperature state such as during the operation of a nuclear reactor, and to eliminate the disassembly and removal of the fuel assembly fixing device when replacing the fuel assembly. The purpose is to reduce the diameter of the riser pipe, increase the applicability to the reactor that increases the installation space of the steam generator, and reduce the labor required for fixing or releasing the fuel assembly. There is.

【0009】[0009]

【課題を解決するための手段】上記課題を解決するた
め、炉心支持板の燃料集合体挿入穴の内壁に形成される
窪部状の係止部と、炉心支持板に載置される燃料集合体
の下端部に一体に配され燃料集合体挿入穴に挿入される
係合筒部と、該係合筒部の外周にその半径方向に移動可
能に支持される複数の拘束ロッドと、係合筒部と拘束ロ
ッドとの間に介在状態に配され原子炉冷却水の運転温度
近傍で記憶形状に変態し拘束ロッドを係止部に係合させ
る熱作動体と、該熱作動体に併設され拘束ロッドを内方
に移動させる弾発部材とを具備する構成の燃料集合体固
定装置としている。
In order to solve the above problems, a recessed engagement portion formed on the inner wall of a fuel assembly insertion hole of a core support plate and a fuel assembly mounted on the core support plate. An engaging cylinder part that is integrally arranged at the lower end of the body and is inserted into the fuel assembly insertion hole, and a plurality of restraint rods that are supported on the outer periphery of the engaging cylinder part so as to be movable in the radial direction thereof. A thermal actuation body disposed between the cylindrical portion and the restraining rod and transformed into a memory shape near the operating temperature of the reactor cooling water to engage the restraining rod with the locking portion; The fuel assembly fixing device is configured to include an elastic member that moves the restraining rod inward.

【0010】[0010]

【作用】熱作動体を変形させ、拘束ロッドを内方に退避
させた状態にして燃料集合体の係合筒部を炉心支持板の
燃料集合体挿入穴に挿入する。熱作動体が原子炉冷却水
の運転温度近傍まで加熱されると、熱作動体が記憶形状
に変態して拘束ロッドを外方に移動させ、拘束ロッドが
係止部に係合することにより、燃料集合体が炉心支持板
に固定される。熱作動体の周囲温度が低下した状態にな
ると、弾発部材の弾発力により熱作動体が内方に変形さ
せられ、燃料集合体の上方への引き抜きが可能な状態と
なる。
The heat actuating body is deformed, the restraining rod is retracted inward, and the engaging cylinder portion of the fuel assembly is inserted into the fuel assembly insertion hole of the core support plate. When the thermal working body is heated to near the operating temperature of the reactor cooling water, the thermal working body transforms into a memory shape and moves the restraining rod outward, and the restraining rod engages with the locking portion. The fuel assembly is fixed to the core support plate. When the ambient temperature of the thermal actuator falls, the thermal actuator deforms inward by the elastic force of the elastic member, and the fuel assembly can be pulled upward.

【0011】[0011]

【実施例】以下、本発明に係る燃料集合体固定装置の一
実施例について、図1ないし図3に基づいて説明する。
図1ないし図3において、符号14aは係合筒部、20
aは燃料集合体挿入穴、20bは係止部、22はハウジ
ング、22aは取付座、23は拘束ロッド、24は熱作
動体、25は弾発部材である。なお、図1ないし図3
は、図6に示した原子炉に適用する場合の実施例を示し
ており、図1において、右半分に燃料集合体の挿入時、
左半分に原子炉運転時の拘束ロッド23の状態を示して
いる。
DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS An embodiment of the fuel assembly fixing device according to the present invention will be described below with reference to FIGS.
In FIGS. 1 to 3, reference numeral 14a denotes an engaging cylinder portion, 20
Reference numeral a is a fuel assembly insertion hole, 20b is a locking portion, 22 is a housing, 22a is a mounting seat, 23 is a restraining rod, 24 is a thermal actuator, and 25 is an elastic member. 1 to 3
Shows an embodiment when applied to the nuclear reactor shown in FIG. 6, and in FIG. 1, when the fuel assembly is inserted in the right half,
The left half shows the state of the restraint rod 23 during operation of the reactor.

【0012】前記係合筒部14aは、燃料集合体14の
下端部に一体に配され、径を狭めた状態の円筒状等に形
成される。
The engagement cylinder portion 14a is integrally arranged at the lower end portion of the fuel assembly 14 and is formed in a cylindrical shape having a reduced diameter.

【0013】前記炉心支持板20には、燃料集合体14
の下端部の係合筒部14aを挿入するための燃料集合体
挿入穴20aが明けられるとともに、該燃料集合体挿入
穴20aの内壁に、環状溝等の窪部状の係止部20bが
配される。
The core support plate 20 has a fuel assembly 14
A fuel assembly insertion hole 20a for inserting the engagement cylinder portion 14a at the lower end of the fuel assembly insertion hole 20a is opened, and a recessed locking portion 20b such as an annular groove is provided on the inner wall of the fuel assembly insertion hole 20a. To be done.

【0014】前記ハウジング22は、その円孔部分を半
径外方向に向けた状態で、取付座22aによって係合筒
部14aの外周面の複数箇所(例えば4箇所に分割状
態)に一体に配される。
The housing 22 is integrally arranged at a plurality of places (for example, divided into four places) on the outer peripheral surface of the engaging cylinder portion 14a by the mounting seats 22a with the circular hole portion thereof directed outward in the radial direction. It

【0015】前記拘束ロッド23は、ハウジング22の
内部に、一部が外方に突出した状態に配され、取付座2
2aと拘束ロッド23との間には、組み合わせた状態の
熱作動体24及び弾発部材25が介在状態に配される。
The restraining rod 23 is arranged inside the housing 22 with a part thereof protruding outward, and the restraining rod 23 is attached to the mounting seat 2
The thermal actuating body 24 and the elastic member 25 in a combined state are arranged between the 2a and the restraining rod 23 in an interposing state.

【0016】熱作動体24は、図2及び図3に示すよう
に、例えば、全体としてコイル状とされ、高温状態で記
憶形状に変態してコイル長が大きくなる形状記憶合金、
例えばTi−Pd合金が適用され、その高温相の変態温
度が、原子炉冷却水の運転温度近傍、または原子炉の運
転時に燃料集合体14や炉心支持板20からの熱伝達に
基づく温度以下等に設定される。
As shown in FIGS. 2 and 3, the thermal actuator 24 is, for example, in the form of a coil as a whole, and a shape memory alloy that transforms into a memorized shape at high temperature to increase the coil length,
For example, a Ti-Pd alloy is applied, and the transformation temperature of its high temperature phase is near the operating temperature of the reactor cooling water, or below the temperature based on heat transfer from the fuel assembly 14 and the core support plate 20 during operation of the reactor, etc. Is set to.

【0017】前記弾発部材25は、熱作動体24に併設
されるもので、図2及び図3にあってはコイル状をなす
とともに、その両端部が、取付座22a及び拘束ロッド
23に接続されており、弾発力によって拘束ロッド23
を内方に移動させるようにしている。つまり、常温状態
等の低温時にあっては、弾発部材25の収縮力が熱作動
体24の変形抵抗力よりも大きくなるように設定してお
き、原子炉運転状態等の高温時にあっては、熱作動体2
4の高温状態での記憶形状への変態力が弾発部材25の
収縮力より大きくなるように設定しておく。
The elastic member 25 is provided along with the thermal actuator 24 and has a coil shape in FIGS. 2 and 3, and both ends thereof are connected to the mounting seat 22a and the restraining rod 23. And is restrained by elastic force 23
I am trying to move inward. That is, it is set such that the contraction force of the elastic member 25 is larger than the deformation resistance force of the thermal actuator 24 at a low temperature such as a room temperature state, and at a high temperature such as a reactor operating state. , Thermal actuator 2
The transformation force to the memorized shape in the high temperature state of 4 is set to be larger than the contraction force of the elastic member 25.

【0018】以下、このように構成されている燃料集合
体固定装置による燃料集合体14の固定及び引き抜き作
業について説明する。
The operation for fixing and withdrawing the fuel assembly 14 by the fuel assembly fixing device thus constructed will be described below.

【0019】低温時にあっては、弾発部材25の収縮力
が大きく作用して、図1の右半分及び図2に示すよう
に、拘束ロッド23が凹んだ状態となる。したがって、
燃料集合体14の係合筒部14aを、炉心支持板20の
燃料集合体挿入穴20aに挿入して、炉心支持板20に
支持させる作業や、炉心支持板20から燃料集合体14
を上方への引き抜く作業が実施可能となる。
At the time of low temperature, the contracting force of the elastic member 25 acts largely, and the restraining rod 23 is in a recessed state as shown in the right half of FIG. 1 and FIG. Therefore,
The engaging cylinder portion 14a of the fuel assembly 14 is inserted into the fuel assembly insertion hole 20a of the core support plate 20 so as to be supported by the core support plate 20, and the fuel assembly 14 is removed from the core support plate 20.
It becomes possible to carry out the work of pulling out upward.

【0020】高温時にあっては、熱作動体24の記憶形
状への変態力が大きく作用するため、図1の左半分及び
図3に示すように、拘束ロッド23が外方に移動した状
態となる。原子炉の運転等によって、熱作動体24が原
子炉冷却水の運転温度近傍まで加熱されると、熱作動体
24の記憶形状への変態に基づいて、拘束ロッド23が
燃料集合体挿入穴20aの係止部20bに係合して、熱
作動体24の上方への移動が抑制され、燃料集合体14
が炉心支持板20に固定された拘束状態となる。
At a high temperature, the transformation force of the thermal actuator 24 into a memorized shape has a large effect, so that the restraint rod 23 moves outward as shown in the left half of FIG. 1 and FIG. Become. When the thermal working body 24 is heated to the vicinity of the operating temperature of the reactor cooling water by the operation of the nuclear reactor or the like, the restraining rod 23 causes the restraint rod 23 to be inserted into the fuel assembly insertion hole 20a based on the transformation of the thermal working body 24 into the memory shape. The engaging portion 20b of the fuel assembly 14 is restrained from moving upward of the thermal actuator 24, and the fuel assembly 14 is prevented from moving upward.
Is in a restrained state in which it is fixed to the core support plate 20.

【0021】〔他の実施態様〕本発明にあっては、各実
施例に代えて、次の技術を採用することができる。 図6例以外のライザ管15の上部開口が狭められてい
る軽水冷却型原子炉に対して適用すること。 ライザ部8の上部開口が炉心2の外径以上である原子
炉や制御棒駆動装置を炉心の下方に設置した原子炉に対
して適用すること。
[Other Embodiments] In the present invention, the following technique can be adopted instead of each embodiment. It should be applied to light water cooled reactors where the upper opening of the riser pipe 15 is narrowed other than the example shown in FIG. The present invention should be applied to a reactor in which the upper opening of the riser portion 8 is equal to or larger than the outer diameter of the core 2 or a control rod drive device installed below the core.

【0022】[0022]

【発明の効果】本発明に係る燃料集合体固定装置にあっ
ては、炉心支持板の燃料集合体挿入穴に形成される窪部
状の係止部と、燃料集合体の下端部に配される係合筒部
と、係合筒部の外周に移動可能に支持される拘束ロッド
と、原子炉冷却水の運転温度近傍で記憶形状に変態し拘
束ロッドを係止部に係合させる熱作動体と、熱作動体に
併設され拘束ロッドを内方に移動させる弾発部材とを具
備する構成を採用しているから、以下の効果を奏する。 (1) 拘束ロッドを移動させて係止部に挿入するもの
であるため、原子炉運転時等の高温状態における固定強
度を向上させることができる。 (2) 燃料集合体の下端部に熱作動体が組み付けられ
るため、燃料集合体の交換時に、従来構造の燃料集合体
固定装置の解体撤去等を不要にして作業性を著しく向上
させることができる。 (3) 熱作動部が高温時に固定状態を形成するため、
燃料集合体の固定時または解除時に要する労力を低減す
ることができる。 (4) 燃料集合体を上下方向に移動させることにより
着脱されるので、ライザ管が狭められている原子炉にあ
っても、炉心上部空間内における燃料集合体の交換作業
を円滑に行なうことができる。 (5) 上記によりライザ管の直径を小さくして蒸気発
生器の設置スペースを増大することができる。
In the fuel assembly fixing device according to the present invention, the recessed engagement portion formed in the fuel assembly insertion hole of the core support plate and the lower end portion of the fuel assembly are arranged. The engaging cylinder part, the restraining rod movably supported on the outer circumference of the engaging cylinder part, and the thermal actuation that transforms into the memory shape near the operating temperature of the reactor cooling water and engages the restraining rod with the locking part. Since the structure including the body and the elastic member that is provided adjacent to the thermal actuator and moves the restraining rod inward is adopted, the following effects are achieved. (1) Since the restraint rod is moved and inserted into the locking portion, it is possible to improve the fixing strength in a high temperature state such as during operation of the nuclear reactor. (2) Since the thermal actuation body is assembled to the lower end portion of the fuel assembly, it is possible to remarkably improve workability by eliminating disassembly and removal of the fuel assembly fixing device having the conventional structure when exchanging the fuel assembly. . (3) Since the heat actuating part forms a fixed state at high temperature,
The labor required when fixing or releasing the fuel assembly can be reduced. (4) Since the fuel assembly is attached and detached by moving the fuel assembly in the vertical direction, it is possible to smoothly perform the work of exchanging the fuel assembly in the upper core space even in a reactor in which the riser tube is narrowed. it can. (5) With the above, the diameter of the riser pipe can be reduced to increase the installation space for the steam generator.

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

【図1】本発明に係る燃料集合体固定装置の一実施例に
あって、右半分に燃料集合体の挿入時、左半分に原子炉
運転時の拘束ロッドの状態を示す正断面図である。
FIG. 1 is a front cross-sectional view showing a state of a restraining rod in an embodiment of a fuel assembly fixing device according to the present invention when a fuel assembly is inserted in a right half and a reactor is operated in a left half. .

【図2】図1における低温時の拘束ロッドの状態を示す
正断面図である。
2 is a front sectional view showing a state of a restraining rod at a low temperature in FIG.

【図3】図1における高温時の拘束ロッドの状態を示す
正断面図である。
FIG. 3 is a front sectional view showing a state of a restraining rod at a high temperature in FIG.

【図4】軽水型原子炉の従来例を示す正断面図である。FIG. 4 is a front sectional view showing a conventional example of a light water reactor.

【図5】図4例における炉心の上方に作業用空間を形成
した状態を示す正断面図である。
5 is a front sectional view showing a state in which a working space is formed above the core in the example of FIG.

【図6】ライザ管が狭められた状態の軽水型原子炉の従
来例を示す正断面図である。
FIG. 6 is a front cross-sectional view showing a conventional example of a light water nuclear reactor with a riser tube being narrowed.

【符号の説明】[Explanation of symbols]

1 原子炉圧力容器 2 炉心 3 蒸気発生器 8 ライザ部 9 仕切壁 10 テレスコープ部 11 燃料棒グリッパ 12 搬送台車 13 横行台車 14 燃料集合体 14a 係合筒部 15 ライザ管 16 ポイズンタンク 17 冷却水入口 18 水圧作動弁 19 ポイズン流通器 20 炉心支持板 20a 燃料集合体挿入穴 20b 係止部 21 燃料集合体固定装置 22 ハウジング 22a 取付座 23 拘束ロッド 24 熱作動体 25 弾発部材 P ほう酸水(炉内プール水) X 燃料交換装置 Y 作業用空間 1 Reactor Pressure Vessel 2 Core 3 Steam Generator 8 Riser Section 9 Partition Wall 10 Telescope Section 11 Fuel Rod Gripper 12 Transport Cart 13 Traverse Cart 14 Fuel Assembly 14a Engaging Tube 15 Riser Pipe 16 Poison Tank 17 Cooling Water Inlet 18 Water Pressure Actuated Valve 19 Poison Distributor 20 Core Support Plate 20a Fuel Assembly Insertion Hole 20b Locking Part 21 Fuel Assembly Fixing Device 22 Housing 22a Mounting Seat 23 Restraint Rod 24 Thermal Activator 25 Repulsive Member P Boric Acid (inside the Reactor) Pool water) X Refueling device Y Working space

Claims (1)

【特許請求の範囲】[Claims] 【請求項1】 炉心支持板の燃料集合体挿入穴の内壁に
形成される窪部状の係止部と、炉心支持板に載置される
燃料集合体の下端部に一体に配され燃料集合体挿入穴に
挿入される係合筒部と、該係合筒部の外周にその半径方
向に移動可能に支持される複数の拘束ロッドと、係合筒
部と拘束ロッドとの間に介在状態に配され原子炉冷却水
の運転温度近傍で記憶形状に変態し拘束ロッドを係止部
に係合させる熱作動体と、該熱作動体に併設され拘束ロ
ッドを内方に移動させる弾発部材とを具備することを特
徴とする燃料集合体固定装置。
1. A fuel assembly which is integrally arranged at a lower end portion of a fuel assembly mounted on the core support plate and a recessed engagement portion formed on the inner wall of the fuel assembly insertion hole of the core support plate. Engagement tubular portion inserted into the body insertion hole, a plurality of restraint rods supported on the outer periphery of the engagement tubular portion so as to be movable in the radial direction, and an intervening state between the engagement tubular portion and the restraint rod. And a thermal actuation body that transforms into a memory shape near the operating temperature of the reactor cooling water and engages the restraining rod with the locking portion, and an elastic member that is attached to the thermal actuating body and moves the restraining rod inward. And a fuel assembly fixing device.
JP4202763A 1992-07-29 1992-07-29 Fuel assembly fixing device Withdrawn JPH0651080A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP4202763A JPH0651080A (en) 1992-07-29 1992-07-29 Fuel assembly fixing device

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP4202763A JPH0651080A (en) 1992-07-29 1992-07-29 Fuel assembly fixing device

Publications (1)

Publication Number Publication Date
JPH0651080A true JPH0651080A (en) 1994-02-25

Family

ID=16462767

Family Applications (1)

Application Number Title Priority Date Filing Date
JP4202763A Withdrawn JPH0651080A (en) 1992-07-29 1992-07-29 Fuel assembly fixing device

Country Status (1)

Country Link
JP (1) JPH0651080A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2006313145A (en) * 2005-05-02 2006-11-16 Westinghouse Electric Co Llc Restricted assembly in core and reactor core

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2006313145A (en) * 2005-05-02 2006-11-16 Westinghouse Electric Co Llc Restricted assembly in core and reactor core

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Effective date: 19991005