JPS6039590A - Holder for core constitutional element - Google Patents

Holder for core constitutional element

Info

Publication number
JPS6039590A
JPS6039590A JP58146546A JP14654683A JPS6039590A JP S6039590 A JPS6039590 A JP S6039590A JP 58146546 A JP58146546 A JP 58146546A JP 14654683 A JP14654683 A JP 14654683A JP S6039590 A JPS6039590 A JP S6039590A
Authority
JP
Japan
Prior art keywords
latch
core
core component
reactor
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
JP58146546A
Other languages
Japanese (ja)
Inventor
康弘 坂井
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 JP58146546A priority Critical patent/JPS6039590A/en
Publication of JPS6039590A publication Critical patent/JPS6039590A/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

  • Fuel-Injection Apparatus (AREA)
  • Gripping On Spindles (AREA)
  • Molds, Cores, And Manufacturing Methods Thereof (AREA)

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】 し発明の技術分野] 本発明は、タンク型原子炉等において地震時等に炉心に
急激な鉛直方向の力が加わっても炉心構成要素の浮」〕
りを防止し得る炉心構成要素の保持装置に関する。
[Detailed Description of the Invention] [Technical Field of the Invention] The present invention provides a method for preventing core components from floating even if a sudden vertical force is applied to the reactor core during an earthquake or the like in a tank-type nuclear reactor.
This invention relates to a holding device for core components that can prevent damage.

[発明の技術的背量と−ての問題点」 炉心を構成する各炉心構成要素には、流過する冷却材に
より常に上向きのLF圧力荷重作用しでおり、地震時等
に鉛直方向の荷重が作用すると、炉心構成要素が浮上っ
てしまう。
[Problems with the technical burden of the invention] Each core component that makes up the reactor core is constantly subjected to an upward LF pressure load by the flowing coolant, and vertical loads may occur during earthquakes, etc. If this happens, the core components will float up.

従来、このような浮上りを防+I: iJるため、炉心
構成要素およびモジュールのエン1−ランスノズル下部
嵌合部の下方に底圧プレナムを設け、下部1■含部の上
下の圧力差により上向きの圧力荷重を低減させ、自重、
圧力荷重およびll!l震荷重をバランスさせるように
した、いわゆるハイド[」リックホールドダウン方式が
用いられでいる。
Conventionally, in order to prevent such floating, a bottom pressure plenum was provided below the lower fitting part of the engine lance nozzle of the core components and modules, and the pressure difference between the upper and lower parts of the lower part was used to Reduces upward pressure load and reduces own weight,
Pressure loads and ll! A so-called Hyde rick holddown method is used to balance the seismic loads.

しかしながら、近年、タンク型原子炉のTtll究が進
むにつれ、炉心に対する鉛直方向応答加速度が1Gを越
える事態の発生が予想されるに到ったIごめ、従来のハ
イドロリックホールドダウン方式のみでは、炉心の浮上
りを十分に防1Fできない危険のあることが判明してき
た。
However, in recent years, as research into TTL of tank-type nuclear reactors has progressed, it has come to be expected that the vertical response acceleration to the reactor core will exceed 1G. It has become clear that there is a danger that 1F cannot sufficiently prevent the core from surfacing.

[発明の目的] 本発明は上述の事情に鑑みてなされたもので、大きな応
答加速度が炉心にかかる鉛直地震に対しても確実に炉心
構成要素の浮上りを防止でき、しかも、炉心構成要素の
交換が必要−な時にはこれに容易に対応ぐきる炉心構成
要素の保持装置を提供】ることを目的とする。
[Object of the Invention] The present invention has been made in view of the above-mentioned circumstances, and can reliably prevent the core components from floating even in the case of a vertical earthquake where a large response acceleration is applied to the reactor core. An object of the present invention is to provide a holding device for core components that can easily be replaced when necessary.

F発明の概要] すなわち本発明は、炉心構成要素のエントランスノズル
を連結管内に保持する炉心構成要素の保持装置において
、前記炉心構成要素内に回転自在に配置されるラッチロ
ッドと、このラッチロッドの下端に配設された冷却材流
通孔を備え、かつ周面の数か所にデラッチ用溝を備えた
ラッチプレ−1〜と、前記エン1ヘランスノズルの周面
数か所に前記デラッヂ用溝に対応して透設される切欠部
と、この切欠部に挿入され前記連結管に形成されるラッ
チ用溝に係合されるラッチ用部材とからなることを特徴
とりる炉心構成要素の保持装置である。
F Summary of the Invention] That is, the present invention provides a core component holding device that holds an entrance nozzle of a core component in a connecting pipe, including a latch rod rotatably disposed within the core component, and a latch rod that is rotatably disposed within the core component. Latch plates 1 to 1 are provided with coolant flow holes arranged at the lower end and have grooves for delatching at several places on the circumferential surface, and corresponding to the grooves for delatching at several places on the circumferential surface of the En-1 Herance nozzle. 1. A holding device for a core component, comprising: a notch provided through the connecting pipe; and a latch member inserted into the notch and engaged with a latch groove formed in the connecting pipe. .

[発明の実施例] 以下図面を参照して本発明の一実施例を説明する。[Embodiments of the invention] An embodiment of the present invention will be described below with reference to the drawings.

第1図は原子炉の概略構成を示すもので、原子炉容器1
は内部に多数本の燃11等の炉心構成要素2、炉心槽3
、炉心支持板4、支持構造物5、原子炉容器内筒6等を
収納しており、上端を炉心上部機構7を備えた回転プラ
グ8および固定プラグ、9で遮蔽されている。
Figure 1 shows the schematic configuration of the reactor, with reactor vessel 1
Inside there are many core components 2, such as fuel 11, and a core tank 3.
, a core support plate 4, a support structure 5, a reactor vessel inner cylinder 6, and the like are housed therein, and the upper end is shielded by a rotary plug 8 and a fixed plug 9 having a core upper mechanism 7.

各炉心要′s21よ、炉心槽3内に垂直に支持され又お
り、それらの下端のエントランスノズル2aは、炉心支
持板4および支持構造物5と組合わけて設けた連結管1
0内に差込まれ、水平方向の移そして、このような原子
炉では、入口配管を通して、原子炉容器1内に導入され
た冷却材は矢符で示すように、エントランスノズル2a
から炉心構成要素2内を分流して加熱された後、原子炉
容器内筒6を経て出口配管12から流j11シ、炉内の
発生熱を熱交換器(図示ぜず)へ伝達する。
Each core element 21 is vertically supported within the core barrel 3, and the entrance nozzle 2a at the lower end of each core is connected to a connecting pipe 1 provided in combination with the core support plate 4 and the support structure 5.
In such a reactor, the coolant introduced into the reactor vessel 1 through the inlet piping passes through the entrance nozzle 2a as shown by the arrow.
The heat generated in the reactor is transferred to a heat exchanger (not shown) through the outlet pipe 12 through the reactor vessel inner cylinder 6 and into a flow j11.

第2図は本発明の炉心構成要素の保持装置の実施例を示
すもので、炉心構成要素2内に収納した燃料ビン21の
中心部には軸方向を山通してラッチロッド22が設けら
れており、このラッチロッド下端にはラッチプレート2
3が固着されている。このラッチプレート23には、第
3図に示ずにうに、ラッチロッド22の周囲に大径の冷
却材流通孔24が複数7m透設され、またラッチプレー
ト23の周縁部には120度間隔で3個のラッチ用溝2
5が段けられている。
FIG. 2 shows an embodiment of the core component holding device of the present invention, in which a latch rod 22 is provided in the center of a fuel bottle 21 housed in the core component 2, passing through the axial direction. There is a latch plate 2 at the lower end of this latch rod.
3 is fixed. As shown in FIG. 3, this latch plate 23 is provided with a plurality of large-diameter coolant flow holes 24 of 7 m around the latch rod 22, and is spaced at 120 degree intervals on the periphery of the latch plate 23. 3 latch grooves 2
5 is stacked.

エントランスノズル2aの上部嵌合部近傍はラッチプレ
ー1・23に対応する位置に120度間隔で3個のり欠
品2bが形成されており、これらの切欠部にはそれぞれ
ばね材等からなるラッチ用部月26が配置されている。
Near the upper fitting part of the entrance nozzle 2a, three missing pieces 2b are formed at 120 degree intervals at positions corresponding to the latch plays 1 and 23, and each of these notches has a latch made of spring material or the like. Part 26 is placed.

これらのラッチ用部材26は、第4図に示t J:うに
、板状体の下端近傍に外方突出部26aが構成されてお
り、各突出部はエントランスノズル2aの切欠部2bを
貫通し、その外方に設けた連結管10のラッチ用溝10
a内に受入れられている。
As shown in FIG. 4, these latch members 26 have outward protrusions 26a formed near the lower end of the plate-like body, and each protrusion passes through the notch 2b of the entrance nozzle 2a. , the latch groove 10 of the connecting pipe 10 provided on the outside thereof.
It is accepted within a.

なお、突出部26aの外面の上下端とこれに対応Jるラ
ッチ用溝10aの内面はそれぞれテーパ状傾斜面とされ
ている1、また、符号27はラッチ用部材26の上下近
傍をエントランスノズル2aの −内面に係止するビン
を示している。
Note that the upper and lower ends of the outer surface of the protruding portion 26a and the inner surface of the corresponding latch groove 10a are each formed into a tapered inclined surface. - Shows a bottle that locks onto the inside surface.

上述のように構成した本発明の炉心構成要素の保持装置
において、原子炉の通常運転時にはラッチプレート23
は第3図に示りJ:うにラッチ溝25がラッチ用部材2
6に合致しない位置にセットされている。この場合、ラ
ッチ用部vJ26は第4図に示すように内面をラッチプ
レート23の外面で押圧され、突出部26aは連結管1
0のラップ用溝10a内に収納されている。 − この状態において、炉心構成要素2が浮上がり力「1を
受けると、ラッチ用部材26の突出部26aは、連結管
10の上側傾斜面により、半経方向内方に向う力F2を
受ける。しかしながらラッチ用部材26の半径方向の動
きを抑制りるので、地震荷重のような大きな浮上り力に
ス(1しても、炉心構成要素7の浮上りは防止される。
In the core component holding device of the present invention configured as described above, the latch plate 23 is
is shown in FIG. 3. J: The latch groove 25 is the latch member 2.
It is set in a position that does not match 6. In this case, the inner surface of the latch portion vJ26 is pressed by the outer surface of the latch plate 23, as shown in FIG.
It is housed in the wrap groove 10a of No. 0. - In this state, when the core component 2 receives a lifting force "1," the protrusion 26a of the latch member 26 receives a force F2 directed inward in the semi-longitudinal direction by the upper inclined surface of the connecting pipe 10. However, since the radial movement of the latch member 26 is suppressed, the core components 7 are prevented from floating even if a large floating force such as an earthquake load is applied.

一方、炉心構成要素の装荷時および交1@時には、ラッ
チロッド22を操作し、ラッチプレ−1〜23のラッチ
デラッチ用溝25がラッチ用部材26の位置に来るよう
にする。このとき、炉心構成要素7に押込ツノあるいは
、引抜力を作用させると、ラッチ用部材26には半径方
向力「2が作用し、ラッチプレート23のラッチ用溝2
5に押込まれる形となり、ラッチ用部材26ど連結管1
0とはかみ合いを解かれるので、炉心構成要素の装荷、
交換が可能となる。
On the other hand, when loading the core components and during the crossing 1@, the latch rod 22 is operated so that the latch delatching grooves 25 of the latch plates 1 to 23 come to the position of the latch member 26. At this time, when a pushing horn or a pulling force is applied to the core component 7, a radial force "2" acts on the latch member 26, and the latch groove of the latch plate 23
5, the latch member 26 and the connecting pipe 1
0 is disengaged, so the loading of core components,
Exchange becomes possible.

[発明の効果1 上述のJ、うに、本発明の炉心(Iは素の保持装置は従
来のハイド臼リンクホールドダウン方式では浮上がり防
止が困f、1(どなるような大きな地震力に対しても炉
心構成要素の浮上がりを防止することができ、原子炉の
安全性、信頼性が向上する。
[Effect of the invention 1] As mentioned above, the reactor core of the present invention (I is an elemental holding device has difficulty in preventing floating with the conventional Hyde link hold-down system, and 1) It also prevents core components from floating up, improving reactor safety and reliability.

また、ラッチプレートに設りる冷fJI材流通孔の開口
面積を変化させることにJ:り流m調節が可能であり、
エントランスノズルの短縮化が可能であると共に、流止
調節装口を簡素化でき、原子炉のコンパクト化が可Oし
となる。
In addition, it is possible to adjust the flow rate by changing the opening area of the cold fJI material flow hole provided in the latch plate.
It is possible to shorten the length of the entrance nozzle, and to simplify the flow stop adjustment fitting, making it possible to make the reactor more compact.

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

第1図は本発明が適用される原子炉の概要を示tSU断
面図、第2図は本発明の一実施例を示す縦断面図、第3
図は第2図の■〜■線に沿う横断面図、第4図は本発明
におけるラッチ用部材の近傍の作用を示す部分拡大縦断
面図である。 1・・・・・・・・・・・・原子炉容器2・・・・・・
・・・・・・炉心構成要素2a・・・・・・・・・エン
トランスノズル2b・・・・・・・・・切欠部 3・・・・・・・・・・・・炉心槽 4・・・・・・・・・・・・炉心支持板5・・・・・・
・・・・・・支持構造物6・・・・・・・・・・・・原
子炉容器内筒7・・・・・・・・・・・・炉心上部機構
8・・・・・・・・・・・・回転プラグ9・・・・・・
・・・・・・固定プラグ10・・・・・・・・・・・・
連結管 10a・・・・・・・・・ラッチ用溝 11・・・・・・・・・・・・入口配管21・・・・・
・・・・・・・燃料ビン22・・・・・・・・・・・・
うt+7手ロッド23・・・・・・・・・・・・ラッチ
プレート24・・・・・・・・・・・・冷却材流通孔2
5・・・・・・・・・・・・デラッチ用溝26・・・・
・・・・・・・・ラッチ用部材26 a・・・・・・・
・・突出部 27・・・・・・・・・・・・係止用ビン代理人弁理士
 則 近 憲 1j (ほか1名) 第1−図 第2図 第3図
FIG. 1 is a tSU sectional view showing an outline of a nuclear reactor to which the present invention is applied, FIG. 2 is a longitudinal sectional view showing an embodiment of the present invention, and FIG.
The figure is a cross-sectional view taken along line 1 to 2 in FIG. 2, and FIG. 4 is a partially enlarged vertical sectional view showing the action of the latch member and its vicinity in the present invention. 1・・・・・・・・・Reactor vessel 2・・・・・・
......Core component 2a...Entrance nozzle 2b...Notch 3...Core barrel 4. ......Core support plate 5...
・・・・・・Support structure 6・・・・・・・・・Reactor vessel inner cylinder 7・・・・・・・・・Core upper mechanism 8・・・・・・...Rotating plug 9...
・・・・・・Fixed plug 10・・・・・・・・・・・・
Connecting pipe 10a... Latch groove 11... Inlet pipe 21...
・・・・・・Fuel bottle 22・・・・・・・・・・・・
Ut+7 hand rod 23... Latch plate 24... Coolant flow hole 2
5......Delatch groove 26...
...... Latch member 26 a...
・Protruding part 27 ・・・・Latching bottle agent Patent attorney Noriyoshi Chika 1j (and 1 other person) Figure 1 - Figure 2 Figure 3

Claims (1)

【特許請求の範囲】[Claims] (1)炉心構成要素のエントランスノズルを連結管内に
保持する炉心構成要素の保持装置において、前記炉心構
成要素内に回転自在に配叙されるラッチロッドと、この
ラッチロッドの下端に配設され冷却材流通孔を備え、か
つ局面の数か所にデラッチ用溝を備えたラッチプレート
と、前記、エントランスノズルの局面に前記デラッチ用
溝に対応して透設される切欠部と、この切欠部に挿入さ
れ前記連結管に形成されるラッチ用溝に係合されるラッ
チ用部材とからなることを特徴とする炉心構成要素の保
持装置。
(1) In a core component holding device that holds an entrance nozzle of a core component in a connecting pipe, a latch rod is rotatably disposed within the core component, and a latch rod disposed at the lower end of the latch rod is cooled. a latch plate provided with a material flow hole and delatching grooves at several places on the surface; a notch provided transparently in the surface of the entrance nozzle corresponding to the delatching groove; A latching member that is inserted and engaged with a latching groove formed in the connecting pipe.
JP58146546A 1983-08-12 1983-08-12 Holder for core constitutional element Pending JPS6039590A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP58146546A JPS6039590A (en) 1983-08-12 1983-08-12 Holder for core constitutional element

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP58146546A JPS6039590A (en) 1983-08-12 1983-08-12 Holder for core constitutional element

Publications (1)

Publication Number Publication Date
JPS6039590A true JPS6039590A (en) 1985-03-01

Family

ID=15410098

Family Applications (1)

Application Number Title Priority Date Filing Date
JP58146546A Pending JPS6039590A (en) 1983-08-12 1983-08-12 Holder for core constitutional element

Country Status (1)

Country Link
JP (1) JPS6039590A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4616810A (en) * 1985-03-28 1986-10-14 Richardson Wayne U Liquid cooled shock absorber

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4616810A (en) * 1985-03-28 1986-10-14 Richardson Wayne U Liquid cooled shock absorber

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