JPH0160796B2 - - Google Patents

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Publication number
JPH0160796B2
JPH0160796B2 JP58080010A JP8001083A JPH0160796B2 JP H0160796 B2 JPH0160796 B2 JP H0160796B2 JP 58080010 A JP58080010 A JP 58080010A JP 8001083 A JP8001083 A JP 8001083A JP H0160796 B2 JPH0160796 B2 JP H0160796B2
Authority
JP
Japan
Prior art keywords
control rod
guide
drive shaft
tube
fuel
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
JP58080010A
Other languages
Japanese (ja)
Other versions
JPS59204793A (en
Inventor
Fumihiro Mori
Kazuo Tanimoto
Yoshinobu Takahashi
Yoshio Tokumaru
Hidenori Nakada
Shizuo Nakada
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.)
Kansai Electric Power Co Inc
Shikoku Research Institute Inc
Mitsubishi Heavy Industries Ltd
Original Assignee
Shikoku Research Institute Inc
Mitsubishi Heavy Industries Ltd
Kansai Denryoku 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 Shikoku Research Institute Inc, Mitsubishi Heavy Industries Ltd, Kansai Denryoku KK filed Critical Shikoku Research Institute Inc
Priority to JP58080010A priority Critical patent/JPS59204793A/en
Publication of JPS59204793A publication Critical patent/JPS59204793A/en
Publication of JPH0160796B2 publication Critical patent/JPH0160796B2/ja
Granted 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

  • Treatment Of Water By Oxidation Or Reduction (AREA)
  • Analysing Materials By The Use Of Radiation (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Description

【発明の詳細な説明】 本発明は加圧水型原子炉の改良に関するもので
ある。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to improvements in pressurized water nuclear reactors.

従来の加圧水型原子炉を第1図により説明する
と、1は冷却材の入口ノズル1a及び出口ノズル
1bを上側部に有する原子炉容器、2は同原子炉
容器1内に垂下支持されて炉心を支持する炉心
槽、3は燃料集合体のそれぞれが複数の燃料棒3
aと複数の制御棒案内管3bと同各燃料棒3a及
び同各制御棒案内管3bを束ねて固定する支持格
子3cとよりなり且つ同各燃料集合体のそれぞれ
が林立状に配設されて炉心を構成する複数の燃料
集合体である。なお前記原子炉容器1の上部に着
脱自在に装着され且つ複数の制御棒駆動装置が上
面に林立状に配設された上蓋、及び前記燃料集合
体3の各制御棒案内管3bに挿脱される複数の制
御棒がスパイダに房状に取付けられ且つ同各スパ
イダから上方に延びた各制御棒駆動軸が前記上蓋
の制御棒駆動装置に着脱自在に装着される複数の
制御棒組立体は図示を省略した。また5は前記炉
心を構成する各燃料集合体3の上端を押える上部
炉心板5aと同上部炉心板5a上に林立状に配設
された複数の制御棒組立体案内筒5bとを有する
上部炉心構造物、6は前記制御棒組立体の制御棒
駆動軸が個別に通る多数の中空チユーブ6aと同
各中空チユーブ6aの上端及び下端を連結する上
下の管板6b,6cとよりなり且つ前記上部炉心
構造物5の上方に配設されて冷却材の出口転向プ
レナムを形成するカランドリア構造物で、同カラ
ンドリア構造物6を上部炉心構造物5の制御棒組
立体案内筒5bの上に直接取付ける一方、制御棒
組立体の制御棒駆動軸4cをカランドリア構造物
6の中空チユーブ6a内を通して、一次冷却水の
横流れの影響を制御棒駆動軸4cに与えないよう
にしている。
To explain a conventional pressurized water reactor with reference to FIG. 1, 1 is a reactor vessel which has a coolant inlet nozzle 1a and an outlet nozzle 1b on the upper side, and 2 is a reactor vessel that is suspended and supported within the reactor vessel 1 and has a reactor core. The supporting core barrel 3 has a fuel assembly each having a plurality of fuel rods 3.
a, a plurality of control rod guide tubes 3b, and a support grid 3c for bundling and fixing each fuel rod 3a and each control rod guide tube 3b, and each of the fuel assemblies is arranged in a forest shape. These are multiple fuel assemblies that make up the core. The upper lid is detachably attached to the upper part of the reactor vessel 1, and a plurality of control rod drive devices are arranged in a forest shape on the upper surface, and the control rod guide tubes 3b of the fuel assembly 3 are inserted into and removed from the upper cover. A plurality of control rod assemblies are shown in which a plurality of control rods are attached to a spider in a cluster, and each control rod drive shaft extending upward from each spider is detachably attached to a control rod drive device of the upper cover. was omitted. Reference numeral 5 denotes an upper core having an upper core plate 5a that presses the upper end of each fuel assembly 3 constituting the core, and a plurality of control rod assembly guide tubes 5b arranged in a forest shape on the upper core plate 5a. The structure 6 consists of a large number of hollow tubes 6a through which control rod drive shafts of the control rod assembly pass individually, and upper and lower tube plates 6b and 6c connecting the upper and lower ends of each hollow tube 6a, and A calandria structure that is disposed above the core structure 5 and forms a coolant outlet diversion plenum, and the calandria structure 6 is directly attached to the control rod assembly guide tube 5b of the upper core structure 5. , the control rod drive shaft 4c of the control rod assembly is passed through the hollow tube 6a of the calandria structure 6 to prevent the control rod drive shaft 4c from being affected by the lateral flow of primary cooling water.

前記加圧型原子炉では、燃料の交換等に際し、
カランドリア構造物6を取り外すと、林立した状
態の制御棒駆動軸4cは若干傾いて、たわみが発
生する。そのためカランドリア構造物6を再び取
付けるとき、各制御棒駆動軸4cの中心とカラン
ドリア構造物6の各中空チユーブ6aの中心とが
一致せず、全ての制御棒駆動軸4cを全ての中空
チユーブ6aに同時に挿入することが困難であつ
た。また一次冷却水が上部炉心構造物5からカラ
ンドリア構造物6へ流入すると、流れの方向が各
中空チユーブ6aの間で出口ノズル1bの方向
(水平方向)へ急激に変るが、制御棒組立体案内
筒5bがカランドリア構造物6に直接取付けられ
ていると、上記横流れが制御棒組立体案内筒5b
の上部内にも発生し、同上部内に位置しているス
パイダ4bが同上部内の横流れの影響を受けて、
振動する可能性があつた。
In the pressurized reactor, when replacing fuel, etc.,
When the calandria structure 6 is removed, the control rod drive shaft 4c in the standing state is slightly tilted and deflected. Therefore, when reinstalling the calandria structure 6, the center of each control rod drive shaft 4c and the center of each hollow tube 6a of the calandria structure 6 do not match, and all control rod drive shafts 4c are connected to all hollow tubes 6a. It was difficult to insert them at the same time. Furthermore, when the primary cooling water flows from the upper core structure 5 to the calandria structure 6, the flow direction changes rapidly between each hollow tube 6a toward the outlet nozzle 1b (horizontal direction), but the control rod assembly guide If the tube 5b is directly attached to the calandria structure 6, the above-mentioned lateral flow will be caused by the control rod assembly guide tube 5b.
The spider 4b located in the upper part is affected by the lateral flow in the upper part, and
There was a possibility of vibration.

本発明は前記の問題点に対処するもので、冷却
材の入口ノズル及び出口ノズルを上側部に有する
原子炉容器、同原子炉容器内に垂下支持されて炉
心を支持する炉心槽、燃料集合体のそれぞれが複
数の燃料棒と複数の制御棒案内管と同各燃料棒及
び同各制御棒案内管を束ねて固定する支持格子と
よりなり且つ同各燃料集合体のそれぞれが林立状
に配設されて炉心を構成する複数の燃料集合体、
前記原子炉容器の上部に着脱自在に装着され且つ
複数の制御棒駆動装置が上面に林立状に配設され
た上蓋、前記燃料集合体の各制御棒案内管に挿脱
される複数の制御棒がスパイダに房状に取付けら
れ且つ同各スパイダから上方に延びた各制御棒駆
動軸が前記上蓋の制御棒駆動装置に着脱自在に装
着される複数の制御棒組立体、前記炉心を構成す
る各燃料集合体の上端を押える上部炉心板と同上
部炉心板上に林立状に配設された複数の制御棒組
立体案内筒とを有する上部炉心構造物、前記制御
棒組立体の制御棒駆動軸が個別に通る多数の中空
チユーブと同各中空チユーブの上端及び下端を連
結する上下の管板とよりなり且つ前記上部炉心構
造物の上方に配設されて冷却材の出口転向プレナ
ムを形成するカランドリア構造物、及び下方に向
つて開いた案内円錐面をもつ多数の駆動軸案内孔
を有し同各駆動軸案内孔が前記カランドリア構造
物の各中空チユーブとその直下で対向し且つ前記
カランドリア構造物の下部管板を通して前記出口
転向プレナムへ冷却材を導く案内構造物とを具え
ていることを特徴とした原子炉に係り、その目的
とする処は、ガンドリア構造物を取付けるとき
に、全ての制御棒駆動軸を全ての中空チユーブに
同時に円滑に挿入できる。また制御棒組立体のス
パイダの振動を可及的に防止できる改良された原
子炉を供する点にある。
The present invention addresses the above-mentioned problems, and consists of a reactor vessel having a coolant inlet nozzle and an outlet nozzle on the upper side, a reactor vessel that is suspended in the reactor vessel and supports the reactor core, and a fuel assembly. each of which consists of a plurality of fuel rods, a plurality of control rod guide tubes, and a support grid for bundling and fixing the fuel rods and control rod guide tubes, and each of the fuel assemblies is arranged in a forest shape. multiple fuel assemblies that make up the core,
an upper cover that is detachably attached to the upper part of the reactor vessel and has a plurality of control rod drive devices arranged in a forest on the upper surface; a plurality of control rods that are inserted into and removed from each control rod guide tube of the fuel assembly; a plurality of control rod assemblies, each of which comprises a plurality of control rod assemblies, each of which is attached to a spider in the form of a tuft, and in which each control rod drive shaft extending upward from each spider is detachably attached to a control rod drive device of the upper lid; An upper core structure having an upper core plate that presses the upper end of a fuel assembly and a plurality of control rod assembly guide tubes arranged in a forest on the upper core plate, and a control rod drive shaft of the control rod assembly. A calandria consisting of a number of hollow tubes through which the tubes individually pass, and upper and lower tube plates connecting the upper and lower ends of each hollow tube, and is disposed above the upper core structure to form a coolant outlet diversion plenum. a structure, and a plurality of drive shaft guide holes each having a guide conical surface opening downward, each drive shaft guide hole facing each hollow tube of the calandria structure directly below the calandria structure, and the calandria structure a guide structure for directing coolant through the lower tube plate of the reactor to the exit diverting plenum, the purpose of which is to The rod drive shaft can be smoothly inserted into all hollow tubes at the same time. Another object of the present invention is to provide an improved nuclear reactor that can prevent vibration of the spider of the control rod assembly as much as possible.

次に本発明の原子炉を第2図乃至第14図に示
す一実施例により説明すると、第2図の1は冷却
材の入口ノズル1a及び出口ノズル1bを上側部
に有する原子炉容器、2は同原子炉容器1内に垂
下支持されて炉心を支持する炉心槽、3は燃料集
合体のそれぞれが複数の燃料棒3aと複数の制御
棒案内管3bと同各燃料棒3a及び同各制御棒案
内管3bを束ねて固定する支持格子3cとよりな
り且つ同各燃料集合体のそれぞれが林立状に配設
されて炉心を構成する複数の燃料集合体である。
なお前記原子炉容器1の上部に着脱自在に装着さ
れ且つ複数の制御棒駆動装置が上面に林立状に配
設された上蓋は図示を省略した。また第3図の4
は前記燃料集合体3の各制御棒案内管3bに挿脱
される複数の制御棒4aがスパイダ4bに房状に
取付けられ且つ同各スパイダ4bから上方に延び
た各制御棒駆動軸4cが前記上蓋の制御棒駆動装
置に着脱自在に装着される複数の制御棒組立体、
第2図の5は前記炉心を構成する各燃料集合体3
の上端を押える上部炉心板5aと同上部炉心板5
a上に林立状に配設された複数の制御棒組立体案
内筒5bとを有する上部炉心構造物、第2,3図
の6は前記制御棒組立体4の制御棒駆動軸4cが
個別に通る多数の中空チユーブ6aと同各中空チ
ユーブ6aの上端及び下端を連結する上下の管板
6b,6cとよりなり且つ前記炉心構造物5の上
方に配設されて冷却材の出口転向プレナムを形成
するカランドリア構造物、7は下方に向つて開い
た案内円錐面をもつ多数の駆動軸案内孔7d,7
e(または7f)を有し同各駆動軸案内孔が前記
カランドリア構造物6の各中空チユーブ6aとそ
の直下で対向し且つ前記カランドリア構造物6の
下部管板6cを通して前記出口転向プレナムへ冷
却材を導く案内構造物である。なお第3図乃至第
7図に前記カランドリア構造物6の詳細を示し
た。同各図において、6dは円筒状の胴体、6e
は同胴体6dの上端部に設けたフランジ、6fは
下部管板6cに設けた多数の流路孔、6gが上記
胴体6dに設けた出口開口部、6hが案内構造物
7取付用ナツトである。また第3図及び第8図乃
至第13図に前記案内構造物7の詳細を示した。
同各図において、7aは上部流路板、7bは下部
流路板、7cが同各流路板7a,7bを連結する
格子状の仕切板、7dは前記各中空チユーブ6a
の直下で同各中空チユーブ6aに正対するように
上部流路板7aに設けた多数の駆動軸案内孔、7
eは同各駆動軸案内孔7dの直下で同各駆動軸案
内孔7dに正対するように下部流路板7bに設け
た多数の駆動軸案内孔で、これらの駆動軸案内孔
7d,7eは、下方に向つて開いた案内円錐面を
もつている。なおこれらの駆動軸案内孔7d,7
eは、下方に向いて開いた案内円錐面をもつ案内
筒7f等により連結してもよい。また7gは上部
流路板7aに設けた多数の流路孔、7hは下部流
路板7bに設けた多数の流路孔、7iは仕切板7
c及び案内筒7fに設けた流路孔、7jは上部流
路板7aに設けた位置決めピンで、同位置決めピ
ン7jはカランドリア構造物6のピン孔(第3図
の6i参照)に挿入される。また7kはカンドリ
ア構造物6のナツト6hに螺合されるボルト、7
lは下部流路板7bに設けたピン孔である。また
第3図の5cは前記制御棒組立体案内筒5bの上
端に固定したフランジ、5dは同フランジ5c上
に設けた位置決めピンで、上記ピン孔7lに係合
するようになつている。以上の説明から明らかな
ように本発明の原子炉では(第2図参照)、原子
炉容器1に組み込まれる炉心構造物が、炉心槽2
と上部炉心構造物5とカランドリア構造物6と案
内構造物7と制御棒組立体案内筒5b等とにより
構成され、炉心槽2内の下部に、燃料集合体3が
装荷されている。また同燃料集合体3の上部に
は、上部炉心構造物5が取付けられ、同上部炉心
構造物5の中には、複数の制御棒組立体案内筒5
bが配置されている。また同各制御棒組立体案内
筒5bの上には、底部に案内構造物7をボルトを
介し取付けたカランドリア構造物6が組込まれて
いる。また同カランドリア構造物6は、第5〜7
図に示す通り制御棒駆動軸4cを一次冷却水の横
流れによる流体荷重から保護するために、各中空
チユーブ6aとそれらの両端部分を支持する上部
管板6b及び下部管板6cと胴体6dとがあり、
胴体6dの上縁には、フランジ6eがある。また
下部管板6cには、案内構造物7から出た一次冷
却水がカランドリア構造物6内へ流入するように
流路孔6fが多数設けられ、胴体6dの原子炉容
器1側出口ノズル1bの対向位置には、カランド
リア側の開口部6gが設けられている。また下部
管板6cには、案内構造物取付ボルト用ナツト6
hが複数個所に取付けられている。また制御棒駆
動軸4cと同数の中空チユーブ6aは、内径が制
御棒駆動軸4cの外径よりも大きく、両端が上部
管板6b及び下部管板6cに溶接またはねじ込み
により固定されている。また案内構造物7は第8
〜12図に示す通り上部流路板7aと下部流路板
7bと格子状の仕切板7cと案内筒7fと位置決
めピン7j等とにより構成されている。上部流路
板7aには、第10,11図に示すように流路孔
7gが設けられ、制御棒駆動軸4cが通過する部
分には、駆動軸案内孔7d及び駆動軸案内管取付
け用穴7mが設けられている。また取付けボルト
7kは、案内構造物7をカランドリア構造物6に
固定するためのもの、位置ピン7jは、中空チユ
ーブ6aの中心と駆動軸案内孔7dの中心とを一
致させるためである。また下部流路板7bにも流
路穴7hが設けられている。また上部流路板7a
及び下部流路板7bに設けられた駆動軸案内孔7
d,7eは、制御棒駆動軸の先端を案内し易くす
るように、第13図に示すように下方に向つて開
いた案内円錐面をもつている。同駆動軸案内孔7
eの平均内径D1は、駆動軸案内孔7dの平均内
径D2よりも大きくなつている。このため制御棒
駆動軸4cの先端が一旦下部の案内孔7eに入つ
て案内されれば、駆動軸4cが上方へ移動するに
つれその先端が案内孔の中心線に接近して、駆動
軸4cの先端が上部の案内孔7dへ円滑に入るよ
うになつている。
Next, the nuclear reactor of the present invention will be described with reference to an embodiment shown in FIGS. 2 to 14. 1 in FIG. 3 is a reactor core tank that is suspended in the reactor vessel 1 and supports the reactor core, and 3 is a fuel assembly that includes a plurality of fuel rods 3a, a plurality of control rod guide tubes 3b, each fuel rod 3a, and each control rod. It consists of a support grid 3c that bundles and fixes rod guide tubes 3b, and each of the fuel assemblies is arranged in a forest shape to constitute a reactor core.
Note that the upper cover, which is detachably attached to the upper part of the reactor vessel 1 and has a plurality of control rod drive devices arranged in a forest on the upper surface, is not shown. Also, 4 in Figure 3
A plurality of control rods 4a to be inserted into and removed from each control rod guide tube 3b of the fuel assembly 3 are attached to a spider 4b in a cluster, and each control rod drive shaft 4c extending upward from each spider 4b is connected to the control rod guide tube 3b of the fuel assembly 3. a plurality of control rod assemblies that are removably attached to the control rod drive device in the top lid;
5 in FIG. 2 denotes each fuel assembly 3 constituting the core.
The upper core plate 5a that presses the upper end of the upper core plate 5a and the upper core plate 5
6 in FIGS. 2 and 3 is an upper core structure having a plurality of control rod assembly guide tubes 5b arranged in a forest shape on the upper core structure. It consists of a large number of hollow tubes 6a that pass through it, and upper and lower tube plates 6b and 6c that connect the upper and lower ends of each hollow tube 6a, and is arranged above the core structure 5 to form a coolant outlet diversion plenum. The calandria structure 7 has a large number of drive shaft guide holes 7d, 7 each having a guide conical surface that opens downward.
e (or 7f), each drive shaft guide hole is opposite to each hollow tube 6a of the calandria structure 6 directly below, and the coolant is passed through the lower tube plate 6c of the calandria structure 6 to the outlet diverting plenum. It is a guide structure that guides people. The details of the calandria structure 6 are shown in FIGS. 3 to 7. In each figure, 6d is a cylindrical body, 6e
6f is a flange provided at the upper end of the body 6d, 6f is a number of passage holes provided in the lower tube plate 6c, 6g is an outlet opening provided in the body 6d, and 6h is a nut for mounting the guide structure 7. . Further, details of the guide structure 7 are shown in FIG. 3 and FIGS. 8 to 13.
In each figure, 7a is an upper passage plate, 7b is a lower passage plate, 7c is a lattice-like partition plate connecting the passage plates 7a and 7b, and 7d is the hollow tube 6a.
A large number of drive shaft guide holes, 7, are provided in the upper channel plate 7a directly below the hollow tubes 6a.
Numerous drive shaft guide holes e are provided in the lower channel plate 7b so as to be directly below and directly opposite each of the drive shaft guide holes 7d, and these drive shaft guide holes 7d and 7e are , has a guide conical surface that opens downward. Note that these drive shaft guide holes 7d, 7
e may be connected by a guide tube 7f having a conical guide surface facing downward. Further, 7g is a large number of channel holes provided in the upper channel plate 7a, 7h is a large number of channel holes provided in the lower channel plate 7b, and 7i is a partition plate 7.
7j is a positioning pin provided in the upper flow path plate 7a, and the positioning pin 7j is inserted into the pin hole (see 6i in FIG. 3) of the calandria structure 6. . Further, 7k is a bolt screwed into the nut 6h of the candoria structure 6;
1 is a pin hole provided in the lower channel plate 7b. Further, 5c in FIG. 3 is a flange fixed to the upper end of the control rod assembly guide cylinder 5b, and 5d is a positioning pin provided on the flange 5c, which is adapted to engage with the pin hole 7l. As is clear from the above description, in the nuclear reactor of the present invention (see FIG. 2), the core structure incorporated in the reactor vessel 1 is
It is composed of an upper core structure 5, a calandria structure 6, a guide structure 7, a control rod assembly guide tube 5b, etc., and a fuel assembly 3 is loaded in the lower part of the core barrel 2. Further, an upper core structure 5 is attached to the upper part of the fuel assembly 3, and a plurality of control rod assembly guide tubes 5 are installed in the upper core structure 5.
b is placed. Further, a calandria structure 6 having a guide structure 7 attached to the bottom thereof via a bolt is installed on each control rod assembly guide tube 5b. In addition, the calandria structure 6 is the fifth to seventh
As shown in the figure, in order to protect the control rod drive shaft 4c from the fluid load due to the lateral flow of primary cooling water, an upper tube plate 6b and a lower tube plate 6c supporting each hollow tube 6a and both ends thereof, and a body 6d are provided. can be,
There is a flange 6e on the upper edge of the body 6d. Further, the lower tube plate 6c is provided with a large number of flow passage holes 6f so that the primary cooling water discharged from the guide structure 7 flows into the calandria structure 6, and the outlet nozzle 1b on the reactor vessel 1 side of the fuselage 6d An opening 6g on the calandria side is provided at the opposing position. Further, nuts 6 for guide structure mounting bolts are provided on the lower tube plate 6c.
h is attached at multiple locations. Further, the same number of hollow tubes 6a as the control rod drive shafts 4c have inner diameters larger than the outer diameters of the control rod drive shafts 4c, and both ends are fixed to the upper tube plate 6b and the lower tube plate 6c by welding or screwing. Further, the guide structure 7 is the eighth
As shown in Figures 1 to 12, it is composed of an upper passage plate 7a, a lower passage plate 7b, a lattice-shaped partition plate 7c, a guide tube 7f, a positioning pin 7j, and the like. The upper channel plate 7a is provided with a channel hole 7g as shown in FIGS. 10 and 11, and the portion through which the control rod drive shaft 4c passes is provided with a drive shaft guide hole 7d and a drive shaft guide tube mounting hole. 7m is provided. The mounting bolt 7k is for fixing the guide structure 7 to the calandria structure 6, and the positioning pin 7j is for aligning the center of the hollow tube 6a with the center of the drive shaft guide hole 7d. Further, the lower flow passage plate 7b is also provided with flow passage holes 7h. Also, the upper channel plate 7a
and a drive shaft guide hole 7 provided in the lower channel plate 7b.
d and 7e have guide conical surfaces that open downward, as shown in FIG. 13, to facilitate guiding the tip of the control rod drive shaft. Drive shaft guide hole 7
The average inner diameter D 1 of e is larger than the average inner diameter D 2 of the drive shaft guide hole 7d. Therefore, once the tip of the control rod drive shaft 4c enters the lower guide hole 7e and is guided, as the drive shaft 4c moves upward, the tip approaches the center line of the guide hole, and the tip of the drive shaft 4c moves upward. The tip is designed to smoothly enter the upper guide hole 7d.

次に前記原子炉の作用を説明する。制御棒組立
体案内筒5b内を上昇した一次冷却水は、案内構
造物7内に一旦集められ、次いでカランドリア構
造物6へ流入する。このとき、カランドリア構造
物6内では、流れの方向が中空チユーブ6aの間
で原子炉容器1の出口ノズル1bの方向(水平方
向)へ急激するが、カランドリア構造物6と制御
棒組立体案内筒5bとの間に、整流作用をもつ案
内構造物7があり、カランドリア構造物6内の横
流れの影響が制御棒組立体案内筒5bの上部内に
伝わらなくて、同上部内に位置しているスパイダ
4bが振動しない。また制御棒組立体案内筒5b
が横流れの影響を受けないので、位置決めピン5
dに負荷される横荷重が軽減される。
Next, the operation of the nuclear reactor will be explained. The primary cooling water that has risen within the control rod assembly guide tube 5b is once collected within the guide structure 7, and then flows into the calandria structure 6. At this time, within the calandria structure 6, the direction of flow suddenly increases in the direction of the outlet nozzle 1b of the reactor vessel 1 (horizontal direction) between the hollow tube 6a, but 5b, there is a guide structure 7 with a rectifying effect, which prevents the influence of the cross flow in the calandria structure 6 from being transmitted to the upper part of the control rod assembly guide tube 5b, and prevents the spider located in the upper part of the control rod assembly guide tube 5b 4b does not vibrate. Also, the control rod assembly guide tube 5b
is not affected by cross flow, so positioning pin 5
The lateral load applied to d is reduced.

また燃料交換時等には、原子炉容器1の上蓋を
取外し、次いで第15図に示すように制御棒組立
体4上部炉心構造物5カランドリア構造物6案内
構造物7等をリフテイングリグ8によりキヤビテ
イ9内の上部炉心構造物保管台10上に載置し、
次いで第16図に示すようにカランドリア構造物
6及び案内構造物7をリフテイングリグ8により
取外し、次いで第17図に示すように制御棒組立
体4を取外す。第18図は制御棒組立体4が完全
に取外された状態を示している。また燃料の交換
等が終つたら、第19図に示すように制御棒組立
体4を挿入して、林立させる。このとき、各制御
棒組立体4の制御棒駆動軸4cは、上端側が支持
されておらず、若干傾いて、たわむ。次いで第2
0図に示すようにカランドリア構造物6及び案内
構造物7がリフテイングリグ8により上部炉心構
造物5の上方へ移送され、次いで第21図に示す
ようにリフテイングリグ8の外側部分が下降し
て、その下端が上部炉心構造物5のフランジ上に
位置決め固定され、次いで第22図に示すように
リフテイングリグ8の内側部分が下降するが、こ
のとき、案内構造物7の駆動軸案内孔7e,7d
(下方に向つて開いた案内円錐面をもつ案内孔)
が各制御棒駆動軸4cをカランドリア構造物6の
各中空チユーブ6aの中心に近づけるように案内
して、各制御棒駆動軸4cの先端をカランドリア
構造物6の各中空チユーブ6aへ誘導する。第2
3図は、案内構造物7のピン孔7lに制御棒組立
体5側の位置決めピン5dが係合して、組立を完
了した状態を示している。
When exchanging fuel, etc., the upper cover of the reactor vessel 1 is removed, and then the control rod assembly 4 upper core structure 5 calandria structure 6 guide structure 7 etc. are removed using a lifting rig 8 as shown in FIG. Placed on the upper core structure storage stand 10 in the cavity 9,
Next, as shown in FIG. 16, the calandria structure 6 and the guide structure 7 are removed by the lifting rig 8, and then the control rod assembly 4 is removed as shown in FIG. FIG. 18 shows the control rod assembly 4 completely removed. After the fuel exchange is completed, the control rod assembly 4 is inserted and stood up as shown in FIG. 19. At this time, the upper end side of the control rod drive shaft 4c of each control rod assembly 4 is not supported, and the control rod drive shaft 4c is slightly tilted and bent. Then the second
As shown in Figure 21, the calandria structure 6 and guide structure 7 are transferred above the upper core structure 5 by the lifting rig 8, and then the outer part of the lifting rig 8 is lowered as shown in Figure 21. Then, the lower end of the lifting rig is positioned and fixed on the flange of the upper core structure 5, and then the inner part of the lifting rig 8 is lowered as shown in FIG. 7e, 7d
(Guide hole with a guide conical surface that opens downward)
guides each control rod drive shaft 4c close to the center of each hollow tube 6a of the calandria structure 6, and guides the tip of each control rod drive shaft 4c to each hollow tube 6a of the calandria structure 6. Second
FIG. 3 shows a state in which the positioning pin 5d on the control rod assembly 5 side is engaged with the pin hole 7l of the guide structure 7, and the assembly is completed.

本発明の原子炉は前記のように構成されてお
り、カランドリア構造物6及び案内構造物7が林
立する各制御棒駆動軸4cに向つて下降すると
き、案内構造物7の駆動軸案内孔7e,7d(下
方に向つて開いた案内円錐面をもつ案内孔)が各
制御棒駆動軸4cをカランドリア構造物6の各中
空チユーブ6aの中心に近づけるように案内し
て、各制御棒駆動軸4cの先端をカランドリア構
造物6の各中空チユーブ6aへ誘導するので、カ
ランドリア構造物7を取付けるとき、全ての制御
棒駆動軸4cを全ての中空チユーブ6aへ同時
に、円滑に挿入できる効果がある。また一次冷却
水がカランドリア構造物6へ流入するとき、カラ
ンドリア構造物6内では、流れの方向が中空チユ
ーブ6aの間で原子炉容器1の出口ノズル1bの
方向(水平方向)へ急激するが、カランドリア構
造物6と制御棒組立体案内筒5bとの間に、整流
作用をもつ案内構造物7があり、カランドリア構
造物6内の横流れの影響が制御棒組立体案内筒5
bの上部内に伝わらなくて、同上部内に位置して
いるスパイダ4bが振動しない。また制御棒組立
体案内筒5bが横流れの影響を受けないので、位
置決めピン5dに負荷される横荷重を軽減できる
効果がある。
The nuclear reactor of the present invention is configured as described above, and when the calandria structure 6 and the guide structure 7 descend toward each of the control rod drive shafts 4c, the drive shaft guide holes 7e of the guide structure 7 , 7d (guide holes with downwardly open guide conical surfaces) guide each control rod drive shaft 4c so as to approach the center of each hollow tube 6a of the calandria structure 6, and each control rod drive shaft 4c Since the tips of the rods are guided to each hollow tube 6a of the calandria structure 6, when installing the calandria structure 7, all the control rod drive shafts 4c can be smoothly inserted into all the hollow tubes 6a at the same time. Furthermore, when the primary cooling water flows into the calandria structure 6, the flow direction suddenly changes between the hollow tubes 6a toward the outlet nozzle 1b of the reactor vessel 1 (horizontal direction). There is a guide structure 7 with a rectifying effect between the calandria structure 6 and the control rod assembly guide tube 5b, so that the influence of the lateral flow within the calandria structure 6 is transferred to the control rod assembly guide tube 5b.
The vibration is not transmitted to the upper part of the spider 4b, and the spider 4b located in the upper part does not vibrate. Furthermore, since the control rod assembly guide tube 5b is not affected by lateral flow, there is an effect that the lateral load applied to the positioning pin 5d can be reduced.

以上本発明を実施例について説明したが、勿論
本発明はこのような実施例にだけ局限されるもの
ではなく、本発明の精神を逸脱しない範囲内で
種々の設計の改変を施しうるものである。
Although the present invention has been described above with reference to embodiments, it goes without saying that the present invention is not limited to such embodiments, and that various design modifications can be made without departing from the spirit of the present invention. .

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

第1図は従来の原子炉を示す縦断側面図、第2
図は本発明に係る原子炉の一実施例を示す縦断側
面図、第3図はその要部を示す一部切断斜視図、
第4図はカランドリア構造物の縦断側面図、第5
図は第4図V−V線に沿う横断平面図、第6図は
第5図矢印部分の拡大平面図、第7図は第4図
矢印部分の拡大縦断側面図、第8図は案内構造
物の一部切断平面図、第9図はその縦断側面図、
第10図は第9図矢印X部分の拡大縦断側面図、
第11図は第10図矢視XI−XI線に沿う平面図、
第12図は第10図矢視XII−XII線に沿う横断平面
図、第13図は第14図矢印部分の拡大縦断
側面図、第14図は制御棒組立体の側面図、第1
5図乃至第23図は作用説明図である。 1……原子炉容器、1a……入口ノズル、1b
……出口ノズル、2……炉心槽、3……燃料集合
体、3a……燃料棒、3b……制御棒案内管、4
……制御棒組立体、4a……制御棒、4b……ス
パイダ、4c……制御棒駆動軸、5……上部炉心
構造物、5a……上部炉心板、5b……制御棒組
立体案内筒、6……カランドリア構造物、6a…
…中空チユーブ、6a……上部管板、6b……下
部管板、7……案内構造物、7d,7eまたは7
f……駆動軸案内孔。
Figure 1 is a longitudinal side view of a conventional nuclear reactor;
The figure is a vertical side view showing an embodiment of the nuclear reactor according to the present invention, and FIG. 3 is a partially cutaway perspective view showing the main parts thereof.
Figure 4 is a longitudinal side view of the calandria structure, Figure 5
The figure is a cross-sectional plan view along the line V-V in Figure 4, Figure 6 is an enlarged plan view of the arrowed part in Figure 5, Figure 7 is an enlarged vertical sectional side view of the arrowed part in Figure 4, and Figure 8 is the guide structure. A partially cutaway plan view of the object, FIG. 9 is a longitudinal side view thereof,
Fig. 10 is an enlarged vertical sectional side view of the arrow X portion in Fig. 9;
Figure 11 is a plan view taken along the arrow XI-XI line in Figure 10;
12 is a cross-sectional plan view taken along the arrow XII-XII line in FIG.
5 to 23 are action explanatory diagrams. 1... Reactor vessel, 1a... Inlet nozzle, 1b
... Outlet nozzle, 2 ... Core barrel, 3 ... Fuel assembly, 3a ... Fuel rod, 3b ... Control rod guide tube, 4
...Control rod assembly, 4a...Control rod, 4b...Spider, 4c...Control rod drive shaft, 5...Upper core structure, 5a...Upper core plate, 5b...Control rod assembly guide tube , 6... Calandria structure, 6a...
...Hollow tube, 6a... Upper tube sheet, 6b... Lower tube sheet, 7... Guide structure, 7d, 7e or 7
f...Drive shaft guide hole.

Claims (1)

【特許請求の範囲】[Claims] 1 冷却材の入口ノズル及び出口ノズルを上側部
に有する原子炉容器、同原子炉容器内に垂下支持
されて炉心を支持する炉心槽、燃料集合体のそれ
ぞれが複数の燃料棒と複数の制御棒案内管と同各
燃料棒及び同各制御棒案内管を束ねて固定する支
持格子とよりなり且つ同各燃料集合体のそれぞれ
が林立状に配設されて炉心を構成する複数の燃料
集合体、前記原子炉容器の上部に着脱自在に装着
され且つ複数の制御棒駆動装置が上面に林立状に
配設された上蓋、前記燃料集合体の各制御棒案内
管に挿脱される複数の制御棒がスパイダに房状に
取付けられ且つ同各スパイダから上方に延びた各
制御棒駆動軸が前記上蓋の制御棒駆動装置に着脱
自在に装着される複数の制御棒組立体、前記炉心
を構成する各燃料集合体の上端を押える上部炉心
板と同上部炉心板上に林立状に配設された複数の
制御棒組立体案内筒とを有する上部炉心構造物、
前記制御棒組立体の制御棒駆動軸が個別に通る多
数の中空チユーブと同各中空チユーブの上端及び
下端を連結する上下の管板とよりなり且つ前記上
部炉心構造物の上方に配設されて冷却材の出口転
向プレナムを形成するカランドリア構造物、及び
下方に向つて開いた案内円錐面をもつ多数の駆動
軸案内孔を有し同各駆動軸案内孔が前記カランド
リア構造物の各中空チユーブとその直下で対向し
且つ前記カランドリア構造物の下部管板を通して
前記出口転向プレナムへ冷却材を導く案内構造物
とを具えていることを特徴とした原子炉。
1. A reactor vessel having coolant inlet and outlet nozzles on the upper side, a core tank that is suspended in the reactor vessel and supports the reactor core, and a fuel assembly each having a plurality of fuel rods and a plurality of control rods. a plurality of fuel assemblies comprising a guide tube and a support grid for bundling and fixing the fuel rods and the control rod guide tubes, and each of the fuel assemblies is arranged in a forest shape to constitute a reactor core; an upper cover that is detachably attached to the upper part of the reactor vessel and has a plurality of control rod drive devices arranged in a forest on the upper surface; a plurality of control rods that are inserted into and removed from each control rod guide tube of the fuel assembly; a plurality of control rod assemblies, each of which comprises a plurality of control rod assemblies, each of which is attached to a spider in the form of a tuft, and in which each control rod drive shaft extending upward from each spider is detachably attached to a control rod drive device of the upper lid; an upper core structure having an upper core plate that presses the upper end of a fuel assembly; and a plurality of control rod assembly guide tubes arranged in a forest on the upper core plate;
The control rod assembly includes a plurality of hollow tubes through which the control rod drive shafts of the control rod assembly pass individually, and upper and lower tube plates connecting the upper and lower ends of each hollow tube, and is disposed above the upper core structure. a calandria structure forming a coolant outlet diverting plenum, and a plurality of drive shaft guide holes having downwardly open guide conical surfaces, each drive shaft guide hole being connected to each hollow tube of the calandria structure. a guide structure directly below and opposing the guide structure for directing coolant to the outlet diverting plenum through the lower tube plate of the calandria structure.
JP58080010A 1983-05-10 1983-05-10 Reactor Granted JPS59204793A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP58080010A JPS59204793A (en) 1983-05-10 1983-05-10 Reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP58080010A JPS59204793A (en) 1983-05-10 1983-05-10 Reactor

Publications (2)

Publication Number Publication Date
JPS59204793A JPS59204793A (en) 1984-11-20
JPH0160796B2 true JPH0160796B2 (en) 1989-12-25

Family

ID=13706350

Family Applications (1)

Application Number Title Priority Date Filing Date
JP58080010A Granted JPS59204793A (en) 1983-05-10 1983-05-10 Reactor

Country Status (1)

Country Link
JP (1) JPS59204793A (en)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4759904A (en) * 1986-04-04 1988-07-26 Westinghouse Electric Corp. Pressurized water reactor having improved calandria assembly

Also Published As

Publication number Publication date
JPS59204793A (en) 1984-11-20

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