JPH0886895A - Fuel assembly for nuclear reactor - Google Patents

Fuel assembly for nuclear reactor

Info

Publication number
JPH0886895A
JPH0886895A JP6221963A JP22196394A JPH0886895A JP H0886895 A JPH0886895 A JP H0886895A JP 6221963 A JP6221963 A JP 6221963A JP 22196394 A JP22196394 A JP 22196394A JP H0886895 A JPH0886895 A JP H0886895A
Authority
JP
Japan
Prior art keywords
adapter plate
fuel assembly
control rod
rod guide
lower nozzle
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Withdrawn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
JP6221963A
Other languages
Japanese (ja)
Inventor
Yoshiharu Kamiwaki
好春 上脇
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.)
Mitsubishi Heavy Industries Ltd
Original Assignee
Mitsubishi Heavy Industries Ltd
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 Mitsubishi Heavy Industries Ltd filed Critical Mitsubishi Heavy Industries Ltd
Priority to JP6221963A priority Critical patent/JPH0886895A/en
Publication of JPH0886895A publication Critical patent/JPH0886895A/en
Withdrawn legal-status Critical Current

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

(57)【要約】 【目的】 原子炉炉心内に装荷したときに、隣接した燃
料集合体の間に異物が侵入して核燃料棒に接触し、これ
を損傷することを防止する。 【構成】 原子炉用燃料集合体は、上部ノズル、下部ノ
ズル、複数の制御棒案内管、複数の支持格子及び複数の
核燃料棒からなる。その下部ノズルは、冷却材流路孔2
1が分布して形成されたアダプタ板23と、脚とから構
成され、脚のない辺縁部の下面に棚段25が形成されて
いる。棚段25は下方に棚段状空間を形成し、隣接核燃
料集合体のアダプタ板のものと協働して捕獲空間Sを画
成する。
(57) [Summary] [Objective] When loaded in the reactor core, foreign matter is prevented from invading between adjacent fuel assemblies and coming into contact with the nuclear fuel rods and damaging them. [Structure] A fuel assembly for a nuclear reactor comprises an upper nozzle, a lower nozzle, a plurality of control rod guide tubes, a plurality of support grids, and a plurality of nuclear fuel rods. The lower nozzle has a coolant flow passage hole 2
1 is distributed and formed on the adapter plate 23 and legs, and a shelf 25 is formed on the lower surface of the edge portion without legs. The tray 25 forms a tray-like space below, and cooperates with that of the adapter plate of the adjacent nuclear fuel assembly to define the trapping space S.

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、原子炉用燃料集合体に
関し、特に加圧水型原子炉の燃料集合体の構造に関す
る。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a fuel assembly for a nuclear reactor, and more particularly to a structure of a fuel assembly for a pressurized water reactor.

【0002】[0002]

【従来の技術】現在、加圧水型原子炉で一般的に使用さ
れている燃料集合体は、外筒すなわちキャンのない構造
のもので、主として、上部ノズル、下部ノズル、これら
の両ノズルを連結する平行な複数の制御棒案内管、これ
に取着される支持格子及びこの支持格子の複数の開口内
にそれぞれ挿通支持された複数の核燃料棒からなってい
る。このような燃料集合体は、原子炉容器内に規則的に
並べて用いられるが、その平面投影形状は、ほぼ正方形
をなしている。図5に、下部ノズル1の斜視図が示され
ている。下部ノズル1は、平板状のアダプタ板3と、そ
の下面四隅に突設された4本の脚5とからなり、脚5が
下部炉心板に接して置かれる。アダプタ板3には、多数
の冷却材流路孔7を有し、原子炉容器内を上方へ向かっ
て流れる冷却材を通す。アダプタ板3は、又、対称的に
配置された制御棒案内管取付孔9を有し、構造部材とし
ても機能する制御棒案内管の端部を受け入れ、連結され
る。アダプタ板3の辺縁部は、図6に示すような形状を
しており、上下に面取り3a、3Bが施されている。炉
心に装荷されたとき、図6において矢印Fに示すように
冷却材が流れ、隣の燃料集合体の下部ノズルのアダプタ
板(2点鎖線で示す。)との間に隙間Cを形成する。
2. Description of the Related Art At present, a fuel assembly generally used in a pressurized water nuclear reactor has a structure without an outer cylinder, that is, a can, and is mainly composed of an upper nozzle, a lower nozzle, and both nozzles. It is composed of a plurality of parallel control rod guide tubes, a support grid attached to the control rod guide tubes, and a plurality of nuclear fuel rods inserted and supported in a plurality of openings of the support grid. Such fuel assemblies are regularly arranged in the reactor vessel and used, but the plane projection shape thereof is almost square. FIG. 5 shows a perspective view of the lower nozzle 1. The lower nozzle 1 is composed of a flat adapter plate 3 and four legs 5 protruding from the four corners of the lower surface thereof, and the legs 5 are placed in contact with the lower core plate. The adapter plate 3 has a large number of coolant passage holes 7 through which the coolant flowing upward in the reactor vessel is passed. The adapter plate 3 also has symmetrically arranged control rod guide tube mounting holes 9 for receiving and connecting the ends of the control rod guide tube which also function as structural members. The edge portion of the adapter plate 3 has a shape as shown in FIG. 6, and is chamfered 3a and 3B on the top and bottom. When loaded in the core, the coolant flows as shown by the arrow F in FIG. 6, and forms a gap C between the lower nozzle of the adjacent fuel assembly and the adapter plate (shown by the chain double-dashed line).

【0003】[0003]

【発明が解決しようとする課題】以上のような構造の燃
料集合体を原子炉容器内に装荷すると、図6に示すよう
な隙間Cは、必然的なものとなる。燃料集合体や原子炉
容器は、高精度即ち厳しい製作公差で製作されるのであ
るが、避けられない誤差はあり、隙間Cの大きさは分散
することとなる。更に、下面の面取り3aと隣接のアダ
プタ板の下面面取りが協働して漏斗状断面流路を形成し
ている。したがって、隙間Cが大きいと、冷却材流に伴
流する異物が、隙間Cを通って隣接燃料集合体間に侵入
し、燃料棒に接触して損傷を生ずるおそれがある。した
がって、本発明の目的は、隣接した燃料集合体の下部ノ
ズルの間を異物が貫流しないような構造の原子炉用燃料
集合体を提供することにある。
When the fuel assembly having the above structure is loaded in the reactor vessel, the gap C as shown in FIG. 6 becomes inevitable. Although the fuel assembly and the reactor vessel are manufactured with high precision, that is, with strict manufacturing tolerances, there are unavoidable errors and the size of the gap C is dispersed. Further, the chamfer 3a on the lower surface and the chamfer on the lower surface of the adjacent adapter plate cooperate to form a funnel-shaped cross-section flow path. Therefore, if the gap C is large, foreign substances accompanying the coolant flow may penetrate between the adjacent fuel assemblies through the gap C and come into contact with the fuel rods to cause damage. Therefore, an object of the present invention is to provide a fuel assembly for a nuclear reactor having a structure in which foreign matter does not flow between the lower nozzles of adjacent fuel assemblies.

【0004】[0004]

【課題を解決するための手段】このような目的の下に、
本発明によれば、それぞれ冷却材流路孔が多数削成され
ると共に離れて対向した上部ノズル及び下部ノズルと、
これら両ノズルの間に互いに平行にのびた複数の制御棒
案内管と、この制御棒案内管を開口に受け入れこれに交
差して取り付けられた支持格子と、この支持格子の開口
にそれぞれ挿通され前記制御棒案内管に対して平行にの
びた複数の核燃料棒とから構成された原子炉用燃料集合
体において、矩形のアダプタ板とその下面四隅に突出し
て形成された脚とから構成された下部ノズルのアダプタ
板辺縁部下面に棚段状空所が形成されている。この場
合、棚段状空所の形状としては、断面が台形状としても
よいし、台形の角を丸めたものや4分の1円のようにし
てもよい。
[Means for Solving the Problems] Under such a purpose,
According to the present invention, an upper nozzle and a lower nozzle facing each other with a large number of coolant passage holes each being cut away,
A plurality of control rod guide tubes extending in parallel to each other between the two nozzles, a support grid which receives the control rod guide tubes in an opening and is attached to intersect with the control rod guide tube, and the control grid inserted through the openings of the support grid. In a fuel assembly for a nuclear reactor composed of a plurality of nuclear fuel rods extending in parallel to a rod guide tube, an adapter for a lower nozzle composed of a rectangular adapter plate and legs protruding from four corners of the lower surface of the adapter plate. A shelf-like void is formed on the lower surface of the board edge. In this case, the shape of the shelf-like void may be a trapezoidal cross section, a trapezoid with rounded corners, or a quarter circle.

【0005】[0005]

【作用】前記したような構成の原子炉用燃料集合体を装
荷したとき、隣接した2つの燃料集合体の下部ノズル
は、両者の間の隙間の入口側に、大略台形状又はこれに
類似の形状の捕獲空間を画成する。この捕獲空間は、冷
却材流が衝突する衝接天面を有し、冷却材流に伴流した
異物は、その衝接天面に当たって捕獲される。更に、捕
獲空間と隙間の間で冷却材流の流路断面積が急減し隙間
を流れる冷却材量も少なくなり、異物を吸引する力も大
巾に減少する。
When the fuel assembly for a nuclear reactor having the above-mentioned structure is loaded, the lower nozzles of two adjacent fuel assemblies have a substantially trapezoidal shape or a similar shape at the inlet side of the gap between them. Define a shape capture space. This capture space has an impact ceiling surface with which the coolant flow collides, and the foreign matter that accompanied the coolant stream hits the impact ceiling surface and is captured. Further, the cross-sectional area of the flow path of the coolant flow is sharply reduced between the trapping space and the gap, the amount of the coolant flowing through the gap is reduced, and the force for sucking the foreign matter is greatly reduced.

【0006】[0006]

【実施例】以下、添付の図面を参照して本発明の実施例
を説明する。図1において、燃料集合体10は、上部ノ
ズル11、下部ノズル13、制御棒案内管15、9個の
支持格子17、及び複数の核燃料棒19からなってい
る。勿論支持格子17の数は、燃料集合体10の大きさ
によって適宜増減されるものであり、隣接する支持格子
17間の制御棒案内管15や核燃料棒19は、一部切除
して短縮化されて図示されている。図から判るように、
制御棒案内管15の両端は、核燃料棒19よりも上方及
び下方へ延出しており、上部ノズル11及び下部ノズル
13にそれぞれ連結固定されている。
Embodiments of the present invention will be described below with reference to the accompanying drawings. In FIG. 1, the fuel assembly 10 includes an upper nozzle 11, a lower nozzle 13, a control rod guide tube 15, nine support grids 17, and a plurality of nuclear fuel rods 19. Of course, the number of the support grids 17 is appropriately increased or decreased according to the size of the fuel assembly 10, and the control rod guide tubes 15 and the nuclear fuel rods 19 between the adjacent support grids 17 are partially cut and shortened. Is illustrated. As you can see from the figure,
Both ends of the control rod guide tube 15 extend above and below the nuclear fuel rod 19, and are connected and fixed to the upper nozzle 11 and the lower nozzle 13, respectively.

【0007】下部ノズル13の形状は、大略図5のもの
と同じであるが、アダプタ板の辺縁部の形状が図2に示
されている。図2において、下部ノズル13は、図5の
ように分布して形成された冷却材流路孔21をもつアダ
プタ板23を有し、辺縁部下面に棚段25が形成され、
この棚段25の下方に棚段状空間が画成される。辺縁部
上面には、従来のものと同ような45度の面取り27が
施されている。以上のような下部ノズル13をもつ燃料
集合体10を原子炉容器内に装荷すると、下部ノズル1
3のアダプタ板23と隣の燃料集合体のアダプタ板2
3’(2点鎖線で示す。)との間に隙間Cが生じ、その
入口側に台形断面の捕獲空間Sが画成される。そして、
主流がアダプタ板23の冷却材流路孔21を流れる冷却
材流下の一部は、捕獲空間Sに流入し、その天面に衝突
する。その際、伴流してきた異物は、台形断面の捕獲空
間Sの天面に衝突して捕獲される。捕獲空間S内では、
スタグナントが生じ、一部の冷却材は、隙間Cを貫流す
る。燃料集合体10の本来機能及びその周囲を流れる冷
却材の作用は、当業者にとって自明なので説明を省略す
る。
The shape of the lower nozzle 13 is roughly the same as that of FIG. 5, but the shape of the peripheral portion of the adapter plate is shown in FIG. In FIG. 2, the lower nozzle 13 has an adapter plate 23 having the coolant flow passage holes 21 formed in a distributed manner as shown in FIG. 5, and a shelf 25 is formed on the lower surface of the edge portion.
A shelf-like space is defined below the shelf 25. The upper surface of the peripheral portion is chamfered at 45 degrees similar to the conventional one. When the fuel assembly 10 having the lower nozzle 13 as described above is loaded into the reactor vessel, the lower nozzle 1
Adapter plate 23 of 3 and the adapter plate 2 of the adjacent fuel assembly
3 '(shown by a chain double-dashed line) creates a gap C, and a trapping space S having a trapezoidal cross section is defined on the inlet side thereof. And
A part of the downward flow of the coolant flowing through the coolant passage hole 21 of the adapter plate 23 flows into the capture space S and collides with the top surface thereof. At that time, the foreign matter which has waked up collides with the top surface of the trapping space S having a trapezoidal cross section and is captured. In the capture space S,
Stagnant occurs and some of the coolant flows through the gap C. Since the original function of the fuel assembly 10 and the action of the coolant flowing around the fuel assembly 10 are obvious to those skilled in the art, description thereof will be omitted.

【0008】なお、以上の実施例において、下部ノズル
13のアダプタ板23の棚段25は、左上隅を鈍角の台
形状としたが、図3に示すように、角を丸めて4分の1
円周状の棚段125としてもよく、更にこれを2つ重ね
て階段状棚段225(図4)としてもよい。図3及び図
4において、符号123、123’、223、223’
は、それぞれアダプタ板を示している。
In the above embodiment, the shelf 25 of the adapter plate 23 of the lower nozzle 13 has an obtuse trapezoidal upper left corner, but as shown in FIG. 3, the corner is rounded to a quarter.
It may be a circular tray 125, or two of these may be stacked to form a stepped tray 225 (FIG. 4). 3 and 4, reference numerals 123, 123 ', 223, 223'
Indicate adapter plates, respectively.

【0009】[0009]

【発明の効果】以上説明したように、本発明によれば、
燃料集合体の下部ノズルのアダプタ板の辺縁部下面に棚
段を形成したので、炉心装荷時隣接した燃料集合体の下
部ノズル間の隙間の入口側に略台形状断面の捕獲空間が
形成され、冷却材伴流異物がここで捕獲され、隙間を貫
流して燃料集合体間に侵入することが防止される。
As described above, according to the present invention,
Since a shelf is formed on the lower surface of the edge of the adapter plate of the lower nozzle of the fuel assembly, a trapezoidal trap space is formed at the inlet side of the gap between the lower nozzles of the adjacent fuel assemblies during core loading. The coolant wake foreign matter is prevented from being trapped here, flowing through the gap and entering between the fuel assemblies.

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

【図1】本発明の実施例に係る燃料集合体の立面図であ
る。
FIG. 1 is an elevation view of a fuel assembly according to an embodiment of the present invention.

【図2】前記実施例の要部を示す部分断面図である。FIG. 2 is a partial cross-sectional view showing a main part of the embodiment.

【図3】本発明の改変実施例の要部を示す部分断面図で
ある。
FIG. 3 is a partial cross-sectional view showing a main part of a modified embodiment of the present invention.

【図4】本発明の別の改変実施例の要部を示す部分断面
図である。
FIG. 4 is a partial cross-sectional view showing the main parts of another modified embodiment of the present invention.

【図5】従来の燃料集合体の下部ノズルを示す斜視図で
ある。
FIG. 5 is a perspective view showing a lower nozzle of a conventional fuel assembly.

【図6】図5のVI−VI線に沿う部分断面図である。6 is a partial cross-sectional view taken along the line VI-VI of FIG.

【符号の説明】[Explanation of symbols]

10 燃料集合体 11 上部ノズル 13 下部ノズル 15 制御棒案内管 17 支持格子 19 核燃料棒 21 冷却材流路孔 23 アダプタ板 25 棚段 125 棚段 225 棚段 C 隙間 F 冷却材流 S 捕獲空間 10 Fuel Assembly 11 Upper Nozzle 13 Lower Nozzle 15 Control Rod Guide Tube 17 Support Lattice 19 Nuclear Fuel Rod 21 Coolant Channel Hole 23 Adapter Plate 25 Shelf 125 Shelf 225 Shelf C Gap F Coolant Flow S Capture Space

Claims (1)

【特許請求の範囲】[Claims] 【請求項1】 それぞれ冷却材流路孔が多数削成される
と共に離れて対向した上部ノズル及び下部ノズルと、前
記両ノズルの間に互いに平行にのびた複数の制御棒案内
管と、同制御棒案内管を開口に受け入れ同制御棒案内管
に交差して取りつけられた支持格子と、同支持格子の開
口に挿通され前記制御棒案内管に対して平行にのびた複
数の核燃料棒とから構成され、前記下部ノズルは、矩形
のアダプタ板と同アダプタ板の下面四隅に突出して形成
された脚とから構成され、前記アダプタ板の脚のない辺
縁部下面に棚段状空所を形成したことを特徴とする原子
炉用燃料集合体。
1. An upper nozzle and a lower nozzle facing each other with a large number of coolant passage holes formed therein, and a plurality of control rod guide tubes extending in parallel between the both nozzles, and the control rod. A support grid that receives the guide tube in the opening and is attached to intersect with the control rod guide tube, and a plurality of nuclear fuel rods that are inserted into the opening of the support grid and extend parallel to the control rod guide tube. The lower nozzle is composed of a rectangular adapter plate and legs formed so as to project from the four corners of the lower surface of the adapter plate, and a shelf-like space is formed on the lower surface of the edge portion of the adapter plate without legs. A characteristic fuel assembly for a nuclear reactor.
JP6221963A 1994-09-16 1994-09-16 Fuel assembly for nuclear reactor Withdrawn JPH0886895A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP6221963A JPH0886895A (en) 1994-09-16 1994-09-16 Fuel assembly for nuclear reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP6221963A JPH0886895A (en) 1994-09-16 1994-09-16 Fuel assembly for nuclear reactor

Publications (1)

Publication Number Publication Date
JPH0886895A true JPH0886895A (en) 1996-04-02

Family

ID=16774909

Family Applications (1)

Application Number Title Priority Date Filing Date
JP6221963A Withdrawn JPH0886895A (en) 1994-09-16 1994-09-16 Fuel assembly for nuclear reactor

Country Status (1)

Country Link
JP (1) JPH0886895A (en)

Similar Documents

Publication Publication Date Title
US5037605A (en) Nuclear fuel assembly debris filter
US5094802A (en) Nuclear fuel assembly debris filter
US4664880A (en) Wire mesh debris trap for a fuel assembly
EP2031599B1 (en) Debris shield for upper tie plate in a nuclear fuel bundle and method for filtering debris
JP3044338B2 (en) PWR fuel assembly
US5483564A (en) Lower tie plate strainers including double corrugated strainers for boiling water reactors
US5748694A (en) Fuel bundle filter for a nuclear reactor fuel bundle assembly
JPH0439918B2 (en)
EP0620558A1 (en) Debris catching arrangement for boiling water reactors
JPH04233494A (en) Nozzle plate at bottom part of nuclear fuel assembly
US5539793A (en) Lower tie plate debris catcher for a nuclear reactor
JPS646423B2 (en)
JPH0324494A (en) Fuel assemby of reactor including equipment for capturing particles contained in cooling fluid of reactor
JPH08240679A (en) Lower-part tie plate lattice and fuel rod support structure
JP3977969B2 (en) Fuel assembly
JP4134460B2 (en) Fuel assembly debris filter
JP3054807B2 (en) Lower nozzle of PWR fuel assembly
JP2002062392A (en) Lower tie plate of boiling water reactor fuel assembly
JP3188155B2 (en) Lower nozzle for fuel assembly
JP2009058506A (en) Debris shield upper tie plate for nuclear fuel assembly and method to shield assembly from debris
JPH08313667A (en) Reactor fuel assembly and nuclear fuel rod therefor
JPH0513596B2 (en)
JPH08136680A (en) Lower nozzle of PWR fuel assembly
JPH0894783A (en) Lower nozzle of PWR fuel assembly
JPS5961798A (en) Nozzle with skirt of fuel assembly

Legal Events

Date Code Title Description
A300 Withdrawal of application because of no request for examination

Free format text: JAPANESE INTERMEDIATE CODE: A300

Effective date: 20011120