JP2003098285A - Fuel assembly for pwr nuclear reactor - Google Patents
Fuel assembly for pwr nuclear reactorInfo
- Publication number
- JP2003098285A JP2003098285A JP2001294559A JP2001294559A JP2003098285A JP 2003098285 A JP2003098285 A JP 2003098285A JP 2001294559 A JP2001294559 A JP 2001294559A JP 2001294559 A JP2001294559 A JP 2001294559A JP 2003098285 A JP2003098285 A JP 2003098285A
- Authority
- JP
- Japan
- Prior art keywords
- control rod
- fuel assembly
- flow passage
- guide tube
- rod guide
- 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
【０００１】[0001]
【発明の属する技術分野】本発明は、加圧水型原子炉
（ＰＷＲ原子炉）用の制御棒集合体側の制御棒外面及び
燃料集合体側制御棒案内シンブル内面における摩耗を抑
制するための新規な改良に関する。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a novel improvement for suppressing wear on the control rod outer surface of a control rod assembly side and the fuel assembly side control rod guide thimble inner surface of a pressurized water reactor (PWR reactor). .
【０００２】[0002]
【従来の技術】図４に示すように、一般的に加圧水型原
子炉で使用されている制御棒集合体は、図示しない制御
棒駆動装置によって駆動されるスパイダ２に複数本の制
御棒１を吊設した構成である。このような制御棒集合体
では、図５に示すように、前記制御棒駆動装置で制御棒
１を駆動し、原子炉に装荷されている燃料集合体の制御
棒案内シンブル３内で前記制御棒１を深く挿入したり浅
く引き抜くことにより、炉心の反応度を制御している。2. Description of the Related Art As shown in FIG. 4, a control rod assembly generally used in a pressurized water reactor has a plurality of control rods 1 mounted on a spider 2 driven by a control rod driving device (not shown). It is a suspended structure. In such a control rod assembly, as shown in FIG. 5, the control rod driving device drives the control rods 1 to cause the control rods in the control rod guide thimbles 3 of the fuel assemblies loaded in the reactor. The reactivity of the core is controlled by inserting 1 deeply or withdrawing shallowly.
【０００３】[0003]
【発明が解決しようとする課題】しかしながら、制御棒
１は、原子炉運転中において制御棒駆動装置により駆動
されながら、燃料集合体内の制御棒案内シンブル３内に
挿入した状態で使用されるため、原子炉運転時の冷却材
の流れにより制御棒１が振動し制御棒案内シンブル３と
の接触により制御棒外面摩耗が生じる恐れがある。ま
た、制御棒案内シンブル３内面も制御棒１の振動に起因
して内面摩耗が生じる可能性がある。However, since the control rod 1 is used by being inserted into the control rod guide thimble 3 in the fuel assembly while being driven by the control rod driving device during the operation of the reactor. The control rod 1 may vibrate due to the flow of the coolant during the operation of the reactor, and the control rod guide thimble 3 may come into contact with the control rod outer surface to cause abrasion. Further, the inner surface of the control rod guide thimble 3 may also be abraded due to the vibration of the control rod 1.
【０００４】これは冷却材流れに起因して制御棒１が振
動する影響で起こり得るもので、制御棒集合体を制御棒
駆動装置により駆動するためのガイドの役目を果たす制
御棒案内管４（以下Ｇ／Ｔと称す）と上部炉心板５（以
下ＵＣＰと称す）のギャップ及びＵＣＰ５とその下側に
位置する燃料集合体の上部ノズル６とのギャップ（図６
参照）に冷却材流水（下方より上方へと流れる炉心流）
が横方向に流れ、この横方向への流れにより制御棒が振
動し、摩耗は徐々に進行していくことが考えられる。This can occur due to the vibration of the control rod 1 due to the flow of the coolant, and the control rod guide tube 4 (which acts as a guide for driving the control rod assembly by the control rod drive device). A gap between the upper core plate 5 (hereinafter referred to as UCP) and a gap between the UCP 5 and the upper nozzle 6 of the fuel assembly located below the UCP 5 (see FIG. 6).
Coolant flow (see core flow flowing from below to above)
Is considered to flow in a lateral direction, and the lateral flow causes the control rod to vibrate and wear gradually progresses.
【０００５】ここで、特にＧ／Ｔ４の横方向の移動を防
ぐ支持ピン７（左右対称２本）の取付位置付近に位置す
る制御棒１に比べ支持ピン７のない側に位置する制御棒
１は、冷却材の流れをより大きく受けることが考えら
れ、支持ピン７のない側にある制御棒１に局部的に大き
な摩耗が発生することが考えられる。また、このような
制御棒１が挿入されている相手側の燃料集合体側の制御
棒案内シンブル３内面にも大きな摩耗が生じる恐れがあ
る。Here, in particular, as compared with the control rod 1 located near the mounting position of the support pins 7 (two symmetrically arranged) that prevent lateral movement of the G / T 4, the control rod 1 located on the side where the support pins 7 are not present. It is conceivable that the control rod 1 on the side where the support pin 7 is absent is subject to a large amount of wear locally due to the greater flow of the coolant. Further, the inner surface of the control rod guide thimble 3 on the opposite fuel assembly side into which the control rod 1 is inserted may be greatly worn.
【０００６】図７に示す通り燃料集合体の上部ノズル６
の下部を構成する部材である、アダプタプレート８に開
口されている流路孔の長手方向が摩耗の大きさに影響す
ることが考えられる。つまり、前記流路孔８Ａはすべて
同じ方向に開口（流路孔８Ａの長手方向とは図７では矢
印Ｂの方向）されており、燃料集合体の下方向（図７中
紙面を裏面から表面側に貫通する方向）から流れる冷却
材流水は上部ノズル６の流路孔８Ａを通過した後は流路
孔の方向に多く流れる傾向を持つため、図中のＢ方向に
多く流れることが考えられる。As shown in FIG. 7, the upper nozzle 6 of the fuel assembly is shown.
It is conceivable that the longitudinal direction of the flow path hole, which is a member that constitutes the lower part of the above, of the adapter plate 8 affects the magnitude of wear. That is, all the flow passage holes 8A are opened in the same direction (the longitudinal direction of the flow passage hole 8A is the direction of arrow B in FIG. 7), and the fuel assembly is downward (from the back surface to the front surface in FIG. 7). Since the coolant running water flowing from the direction (passing through to the side) tends to flow in the direction of the flow path hole after passing through the flow path hole 8A of the upper nozzle 6, it is considered that a large amount flows in the direction B in the figure. .
【０００７】また、前記冷却材の横方向への流れの増大
に伴い、制御棒１が挿入されている相手側の燃料集合体
側の制御棒案内シンブル３内面にも大きな摩耗が生じる
恐れがある。以上のことは、支持ピン７のない方向と上
部ノズル６の流路孔８Ａの方向が一致している場合、前
記の通り摩耗が大きくなる要因が２つ重複しているとい
う課題がある。Further, as the flow of the coolant in the lateral direction increases, the inner surface of the control rod guide thimble 3 on the fuel assembly side of the mating control rod 1 may be greatly worn. As described above, when the direction without the support pin 7 and the direction of the flow path hole 8A of the upper nozzle 6 coincide with each other, there is a problem that two factors that cause large wear overlap as described above.
【０００８】従って、本発明は、上述した従来の技術の
問題を解決するためになされたもので、制御棒や案内シ
ンブルの内面に局部的な摩耗の生じにくいＰＷＲ原子炉
用燃料集合体を提供することを主な目的とするものであ
る。Therefore, the present invention has been made to solve the above-mentioned problems of the prior art, and provides a fuel assembly for a PWR reactor in which internal wear of the control rod and the guide thimble is unlikely to occur locally. The main purpose is to do.
【０００９】[0009]
【課題を解決するための手段】前記燃料集合体の上部に
取り付けられ、制御棒集合体を制御棒駆動装置により駆
動するためのガイドである制御棒案内管の下部にある上
部炉心板を介して前記燃料集合体側に前記制御棒集合体
を挿入する入り口となる上部ノズルに関し、前記上部ノ
ズルの下部構造をなすアダプタプレートは、流路孔の長
手方向と制御棒案内管に取り付けられ、上部炉心板に差
し込まれて制御棒案内管を横方向に移動することを防ぐ
ための支持ピンが存在しない辺の方向とが直交するよう
に前記流路孔を配設した構成である。また、本発明の他
の形態に係るＰＷＲ原子炉用燃料集合体は、ＰＷＲ原子
炉用の燃料集合体と、前記燃料集合体の上部に取り付け
られ、制御棒集合体を制御棒駆動装置により駆動するた
めのガイドである制御棒案内管の下部にある上部炉心板
を介して前記燃料集合体側に前記制御棒集合体を挿入す
る入り口となる上部ノズルに関し、前記上部ノズルの下
部構造をなすアダプタプレートは、流路孔の長手方向と
制御棒案内管に取り付けられ、上部炉心板に差し込まれ
て制御棒案内管を横方向に移動することを防ぐための支
持ピンが存在しない辺の方向に流路孔の長手方向が向い
ている流路孔の数をその総数に対して少なくした構成で
あり、さらに、前記アダプタプレートの流路面には、前
記流路面の中心および対角を通る相直交する２本の直線
によって仕切られる４つの領域における流路面積が均一
になるように流路孔が配設されている構成である。A control rod guide, which is a guide for driving the control rod assembly by a control rod driving device, is attached to the upper portion of the fuel assembly via an upper core plate under the control rod guide tube. Regarding an upper nozzle that serves as an inlet for inserting the control rod assembly into the fuel assembly side, an adapter plate forming a lower structure of the upper nozzle is attached to a longitudinal direction of a flow path hole and a control rod guide tube, and an upper core plate The flow path hole is arranged so as to be orthogonal to the direction of the side where there is no support pin for preventing the control rod guide tube from moving laterally by being inserted into. A fuel assembly for a PWR reactor according to another embodiment of the present invention is attached to a fuel assembly for a PWR reactor and an upper portion of the fuel assembly, and the control rod assembly is driven by a control rod drive device. A control rod guide tube which is a guide for controlling the upper nozzle as an inlet for inserting the control rod assembly to the fuel assembly side through an upper core plate, and an adapter plate forming a lower structure of the upper nozzle. Is attached to the control rod guide tube in the longitudinal direction of the flow passage hole, and is inserted in the upper core plate to prevent passage of the control rod guide pipe in the lateral direction. The number of the flow passage holes in which the longitudinal direction of the holes is oriented is smaller than the total number, and the flow passage surface of the adapter plate is orthogonal to each other passing through the center and the diagonal of the flow passage surface. Book straight line Thus the passage hole as the flow passage area becomes uniform in the four regions partitioned is configured to are disposed.
【００１０】[0010]
【発明の実施の形態】実施の形態１．以下、図面と共に
本発明によるＰＷＲ原子炉用燃料集合体の好適な実施の
形態について詳細に説明する。なお、従来装置と同一ま
たは同等部分には同一符号を付し、その説明を省略す
る。BEST MODE FOR CARRYING OUT THE INVENTION Embodiment 1. Hereinafter, preferred embodiments of a fuel assembly for a PWR reactor according to the present invention will be described in detail with reference to the drawings. The same or equivalent parts as those of the conventional device are designated by the same reference numerals, and the description thereof will be omitted.
【００１１】図１は本発明の実施の形態１に係るＰＷＲ
原子炉用燃料集合体を概略的に示す構成図である。図１
において、本発明のＰＷＲ原子炉用燃料集合体では、燃
料集合体の上部に取り付けられ、制御棒集合体を制御棒
駆動装置により駆動するためのガイドである制御棒案内
管４の下部にある上部炉心板５を介して前記燃料集合体
側に前記制御棒集合体を挿入する入り口となる上部ノズ
ル６の下部構造をなすアダプタプレート８を従来の取り
付け方（図３参照）に対して９０°回転させて取り付け
ている。FIG. 1 shows a PWR according to the first embodiment of the present invention.
It is a block diagram which shows schematically the fuel assembly for nuclear reactors. Figure 1
In the fuel assembly for a PWR reactor of the present invention, the upper portion of the control rod guide tube 4 which is attached to the upper portion of the fuel assembly and is a guide for driving the control rod assembly by the control rod drive device. The adapter plate 8 forming the lower structure of the upper nozzle 6 serving as an inlet for inserting the control rod assembly to the fuel assembly side through the core plate 5 is rotated 90 ° with respect to the conventional mounting method (see FIG. 3). Installed.
【００１２】このアダプタプレート８は、図１に示すよ
うに開口部が扁平している流路孔を備えるため、本発明
のＰＷＲ原子炉用燃料集合体では、流路孔８Ａの長手方
向と、２つの支持ピン７を結ぶ方向とが同一方向になる
ようにアダプタプレート８を取り付けて燃料集合体を組
立てれば、Ｇ／Ｔ４とＵＣＰ５のギャップを流れる冷却
材の流れが大きい支持ピン７のない側と、ＵＣＰ５と燃
料集合体のギャップを流れる冷却材の流れが大きいアダ
プタプレート８の流路孔８Ａの長手方向が直交すること
になるので、炉内挿入配置により局部的な摩耗進行を防
止することができる。As shown in FIG. 1, the adapter plate 8 has flow passage holes whose openings are flat. Therefore, in the fuel assembly for a PWR reactor of the present invention, the flow passage holes 8A are arranged in the longitudinal direction. If the fuel assembly is assembled by mounting the adapter plate 8 so that the direction connecting the two support pins 7 is the same, there is no support pin 7 in which the flow of the coolant flowing through the gap between the G / T 4 and the UCP 5 is large. Side and the longitudinal direction of the flow path hole 8A of the adapter plate 8 in which the flow of the coolant flowing through the gap between the UCP 5 and the fuel assembly is large are orthogonal to each other, so that the internal wear arrangement prevents the progress of local wear. be able to.
【００１３】具体的には、本発明では、従来の燃料集合
体の上部ノズル６のアダプタプレート８の流路孔８Ａの
長手方向と、Ｇ／Ｔ４及びＵＣＰ５を支持している支持
ピン７を結ぶ方向が同一方向になるように、従来の場合
と比較して、アダプタプレート８のみを予め９０°回転
させた状態で上部ノズル組立体として炉内へ装荷してい
る。Specifically, in the present invention, the longitudinal direction of the flow path hole 8A of the adapter plate 8 of the upper nozzle 6 of the conventional fuel assembly is connected to the support pin 7 supporting the G / T 4 and the UCP 5. Compared with the conventional case, only the adapter plate 8 is rotated 90 ° in advance so that the directions are the same, and the upper nozzle assembly is loaded into the furnace.
【００１４】このように、本発明の実施の形態１に係る
ＰＷＲ原子炉用燃料集合体においては、上部ノズル６の
下部構造をなすアダプタプレート８は、流路孔８Ａの長
手方向と制御棒案内管４に取り付けられ、上部炉心板５
に差し込まれて制御棒案内管４を横方向に移動すること
を防ぐための支持ピン７が存在しない辺の方向とが直交
するように流路孔８Ａを配設したので、Ｇ／Ｔ４の支持
ピン７が存在しない方向（図７の矢印Ｂ方向参照）と流
路孔８Ａの長手方向が重複することがなくなり、Ｇ／Ｔ
４とＵＣＰ５のギャップを流れる冷却材流水の影響とＵ
ＣＰ５とその下側に位置する燃料集合体の上部ノズル６
とのギャップに流れる冷却材流水の影響による制御棒１
の振動が従来より均等化され、局部的な制御棒１の外面
摩耗が低減され、しいては燃料集合体内の制御棒案内シ
ンブル３の内面への摩耗を低減することができる。As described above, in the fuel assembly for a PWR reactor according to the first embodiment of the present invention, the adapter plate 8 constituting the lower structure of the upper nozzle 6 is provided with the longitudinal direction of the passage hole 8A and the control rod guide. Attached to tube 4, upper core plate 5
Since the flow path hole 8A is arranged so as to be orthogonal to the direction of the side where the support pin 7 for preventing the lateral movement of the control rod guide tube 4 when inserted into the G / T4 is supported. The direction in which the pin 7 does not exist (see the arrow B direction in FIG. 7) and the longitudinal direction of the flow path hole 8A do not overlap, and G / T
4 and UCP5 gap coolant flow effect and U
CP5 and the upper nozzle 6 of the fuel assembly located below it
Control rod due to the influence of the coolant flowing in the gap between
Of the control rod 1 can be made more uniform than before, and local wear of the outer surface of the control rod 1 can be reduced, and thus wear on the inner surface of the control rod guide thimble 3 in the fuel assembly can be reduced.
【００１５】実施の形態２．図２は、本発明の実施の形
態２に係るＰＷＲ原子炉用燃料集合体の要部を示す図で
ある。前述の課題を解決するため、本発明の実施の形態
２に係るＰＷＲ原子炉用燃料集合体では、上部ノズル９
の下部構造をなすアダプタプレート１０に設けられた流
路孔１０Ａは、制御棒案内管に取り付けられ、上部炉心
板に差し込まれて制御棒案内管を横方向に移動すること
を防ぐための支持ピン７が存在しない辺の方向に流路孔
の長手方向が向いている流路孔の数をその総数に対して
少なくすることにより、上部ノズル９を下方より流れる
冷却材が通過する際に制御棒集合体に均等に力が作用す
るように構成している。Embodiment 2. FIG. 2 is a view showing a main part of a PWR nuclear reactor fuel assembly according to a second embodiment of the present invention. In order to solve the above-mentioned problems, in the PWR nuclear reactor fuel assembly according to the second embodiment of the present invention, the upper nozzle 9
Of the flow path hole 10A provided in the adapter plate 10 forming the lower structure of the control pin is attached to the control rod guide tube and is inserted into the upper core plate to prevent the control rod guide tube from moving laterally. By reducing the number of the flow passage holes whose longitudinal direction is oriented in the direction of the side where 7 does not exist with respect to the total number, the control rods when the coolant flowing from below through the upper nozzle 9 passes. The force is evenly applied to the aggregate.
【００１６】前記上部ノズル９の下方に取り付けられた
アダプタプレート１０において、可能な範囲で従来のよ
うに支持ピン７を結ぶ方向と直交する方向に長手方向を
有する流路孔をなくすか又は少なくした構造（図２
（ｄ）参照）とするか、上部ノズル９の流路孔１０Ａの
方向性をなくした構造（図２（ｂ、c)参照）又は少なく
した構造（図２（a）参照）とすると共に、対角線で区
切られる４つの領域（i）、（ii）、（iii）、（iv）内
の流路面積が等しくなるように均等に流路孔１０Ａを配
設する。In the adapter plate 10 mounted below the upper nozzle 9, passage holes having a longitudinal direction in a direction orthogonal to the direction in which the support pins 7 are connected are eliminated or reduced as much as possible in the conventional manner. Structure (Fig. 2
(See (d)), or a structure in which the directionality of the flow passage hole 10A of the upper nozzle 9 is eliminated (see FIGS. 2B and 2C) or reduced (see FIG. 2A), and The flow passage holes 10A are evenly arranged so that the flow passage areas in the four regions (i), (ii), (iii), and (iv) divided by the diagonal line are equal.
【００１７】このように、上部ノズル９の外寸や制御棒
集合体の挿入孔形状や位置は従来と同様となる範囲で、
流路孔１０Ａの形状配置を変更し、流路孔１０Ａを通流
する冷却材の流れを均等化させている。As described above, the outer size of the upper nozzle 9 and the shape and position of the insertion hole of the control rod assembly are within the same range as in the conventional case.
The shape of the flow path hole 10A is changed to equalize the flow of the coolant flowing through the flow path hole 10A.
【００１８】以上のように、この発明の実施の形態２に
係るＰＷＲ原子炉用燃料集合体によれば、上部ノズル６
の下部構造をなすアダプタプレート８に設けられた流路
孔８Ａは、制御棒案内管４に取り付けられ、上部炉心板
５に差し込まれて制御棒案内管を横方向に移動すること
を防ぐための支持ピン７が存在しない辺の方向に流路孔
８Ａの長手方向が向いている流路孔８Ａの数をその総数
に対して少なくしたので、冷却材が上部ノズルを均等に
通流することにより制御棒１の振動が均等化され、前記
の振動により生じ得る制御棒１の局部的な摩耗を大幅に
抑制することができる。また、それに伴う制御棒案内シ
ンブル３の内面に生じ得る摩耗も最小限に抑えることが
できる。As described above, according to the PWR reactor fuel assembly according to the second embodiment of the present invention, the upper nozzle 6
The flow path hole 8A provided in the adapter plate 8 forming the lower structure of is attached to the control rod guide tube 4 and is inserted into the upper core plate 5 to prevent the control rod guide tube from moving laterally. Since the number of the flow path holes 8A in which the longitudinal direction of the flow path holes 8A is oriented in the direction of the side where the support pin 7 does not exist is smaller than the total number, the coolant can flow through the upper nozzles evenly. The vibration of the control rod 1 is equalized, and local wear of the control rod 1 which may be caused by the vibration can be significantly suppressed. In addition, wear that may occur on the inner surface of the control rod guide thimble 3 due to it can be minimized.
【００１９】[0019]
【発明の効果】本発明のＰＷＲ原子炉用燃料集合体によ
れば、上部ノズルの下部構造をなすアダプタプレート
は、流路孔の長手方向と制御棒案内管に取り付けられ、
上部炉心板に差し込まれて制御棒案内管を横方向に移動
することを防ぐための支持ピンが存在しない辺の方向と
が直交するように流路孔を配設した構成であるので、Ｇ
／Ｔの支持ピンが存在しない方向と流路孔の長手方向が
重複することがなくなり、Ｇ／ＴとＵＣＰのギャップ及
びＵＣＰとの下側に位置する燃料集合体の上部ノズルと
のギャップに流れる冷却材流水の影響による制御棒の振
動が従来より均等化され、局部的な制御棒の外面におけ
る摩耗が低減され、しいては燃料集合体内の案内シンブ
ルの内面への摩耗を低減することができる。また、本発
明の他の形態に係るＰＷＲ原子炉用燃料集合体によれ
ば、上部ノズルの下部構造をなすアダプタプレートに設
けられた流路孔は、制御棒案内管に取り付けられ、上部
炉心板に差し込まれて制御棒案内管を横方向に移動する
ことを防ぐための支持ピンが存在しない辺の方向に流路
孔の長手方向が向いている流路孔の数をその総数に対し
て少なくした構成であるので、冷却材が上部ノズルを均
等に通流することにより制御棒の振動方向が均等化さ
れ、この振動により生じ得る制御棒の局部的な摩耗を大
幅に抑制することができる。また、それに伴う案内シン
ブルの内面に生じ得る摩耗も最小限に抑えることができ
る。さらに、アダプタプレートの流路面には、前記流路
面の中心と対角を通る相直交する２本の直線によって仕
切られる４つの領域における流路面積が均一になるよう
に流路孔が配設されているので、制御棒集合体側の制御
棒外面及び燃料集合体側制御棒案内管内面における摩耗
を抑制したＰＷＲ原子炉用燃料集合体を提供することが
できる。According to the fuel assembly for a PWR reactor of the present invention, the adapter plate constituting the lower structure of the upper nozzle is attached to the longitudinal direction of the flow path hole and the control rod guide tube.
Since the flow path hole is arranged so as to be orthogonal to the direction of the side in which the supporting pin for preventing the lateral movement of the control rod guide tube by being inserted into the upper core plate is arranged, G
The direction in which the support pin of / T does not exist and the longitudinal direction of the flow path hole do not overlap, and flow in the gap between G / T and UCP and the gap between the upper nozzle of the fuel assembly located below UCP. Vibration of the control rod due to the influence of the coolant flowing water is equalized compared with the conventional one, and local wear on the outer surface of the control rod is reduced, which in turn reduces wear on the inner surface of the guide thimble in the fuel assembly. . Further, according to a fuel assembly for a PWR reactor according to another embodiment of the present invention, the flow passage hole provided in the adapter plate forming the lower structure of the upper nozzle is attached to the control rod guide tube, and the upper reactor core plate is attached. The number of flow passage holes whose longitudinal direction is oriented in the direction of the side where there is no support pin for preventing the control rod guide tube from moving laterally when inserted into With this configuration, the coolant flows evenly through the upper nozzle, so that the vibration direction of the control rod is equalized, and local wear of the control rod that may be caused by this vibration can be significantly suppressed. In addition, it is possible to minimize wear that may occur on the inner surface of the guide thimble. Further, the flow passage surface of the adapter plate is provided with flow passage holes such that the flow passage areas in the four regions divided by two straight lines which are orthogonal to each other and diagonally intersect the center of the flow passage surface are uniform. Therefore, it is possible to provide a fuel assembly for a PWR reactor in which wear on the control rod outer surface on the control rod assembly side and the inner surface on the fuel assembly side control rod guide tube is suppressed.
【図１】 本発明の実施の形態１に係るＰＷＲ原子炉用
燃料集合体を概略的に示す構成図である。FIG. 1 is a configuration diagram schematically showing a PWR nuclear reactor fuel assembly according to a first embodiment of the present invention.
【図２】 本発明の実施の形態２に係るＰＷＲ原子炉用
燃料集合体の要部を示す図である。FIG. 2 is a diagram showing a main part of a PWR nuclear reactor fuel assembly according to a second embodiment of the present invention.
【図３】 従来のＰＷＲ原子炉用燃料集合体を概略的に
示す構成図である。FIG. 3 is a configuration diagram schematically showing a conventional PWR nuclear reactor fuel assembly.
【図４】 一般的に加圧水型原子炉で使用されている制
御棒集合体の構成を概略的に示す図である。FIG. 4 is a diagram schematically showing a configuration of a control rod assembly generally used in a pressurized water nuclear reactor.
【図５】 従来の燃料集合体及び制御棒集合体の構成を
概略的に示す斜視図である。FIG. 5 is a perspective view schematically showing a configuration of a conventional fuel assembly and control rod assembly.
【図６】 燃料集合体の上部ノズルとのギャップにおけ
る冷却材流水の通流方向を概念的に示す図である。FIG. 6 is a diagram conceptually showing a flowing direction of coolant flowing water in a gap between the fuel assembly and an upper nozzle.
【図７】 従来の上部ノズル及びアダプタプレートの構
成を概略的に示す構成図である。FIG. 7 is a configuration diagram schematically showing a configuration of a conventional upper nozzle and an adapter plate.
１ 制御棒、２ スパイダ、３ 制御棒案内シンブル、
４ 制御棒案内管、５上部炉心板、６ 上部ノズル、
７ 支持ピン、８ アダプタプレート、８Ａ流路孔、９
上部ノズル、１０ アダプタプレート、１０Ａ 流路
孔。1 control rod, 2 spider, 3 control rod guide thimble,
4 control rod guide tubes, 5 upper core plates, 6 upper nozzles,
7 Support pin, 8 Adapter plate, 8A flow path hole, 9
Upper nozzle, 10 adapter plate, 10A channel hole.
───────────────────────────────────────────────────── フロントページの続き (72)発明者 今泉 正彦 兵庫県神戸市兵庫区和田崎町一丁目１番１ 号 三菱重工業株式会社神戸造船所内 (72)発明者 山口 康直 兵庫県神戸市兵庫区和田崎町一丁目１番１ 号 三菱重工業株式会社神戸造船所内 (72)発明者 鈴木 成光 兵庫県神戸市兵庫区和田崎町一丁目１番１ 号 三菱重工業株式会社神戸造船所内 ─────────────────────────────────────────────────── ─── Continued front page (72) Inventor Masahiko Imaizumi 1-1 1-1 Wadasaki-cho, Hyogo-ku, Kobe-shi, Hyogo No. Mitsubishi Heavy Industries, Ltd.Kobe Shipyard (72) Inventor Yasunao Yamaguchi 1-1 1-1 Wadasaki-cho, Hyogo-ku, Kobe-shi, Hyogo No. Mitsubishi Heavy Industries, Ltd.Kobe Shipyard (72) Inventor Shigemitsu Suzuki 1-1 1-1 Wadasaki-cho, Hyogo-ku, Kobe-shi, Hyogo No. Mitsubishi Heavy Industries, Ltd.Kobe Shipyard
Claims (3)
制御棒駆動装置により駆動するためのガイドである制御
棒案内管の下部にある上部炉心板を介して前記燃料集合
体側に前記制御棒集合体を挿入する入り口となる上部ノ
ズルに関し、 前記上部ノズルの下部構造をなすアダプタプレートは、
流路孔の長手方向と制御棒案内管に取り付けられ、上部
炉心板に差し込まれて制御棒案内管を横方向に移動する
ことを防ぐための支持ピンが存在しない辺の方向とが直
交するように前記流路孔を配設したことを特徴とするＰ
ＷＲ原子炉用燃料集合体。1. A fuel assembly for a PWR reactor, and a lower part of a control rod guide tube which is a guide attached to an upper portion of the fuel assembly and for driving the control rod assembly by a control rod driving device. Regarding an upper nozzle that is an inlet for inserting the control rod assembly to the fuel assembly side through an upper core plate, an adapter plate forming a lower structure of the upper nozzle,
Make sure that the longitudinal direction of the flow path hole is perpendicular to the direction of the side that is attached to the control rod guide tube and is not inserted into the upper core plate to prevent the control rod guide tube from moving laterally. P is characterized in that the flow path hole is provided in
Fuel assembly for WR reactor.
制御棒駆動装置により駆動するためのガイドである制御
棒案内管の下部にある上部炉心板を介して前記燃料集合
体側に前記制御棒集合体を挿入する入り口となる上部ノ
ズルに関し、 前記上部ノズルの下部構造をなすアダプタプレートは、
流路孔の長手方向と制御棒案内管に取り付けられ、上部
炉心板に差し込まれて制御棒案内管を横方向に移動する
ことを防ぐための支持ピンが存在しない辺の方向に向い
ている流路孔の数をその総数に対して少なくしたことを
特徴とするＰＷＲ原子炉用燃料集合体。2. A fuel assembly for a PWR nuclear reactor, and a control rod guide tube which is attached to an upper portion of the fuel assembly and is a guide for driving the control rod assembly by a control rod driving device. Regarding an upper nozzle that is an inlet for inserting the control rod assembly to the fuel assembly side through an upper core plate, an adapter plate forming a lower structure of the upper nozzle,
A flow that is attached to the longitudinal direction of the flow path hole and the control rod guide tube and is directed to the side where there is no support pin to prevent it from being inserted into the upper core plate and moving the control rod guide tube laterally. A fuel assembly for a PWR reactor characterized in that the number of passage holes is reduced with respect to the total number.
記流路面の中心および対角を通る相直交する２本の直線
によって仕切られる４つの領域における流路面積が均一
になるように前記流路孔が配設されていることを特徴と
する請求項１または２記載のＰＷＲ原子炉用燃料集合
体。3. The flow passage surface of the adapter plate is formed such that the flow passage areas are uniform in four regions partitioned by two straight lines that pass through the center of the flow passage surface and a diagonal line and are orthogonal to each other. The fuel assembly for a PWR reactor according to claim 1 or 2, wherein holes are provided.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP2001294559A JP4625212B2 (en) | 2001-09-26 | 2001-09-26 | Fuel assembly for PWR reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP2001294559A JP4625212B2 (en) | 2001-09-26 | 2001-09-26 | Fuel assembly for PWR reactor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JP2003098285A true JP2003098285A (en) | 2003-04-03 |
| JP4625212B2 JP4625212B2 (en) | 2011-02-02 |
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ID=19116139
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| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP2001294559A Expired - Lifetime JP4625212B2 (en) | 2001-09-26 | 2001-09-26 | Fuel assembly for PWR reactor |
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| JP (1) | JP4625212B2 (en) |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2007094509A1 (en) | 2006-02-17 | 2007-08-23 | Mitsubishi Heavy Industries, Ltd. | Pwr reactor fuel assembly |
| KR100784008B1 (en) | 2005-04-08 | 2007-12-07 | 웨스팅하우스 일렉트릭 컴퍼니 엘엘씨 | Nuclear fuel assembly low pressure drop top nozzle |
| CN102592687A (en) * | 2011-01-14 | 2012-07-18 | 中科华核电技术研究院有限公司 | Low-pressure-drop fuel assembly upper tube seat |
| CN112037943A (en) * | 2020-07-28 | 2020-12-04 | 中国原子能科学研究院 | Hydraulic suspension split type passive shutdown assembly for fast neutron reactor |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103247353A (en) * | 2013-04-24 | 2013-08-14 | 中国核动力研究设计院 | Upper pipe base of reactor fuel assembly |
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| JP2000504108A (en) * | 1996-02-02 | 2000-04-04 | フラマトーム | Nuclear fuel assembly with improved top nozzle |
| JP2001108782A (en) * | 1999-10-05 | 2001-04-20 | Mitsubishi Heavy Ind Ltd | Loading method and rotating device for control-rod assembly for nuclear reactor |
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2001
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| JPS6117981A (en) * | 1984-07-04 | 1986-01-25 | 北海道電力株式会社 | Guide support device for control rod of nuclear reactor |
| JP2000504108A (en) * | 1996-02-02 | 2000-04-04 | フラマトーム | Nuclear fuel assembly with improved top nozzle |
| JP2001108782A (en) * | 1999-10-05 | 2001-04-20 | Mitsubishi Heavy Ind Ltd | Loading method and rotating device for control-rod assembly for nuclear reactor |
Cited By (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| KR100784008B1 (en) | 2005-04-08 | 2007-12-07 | 웨스팅하우스 일렉트릭 컴퍼니 엘엘씨 | Nuclear fuel assembly low pressure drop top nozzle |
| WO2007094509A1 (en) | 2006-02-17 | 2007-08-23 | Mitsubishi Heavy Industries, Ltd. | Pwr reactor fuel assembly |
| EP1986197A1 (en) * | 2006-02-17 | 2008-10-29 | Mitsubishi Heavy Industries, Ltd. | Pwr reactor fuel assembly |
| KR101010552B1 (en) * | 2006-02-17 | 2011-01-24 | 미츠비시 쥬고교 가부시키가이샤 | Pwr reactor fuel assembly |
| EP1986197A4 (en) * | 2006-02-17 | 2011-03-30 | Mitsubishi Heavy Ind Ltd | Pwr reactor fuel assembly |
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| US8406369B2 (en) | 2006-02-17 | 2013-03-26 | Mitsubishi Heavy Industries, Ltd. | Fuel assembly for PWR nuclear reactor |
| CN102592687A (en) * | 2011-01-14 | 2012-07-18 | 中科华核电技术研究院有限公司 | Low-pressure-drop fuel assembly upper tube seat |
| CN112037943A (en) * | 2020-07-28 | 2020-12-04 | 中国原子能科学研究院 | Hydraulic suspension split type passive shutdown assembly for fast neutron reactor |
| CN112037943B (en) * | 2020-07-28 | 2023-03-14 | 中国原子能科学研究院 | Hydraulic suspension split type passive shutdown assembly for fast neutron reactor |
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