JPS62119492A - Guide protective structure for reactor control-rod assembly - Google Patents

Guide protective structure for reactor control-rod assembly

Info

Publication number
JPS62119492A
JPS62119492A JP60258642A JP25864285A JPS62119492A JP S62119492 A JPS62119492 A JP S62119492A JP 60258642 A JP60258642 A JP 60258642A JP 25864285 A JP25864285 A JP 25864285A JP S62119492 A JPS62119492 A JP S62119492A
Authority
JP
Japan
Prior art keywords
guide
control rod
gap
plate
rod assembly
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
JP60258642A
Other languages
Japanese (ja)
Inventor
小西 政彦
英昭 鈴木
英治 吉川
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.)
Hokkaido Electric Power Co Inc
Kansai Electric Power Co Inc
Kyushu Electric Power Co Inc
Japan Atomic Power Co Ltd
Shikoku Electric Power Co Inc
Mitsubishi Heavy Industries Ltd
Original Assignee
Hokkaido Electric Power Co Inc
Kansai Electric Power Co Inc
Kyushu Electric Power Co Inc
Japan Atomic Power Co Ltd
Shikoku Electric Power Co Inc
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 Hokkaido Electric Power Co Inc, Kansai Electric Power Co Inc, Kyushu Electric Power Co Inc, Japan Atomic Power Co Ltd, Shikoku Electric Power Co Inc, Mitsubishi Heavy Industries Ltd filed Critical Hokkaido Electric Power Co Inc
Priority to JP60258642A priority Critical patent/JPS62119492A/en
Publication of JPS62119492A publication Critical patent/JPS62119492A/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

  • Monitoring And Testing Of Nuclear Reactors (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】 [産業上の利用分野] 本発明は原子炉の制御棒組立体を案内し保護する構造体
に関するものである。
DETAILED DESCRIPTION OF THE INVENTION Field of the Invention The present invention relates to a structure for guiding and protecting a control rod assembly of a nuclear reactor.

[従来の技術1 原子炉の炉心を構成する燃料集合体は、その反応度を制
御するため、周知のように、該燃料集合体に対して制御
棒を挿入及び引き抜き可能に構成されている。制御棒は
複数のものが房状に組み立てられて制御棒組立体を構成
しており、該制御棒組立体は、炉心上方の上部炉内構造
物内に配設された案内保護構造体によって、その挿入及
び引き抜きを案内され保護される。
[Prior Art 1] As is well known, a fuel assembly constituting the core of a nuclear reactor is configured such that control rods can be inserted into and withdrawn from the fuel assembly in order to control its reactivity. A plurality of control rods are assembled into a tuft to form a control rod assembly, and the control rod assembly is controlled by a guide protection structure disposed in an upper internal structure above the reactor core. Its insertion and withdrawal is guided and protected.

かかる案内保護構造体に要求される機能は、制御棒の挿
入及び引き抜きに対して十分な機械的案内を提供すると
共に、案内保護構造体の内外を上方に流れる冷却材流体
による振動から制御棒を保護することであり、そのため
、案内係v1構造体は各制御棒を取り囲むC型断面の保
護管を備えておリ、該制御棒と該保険管の内面との間に
は適当な隙間が必要である。しかし、この隙間が大きい
場合、保護管全長にわたって一様な隙間を与えることは
制御棒全体の振動抑制に対して効果が少なく、隙間を保
護管全長にわたって小さくすることは、1本の制御棒の
直径(十数arm)が長さに比較して非常に小さいので
、製造上の困難を伴う。
The required functionality of such a guide protection structure is to provide sufficient mechanical guidance for control rod insertion and withdrawal, and to protect the control rods from vibrations caused by coolant fluid flowing upwardly in and out of the guide protection structure. Therefore, the guide v1 structure is equipped with a C-shaped cross-section protection tube surrounding each control rod, and there must be an appropriate gap between the control rod and the inner surface of the insurance tube. It is. However, if this gap is large, providing a uniform gap over the entire length of the protection tube has little effect on vibration suppression of the entire control rod, and reducing the gap over the entire length of the protection tube is Since the diameter (more than 10 arms) is very small compared to the length, it is difficult to manufacture.

[発明が解決しようとする問題点] 制御棒の振動抑制のためには、この隙間を艮手力向に一
様にするのではなく、該隙間を局部的に絞ったほうが、
より実効的であるが、局部的な絞り手段として、個々の
保護管の端にブツシュ、即ち絞り部材を溶接していたの
では、溶接歪みによる保護管の変形の懸念、溶接及びそ
の検査のための工数増加等の問題がある。
[Problems to be Solved by the Invention] In order to suppress the vibration of the control rod, it is better to narrow the gap locally instead of making it uniform in the direction of the hand force.
Although it is more effective, welding bushings, i.e., throttle members, to the ends of individual protection tubes as a local squeezing means raises concerns about deformation of the protection tubes due to welding distortion, and prevents welding and its inspection. There are problems such as increased man-hours.

本発明は、これ等の問題なしに、簡単な構造で、制御棒
とC型断面の保護管との間の間隙を局部的に且つ相対的
に小さくすることができる原子炉制御棒組立体用案内保
護R1を遺体を提供することを目的とするものである。
The present invention is directed to a nuclear reactor control rod assembly in which the gap between the control rod and the C-section protective tube can be locally and relatively small without these problems and with a simple structure. The purpose of the guide protection R1 is to provide a dead body.

E問題点を解決するための手段1 この目的から、本発明は、複数の細い制御棒が房状に組
み立てられた原子炉制御棒組立体を案内保護する案内保
護構造体において、筒状の囲い板と、該囲い板の上端及
び下端に固設された上下の端板と、該上下の端板間に設
けられ、前記制御棒の各々を個別に取り囲むC型断面保
l管とから一つの案内ユニットを形成し、複数の該案内
ユニットを積重して、前記案内保護構造体を構成したこ
と、及び該複数の案内ユニットのうち少なくとも一組の
隣接する案内ユニット間に、前記制御棒を個別に取り囲
む支持孔を有する隙間調整板が配設されており、前記制
御棒と前記支持孔の内面との間の隙間を前記制御棒と前
記C型断面保護管の内面との間の隙間よりも小さくした
ことを特徴とするものである。
Means for Solving Problem E 1 For this purpose, the present invention provides a guide and protect structure that guides and protects a nuclear reactor control rod assembly in which a plurality of thin control rods are assembled in a tuft. A plate, upper and lower end plates fixed to the upper and lower ends of the shrouding plate, and a C-shaped cross-section storage tube provided between the upper and lower end plates and individually surrounding each of the control rods. The guide protection structure is configured by forming a guide unit and stacking a plurality of the guide units, and the control rod is arranged between at least one set of adjacent guide units among the plurality of guide units. A gap adjustment plate having support holes that individually surround each other is provided, and the gap between the control rod and the inner surface of the support hole is made smaller than the gap between the control rod and the inner surface of the C-shaped section protection tube. It is also characterized by being smaller.

[作用] 案内係1m造体を複数の案内ユニットにより構成し、隣
接する案内ユニット間に隙間調整板を設置したことによ
り、制御棒そのものの支持点を増やして、該制御棒の振
幅を小さくし、その振動特性を変える。隙間調整板は各
制御棒を個別に取り囲んで隙間を局部的に絞る支持孔を
有するので、各保護管毎に、ブツシュを絞り部材として
溶接により取り付ける必要がない。しかも、組み立て前
は、各案内ユニットと隙間調整板とは別体であるから、
それ等を独立して並行に製作することができる。
[Function] By configuring the 1m guide structure with multiple guide units and installing gap adjustment plates between adjacent guide units, the number of support points for the control rod itself is increased, and the amplitude of the control rod is reduced. , change its vibration characteristics. Since the gap adjusting plate has a support hole that individually surrounds each control rod and narrows the gap locally, there is no need to attach a bush as a narrowing member to each protective tube by welding. Moreover, each guide unit and gap adjustment plate are separate pieces before assembly, so
They can be manufactured independently and in parallel.

[実施例] 次に、本発明の好適な実施例を添付図面を参照して説明
するが、図中、同一符号は同−又は対応部分を示すもの
とする。
[Embodiments] Next, preferred embodiments of the present invention will be described with reference to the accompanying drawings, in which the same reference numerals indicate the same or corresponding parts.

第2図は本発明を実施した原子炉1の断面を示すもので
あり、該原子炉1は、原子炉容器2、該原子炉容器2内
に垂下された筒状の炉心槽3、該炉心槽3内において下
部炉心支持板4及び上部炉心支持板5間に支持される複
数の燃料集合体6がら構成される炉心7、及び該炉心7
の上方の上部炉内構造物8等から形成されており、上部
炉内構造物8内には、第3図に示すように複数の制御棒
9を房状に組み立てて構成された周知の制御棒組立体1
0を案内し保護するための案内保護構造体11が配設さ
れでいる。
FIG. 2 shows a cross section of a nuclear reactor 1 in which the present invention is implemented, and the reactor 1 includes a reactor vessel 2, a cylindrical core barrel 3 suspended within the reactor vessel 2, and a reactor core. A core 7 comprising a plurality of fuel assemblies 6 supported between a lower core support plate 4 and an upper core support plate 5 in the tank 3, and the core 7
It is formed from an upper reactor internal structure 8 and the like, and inside the upper reactor internal structure 8, there is a well-known control system constructed by assembling a plurality of control rods 9 in a cluster as shown in FIG. Rod assembly 1
A guiding and protecting structure 11 is provided for guiding and protecting 0.

fjS2図において、原子炉冷却材は、矢印で示すよう
に、入口ノズル12から原子炉容器2内に入り、該原子
炉容器2と炉心槽3との間の環状下降領域13を流下し
て下部炉心支持板4の下方のプレナム14に至り、該プ
レナム14で反転して、炉心7内を上方に流れる。炉心
7の燃料集合体6により加熱された冷却材は上述した案
内保護構造体11の内外を更に上方に流れ、上部炉内構
造物8のカランドリア構造体15で横向きに流れを変え
、出口ノズル16から図示しない二次冷却系に排出され
る。
In the fjS2 diagram, the reactor coolant enters the reactor vessel 2 from the inlet nozzle 12 as shown by the arrow, flows down the annular descending region 13 between the reactor vessel 2 and the core tank 3, and flows to the lower part. It reaches the plenum 14 below the core support plate 4, turns around at the plenum 14, and flows upward in the core 7. The coolant heated by the fuel assembly 6 of the reactor core 7 flows further upward inside and outside the guide and protection structure 11 described above, changes its flow sideways at the calandria structure 15 of the upper internals 8, and flows through the outlet nozzle 16. from there to a secondary cooling system (not shown).

このように案内保護構造体11の内外を冷却材が貫流す
るので、該案内保護構造体11内の制御棒組立体10(
第3図)の各制御棒9を冷却材流による振動から保護す
る必要がある。第1図はこのような保護機能を備えた本
発明の案内保護構造体11をボしている。
Since the coolant flows through the inside and outside of the guide protection structure 11 in this way, the control rod assembly 10 (
It is necessary to protect each control rod 9 (FIG. 3) from vibrations caused by the coolant flow. FIG. 1 shows a guide protection structure 11 of the present invention having such a protection function.

第1図において、この案内保護構造体11は5個の案内
ユニツ) lla〜lieを長手方向に積重しで組み立
てられており、隣接した各組の案内ユニット間には、隙
間調整板17が本発明に従って配設されている。各案内
ユニットは実質的に同一構造のものでよ仁第1図及びそ
の■へ−I^線における断面を示す第1八図から諒解さ
れるように、各案内ユニットは、長手方向に二・分割さ
れた板部材を溶接して筒状に形成された囲い板18と、
該囲b1板18の上端及び下端に突出部18cで溶接取
着された、実質的に同一構造のものでよい上下の端板1
8a及び18bとを備えるものである。
In FIG. 1, this guide protection structure 11 is assembled by stacking five guide units) lla to lie in the longitudinal direction, and a gap adjusting plate 17 is provided between each set of adjacent guide units. Arranged according to the invention. Each guide unit has substantially the same structure, and as can be understood from FIG. 1 and FIG. A shroud plate 18 formed into a cylindrical shape by welding divided plate members;
Upper and lower end plates 1, which may be of substantially the same structure, are welded to the upper and lower ends of the surrounding b1 plate 18 at protrusions 18c.
8a and 18b.

また、案内ユニットの囲い板18を取り除いて示す第4
図から諒解されるように、各案内ユニットは、第3図の
制御棒9を個別に取り囲むことのできるように上述した
端板18a及び18b間に取着されたC型断面の保護管
19を備えている。各保護管19は、第5八図(第4図
の平面図である第5図の■^−V^線における断面を示
す)に示すような態様で各端板に溶接により取着される
Also, the fourth part shown with the guide unit's shroud 18 removed
As can be seen from the figure, each guide unit has a protective tube 19 with a C-shaped cross section attached between the aforementioned end plates 18a and 18b so as to be able to individually surround the control rod 9 of FIG. We are prepared. Each protection tube 19 is attached to each end plate by welding in the manner shown in FIG. .

このような構成を有する隣接案内ユニット間に上述した
隙間714整板17が介挿されるが、該隙間調整板17
は、その平面図を示す第6図と端板18aの平面図を最
も良く示す第5図とを比較すると明らかなように、外形
的には該端板とほぼ同様の構造を有するものである。し
かし、第1図において鎖線で囲まれた領域■を拡大して
縦断面で代表的に示す第7図から諒解される通り、端板
のC型断面の各保護管19に軸方向に整列するように隙
間調整板17に設けられた制御棒9の支持孔1フaの内
径は、保IW19の内径よりも相対的に小さく形成され
ており、また、制御棒9の案内を円滑に行うため、各支
持孔17aの上端及び下端は中央部よりも拡径されてい
る。
The gap 714 adjustment plate 17 described above is inserted between adjacent guide units having such a configuration.
As is clear from a comparison between FIG. 6, which shows the plan view thereof, and FIG. 5, which best shows the plan view of the end plate 18a, the end plate 18a has a structure that is almost the same in external shape as the end plate. . However, as can be understood from FIG. 7, which is a typical vertical cross-sectional view of an enlarged area (2) surrounded by a chain line in FIG. The inner diameter of the support hole 1a of the control rod 9 provided in the clearance adjustment plate 17 is formed to be relatively smaller than the inner diameter of the retaining IW 19, and in order to guide the control rod 9 smoothly. , the upper and lower ends of each support hole 17a are larger in diameter than the central portion.

隙間調整板17の取り付けは、第6図及び第7図から諒
解されるように、例えば上側の案内ユニットの下端板1
8bに適宜設けられた図示しない位置決めピンに、隙間
調整板17に設けた穴17bを嵌合して隙間111g板
17の位置決めを行った後、隙間調整板1フのボルト穴
17cにポル)17dを通し、上記下端板18bに螺合
すればよい。勿論、隙間調整板17は下側案内ユニット
の上端板18aに取り付けてもよい。
As can be understood from FIGS. 6 and 7, the gap adjusting plate 17 is installed, for example, by attaching the lower end plate 1 of the upper guide unit.
After positioning the plate 17 in the gap 111g by fitting the hole 17b provided in the gap adjustment plate 17 into the positioning pin (not shown) provided in the gap adjustment plate 17, the bolt hole 17c in the gap adjustment plate 1f is inserted into the hole 17d. , and screwed onto the lower end plate 18b. Of course, the gap adjustment plate 17 may be attached to the upper end plate 18a of the lower guide unit.

尚、実施例では案内ユニットの数は5個であり、隣接す
る全案内ユニット組に隙間1!!整板1フが介挿されて
いるが、案内ユニ・ントの数は2個以上ならよく、また
、隣接する少なくとも1.Itの案内ユニット間に隙間
m!!板17を設ければより・。
In this embodiment, the number of guide units is 5, and there is a gap of 1 between all adjacent guide unit sets! ! Although a straightening plate 1 is inserted, the number of guide units may be two or more, and at least one adjacent guide unit. Gap m between the guide units of It! ! It would be better if the plate 17 was installed.

[発明の効果] 本発明の制御棒組立体用案内係lvt遺体は以上のよう
に構成されているので、C型断面の保護管19を有する
案内ユニットの囲い板18が原子炉の上部炉心構造物8
内の流れを細流に保つと共に、案内保護構造体11にv
t遣強度を与える。このような案内二二ツ) lla〜
lieを、隣接する少なくとも一組の案内ユニ・シト間
に相対的に小径の支持孔17cを有する隙間調整板17
を介挿して、複数個積重することによって、制御棒9は
、−列に整列した支持孔17c及び保護管19により挿
入及び引き抜きを案内され、流体振動から保護されるだ
けでなく、λf図nIl馴格板17の支持孔17cの部
位で局部的に支持され、流体による振動の振幅がこの部
位で小さくなるなど、制御棒全体の振動特性が好適に変
わる。
[Effects of the Invention] Since the control rod assembly guide lvt body of the present invention is configured as described above, the guide unit shroud 18 having the C-shaped cross-section protection tube 19 is connected to the upper core structure of the reactor. Thing 8
While keeping the flow in the guide and protection structure 11 at a trickle,
Gives the t-force strength. 22 such guidance) lla~
The gap adjusting plate 17 has a relatively small diameter support hole 17c between at least one set of adjacent guide units.
By inserting and stacking a plurality of control rods, the control rods 9 are guided in insertion and withdrawal by the support holes 17c and the protection tubes 19 arranged in the - row, and are not only protected from fluid vibration but also have a λf diagram. It is locally supported at the support hole 17c of the nIl conditioning plate 17, and the vibration characteristics of the entire control rod are suitably changed, such as the amplitude of vibration caused by the fluid becoming smaller at this location.

また、本発明によれば、隙間の絞り機能を有する隙間調
整板が案内ユニットとは別個に製作できるので、しかも
、一つの隙間調整板によって案内保護構造体の全断面の
隙間を局部的に絞ることができるので、案内保護構造体
の製作工程を可及的に短縮することが可能になる。
Furthermore, according to the present invention, the gap adjusting plate having the function of narrowing the gap can be manufactured separately from the guide unit, and moreover, the gap in the entire cross section of the guide protection structure can be locally narrowed by one gap adjusting plate. Therefore, it becomes possible to shorten the manufacturing process of the guide protection structure as much as possible.

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

第1図は本発明による原子炉制御棒組立体用案内保護構
造体の概略側面図、第1八図はi1図のI^−rA#i
における拡大断面図、第2図はtIS1図の案内保、J
!構造体を装着した原子炉の概略断面図、第3図はfj
S1図の案内保護vI構造体より案内保護される制御棒
組立体の一部省略側面図、第4図はm1図の案内係:J
ivi遺体を形成する案内ユニントの一つをその囲い板
を除去して示す側面図、第5図は第4図の平面図、fj
S5A図は第5図の■Δ−■八線にへける拡大断面図、
第6図は第1図の案内保護構遺体で使用されている隙間
714g!板の拡大平面図、第7図は第1図に鎖線で囲
まれた楕円形の領域■の拡大縦断面図である。 1 ・・・原子炉     9 ・・・制御棒11・・
・案内係11m造体 17・・・隙間調整板17a・・
・支持孔     18・・・囲い板18a・・・上の
端板    18b・・・下の端板19・・・C型断面
保護管 11a〜lie・・・案内ユ千ット に2図 篤3図 葛7図
FIG. 1 is a schematic side view of the guide protection structure for a nuclear reactor control rod assembly according to the present invention, and FIG.
2 is an enlarged cross-sectional view of the tIS1 diagram, J
! A schematic cross-sectional view of the reactor with the structure installed, Figure 3 is fj
A partially omitted side view of the control rod assembly guided and protected by the guidance and protection vI structure in Figure S1, and Figure 4 is the guide member in Figure m1: J
ivi A side view showing one of the guide units forming the corpse with its shroud removed, FIG. 5 is a plan view of FIG. 4, fj
Figure S5A is an enlarged sectional view taken along the ■Δ-■ 8th line in Figure 5.
Figure 6 shows the gap 714g used in the guide protection structure in Figure 1! FIG. 7 is an enlarged plan view of the plate and an enlarged longitudinal sectional view of the elliptical area (2) surrounded by a chain line in FIG. 1. 1... Nuclear reactor 9... Control rod 11...
・Guidance staff 11m structure 17...Gap adjustment plate 17a...
・Support hole 18...Shrouding plate 18a...Upper end plate 18b...Lower end plate 19...C-shaped cross-section protective tube 11a-lie...Guiding unit 1,000 pieces 2 figures 3 Figure 7

Claims (1)

【特許請求の範囲】 複数の細い制御棒が房状に組み立てられた原子炉制御棒
組立体を案内保護する案内保護構造体において、 筒状の囲い板と、該囲い板の上端及び下端に固設された
上下の端板と、該上下の端板間に設けられ、前記制御棒
の各々を個別に取り囲むC型断面保護管とから一つの案
内ユニットを形成し、複数の該案内ユニットを積重して
、前記案内保護構造体を構成したこと、及び 該複数の案内ユニットのうち少なくとも一組の隣接する
案内ユニット間に、前記制御棒を個別に取り囲む支持孔
を有する隙間調整板が配設されており、前記制御棒と前
記支持孔の内面との間の隙間を前記制御棒と前記C型断
面保護管の内面との間の隙間よりも小さくしたこと、 を特徴とする原子炉制御棒組立体用案内保護構造体。
[Scope of Claims] A guiding and protecting structure that guides and protects a nuclear reactor control rod assembly in which a plurality of thin control rods are assembled in a tuft, includes a cylindrical shrouding plate and a structure fixed to the upper and lower ends of the shrouding plate. One guide unit is formed from upper and lower end plates provided and a C-shaped cross-section protection tube provided between the upper and lower end plates and individually surrounding each of the control rods, and a plurality of the guide units are stacked. Furthermore, the guide protection structure is configured, and a gap adjustment plate having support holes that individually surround the control rods is disposed between at least one set of adjacent guide units among the plurality of guide units. A nuclear reactor control rod characterized in that the gap between the control rod and the inner surface of the support hole is smaller than the gap between the control rod and the inner surface of the C-shaped cross-section protection tube. Guide protection structure for assembly.
JP60258642A 1985-11-20 1985-11-20 Guide protective structure for reactor control-rod assembly Pending JPS62119492A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP60258642A JPS62119492A (en) 1985-11-20 1985-11-20 Guide protective structure for reactor control-rod assembly

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP60258642A JPS62119492A (en) 1985-11-20 1985-11-20 Guide protective structure for reactor control-rod assembly

Publications (1)

Publication Number Publication Date
JPS62119492A true JPS62119492A (en) 1987-05-30

Family

ID=17323102

Family Applications (1)

Application Number Title Priority Date Filing Date
JP60258642A Pending JPS62119492A (en) 1985-11-20 1985-11-20 Guide protective structure for reactor control-rod assembly

Country Status (1)

Country Link
JP (1) JPS62119492A (en)

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