[go: up one dir, main page]

JP2005214838A - Upper nozzle of fuel assembly for pressurized water reactor - Google Patents

Upper nozzle of fuel assembly for pressurized water reactor Download PDF

Info

Publication number
JP2005214838A
JP2005214838A JP2004023160A JP2004023160A JP2005214838A JP 2005214838 A JP2005214838 A JP 2005214838A JP 2004023160 A JP2004023160 A JP 2004023160A JP 2004023160 A JP2004023160 A JP 2004023160A JP 2005214838 A JP2005214838 A JP 2005214838A
Authority
JP
Japan
Prior art keywords
upper nozzle
fuel assembly
coolant
top plate
pressurized water
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
Application number
JP2004023160A
Other languages
Japanese (ja)
Other versions
JP4532127B2 (en
Inventor
Eizo Okuda
英三 億田
Toshihiko Motomura
俊彦 本村
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.)
Nuclear Fuel Industries Ltd
Original Assignee
Nuclear Fuel 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 Nuclear Fuel Industries Ltd filed Critical Nuclear Fuel Industries Ltd
Priority to JP2004023160A priority Critical patent/JP4532127B2/en
Publication of JP2005214838A publication Critical patent/JP2005214838A/en
Application granted granted Critical
Publication of JP4532127B2 publication Critical patent/JP4532127B2/en
Anticipated expiration legal-status Critical
Expired - Fee Related legal-status Critical Current

Links

Images

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

【課題】 制御棒が冷却材の流れによって振動を受ける度合いを減少し、制御棒案内シンブルの摩耗量を低減して燃料集合体の強度を維持する。
【解決手段】 上部ノズル本体３４のトッププレート３２に垂直方向に貫通する複数の流水孔４２Ａを設けて上部ノズル本体３４を上向きに流れてトッププレート３２に当たる冷却材Ｃの大部分をこれらの流水孔４２Ａを経て上昇して冷却材Ｃの流れによって制御棒に振動が付与される程度を少なくする。
【選択図】 図２
PROBLEM TO BE SOLVED: To maintain the strength of a fuel assembly by reducing the degree to which a control rod receives vibration due to the flow of a coolant and reducing the amount of wear of the control rod guide thimble.
SOLUTION: A plurality of water holes 42A penetrating the top plate 32 of the upper nozzle body 34 in the vertical direction are provided so that most of the coolant C that flows upward through the upper nozzle body 34 and hits the top plate 32 is formed in these water holes. The degree to which vibration is imparted to the control rod by the flow of the coolant C rising through 42A is reduced.
[Selection] Figure 2

Description

本発明は、加圧水型原子炉用燃料集合体上部ノズルの改良に関し、更に詳細に述べると、制御棒の振動を低減することができる加圧水型原子炉用燃料集合体上部ノズルに関するものである。   The present invention relates to an improvement of a pressurized water reactor fuel assembly upper nozzle, and more particularly to a pressurized water reactor fuel assembly upper nozzle capable of reducing vibration of a control rod.

図１に示すように、加圧水型原子炉用燃料集合体１０は、複数段の支持格子１２によって束ねられた多数の燃料棒１４から成り、上下のノズル２０、２２は、制御棒案内シンブル１６によってこの束に結合されている。なお、図１において符号１８は、上部ノズル２０に取付けられて炉内で上部炉心板に当接するリーフスプリングであり、これは、冷却材によって燃料集合体１０が浮き上がるのを防止する機能を有する。   As shown in FIG. 1, the pressurized water reactor fuel assembly 10 is composed of a number of fuel rods 14 bundled by a plurality of stages of support grids 12, and the upper and lower nozzles 20, 22 are controlled by control rod guide thimbles 16. Combined with this bundle. In FIG. 1, reference numeral 18 denotes a leaf spring that is attached to the upper nozzle 20 and contacts the upper core plate in the furnace, and has a function of preventing the fuel assembly 10 from being lifted by the coolant.

図６に示すように、この加圧水型原子炉の運転中、制御棒クラスタは、燃料集合体から殆ど引き抜かれており、制御棒１７の先端部が燃料集合体の上部ノズル２０に取付けられた制御棒案内シンブル１６に挿入された状態になっている。この挿入深さLは、すべての燃料集合体に対して等しいわけではないが、いずれにしても制御棒１７の先端部は、制御棒案内シンブル１６内にある。   As shown in FIG. 6, during operation of this pressurized water reactor, the control rod cluster is almost pulled out of the fuel assembly, and the control rod 17 is attached to the upper nozzle 20 of the fuel assembly. The rod guide thimble 16 is inserted. The insertion depth L is not the same for all fuel assemblies, but in any case, the tip of the control rod 17 is in the control rod guide thimble 16.

一方、図６に示すように、原子炉の運転中、燃料集合体１０の上部ノズル２０のノズルプレート３１の流水孔を経て図６の矢印Ｖ方向に上向きに流れる冷却材Ｃは、上部ノズル２０のトッププレート３４に当たって水平方向に向きを変え制御棒１７に向かって水平方向に流れる。   On the other hand, as shown in FIG. 6, during operation of the nuclear reactor, the coolant C flowing upward in the direction of arrow V in FIG. 6 through the flow holes of the nozzle plate 31 of the upper nozzle 20 of the fuel assembly 10 is transferred to the upper nozzle 20. The top plate 34 is changed in the horizontal direction and flows in the horizontal direction toward the control rod 17.

しかし、制御棒案内シンブル１６に挿入された制御棒１７の先端部は、このような冷却材Ｃの水平方向の流れを受けると、振動し、制御棒１７とこの制御棒の先端が挿入された制御棒案内シンブル１６とが繰り返し接触し、制御棒案内シンブル１６が摩耗する。   However, the tip of the control rod 17 inserted into the control rod guide thimble 16 vibrates when receiving the horizontal flow of the coolant C, and the control rod 17 and the tip of the control rod are inserted. The control rod guide thimble 16 repeatedly contacts and the control rod guide thimble 16 is worn.

制御棒案内シンブル１６は、燃料集合体の骨格としての機能を有し、燃料集合体１０の全重量を支持しているので、制御棒案内シンブル１６が摩耗すると、燃料集合体１０の強度が低下し、燃料集合体の品質の低下を招く。   Since the control rod guide thimble 16 has a function as a skeleton of the fuel assembly and supports the entire weight of the fuel assembly 10, the strength of the fuel assembly 10 decreases when the control rod guide thimble 16 is worn. As a result, the quality of the fuel assembly is degraded.

本発明が解決しようとする課題は、制御棒が冷却材の流れによって振動を受けるのを低減し、燃料集合体の強度の低下を起すことがない加圧水型原子炉用燃料集合体を提供することにある。   The problem to be solved by the present invention is to provide a fuel assembly for a pressurized water reactor in which the control rod is less subject to vibration due to the flow of the coolant and does not cause a decrease in the strength of the fuel assembly. It is in.

本発明の基本的な課題解決手段は、上部ノズル本体の内周面にトッププレートを有する加圧水型原子炉用燃料集合体上部ノズルにおいて、このトッププレートによって発生して制御棒に向かう冷却材の水平方向の流れを低減するように冷却材の流れを制御する冷却材流れ制御手段を備えたことを特徴とする加圧水型原子炉用燃料集合体上部ノズルを提供することにある。   The basic problem-solving means of the present invention is that, in a pressurized water reactor fuel assembly upper nozzle having a top plate on the inner peripheral surface of the upper nozzle body, the coolant generated horizontally by this top plate and directed toward the control rod An object of the present invention is to provide a fuel assembly upper nozzle for a pressurized water reactor, characterized by comprising coolant flow control means for controlling the flow of coolant so as to reduce the flow in the direction.

本発明の基本的な課題解決手段において、冷却材流れ制御手段は、トッププレートに垂直方向に貫通して設けられた複数の流水孔又は流水スリットから成っていてもよいし、上部ノズル本体のトッププレートの下方側の壁部分で水平方向に貫通して設けられて冷却材をトッププレートの下方で上部ノズル本体の外側に誘導する流水孔から成っていてもよい。   In the basic problem-solving means of the present invention, the coolant flow control means may consist of a plurality of flow holes or flow slits that are provided to penetrate the top plate in the vertical direction, or the top of the upper nozzle body. It may consist of a flow hole provided in a horizontal direction in the wall portion on the lower side of the plate and guiding the coolant to the outside of the upper nozzle body below the top plate.

また、本発明の基本的な課題解決手段において、冷却材流れ制御手段は、トッププレートの内周部に冷却材を水平方向ではなく内周部に沿って上方に誘導する丸みを有する誘導面から成っていてもよい。   Further, in the basic problem solving means of the present invention, the coolant flow control means is provided on the inner peripheral portion of the top plate from a guide surface having a roundness that guides the coolant upward along the inner peripheral portion, not in the horizontal direction. It may be made up.

本発明によれば、燃料集合体内を上向きに流れる冷却材は、上部ノズルのトッププレートに当たっても、水平方向に流れないで、垂直流水孔または流水スリットを貫通して又はトッププレートの内周誘導面に沿ってトッププレートの上方に誘導され又は水平流水孔を貫通して上部ノズルの外側に誘導されるので、制御棒がこの冷却材の流れによって振動を受ける度合いが減少し、従って制御棒案内シンブルの摩耗量が低減し、燃料集合体の強度を低下することがない。   According to the present invention, the coolant flowing upward in the fuel assembly does not flow in the horizontal direction even when it hits the top plate of the upper nozzle, passes through the vertical water flow hole or the water flow slit, or the inner peripheral guide surface of the top plate. Along the top plate or through the horizontal water holes and outside the upper nozzle, so that the degree of vibration of the control rods due to this coolant flow is reduced, and therefore the control rod guide thimble This reduces the amount of wear of the fuel assembly and does not reduce the strength of the fuel assembly.

本発明の実施の形態を図面を参照して詳細に述べると、図２及び図３は、本発明に係わる加圧水型原子炉用燃料集合体上部ノズル２０を示し、この上部ノズル２０は、下側にノズルプレート３１を有し上端縁の内周面に鍔状のトッププレート３２を有する略四角形の上部ノズル本体３４から成っている。ノズルプレート３１には多数の流水孔３１ＷＨとシンブル貫通孔３１ＳＨとを有する。なお、図２において符号３６は、上部ノズル本体３４の２つのコーナ立上がり部に設けられたロック部、符号３８は、上部ノズル本体３４の他の２つのコーナ立上がり部に設けられて各リーフスプリング（図１の符号１８参照）の基部を固定するボルトがねじ込まれるねじ孔、また符号４０は、トッププレート３２に設けられて各リーフスプリングの脚部（図１の符号１８ａ参照）が入り込むスリットである。   The embodiment of the present invention will be described in detail with reference to the drawings. FIGS. 2 and 3 show a pressurized water reactor fuel assembly upper nozzle 20 according to the present invention. The nozzle plate 31 has a substantially rectangular upper nozzle body 34 having a bowl-shaped top plate 32 on the inner peripheral surface of the upper end edge. The nozzle plate 31 has a large number of flowing water holes 31WH and thimble through holes 31SH. In FIG. 2, reference numeral 36 denotes a lock part provided at two corner rising parts of the upper nozzle body 34, and reference numeral 38 denotes a leaf spring (provided at the other two corner rising parts of the upper nozzle body 34). A screw hole into which a bolt for fixing the base of FIG. 1 (see reference numeral 18) is screwed, and reference numeral 40 denotes a slit provided in the top plate 32 into which a leg portion of each leaf spring (see reference numeral 18a in FIG. 1) enters. .

本発明の上部ノズル２０は、トッププレート３２によって発生する傾向があって制御棒に向かう水平方向の冷却材Ｃの流れを制御する冷却材流れ制御手段４２を備えている。図２及び図３の形態では、この冷却材流れ制御手段４２は、トッププレート３２に垂直方向に貫通して設けられた複数の流水孔４２Ａから成っている。   The upper nozzle 20 of the present invention includes coolant flow control means 42 that controls the flow of coolant C in the horizontal direction, which tends to be generated by the top plate 32 and toward the control rod. 2 and 3, the coolant flow control means 42 includes a plurality of water flow holes 42 </ b> A provided so as to penetrate the top plate 32 in the vertical direction.

このように、トッププレート３２に垂直流水孔４２Ａを設けると、燃料集合体１０内を上向きに流れる冷却材Ｃの大部分は、トッププレート３２によって水平方向に方向変換することなく、これらの流水孔４２Ａを経て上昇し、従って、制御棒（図６の符号１７参照）が冷却材Ｃの流れによって振動を受ける度合いが減少するので、制御棒案内シンブル（図１の符号１６参照）の摩耗量が低減し、燃料集合体１０の強度を低下することがない。   As described above, when the vertical flow holes 42A are provided in the top plate 32, most of the coolant C flowing upward in the fuel assembly 10 does not change the direction in the horizontal direction by the top plate 32, and these flow holes are formed. Therefore, the degree of wear of the control rod guide thimble (see reference numeral 16 in FIG. 1) is reduced because the degree to which the control rod (see reference numeral 17 in FIG. 6) is vibrated by the flow of the coolant C decreases. And the strength of the fuel assembly 10 is not lowered.

本発明の他の実施の形態が図３及び図４に示されている。図３の実施の形態では、冷却材流れ制御手段４２、トッププレート３２の内周面に設けられた複数の垂直スリット４２Ｂから成っており、また図４の形態では、冷却材流れ制御手段４２は、トッププレート３２の下側で上部ノズル本体３４の壁を水平方向に貫通する水平流水孔４２Ｃから成っている。   Another embodiment of the present invention is shown in FIGS. In the embodiment shown in FIG. 3, the coolant flow control means 42 and a plurality of vertical slits 42B provided on the inner peripheral surface of the top plate 32 are formed. In the embodiment shown in FIG. The horizontal flow hole 42 </ b> C penetrates the wall of the upper nozzle body 34 in the horizontal direction below the top plate 32.

図３及び図４の冷却材流れ制御手段４２も、図２の垂直流水孔４２Ａと同様に、冷却材Ｃの大部分を流水スリット４２Ｂ（図３）によって垂直方向に、また冷却材Ｃの相当部分を水平流水孔４２Ｃ（図４）を経て制御棒とは反対側に水平方向に逃し、従って、制御棒が冷却材Ｃの流れによって振動を受ける度合いを減少することができる。   The coolant flow control means 42 in FIG. 3 and FIG. 4 also has a large part of the coolant C in the vertical direction by the water flow slit 42B (FIG. 3) and the equivalent of the coolant C, similarly to the vertical water flow hole 42A in FIG. The portion is allowed to escape horizontally through the horizontal flow holes 42C (FIG. 4) to the opposite side of the control rod, thus reducing the degree to which the control rod is vibrated by the flow of coolant C.

本発明の更に他の実施の形態が図５に示されており、この実施の形態では、冷却材流れ制御手段４２は、トッププレート３２の内周部に冷却材を水平方向ではなく内周部に沿って上方に誘導するように丸みをもって面取りされた誘導面４２Ｄから成っている。   Still another embodiment of the present invention is shown in FIG. 5, in which the coolant flow control means 42 places the coolant on the inner periphery of the top plate 32 rather than in the horizontal direction. The guide surface 42D is rounded and chamfered so as to be guided upward along the line.

図５の冷却材流れ制御手段４２も、冷却材Ｃの大部分をトッププレート３２の内周の丸みを有する誘導面４２Ｄによって垂直方向に誘導するので、制御棒が冷却材Ｃの流れによって振動を受ける度合いを減少することができる。   The coolant flow control means 42 of FIG. 5 also guides most of the coolant C in the vertical direction by the guide surface 42D having the inner peripheral roundness of the top plate 32, so that the control rod vibrates due to the flow of the coolant C. The degree of receiving can be reduced.

本発明の燃料集合体上部ノズルによれば、制御棒が冷却材の流れによって振動を受ける度合いが減少し、従って制御棒案内シンブルの摩耗を低減して燃料集合体の強度の低下を抑制することができる。   According to the fuel assembly upper nozzle of the present invention, the degree to which the control rod is subjected to vibration due to the flow of the coolant is reduced, and therefore the wear of the control rod guide thimble is reduced and the decrease in the strength of the fuel assembly is suppressed. Can do.

本発明の上部ノズルが用いられた燃料集合体の正面図である。It is a front view of the fuel assembly in which the upper nozzle of the present invention is used. 本発明の１つの形態による燃料集合体上部ノズルを示し、同図（Ａ）は、上面図、同図（Ｂ）は、正面図である。The fuel assembly upper part nozzle by one form of the present invention is shown, the figure (A) is a top view and the figure (B) is a front view. 本発明の他の形態による燃料集合体上部ノズルの上面図である。FIG. 6 is a top view of a fuel assembly upper nozzle according to another embodiment of the present invention. 本発明の更に他の形態による燃料集合体上部ノズルの正面図である。It is a front view of the fuel assembly upper nozzle by the further another form of the present invention. 本発明の別の形態による燃料集合体上部ノズルの一部の拡大正面図である。FIG. 5 is an enlarged front view of a part of a fuel assembly upper nozzle according to another embodiment of the present invention. 従来技術による燃料集合体上部ノズルの正面図である。It is a front view of the fuel assembly upper nozzle by a prior art.

符号の説明Explanation of symbols

１０ 燃料集合体
１２ 支持格子
１４ 燃料棒
１６ 制御棒案内シンブル
１７ 制御棒
１８ リーフスプリング
１８ａ スプリング脚
２０ 上部ノズル
２２ 下部ノズル
３１ ノズルプレート
３１ＷＨ 流水孔
３１ＳＨ シンプル貫通孔
３２ トッププレート
３４ 上部ノズル本体
３６ ロック部
３８ スプリング固定用ボルト孔
４０ スリット
４２ 冷却材流れ制御手段
４２Ａ 垂直流水孔
４２Ｂ 流水スリット
４２Ｃ 水平流水孔
４２Ｄ 面取り誘導面
Ｃ 冷却材













































DESCRIPTION OF SYMBOLS 10 Fuel assembly 12 Support grid 14 Fuel rod 16 Control rod guide thimble 17 Control rod 18 Leaf spring 18a Spring leg 20 Upper nozzle 22 Lower nozzle 31 Nozzle plate 31WH Flow hole 31SH Simple through hole 32 Top plate 34 Upper nozzle main body 36 Lock part 38 Bolt hole for fixing spring 40 Slit 42 Coolant flow control means 42A Vertical flow hole 42B Flowing slit 42C Horizontal flow hole 42D Chamfering guide surface C Coolant













































Claims (4)

上部ノズル本体の上縁内周面にトッププレートを有する加圧水型原子炉用燃料集合体上部ノズルにおいて、前記トッププレートによって発生して制御棒に向かう冷却材の水平方向の流れを低減するように冷却材の流れを制御する冷却材流れ制御手段を備えたことを特徴とする加圧水型原子炉用燃料集合体上部ノズル。 In the upper nozzle of a pressurized water reactor fuel assembly having a top plate on the inner peripheral surface of the upper nozzle body, cooling is performed so as to reduce the horizontal flow of the coolant generated by the top plate and directed to the control rod. A fuel assembly upper nozzle for a pressurized water reactor, comprising a coolant flow control means for controlling a material flow. 請求項１に記載の加圧水型原子炉用燃料集合体上部ノズルであって、前記冷却材流れ制御手段は、前記トッププレートに垂直方向に貫通して設けられた複数の流水孔又は流水スリットから成っていることを特徴とする加圧水型原子炉用燃料集合体上部ノズル。 2. The fuel assembly upper nozzle of the pressurized water reactor according to claim 1, wherein the coolant flow control means includes a plurality of water flow holes or flow water slits that are vertically provided through the top plate. An upper nozzle for a fuel assembly for a pressurized water reactor, characterized in that 請求項１に記載の加圧水型原子炉用燃料集合体上部ノズルであって、前記冷却材流れ制御手段は、前記上部ノズル本体の前記トッププレートの下方側の壁部分を水平方向に貫通して設けられて前記トッププレートの下方で前記上部ノズル本体の外側に前記冷却材を誘導する流水孔から成っていることを特徴とする加圧水型原子炉用燃料集合体上部ノズル。 2. The fuel assembly upper nozzle of the pressurized water reactor according to claim 1, wherein the coolant flow control means is provided by horizontally penetrating a lower wall portion of the top plate of the upper nozzle body. An upper nozzle for a fuel assembly for a pressurized water reactor, wherein the upper nozzle body comprises a water flow hole for guiding the coolant to the outside of the upper nozzle body below the top plate. 請求項１に記載の加圧水型原子炉用燃料集合体上部ノズルであって、前記冷却材流れ制御手段は、前記トッププレートの内周部に前記冷却材を水平方向ではなく前記内周部に沿って上方に誘導する丸みを有する誘導面から成っていることを特徴とする加圧水型原子炉用燃料集合体上部ノズル。




























2. The pressurized water reactor fuel assembly upper nozzle according to claim 1, wherein the coolant flow control means moves the coolant to the inner peripheral portion of the top plate along the inner peripheral portion instead of horizontally. 3. An upper nozzle for a fuel assembly for a pressurized water reactor, characterized by comprising a guiding surface having a roundness that is guided upward.




























JP2004023160A 2004-01-30 2004-01-30 Fuel assembly upper nozzle for pressurized water reactors Expired - Fee Related JP4532127B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP2004023160A JP4532127B2 (en) 2004-01-30 2004-01-30 Fuel assembly upper nozzle for pressurized water reactors

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP2004023160A JP4532127B2 (en) 2004-01-30 2004-01-30 Fuel assembly upper nozzle for pressurized water reactors

Related Child Applications (1)

Application Number Title Priority Date Filing Date
JP2009236343A Division JP2010044086A (en) 2009-10-13 2009-10-13 Fuel assembly upper nozzle for pressurized water reactor

Publications (2)

Publication Number Publication Date
JP2005214838A true JP2005214838A (en) 2005-08-11
JP4532127B2 JP4532127B2 (en) 2010-08-25

Family

ID=34906278

Family Applications (1)

Application Number Title Priority Date Filing Date
JP2004023160A Expired - Fee Related JP4532127B2 (en) 2004-01-30 2004-01-30 Fuel assembly upper nozzle for pressurized water reactors

Country Status (1)

Country Link
JP (1) JP4532127B2 (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP1986197A4 (en) * 2006-02-17 2011-03-30 Mitsubishi Heavy Ind Ltd Pwr reactor fuel assembly
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

Families Citing this family (1)

* Cited by examiner, † Cited by third party
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

Citations (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS58123494A (en) * 1982-01-18 1983-07-22 コミツサレ・ア・レナジイ・アトミツク End fitting for nuclear fuel assembly
US4618472A (en) * 1983-10-25 1986-10-21 Westinghouse Electric Corp. Nuclear reactor fuel assembly with fuel rod removal means
JPS62189697U (en) * 1986-05-23 1987-12-02
JPS63293492A (en) * 1987-05-13 1988-11-30 ウエスチングハウス・エレクトリック・コーポレーション Nuclear reactor fuel aggregate
JPH0290096A (en) * 1988-09-28 1990-03-29 Hitachi Ltd Light water reactor fuel assembly
JPH036492A (en) * 1989-05-17 1991-01-11 Westinghouse Electric Corp <We> Upper nozzle sub-assembly of nuclear fuel aggregate
JPH03255390A (en) * 1990-03-05 1991-11-14 Nuclear Fuel Ind Ltd Upper nozzle for nuclear fuel assembly
JPH08271663A (en) * 1995-03-28 1996-10-18 Nuclear Fuel Ind Ltd Low pressure loss type upper tie plate of fuel assembly for boiling water reactor

Patent Citations (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS58123494A (en) * 1982-01-18 1983-07-22 コミツサレ・ア・レナジイ・アトミツク End fitting for nuclear fuel assembly
US4618472A (en) * 1983-10-25 1986-10-21 Westinghouse Electric Corp. Nuclear reactor fuel assembly with fuel rod removal means
JPS62189697U (en) * 1986-05-23 1987-12-02
JPS63293492A (en) * 1987-05-13 1988-11-30 ウエスチングハウス・エレクトリック・コーポレーション Nuclear reactor fuel aggregate
JPH0290096A (en) * 1988-09-28 1990-03-29 Hitachi Ltd Light water reactor fuel assembly
JPH036492A (en) * 1989-05-17 1991-01-11 Westinghouse Electric Corp <We> Upper nozzle sub-assembly of nuclear fuel aggregate
JPH03255390A (en) * 1990-03-05 1991-11-14 Nuclear Fuel Ind Ltd Upper nozzle for nuclear fuel assembly
JPH08271663A (en) * 1995-03-28 1996-10-18 Nuclear Fuel Ind Ltd Low pressure loss type upper tie plate of fuel assembly for boiling water reactor

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP1986197A4 (en) * 2006-02-17 2011-03-30 Mitsubishi Heavy Ind Ltd Pwr reactor fuel assembly
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

Also Published As

Publication number Publication date
JP4532127B2 (en) 2010-08-25

Similar Documents

Publication Publication Date Title
JP2008157942A (en) Fuel support fitting and method for adjusting coolant flow in a nuclear reactor
US20150187445A1 (en) Burnable absorber-integrated control rod guide thimble
JP2005214838A (en) Upper nozzle of fuel assembly for pressurized water reactor
JP3859016B2 (en) Nuclear fuel assembly with improved top nozzle
JP2010044086A (en) Fuel assembly upper nozzle for pressurized water reactor
KR100844469B1 (en) Apparatus for falling shock absorption of control rod of nuclear reactor
US9171647B2 (en) Spacer grid for nuclear fuel assembly for reducing flow-induced vibration
US4933137A (en) Nuclear fuel assembly with means for retarding detector tube wear
EP0169421A2 (en) Control rod for a nuclear reactor
JPH08114691A (en) Fuel assembly of boiling water reactor
JP2021520491A (en) Reactor and corresponding maintenance method
KR100956763B1 (en) Reverse conical lower end cap of dual cooled nuclear fuel rods
US9196386B2 (en) Spacer grid for nuclear fuel assembly for reducing high frequency vibration
US5132077A (en) Lower end fitting
JP5031665B2 (en) Boiling water reactor fuel assembly to prevent abnormal landing
JP4351782B2 (en) Fuel assembly
KR101057540B1 (en) Superstructure of Integral Reactor
US9484118B2 (en) BWR nuclear fuel assembly with non-retained partial length fuel rods
JP2014066582A (en) Nuclear fuel assembly for pressurized water reactor and lower nozzle used therein
CN221940772U (en) Crochet machine needle bed assembly and crochet machine
CN219603820U (en) Supporting device for electric control circuit trunking of water-jet loom
JPS61200494A (en) flow control thimble tube
CN212535907U (en) Ignition coil assembly for gas generator and gas generator
CN210765437U (en) Cable copper line annealing stove
JP2003248078A (en) Fuel assembly for nuclear reactor

Legal Events

Date Code Title Description
A621 Written request for application examination

Free format text: JAPANESE INTERMEDIATE CODE: A621

Effective date: 20060120

A977 Report on retrieval

Free format text: JAPANESE INTERMEDIATE CODE: A971007

Effective date: 20081020

A131 Notification of reasons for refusal

Free format text: JAPANESE INTERMEDIATE CODE: A131

Effective date: 20090324

A521 Written amendment

Free format text: JAPANESE INTERMEDIATE CODE: A523

Effective date: 20090525

A131 Notification of reasons for refusal

Free format text: JAPANESE INTERMEDIATE CODE: A131

Effective date: 20090811

A521 Written amendment

Free format text: JAPANESE INTERMEDIATE CODE: A523

Effective date: 20091013

A02 Decision of refusal

Free format text: JAPANESE INTERMEDIATE CODE: A02

Effective date: 20091208

A521 Written amendment

Free format text: JAPANESE INTERMEDIATE CODE: A523

Effective date: 20100308

A911 Transfer of reconsideration by examiner before appeal (zenchi)

Free format text: JAPANESE INTERMEDIATE CODE: A911

Effective date: 20100316

TRDD Decision of grant or rejection written
A01 Written decision to grant a patent or to grant a registration (utility model)

Free format text: JAPANESE INTERMEDIATE CODE: A01

Effective date: 20100608

A01 Written decision to grant a patent or to grant a registration (utility model)

Free format text: JAPANESE INTERMEDIATE CODE: A01

A61 First payment of annual fees (during grant procedure)

Free format text: JAPANESE INTERMEDIATE CODE: A61

Effective date: 20100610

R150 Certificate of patent or registration of utility model

Free format text: JAPANESE INTERMEDIATE CODE: R150

FPAY Renewal fee payment (event date is renewal date of database)

Free format text: PAYMENT UNTIL: 20130618

Year of fee payment: 3

LAPS Cancellation because of no payment of annual fees