JPH02195295A - Atomic fuel assembly - Google Patents

Atomic fuel assembly

Info

Publication number
JPH02195295A
JPH02195295A JP1015535A JP1553589A JPH02195295A JP H02195295 A JPH02195295 A JP H02195295A JP 1015535 A JP1015535 A JP 1015535A JP 1553589 A JP1553589 A JP 1553589A JP H02195295 A JPH02195295 A JP H02195295A
Authority
JP
Japan
Prior art keywords
plate
nozzle
fuel assembly
nozzle frame
frame
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
JP1015535A
Other languages
Japanese (ja)
Inventor
Kazuma Mori
森 一麻
Tatsuaki Nakamura
中村 辰昭
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 JP1015535A priority Critical patent/JPH02195295A/en
Publication of JPH02195295A publication Critical patent/JPH02195295A/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

  • Fuel-Injection Apparatus (AREA)

Abstract

PURPOSE:To secure mechanical soundness by a construction wherein a plate and a nozzle frame are formed separately from each other and the plate is made movable only in the upward direction in relation to the nozzle frame, while a hold-down spring is incorporated between the plate and the nozzle frame. CONSTITUTION:A plate 11 has water flow holes 14 joining the upper part of a control rod guide tube 2, and although it is similar to a conventional nozzle plate in respect that it provides a flow channel for a coolant, it is formed as a body separate from a nozzle plate 12 and, accordingly, has a structure of making it movable only in the upward direction in relation to an upper nozzle frame 12. The upper nozzle frame 12 has engaging elements 12a, and springs 13 are engaged with spring fasteners on the lower side and with said engaging elements 12a on the upper side and thus incorporated in a state wherein they alternate on the two sides of an upper nozzle being opposite to each other. By making the nozzle plate movable in relation to the nozzle frame in this way, a change in elongation of a fuel assembly can be absorbed to a large extent.

Description

【発明の詳細な説明】 (産業上の利用分野) 本発明は原子燃料集合体、特に加圧木型原子炉用燃料集
合体に係り、詳しくは、高燃焼化度炉心に求められる高
燃焼時の機械的健全性を保障する上記燃料集合体に関す
るものである。
Detailed Description of the Invention (Industrial Field of Application) The present invention relates to a nuclear fuel assembly, particularly a fuel assembly for a pressurized wooden nuclear reactor. The present invention relates to the above-mentioned fuel assembly that ensures the mechanical integrity of the fuel assembly.

(従来の技術) 従来の加圧水型原子炉用燃料集合体は第4図に示す如く
多数の燃料棒(1)を並列し、かつ制御棒案内管(2)
などを混入して複数の支持格子(3)で支持せしめた燃
料支持部と、それを固定する上下部ノズル(41,(5
)から構成されており、上部ノズル(4)には上部炉心
板に抗して原子炉運転中の流体力による同集合体の浮き
上がりを防止するために押さえばね(ホールドダウンス
プリング)(6)が四辺に取り付けられている。
(Prior Art) A conventional fuel assembly for a pressurized water reactor has a large number of fuel rods (1) arranged in parallel as shown in Fig. 4, and a control rod guide pipe (2).
The fuel support part is supported by a plurality of support grids (3), and the upper and lower nozzles (41, (5)
), and a hold-down spring (6) is installed in the upper nozzle (4) to prevent the assembly from floating up due to fluid force during reactor operation against the upper core plate. attached on all four sides.

ところで、近時、原子力発電の経済性向上を自損して燃
料の改良研究が進められており、運転サイクルの長さを
延長する高燃焼度化炉心はその有効な方策として注目さ
れているが、このように燃料を高燃焼度まで使用する場
合の問題に燃料集合体の伸び量の増加の問題がある。
By the way, recently, research has been carried out to improve fuels at the expense of improving the economic efficiency of nuclear power generation, and high burnup reactor cores that extend the length of the operating cycle are attracting attention as an effective measure. A problem when using fuel to a high burnup as described above is that the amount of elongation of the fuel assembly increases.

即ち、燃料集合体において燃料棒被覆管や制御棒案内管
が燃料の燃焼中に中性子照射によって軸方向に伸びた結
果、燃料集合体の全長が増加する。
That is, as a result of the fuel rod cladding tubes and control rod guide tubes in the fuel assembly being elongated in the axial direction by neutron irradiation during fuel combustion, the overall length of the fuel assembly increases.

この全長の増加量、即ち、伸び量は燃料の燃焼度に依存
し燃料度が増加するとこの伸び量も増加する。この結果
、集合体全長の伸び量だけ集合体上部と上部炉心板の距
離は短くなる。
The amount of increase in the total length, that is, the amount of elongation depends on the burnup of the fuel, and as the fuel burnup increases, the amount of elongation also increases. As a result, the distance between the upper part of the assembly and the upper core plate becomes shorter by the amount of elongation of the overall length of the assembly.

そこで集合体の伸び量が増加すると前述した燃料集合体
上部ノズルのホールドダウンスプリングの変位量も大き
くなる。さらに原子炉停止時には原子炉温度低下によっ
て炉心寸法が小さくなり、燃料集合体上部と上部炉心板
の距離は更に小さくなり、その結果、ホールドダウンス
プリングに要求される許容変位量はさらに太き(なる。
Therefore, as the amount of elongation of the assembly increases, the amount of displacement of the hold-down spring of the upper nozzle of the fuel assembly described above also increases. Furthermore, when the reactor is shut down, the reactor temperature decreases and the core dimensions become smaller, and the distance between the upper part of the fuel assembly and the upper core plate becomes even smaller.As a result, the permissible displacement required for the hold-down spring becomes wider ( .

(発明が解決しようとする課題) しかし、前述した従来の燃料集合体の場合、そのホール
ドダウンスプリングには特に上記の如き燃料の高燃焼度
化に対する対策は充分でなく、従って、燃料集合体の伸
びが大きくなりすぎると、このスプリングは強く押圧さ
れて変形し、ばね力を失うのみならず、ばねとしての撓
みも小さくなって本来のホールドダウン機能が損なわれ
て了うという問題がある。
(Problem to be Solved by the Invention) However, in the case of the conventional fuel assembly described above, the hold-down spring does not have sufficient countermeasures especially for the above-mentioned high burnup of the fuel, and therefore the fuel assembly If the elongation becomes too large, this spring will not only be strongly pressed and deformed and lose its spring force, but also have a problem in that its deflection as a spring will become small and its original hold-down function will be impaired.

そこで、これに対処し燃料の高燃焼度化を考慮し、燃料
集合体の伸びに対する改善策として構造部材である上、
下部ノズルの高さ方向寸法を小さくすることが考えられ
るが、この手段は強度が低下するため、詳細な応力解析
を実施するとか、強度の高い材料を採用するとの点を考
える必要があり、またいずれにせよ、寸法を小さくでき
る量に限りがあって余り得策ではない。
Therefore, in order to deal with this and consider increasing the burnup of the fuel, as a measure to improve the elongation of the fuel assembly, in addition to being a structural member,
It is possible to reduce the height dimension of the lower nozzle, but this method reduces the strength, so it is necessary to consider carrying out detailed stress analysis or using a material with high strength. In any case, there is a limit to how much the size can be reduced, so it is not a good idea.

また、一方、上部ノズルのノズルプレートを可動とする
型にあって、制御棒案内管上部のまわりにスプリングを
入れて上部ノズル全体と制御棒案内管を相対的に可動す
る設計が行われているが(GE社)、これは制御棒案内
管が多い燃料タイプに採用するのは困難である。何故な
らばスプリングの径は大きくなり数が多いと互いに干渉
を起こすことになるからである。
On the other hand, in a type in which the nozzle plate of the upper nozzle is movable, a spring is inserted around the upper part of the control rod guide tube so that the entire upper nozzle and the control rod guide tube can be moved relative to each other. (GE), but it is difficult to adopt this for fuel types that have many control rod guide tubes. This is because the diameter of the springs becomes large and if there are many springs, they will interfere with each other.

かくて、本発明は上述の如き点に着目し、更にその改善
を図り、高燃焼度化炉心における燃料集合体の伸びによ
ってホールドダウンスプリングのホールドダウン機能が
損なわれ難いようなホールドダウンスプリング形式の燃
料集合体を提供することを目的とするものである。
Thus, the present invention focuses on the above-mentioned points and aims to further improve them, and provides a hold-down spring type in which the hold-down function of the hold-down spring is unlikely to be impaired by the elongation of the fuel assembly in a high-burnup core. The purpose is to provide fuel assemblies.

(課題を解決するための手段) 即ち、上記目的に適合するため、本発明燃料集合体はそ
の特徴として、前記原子燃料集合体の上部ノズルのプレ
ートとノズル枠を別体としてプレートが上方向にのみ可
動し得るようにし、かつ上部ノズル頂部にホールドダウ
ンスプリングを設ける代わりに上部ノズルの枠の中にホ
ールドダウンスプリングを組み込んでスプリングのばね
しろを大きくし、燃料集合体の伸びに対して、より大き
な弾性域を確保できるようにしている。
(Means for Solving the Problem) That is, in order to meet the above object, the fuel assembly of the present invention is characterized in that the plate and nozzle frame of the upper nozzle of the nuclear fuel assembly are separated, and the plate is oriented upward. In addition, instead of installing a hold-down spring at the top of the upper nozzle, a hold-down spring is built into the frame of the upper nozzle to increase the spring margin of the upper nozzle. This ensures a large elastic range.

(作用) 上記の如く構成することにより燃料集合体の伸びに対し
て上部ノズル全体が従来同様上方へ移行する外、プレー
トが更に上方へ移行し、スプリングを押圧して従来に比
し、より多くの伸びを吸収することになり、従来のリー
フスプリングを取り付けたものより全体として可動寸法
が大きく、従って高燃焼度の使用においても、スプリン
グの破損、ひいては燃料集合体の破損を防止する。
(Function) By configuring as above, the entire upper nozzle moves upward as the fuel assembly expands, as before, but the plate moves further upwards, pressing the spring and increasing the The overall movable dimension is larger than that of conventional leaf springs, and therefore, even in high burn-up applications, damage to the springs and, ultimately, to the fuel assembly is prevented.

(実施例) 以下、添付図面を参照し、本発明の詳細な説明する。(Example) Hereinafter, the present invention will be described in detail with reference to the accompanying drawings.

第1図ないし第3図は本発明に係る燃料集合体の上部ノ
ズル(4)の構成を示しており、図においてαυはプレ
ート、亜は上部ノズル枠、θ咄よホールドダウンスプリ
ングで、プレートQυは制御棒案内管(2)上部と結合
する流水孔0句を有しており、冷却材の流路となる点で
は従来のノズルプレートと同様であるが、本発明ではノ
ズル枠(2)と別体として形成され、従って、該プレー
トQDは上部ノズル枠(2)に対し上方向へのみ可動な
構造となっている。
Figures 1 to 3 show the structure of the upper nozzle (4) of the fuel assembly according to the present invention. has a water flow hole that connects to the upper part of the control rod guide tube (2), and is similar to a conventional nozzle plate in that it serves as a flow path for the coolant, but in the present invention, the nozzle frame (2) and The plate QD is formed as a separate body, so that the plate QD is movable only upwardly with respect to the upper nozzle frame (2).

そして、上部ノズル枠(2)には上部に集合体吊上げ時
、吊具(図示せず)が係止する係止部(12a)があり
、上部ノズルの互いに対向する二辺において互いに交叉
する状態で前記スプリングa1が下部はスプリング止め
具aSにより、一方、上部は前記係止部(12a)に係
止されて組み込まれている。
The upper nozzle frame (2) has a locking part (12a) at the top where a hanging tool (not shown) locks when lifting the assembly, and the upper nozzle has a locking part (12a) that intersects with each other on two opposing sides. The spring a1 is assembled so that the lower part thereof is engaged with the spring stopper aS, and the upper part thereof is engaged with the engaging part (12a).

そのため、集合体吊上げ時には上記係止部(12a)を
利用して吊上げが行なわれるが、下方向へはプレートα
Dが下がるため(但し、上部ノズル最下端まで)スプリ
ングa3には何らの悪影響はない。
Therefore, when lifting the assembly, the above-mentioned locking part (12a) is used to lift the assembly, but the plate α
Since D is lowered (up to the lowest end of the upper nozzle), there is no adverse effect on the spring a3.

なお、上記スプリングαjとしては図示の如くリーフス
プリングが好ましいが、上部ノズルのコーナーにコイル
スプリングを取り付けるようにしてもよく、要はプレー
トaυの上方向へのみの可動と、スプリングa1による
弾性とを結合することが肝要である。
As shown in the figure, a leaf spring is preferable as the spring αj, but a coil spring may be attached to the corner of the upper nozzle. It is essential to bond.

かくて、この場合には、従来の上部ノズルにおけるリー
フスプリング取付は構造が第5図の(A1)の範囲を可
動寸法とするのに対しくA++Az)の範囲を基本的に
可動寸法とすることになり(図中、Dの寸法が略それに
相当)集合体の伸び変化の吸収がより大となる。
Therefore, in this case, the structure of the conventional leaf spring installation in the upper nozzle has a movable dimension in the range (A1) in Fig. 5, but the movable dimension is basically in the range A++Az). (the dimension D in the figure approximately corresponds to this), the absorption of changes in the elongation of the aggregate becomes greater.

以上の説明は本発明の要部の1例であり、勿論、その目
的を逸脱しない限り適宜、変形が可能であることは云う
までもない。
The above description is just one example of the essential parts of the present invention, and it goes without saying that modifications can be made as appropriate without departing from the purpose thereof.

(発明の効果) 本発明は以上のように原子燃料集合体の構成部品である
上部ノズルにおいて、プレートとノズル枠を別体として
プレートをノズル枠に対し上方向へのみ可動可能とする
と共に、プレートとノズル枠との間にホールドダウンス
プリングを組み込み介設せしめた構成であり、従来の燃
料集合体が、上部ノズル全体と制御棒案内管とを相対的
に可動とするのみであるのに対し更にノズルプレートを
ノズル枠に対し可動として全体の可動範囲を大ならしめ
、従って弾性域をより大きく確保し、燃料集合体の伸び
変化を大きく吸収することができる効用を奏して高燃焼
度化炉心に求められるスプリングの許容変位量の大きさ
に対応し、高燃焼度時の機械的健全性を保障する顕著な
効果を有している。
(Effects of the Invention) As described above, the present invention provides an upper nozzle that is a component of a nuclear fuel assembly by separating the plate and the nozzle frame so that the plate is movable only upwardly with respect to the nozzle frame. This structure incorporates a hold-down spring between the nozzle frame and the nozzle frame. By making the nozzle plate movable relative to the nozzle frame, the overall movable range is expanded, thereby securing a larger elastic range, and it is effective in absorbing changes in the elongation of the fuel assembly, resulting in a high burnup core. It corresponds to the required allowable displacement of the spring and has a remarkable effect of ensuring mechanical soundness at high burnup.

しかも上部ノズル枠上部の集合体吊上げ時の係止部は従
来通りとすることができるので特に吊具を変更する必要
はなく、極めて実用的である。
Moreover, since the locking portion at the upper part of the upper nozzle frame for lifting the assembly can be the same as before, there is no need to change the hanging tool, which is extremely practical.

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

第1図は本発明燃料集合体の要部に係る上部ノズルの平
面図、第2図は第1図上部ノズルの正面図、第3図は同
じく第1図上部ノズルの右側面図第4図は燃料集合体の
一部省略全体概要図、第5図は第4図の上部ノズル部拡
大図である。 (11・・・燃料棒、 (2)・・・制御棒案内管、 (3)・・・支持格子、 (4)・・・上部ノズル、 (5)・・・下部ノズル、 αυ・・・プレート、 (2)・・・上部ノズル枠、 Q3)・・・ホールドダウンスプリング。
FIG. 1 is a plan view of the upper nozzle related to the main part of the fuel assembly of the present invention, FIG. 2 is a front view of the upper nozzle shown in FIG. 1, and FIG. 3 is a right side view of the upper nozzle shown in FIG. 1. 5 is a partially omitted overall schematic view of the fuel assembly, and FIG. 5 is an enlarged view of the upper nozzle portion of FIG. 4. (11...Fuel rod, (2)...Control rod guide tube, (3)...Support grid, (4)...Upper nozzle, (5)...Lower nozzle, αυ... Plate, (2)... Upper nozzle frame, Q3)... Hold down spring.

Claims (1)

【特許請求の範囲】[Claims] 1、多数の燃料棒を並列し、かつ制御棒案内管などを混
入して複数の支持格子で支持せしめた燃料支持部と、そ
れを固定する上下部ノズルからなる原子燃料集合体にお
いて、上記上部ノズルのプレートとノズル枠を別体で形
成し、プレートをノズル枠に対し上方向へのみ可動可能
とすると共にプレートと上記ノズル枠との間にホールド
ダウンスプリングを組み込み構成してなることを特徴と
する原子燃料集合体。
1. In a nuclear fuel assembly consisting of a fuel support section in which a large number of fuel rods are arranged in parallel and control rod guide tubes are mixed in and supported by a plurality of support grids, and upper and lower nozzles that fix it, the above-mentioned upper The nozzle plate and nozzle frame are formed separately, the plate is movable only upwardly relative to the nozzle frame, and a hold-down spring is incorporated between the plate and the nozzle frame. nuclear fuel assembly.
JP1015535A 1989-01-25 1989-01-25 Atomic fuel assembly Pending JPH02195295A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP1015535A JPH02195295A (en) 1989-01-25 1989-01-25 Atomic fuel assembly

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP1015535A JPH02195295A (en) 1989-01-25 1989-01-25 Atomic fuel assembly

Publications (1)

Publication Number Publication Date
JPH02195295A true JPH02195295A (en) 1990-08-01

Family

ID=11891503

Family Applications (1)

Application Number Title Priority Date Filing Date
JP1015535A Pending JPH02195295A (en) 1989-01-25 1989-01-25 Atomic fuel assembly

Country Status (1)

Country Link
JP (1) JPH02195295A (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH02221893A (en) * 1989-02-21 1990-09-04 Mitsubishi Nuclear Fuel Co Ltd Hold-down assembly
WO1994000848A1 (en) * 1992-06-29 1994-01-06 Siemens Aktiengesellschaft Nuclear reactor fuel rod bundle with lockable head
US6154514A (en) * 1997-06-10 2000-11-28 Mitsubishi Heavy Industries, Ltd. Nuclear reaction fuel assembly for a nuclear reactor fuel assembly

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH02221893A (en) * 1989-02-21 1990-09-04 Mitsubishi Nuclear Fuel Co Ltd Hold-down assembly
WO1994000848A1 (en) * 1992-06-29 1994-01-06 Siemens Aktiengesellschaft Nuclear reactor fuel rod bundle with lockable head
US6154514A (en) * 1997-06-10 2000-11-28 Mitsubishi Heavy Industries, Ltd. Nuclear reaction fuel assembly for a nuclear reactor fuel assembly

Similar Documents

Publication Publication Date Title
US4544522A (en) Nuclear fuel assembly spacer
US4357298A (en) Nuclear fuel assembly space arrangement
US5966419A (en) Spacing grid of a fuel assembly for a nuclear reactor and fuel assembly
US6421407B1 (en) Nuclear fuel spacer grid with dipper vanes
JPH08179070A (en) Fuel assembly for pressurised water reactor
US3338791A (en) Reactor device
JPH0545196B2 (en)
US8483348B2 (en) Method of providing a hold-down force upon a nuclear fuel assembly
US5625657A (en) Method of repairing a nuclear fuel rod assembly with damaged fuel rod and a damaged spacer
JPS61191990A (en) Fuel aggregate for nuclear reactor
CA1075382A (en) Holddown device for nuclear fuel assembly
US11120918B2 (en) Nuclear fuel assembly debris filtering bottom nozzle
CA2078809A1 (en) Spacer sleeve for nuclear fuel assembly
KR100892638B1 (en) Top nozzle assembly having on-off holddown spring in nuclear fuel assembly
JP4895814B2 (en) Nuclear fuel assemblies with lattice reinforcement devices and use of such devices in nuclear fuel assemblies
US6744843B2 (en) Side-slotted nozzle type double sheet spacer grid for nuclear fuel assemblies
JPH02195295A (en) Atomic fuel assembly
JP3108189B2 (en) Top nozzle of nuclear fuel assembly
JPS623691A (en) Fuel aggregate
JPS63235890A (en) Fuel aggregate
JP2569119B2 (en) Fuel assembly
WO2018021044A1 (en) Boiling-water reactor reactor-core
JPH08313667A (en) Reactor fuel assembly and nuclear fuel rod therefor
JPH0566553B2 (en)
JPH06249986A (en) Fuel assembly for pressurized water reactor