JPH11133177A - Nuclear reactor fuel assembly - Google Patents
Nuclear reactor fuel assemblyInfo
- Publication number
- JPH11133177A JPH11133177A JP9292429A JP29242997A JPH11133177A JP H11133177 A JPH11133177 A JP H11133177A JP 9292429 A JP9292429 A JP 9292429A JP 29242997 A JP29242997 A JP 29242997A JP H11133177 A JPH11133177 A JP H11133177A
- Authority
- JP
- Japan
- Prior art keywords
- control rod
- rod guide
- fuel assembly
- control
- guide tube
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Withdrawn
Links
- 239000003758 nuclear fuel Substances 0.000 title claims description 4
- 239000000446 fuel Substances 0.000 claims abstract description 26
- 239000002826 coolant Substances 0.000 claims abstract description 6
- 230000002093 peripheral effect Effects 0.000 claims description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 abstract description 6
- 230000037431 insertion Effects 0.000 abstract description 2
- 238000003780 insertion Methods 0.000 abstract description 2
- 238000002485 combustion reaction Methods 0.000 description 4
- 238000005452 bending Methods 0.000 description 3
- 238000010586 diagram Methods 0.000 description 2
- 238000006243 chemical reaction Methods 0.000 description 1
- 238000010248 power generation Methods 0.000 description 1
- 238000003466 welding Methods 0.000 description 1
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、原子炉において燃
焼に供される燃料集合体に関し、特に加圧水型原子炉用
の燃料集合体における制御棒案内管の取り付け構造に関
する。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a fuel assembly for combustion in a nuclear reactor, and more particularly, to a control rod guide tube mounting structure in a fuel assembly for a pressurized water reactor.
【0002】[0002]
【従来の技術】現在広く発電用として使用されている加
圧水型原子炉においては、一般に細い制御棒をクラスタ
状に組み立てた制御棒組立体いわゆる制御棒クラスタを
使用して炉内核反応を制御することとしている。従っ
て、原子炉炉心を構成する燃料集合体も、その細い制御
棒を受け入れて案内するための管いわゆる制御棒案内管
を含んで構成されている。その燃料集合体の一般的な構
造を概説すれば、次のようになる。即ち、原子炉燃料集
合体は、多数の冷却材貫流口を備え間隔をおいて互いに
対向した上部ノズル及び下部ノズルと、これら両ノズル
間に互いに平行に延び両端が該両ノズルにそれぞれ連結
される複数の制御棒案内管と、この制御棒案内管に沿っ
て間隔をおいて配設された複数の支持格子と、この支持
格子の格子開口に挿通されて支持される複数の燃料棒と
から構成される。そして、運転中に制御棒が冷却材励起
振動をできるだけ受けないようにすること、制御棒の緊
急挿入時(落下時)に衝撃荷重を小さくすることなどの
目的で、制御棒と制御棒案内管の半径方向間隔は大体に
おいて小さく設定されている。又、複数ある支持格子
は、制御棒案内管にバルジ加工や溶接などを利用して固
定されているが、最下段支持格子は図5に示すような状
態で取り付けられている。2. Description of the Related Art In a pressurized water reactor which is currently widely used for power generation, a control rod assembly in which thin control rods are assembled in a cluster shape, a so-called control rod cluster, is used to control the nuclear reaction in the reactor. And Therefore, the fuel assembly constituting the reactor core also includes a tube for receiving and guiding the thin control rod, that is, a control rod guide tube. An outline of the general structure of the fuel assembly is as follows. That is, the reactor fuel assembly has an upper nozzle and a lower nozzle which are provided with a plurality of coolant flow-through ports and are opposed to each other at intervals, and which extend in parallel between these two nozzles and both ends are respectively connected to the two nozzles. It comprises a plurality of control rod guide tubes, a plurality of support lattices arranged at intervals along the control rod guide tubes, and a plurality of fuel rods inserted and supported in the lattice openings of the support lattice. Is done. The control rod and the control rod guide tube are used for the purpose of preventing the control rod from being subjected to coolant-induced vibration during operation as much as possible, and reducing the impact load when the control rod is urgently inserted (when it falls). Are generally set to be small. The plurality of support grids are fixed to the control rod guide tube by using bulging or welding, while the lowermost support grid is mounted in a state as shown in FIG.
【0003】図5は概念的な構造を示しているが、下部
ノズル1に図示しない取り付けボルト等を介して制御棒
案内管3の下端が固定される。そして、制御棒案内管3
の下端部を取り囲む筒状連結部材いわゆるインサート5
が最下段支持格子7を連結支持している。FIG. 5 shows a conceptual structure, in which a lower end of a control rod guide tube 3 is fixed to a lower nozzle 1 via an unillustrated mounting bolt or the like. And the control rod guide tube 3
Cylindrical connecting member surrounding the lower end of the so-called insert 5
Connect and support the lowermost support grid 7.
【0004】[0004]
【発明が解決しようとする課題】而して、燃料集合体
は、必ずしも全域で一様な中性子照射を受けるわけでも
なく、例えば炉心中央側に面する部分と炉心外周側に面
した部分ではわずかに異なり、従って燃焼が進んで行く
と、ボーイング等と称する撓みが発生してくる。この状
況を説明のためかなり誇張して示した図が図6である。
この概念図では、燃料棒は示されていないが、燃料集合
体の曲げ変形により最下段支持格子7と他の支持格子9
が正規位置から横方向に変位し、制御棒案内管3も全体
として弓形に曲がっているが、下端部は前述のインサー
トに拘束されている。一方、制御棒も前述のように極め
て細い棒体であるので、全体的な曲げ変形には追従しや
すい性質を持っている。しかしながら、前述の制御棒案
内管3の下端部のように変形に特異点があると図7に示
すように、制御棒案内管3と内部の制御棒8との間に干
渉が生じ、その挿入性を阻害する。尚、図7も説明のた
めかなり誇張したものとなっている。従って、本発明の
課題は、燃焼が進んで燃料集合体に変形が生じても、制
御棒の円滑挿入性を確保できる構造の燃料集合体を提供
することである。However, the fuel assembly is not necessarily subjected to uniform neutron irradiation over the entire area. For example, a portion facing the center of the core and a portion facing the outer periphery of the core are slightly irradiated. Therefore, as combustion proceeds, a deflection called bowing or the like occurs. FIG. 6 shows this situation in an exaggerated manner for explanation.
Although the fuel rods are not shown in this conceptual diagram, the lowermost support grid 7 and other support grids 9 are bent due to bending deformation of the fuel assembly.
Are displaced laterally from the normal position, and the control rod guide tube 3 is also bowed as a whole, but the lower end is restrained by the above-mentioned insert. On the other hand, since the control rod is also a very thin rod as described above, it has a property of easily following the entire bending deformation. However, if there is a singular point in the deformation, such as the lower end of the control rod guide tube 3, the interference occurs between the control rod guide tube 3 and the internal control rod 8, as shown in FIG. Inhibits sex. FIG. 7 is also greatly exaggerated for explanation. Accordingly, an object of the present invention is to provide a fuel assembly having a structure that can ensure smooth insertion of control rods even when the fuel assembly is deformed due to progress of combustion.
【0005】[0005]
【課題を解決するための手段】如上の課題を解決するた
め、本発明によれば、多数の冷却材貫流口を備え間隔を
おいて互いに対向した上部ノズル及び下部ノズルと、こ
れら両ノズル間に互いに平行に延び両端が該両ノズルに
それぞれ連結される複数の制御棒案内管と、この制御棒
案内管に沿って間隔をおいて配設され最下段支持格子を
含む複数の支持格子と、その支持格子の格子開口に挿通
されて支持される複数の燃料棒を有する原子炉燃料集合
体において、下部ノズルに固定され制御棒案内管の下端
部を取り囲んで延びる最下段支持格子取り付け用インサ
ートの内周面に上端部を残して環状の凹みを形成してい
る。According to the present invention, there is provided, in accordance with the present invention, an upper nozzle and a lower nozzle which are provided with a plurality of coolant through-holes and which are opposed to each other at intervals. A plurality of control rod guide tubes extending parallel to each other and having both ends connected to the nozzles; a plurality of support lattices including a lowermost support lattice disposed at intervals along the control rod guide tubes; In a reactor fuel assembly having a plurality of fuel rods inserted through and supported by a grid opening of a support grid, a lowermost support grid mounting insert fixed to a lower nozzle and extending around a lower end of a control rod guide tube. An annular recess is formed on the peripheral surface except for the upper end.
【0006】[0006]
【発明の実施の形態】以下添付の図面を参照して本発明
の実施形態を説明する。先ず図2を参照して、加圧水型
原子炉用燃料集合体10の全体構造を説明する。下部ノ
ズル11は、燃料装荷時に下部炉心板上に接する部分で
四隅下面に脚を有し、原子炉冷却材である軽水が通る多
数の穴が穿設されている。下部ノズル11に対向する上
端位置に上部ノズル13があり、同様に多数の軽水貫流
用穴が形成されているが、更に上面縁部にノズルスプリ
ング13aが設けられていて、装荷時に上部炉心板によ
り押圧される。そして、上部ノズル13と下部ノズル1
1に両端がそれぞれ連結された複数の制御棒案内管15
が互いに平行に延びている。同様な中空管である計装用
案内管17が燃料集合体10の中心部を軸方向に延び、
核計装用検出器の案内に供される。多数の支持格子19
が長手方向に間隔をおいて制御棒案内管15に固定さ
れ、更に最下段支持格子21は後述するように支持され
ている。制御棒案内管15や計装用案内管17は、支持
格子19の対応する位置の格子開口に挿通されているの
であるが、その他の格子開口に燃料棒23が1本づつ挿
通されて支持されている。Embodiments of the present invention will be described below with reference to the accompanying drawings. First, the overall structure of the fuel assembly 10 for a pressurized water reactor will be described with reference to FIG. The lower nozzle 11 has legs at four corner lower surfaces at a portion in contact with the lower core plate at the time of fuel loading, and is provided with a number of holes through which light water as a reactor coolant passes. An upper nozzle 13 is provided at an upper end position opposite to the lower nozzle 11, and a plurality of light water through holes are similarly formed. However, a nozzle spring 13a is further provided at an upper surface edge, and the upper core plate is used for loading. Pressed. Then, the upper nozzle 13 and the lower nozzle 1
A plurality of control rod guide tubes 15 each having both ends connected to 1
Extend parallel to each other. An instrumentation guide tube 17, which is a similar hollow tube, extends axially through the center of the fuel assembly 10,
Used for guiding nuclear instrumentation detectors. Multiple support grids 19
Are fixed to the control rod guide tube 15 at intervals in the longitudinal direction, and the lowermost support grid 21 is supported as described later. The control rod guide tube 15 and the instrumentation guide tube 17 are inserted through the corresponding grid openings of the support grid 19, and the fuel rods 23 are inserted and supported one by one through the other grid openings. I have.
【0007】本発明の要部が図1に示されている。下部
ノズル11に制御棒案内管15が図示しない取り付けボ
ルトにより固定されていて、下部ノズル11と制御棒案
内管15に挟まれて固定された管状のインサート25が
制御棒案内管15の下端部を取り囲んでいる。インサー
ト25の上端部は最下段支持格子21に連結されてこれ
を支持し、内側に内向きフランジ25aを形成してい
る。換言すれば、インサート25と制御棒案内管15と
の間に、上端部の内向きフランジ25aを除いて環状凹
み27が形成されている。このような環状凹み27の幅
は、実用炉では2mm程度で良い。FIG. 1 shows a main part of the present invention. A control rod guide tube 15 is fixed to the lower nozzle 11 by a mounting bolt (not shown), and a tubular insert 25 fixed between the lower nozzle 11 and the control rod guide tube 15 fixes the lower end of the control rod guide tube 15. Surrounding. The upper end of the insert 25 is connected to and supports the lowermost support grid 21 and forms an inward flange 25a inside. In other words, an annular recess 27 is formed between the insert 25 and the control rod guide tube 15 except for the inward flange 25a at the upper end. The width of such an annular recess 27 may be about 2 mm in a practical furnace.
【0008】以上のような構成の燃料集合体10が燃焼
に供されて曲げ変形した状態を誇張して示すと、図3の
ような状態となる。前述と同様に燃料棒は示されていな
いが、制御棒案内管15はなだらかに全長に渡って弓形
に撓んでいる。この場合、その下端部を取り囲むインサ
ート25は、隙間が大きくて変形を規制しないから、そ
の部分に変形曲線の特異点を形成していない。従って、
その制御棒案内管15に制御棒8を挿入すると、図4に
示すような状態となる。この図4もその説明を分かりや
すくするため、かなり誇張されているが、制御棒8は制
御棒案内管15の内面に追従してなだらかに変形してい
る。このように、制御棒8は制御棒案内管15に案内さ
れて変形するので、摺動抵抗も少なくなり、円滑に挿入
される。FIG. 3 is an exaggerated view of the state in which the fuel assembly 10 having the above-described structure is subjected to combustion and is bent and deformed. As before, the fuel rods are not shown, but the control rod guide tube 15 is gently bowed over its entire length. In this case, since the insert 25 surrounding the lower end has a large gap and does not restrict the deformation, no singular point of the deformation curve is formed at that portion. Therefore,
When the control rod 8 is inserted into the control rod guide tube 15, a state as shown in FIG. 4 is obtained. Although FIG. 4 is also exaggerated in order to make the explanation easy to understand, the control rod 8 is gently deformed following the inner surface of the control rod guide tube 15. As described above, since the control rod 8 is guided and deformed by the control rod guide tube 15, the sliding resistance is reduced and the control rod 8 is inserted smoothly.
【0009】[0009]
【発明の効果】以上説明したように、本発明によれば、
燃料集合体の下部で制御棒案内管の下部を取り囲むイン
サートがその撓み変形を拘束しないので、その変形がな
だらかになるから、制御棒もこれに倣って変形し、相互
間の摩擦抵抗も少なく、制御棒が円滑に挿入される。As described above, according to the present invention,
Since the insert surrounding the lower part of the control rod guide tube at the lower part of the fuel assembly does not restrain the bending deformation, the deformation becomes gentle, so the control rod also deforms according to this, the frictional resistance between them is small, The control rod is inserted smoothly.
【図1】本発明の実施形態の要部を示す概念的断面図で
ある。FIG. 1 is a conceptual sectional view showing a main part of an embodiment of the present invention.
【図2】前記実施形態に係る燃料集合体の一部を切除し
た全体斜視図である。FIG. 2 is an overall perspective view in which a part of the fuel assembly according to the embodiment is cut away.
【図3】前記実施形態の作用説明図である。FIG. 3 is an operation explanatory view of the embodiment.
【図4】前記実施形態の作用説明用部分断面図である。FIG. 4 is a partial sectional view for explaining the operation of the embodiment.
【図5】従来のものの構造を示す概略部分断面である。FIG. 5 is a schematic partial cross section showing the structure of a conventional device.
【図6】従来のものの不具合を説明するための概念図で
ある。FIG. 6 is a conceptual diagram for explaining a problem of a conventional device.
【図7】従来のものの不具合を説明するための部分断面
図である。FIG. 7 is a partial cross-sectional view for explaining a problem of the conventional device.
10 燃料集合体 11 下部ノズル 13 上部ノズル 15 制御棒案内管 17 計装用案内管 19 支持格子 21 最下段支持格子 23 燃料棒 25 インサート 25a 内向きフランジ 27 環状凹み Reference Signs List 10 fuel assembly 11 lower nozzle 13 upper nozzle 15 control rod guide pipe 17 instrumentation guide pipe 19 support grid 21 bottom support grid 23 fuel rod 25 insert 25a inward flange 27 annular recess
Claims (1)
互いに対向した上部ノズル及び下部ノズルと、同両ノズ
ル間に互いに平行に延び両端が該両ノズルにそれぞれ連
結される複数の制御棒案内管と、同制御棒案内管に沿っ
て間隔をおいて配設され最下段支持格子を含む複数の支
持格子と、同支持格子の格子開口に挿通されて支持され
る複数の燃料棒とを有する原子炉燃料集合体において、
前記下部ノズルに固定され前記制御棒案内管の下端部を
取り囲んで延びる最下段支持格子取り付け用インサート
の内周面に上端部を残して環状の凹みを形成してなるこ
とを特徴とする原子炉燃料集合体。1. An upper nozzle and a lower nozzle which are provided with a plurality of coolant through-holes and are opposed to each other at intervals, and a plurality of control rods which extend in parallel between the two nozzles and both ends of which are respectively connected to the two nozzles. A guide pipe, a plurality of support grids including a lowermost support grid arranged at intervals along the control rod guide pipe, and a plurality of fuel rods inserted and supported through the grid openings of the support grid. A reactor fuel assembly having
A nuclear recess formed in the inner peripheral surface of the lowermost support grid mounting insert fixed to the lower nozzle and extending around the lower end of the control rod guide tube, leaving an upper end at the lower end thereof; Fuel assembly.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP9292429A JPH11133177A (en) | 1997-10-24 | 1997-10-24 | Nuclear reactor fuel assembly |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP9292429A JPH11133177A (en) | 1997-10-24 | 1997-10-24 | Nuclear reactor fuel assembly |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH11133177A true JPH11133177A (en) | 1999-05-21 |
Family
ID=17781682
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP9292429A Withdrawn JPH11133177A (en) | 1997-10-24 | 1997-10-24 | Nuclear reactor fuel assembly |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH11133177A (en) |
-
1997
- 1997-10-24 JP JP9292429A patent/JPH11133177A/en not_active Withdrawn
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| A300 | Withdrawal of application because of no request for examination |
Free format text: JAPANESE INTERMEDIATE CODE: A300 Effective date: 20050104 |