JPS6349751Y2 - - Google Patents
Info
- Publication number
- JPS6349751Y2 JPS6349751Y2 JP1988005830U JP583088U JPS6349751Y2 JP S6349751 Y2 JPS6349751 Y2 JP S6349751Y2 JP 1988005830 U JP1988005830 U JP 1988005830U JP 583088 U JP583088 U JP 583088U JP S6349751 Y2 JPS6349751 Y2 JP S6349751Y2
- Authority
- JP
- Japan
- Prior art keywords
- control rod
- guide tube
- rod guide
- sleeve
- fuel 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.)
- Expired
Links
- 239000000463 material Substances 0.000 claims description 10
- 239000003758 nuclear fuel Substances 0.000 claims description 9
- 239000000446 fuel Substances 0.000 claims description 8
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 4
- 238000005219 brazing Methods 0.000 description 3
- 238000003780 insertion Methods 0.000 description 3
- 230000037431 insertion Effects 0.000 description 3
- 238000000034 method Methods 0.000 description 3
- 238000003466 welding Methods 0.000 description 3
- 238000000429 assembly Methods 0.000 description 2
- 230000000712 assembly Effects 0.000 description 2
- 239000002826 coolant Substances 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 238000009835 boiling Methods 0.000 description 1
- 238000002485 combustion reaction Methods 0.000 description 1
- 238000002474 experimental method Methods 0.000 description 1
- 238000009434 installation Methods 0.000 description 1
- 230000002265 prevention Effects 0.000 description 1
- 230000003014 reinforcing effect Effects 0.000 description 1
- 229910001220 stainless steel Inorganic materials 0.000 description 1
- 239000010935 stainless steel Substances 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)
Description
【考案の詳細な説明】
（産業上の利用分野）
本考案は制御棒の振動による制御棒案内管のフ
レツテイング損傷を阻止し、強度低下を防止する
ための構成を有する核燃料集合体に関するもので
ある。[Detailed description of the invention] (Field of industrial application) The present invention relates to a nuclear fuel assembly having a structure for preventing fretting damage to control rod guide tubes due to vibration of control rods and preventing a decrease in strength. .
（従来の技術）
原子炉用核燃料集合体においては、燃料要素間
を流動する冷却材により燃料集合体からの所期の
エネルギー除去性能を得るため燃料要素の間隔を
確実に維持すべく支持格子が使用されている。こ
の支持格子は軸線方向に確実に、かつ垂直に配置
することが要求される関係上、加圧水型燃料集合
体においては制御棒案内管、一方、沸騰水型燃料
要素においてはウオーターロツドなどの支持構造
体などによつて取り付けられる。就中、加圧水型
燃料集合体では制御棒を集合体内部に配置した制
御棒案内管中に収める構造をもち、集合体上部よ
り制御棒を制御棒案内管入口から約150mm前後の
位置に挿入した状態で使用し、必要に応じてその
挿入度合を調整し、更に深く挿入して制御機能を
果たしている。(Prior Art) In nuclear fuel assemblies for nuclear reactors, support grids are used to ensure that the spacing between fuel elements is maintained in order to obtain the desired energy removal performance from the fuel assembly by coolant flowing between the fuel elements. It is used. Since this support grid must be placed firmly and vertically in the axial direction, it is used as a support for control rod guide tubes in pressurized water fuel assemblies, and for water rods in boiling water fuel elements. It is attached by a structure or the like. In particular, the pressurized water fuel assembly has a structure in which the control rods are housed in a control rod guide tube placed inside the assembly, and the control rods are inserted from the top of the assembly at a position approximately 150 mm from the entrance of the control rod guide tube. It is used in this state, and the degree of insertion is adjusted as necessary, and it is inserted deeper to perform the control function.
ところが、このように制御棒案内管入口部だけ
に制御棒が挿入され、長時間にわたつて保持され
ていると制御棒自体約４ｍの長さを有し、かつそ
の支持状況は上方から懸垂されているだけである
から、原子炉運転時においては冷却材流により振
動を起こし、この振動に起因して制御棒と制御棒
案内管とが離間、接触を繰り返す結果、フレツテ
イング現象が生じ、制御棒案内管に損傷を与え
る。 However, if the control rod is inserted only into the entrance of the control rod guide tube and held for a long time, the control rod itself will be approximately 4 m long, and its support will be suspended from above. During reactor operation, the coolant flow causes vibrations, and this vibration causes the control rods and control rod guide tubes to separate and repeatedly come into contact, resulting in a fretting phenomenon, which causes the control rods to Damage to the guide tube.
このことは例えば予備的実験では制御棒案内管
に穴があくという事態を惹起している。そして、
これは集合体骨格をなす制御棒案内管の強度を必
然的に低下する。 This has caused, for example, holes in control rod guide tubes in preliminary experiments. and,
This inevitably reduces the strength of the control rod guide tube that forms the framework of the assembly.
かかる状況にも拘らず、従来特にフレツテイン
グ対策について特別な措置は講じられておらず、
一部、制御棒案内管上部にスリーブを用いた例も
あつたが、これも単に経済的あるいは技術的な問
題解決するためのものであつて、スリーブの長さ
も上部より僅か30〜40mmで制御棒案内管の外側に
装着されていた。 Despite this situation, no special measures have been taken to prevent fretting.
There were some cases in which a sleeve was used at the top of the control rod guide tube, but this was also simply to solve an economic or technical problem, and the length of the sleeve was controlled to be only 30 to 40 mm from the top. It was attached to the outside of the rod guide tube.
（考案が解決しようとする問題点）
本考案は叙上の如きフレツテイング損傷の実状
に鑑み、その解決を図ることを課題とし、特に短
尺スリーブの結合位置とその配置に着目して所期
のフレツテイング損傷防止を達成せんとするもの
である。(Problems to be solved by the invention) In view of the actual situation of fretting damage as described above, the present invention aims to solve the problem.In particular, it focuses on the joining position and arrangement of short sleeves to achieve the desired fretting. The aim is to achieve damage prevention.
（問題点を解決するための手段）
即ち、本考案の特徴とするところは、核分裂性
物質の焼結体を集合した燃料要素と、制御棒案内
管、支持格子などからなる核燃料集合体におい
て、前記制御棒案内管に挿入される制御棒先端位
置近傍を含み、制御棒案内管上端部のフレツテイ
ング損傷発生可能位置内面を短尺スリーブで覆
い、該部を二重壁構造となした点にある。(Means for Solving the Problems) That is, the present invention is characterized in that a nuclear fuel assembly consisting of a fuel element made up of sintered bodies of fissile material, a control rod guide tube, a support grid, etc. The inner surface of the upper end of the control rod guide tube where fretting damage can occur, including the vicinity of the tip of the control rod inserted into the control rod guide tube, is covered with a short sleeve, and the portion has a double wall structure.
ここで、フレツテイングは通常、前述の如く制
御棒案内管入口より約150mm前後の位置、即ち制
御棒先端を中心とした範囲で大きいので、この部
分を保護することが肝要であり、制御棒が通常制
御棒案内管入口より約150mm前後の位置に挿入さ
れることから、この位置を含め、ほぼその近傍、
少なくとも50mm、好ましくは50〜100mmの範囲程
度の保護が最も好適である。 Here, as mentioned above, fretting is usually large at a position approximately 150 mm from the entrance of the control rod guide tube, that is, in the area centered on the tip of the control rod, so it is important to protect this area. Since the control rod is inserted at a position approximately 150 mm from the entrance of the control rod guide tube, the
Protection of the order of at least 50 mm, preferably in the range 50 to 100 mm is most preferred.
（作用）
以上のような構成を採用することにより制御棒
のフレツテイング現象が起こるとしても、制御棒
と制御棒案内管との接触をなくし、スリーブの破
損に止め、外層の制御棒案内管を保護することに
なる。(Function) By adopting the above configuration, even if the control rod fretting phenomenon occurs, contact between the control rod and the control rod guide tube is eliminated, damage to the sleeve is prevented, and the control rod guide tube in the outer layer is protected. I will do it.
（実施例）
以下、更に本考案の具体的な実施態様を添付図
面にもとづいて説明すると、第１図は本考案に係
る核燃料集合体の要部の１例を示し、図において
１は制御棒案内管、２は短尺スリーブで、該スリ
ーブ２は案内管１の上端部に上端より所要の長さ
にわたり内側に嵌装され上部のカラー３によつて
案内管１の上端に保持されて被着結合されてい
る。この場合、スリーブ２の結合による二重壁部
の長さは50mm以上とし、制御棒先端が当該二重壁
部に位置するよう構成することが案内管１のフレ
ツテイング損傷を防止する上から適当であり、そ
の範囲において適宜制御棒の挿入度合を勘案して
スリーブの長さが選定される。(Example) Hereinafter, specific embodiments of the present invention will be further explained based on the attached drawings. Fig. 1 shows an example of the main parts of a nuclear fuel assembly according to the present invention, and in the figure, 1 is a control rod. The guide tube 2 is a short sleeve, and the sleeve 2 is fitted inside the upper end of the guide tube 1 over a required length from the upper end, and is held and attached to the upper end of the guide tube 1 by an upper collar 3. combined. In this case, in order to prevent damage to the guide tube 1 due to fretting, it is appropriate to make the length of the double wall by connecting the sleeve 2 to be 50 mm or more, and configure the control rod tip to be located in the double wall. The length of the sleeve is selected within this range, taking into consideration the degree of insertion of the control rod.
なお、制御棒案内管１とスリーブ２との結合は
溶接、あるいはろう付け、スウエージ法などの各
手段が採用され、夫々の素材の種類によつてその
一種または二種以上の手段の併用が行われる。 The control rod guide tube 1 and the sleeve 2 are connected by various means such as welding, brazing, and swaging, and one or more of these methods may be used in combination depending on the type of material. be exposed.
前記第１図はこの内、両者の結合として溶接手
段を採用した場合である。かかる溶接による結合
は、素材が溶接可能な素材でなければならず、例
えば制御棒案内管１とスリーブ２とが同一素材で
形成されている場合に適している。具体的には、
制御棒案内管１がジルカロイ−２、ジルカロイ−
４で形成されている場合、スリーブもそれらの材
料であれば容易にこの手段が適用される。 FIG. 1 shows the case where welding means is used to connect the two. Such welding requires that the material be a weldable material, and is suitable, for example, when the control rod guide tube 1 and the sleeve 2 are made of the same material. in particular,
Control rod guide tube 1 is Zircaloy-2, Zircaloy-
4, this method can be easily applied if the sleeve is also made of those materials.
第２図は第１図に対し制御棒案内管１とスリー
ブ２とが溶接不可能な素材、例えば異種の素材で
構成されている場合に適した二重管構成例であ
り、１個所又は２個所以上、図では１個所である
が、スウエージ法による結合４が採用されてい
る。 FIG. 2 shows an example of a double tube configuration suitable for the case where the control rod guide tube 1 and the sleeve 2 are made of materials that cannot be welded, for example, different materials, compared to FIG. At more than one location, although it is only one location in the figure, connection 4 by the swage method is employed.
かかるスウエージによる結合の場合には、通常
案内管１の上端より100mm以内の範囲において結
合させることが好適である。 In the case of such a swage connection, it is usually preferable to perform the connection within 100 mm from the upper end of the guide tube 1.
勿論、この場合においてもろう付けが可能であ
ればろう付けによる結合も何ら差し支えない。 Of course, even in this case, if brazing is possible, there is no problem in joining by brazing.
なお、上述の如き案内管１と異なる材質のスリ
ーブの例としては炉内における健全性の点よりス
テンレス鋼に選定するのが好適である。 As an example of the sleeve made of a material different from that of the guide tube 1 as described above, it is preferable to select stainless steel from the viewpoint of soundness in the furnace.
第３図は前記第１図及び第２図に示す各例がス
リーブ２を案内管１の平滑な内層面に層着してい
る関係からスリーブ２の下端において段部を生じ
ているのを解消し、制御棒案内管としての内径を
一定とした場合で、制御棒案内管１の上端部即ち
最上部支持格子（図示せず）上面より上部を拡大
し、この中にスリーブ２を装着した態様を示して
いる。この場合には制御棒案内管上端のスリーブ
結合部内層面とこれに連続した制御棒案内管の内
層面とは面一となつて平滑な内面を形成する。本
例でも二重壁は挿入長全長にわたることが望まし
い。従つて前記第１図、第２図の場合と異なり案
内管１の内径が縮少されることがなく、案内管を
使用しない場合と同様な制御棒を挿入することが
できる。 FIG. 3 eliminates the stepped portion at the lower end of the sleeve 2 in the examples shown in FIGS. 1 and 2, in which the sleeve 2 is layered on the smooth inner surface of the guide tube 1. However, when the inner diameter of the control rod guide tube is constant, the upper end of the control rod guide tube 1, that is, the uppermost part of the uppermost support grid (not shown) is enlarged above the upper surface, and the sleeve 2 is installed in this. It shows. In this case, the inner layer surface of the sleeve joint portion at the upper end of the control rod guide tube and the inner layer surface of the control rod guide tube that is continuous therewith are flush with each other to form a smooth inner surface. In this example as well, it is desirable that the double wall extends over the entire insertion length. Therefore, unlike the cases shown in FIGS. 1 and 2, the inner diameter of the guide tube 1 is not reduced, and it is possible to insert the same control rod as in the case where no guide tube is used.
以上の各短尺スリーブ２は何れも平滑な筒状形
状になつているが、必らずしも平滑な円筒状に限
らず、長手方向に複数個所以上の突起５を内側に
全長または一部にわたつて設けることも差し支え
なく、第４図イ，ロはかかる態様を示す。 Each of the above-mentioned short sleeves 2 has a smooth cylindrical shape, but the shape is not necessarily limited to a smooth cylindrical shape. There is no problem in providing it across, and FIGS. 4A and 4B show such an embodiment.
この場合、突起５は１個所でもよいが、図示の
ように３個所以上設けることが好ましく、これに
よつてフレツテイングを局部に留めることができ
る。 In this case, the protrusion 5 may be provided at one location, but it is preferable to provide the protrusion 5 at three or more locations as shown in the figure, so that the fretting can be localized.
以上のような制御棒案内管上端部における短尺
スリーブの結合は、制御棒の振動によるフレツテ
イング現象が起こるとしても、制御棒と制御棒案
内管層面との接触をなくし、スリーブの破損にと
どめ、従つてスリーブを介して外層にある制御棒
案内管を保護することになり、強度低下を確実に
防止することができる。 The connection of the short sleeve at the upper end of the control rod guide tube as described above eliminates contact between the control rod and the layer surface of the control rod guide tube, and prevents damage to the sleeve, even if a fretting phenomenon occurs due to vibration of the control rod. As a result, the control rod guide tube in the outer layer is protected through the sleeve, and a decrease in strength can be reliably prevented.
なお、短尺スリーブは必要に応じ取り替え使用
することが可能である。 Note that the short sleeve can be replaced as needed.
（考案の効果）
本考案は以上の如く制御棒案内管の上端部フレ
ツテイング損傷発生可能位置内層面を短尺スリー
ブにより二重壁構造とし、内層にフレツテイング
による損傷を期待するスリーブを結合し、外層部
は強合部材としてフレツテイングによる損傷は期
待されないようにしたので、原子炉中での燃焼時
に制御棒と制御棒案内管との間で制御棒の振動現
象が起こつた場合でも両者の接触によるフレツテ
イング損傷が起こることはなく、スリーブの損傷
だけに留まり、従つて、その強度低下を問題にす
る必要がなくなり、核燃料集合体の構成に別段の
阻害を来さず、出力を低下させることもなく、使
用期間を大きく延ばすことができる顕著な効果を
有すると共に、原子炉の円滑、かつ効率的な運転
の確保と、その安全性の向上を図ることができ
る。(Effects of the invention) As described above, the present invention has a double-walled structure using a short sleeve on the inner layer surface of the upper end of the control rod guide tube where fretting damage is likely to occur. As a reinforcing member, damage due to fretting is not expected, so even if vibration of the control rod occurs between the control rod and the control rod guide tube during combustion in a nuclear reactor, there will be no fretting damage due to contact between the two. This does not occur, and only damages the sleeve.Therefore, there is no need to worry about the reduction in its strength, and it does not interfere with the configuration of the nuclear fuel assembly, does not reduce the output, and can be used. This has the remarkable effect of greatly extending the period, and also ensures smooth and efficient operation of the nuclear reactor and improves its safety.
第１図は本考案の一例にかかる制御棒案内管、
スリーブ、カラーが溶接可能な場合の縦断面図、
第２図は制御棒案内管とスリーブが溶接不可能な
場合の本考案例を示す縦断面図、第３図は本考案
にかかる更に他のスリーブ装着例を示す縦断面
図、第４図イ，ロはスリーブを変形させた本考案
の他の変形例を示す横断面図及び縦断面図であ
る。
１……制御棒案内管、２……スリーブ、３……
カラー。
FIG. 1 shows an example of a control rod guide tube according to the present invention.
A longitudinal section of a sleeve and collar that can be welded.
Fig. 2 is a vertical cross-sectional view showing an example of the present invention in which the control rod guide tube and the sleeve cannot be welded, Fig. 3 is a vertical cross-sectional view showing yet another example of sleeve installation according to the present invention, and Figs. 4A and 4B are cross-sectional and vertical cross-sectional views showing another modified example of the present invention in which the sleeve is modified. 1... Control rod guide tube, 2... Sleeve, 3...
Color.
Claims (1)
と、制御棒案内管、支持格子などからなる核燃
料集合体において、前記制御棒案内管に挿入さ
れる制御棒先端位置近傍を含み、制御棒案内管
上端部のフレツテイング損傷発生可能位置内面
を短尺スリーブで覆い、該部を二重壁構造とな
したことを特徴とする核燃料集合体。 ２ 短尺スリーブが長手方向に複数の突起をその
内側に全長又は一部にわたつて有している実用
新案登録請求の範囲第１項記載の核燃料集合
体。 ３ 制御棒案内管上端部の短尺スリーブ結合部内
層面がこれに続く制御棒案内管の内層面と面一
である実用新案登録請求の範囲第１項又は第２
項記載の核燃料集合体。[Claims for Utility Model Registration] 1. In a nuclear fuel assembly consisting of a fuel element made up of sintered bodies of fissile material, a control rod guide tube, a support grid, etc., the tip of a control rod inserted into the control rod guide tube. A nuclear fuel assembly characterized in that the inner surface of the upper end of the control rod guide tube where fretting damage is likely to occur, including the vicinity thereof, is covered with a short sleeve, and the portion has a double wall structure. 2. The nuclear fuel assembly according to claim 1, wherein the short sleeve has a plurality of protrusions in the longitudinal direction over the entire length or part of the length thereof. 3 Utility model registration claim 1 or 2, in which the inner layer surface of the short sleeve joint part at the upper end of the control rod guide tube is flush with the inner layer surface of the following control rod guide tube.
Nuclear fuel assembly as described in section.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1988005830U JPS6349751Y2 (en) | 1988-01-19 | 1988-01-19 |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1988005830U JPS6349751Y2 (en) | 1988-01-19 | 1988-01-19 |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS63132393U JPS63132393U (en) | 1988-08-30 |
| JPS6349751Y2 true JPS6349751Y2 (en) | 1988-12-21 |
Family
ID=30787779
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP1988005830U Expired JPS6349751Y2 (en) | 1988-01-19 | 1988-01-19 |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS6349751Y2 (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2787370B1 (en) * | 1998-12-22 | 2001-03-16 | Franco Belge Combustibles | METHOD FOR JOINING TWO COAXIAL TUBULAR PARTS, TOOL FOR MAKING THE SAME AND USE THEREOF |
-
1988
- 1988-01-19 JP JP1988005830U patent/JPS6349751Y2/ja not_active Expired
Also Published As
| Publication number | Publication date |
|---|---|
| JPS63132393U (en) | 1988-08-30 |
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