JP3310787B2 - Reactor control rod protection guide structure - Google Patents
Reactor control rod protection guide structureInfo
- Publication number
- JP3310787B2 JP3310787B2 JP19685794A JP19685794A JP3310787B2 JP 3310787 B2 JP3310787 B2 JP 3310787B2 JP 19685794 A JP19685794 A JP 19685794A JP 19685794 A JP19685794 A JP 19685794A JP 3310787 B2 JP3310787 B2 JP 3310787B2
- Authority
- JP
- Japan
- Prior art keywords
- control rod
- guide structure
- reactor
- protection guide
- reactor control
- 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 - Lifetime
Links
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
【０００１】[0001]
【産業上の利用分野】本発明は、原子炉の制御に関し、
特に、加圧水型原子炉におけるように細長い制御棒要素
を房（クラスタ）状に集合組立ててなる制御棒を案内す
る原子炉容器の内部構造に関する。The present invention relates to the control of a nuclear reactor,
In particular, the present invention relates to an internal structure of a reactor vessel for guiding control rods formed by assembling elongated control rod elements into clusters as in a pressurized water reactor.
【０００２】[0002]
【従来の技術】現在、加圧水型原子炉のような軽水炉に
おいて、制御棒は、細長い制御棒要素を複数、スパイダ
部材に懸垂させ房（クラスタ）状に構成され、使用され
ている。このような制御棒は、通常、原子炉容器の上蓋
上に取付けられた制御棒駆動機構の駆動軸に連結され、
炉心に上方から挿入され、又は上方へ抜き出される。し
たがって、炉心を上方へ貫流して、その流れ方向を横向
きに変える冷却材流に、細長い制御棒要素がさらされる
形になるので、振動を受けやすい。細長い制御棒要素の
長さは、原子炉炉心の全高よりも大きいので、剛性は小
さく撓みやすい。このため、この制御棒要素を個別にか
つ近接して取り囲む細長い保護管即ち鞘が設けられ、複
数の鞘は、他の剛性部材と共に案内構造体として一体化
される。前述のように、制御棒要素の上端は、横方向に
のびるスパイダアームに連結されているから、鞘には、
軸方向にのびるスリットを形成してそのスパイダアーム
の通過を許している。図３に、前述のような制御棒要素
１と、鞘３との断面上の関係が示されているが、前述の
ように鞘３にはスリット５が形成されているので、大部
分の長手方向領域では、Ｃ形断面形状をとる。2. Description of the Related Art At present, in a light water reactor such as a pressurized water reactor, a plurality of control rods are suspended and suspended on a spider member in a cluster shape and used. Such control rods are usually connected to the drive shaft of a control rod drive mechanism mounted on the top lid of the reactor vessel,
It is inserted into the core from above or withdrawn upward. Accordingly, the elongated control rod elements are exposed to the coolant flow which flows through the core upward and changes the flow direction to the side, and is susceptible to vibration. Since the length of the elongated control rod element is greater than the overall height of the reactor core, it is less rigid and more prone to flexing. For this purpose, an elongated protective tube or sheath is provided which individually and closely surrounds the control rod element, the sheaths being integrated with the other rigid members as a guide structure. As described above, since the upper end of the control rod element is connected to the laterally extending spider arm, the sheath has:
An axially extending slit is formed to allow passage of the spider arm. FIG. 3 shows the cross-sectional relationship between the control rod element 1 and the sheath 3 as described above. Since the slit 5 is formed in the sheath 3 as described above, most of the longitudinal In the direction region, a C-shaped cross section is formed.
【０００３】[0003]
【発明が解決しようとする課題】前述したように、制御
棒要素１は、Ｃ形断面鞘３によって全体が囲まれ、冷却
材流に直接さらされないのであるが、スリット５の両側
面及び制御棒要素１の外周面との間にキャビティ７が画
成された形となっている。このような形状では、矢印下
に示すような周方向に向う冷却材流があると、スリット
５の先端のシャープエッジ端５ａとの協働作用により、
キャビティ７の中に渦Ｖが生ずることがある。このよう
な渦が発生すると、鞘３と制御棒要素１とが共振し、干
渉したりして損傷することがある。したがって、本発明
は、制御棒要素を取り囲む保護管にスリットが形成され
ているにもかかわらず、冷却材の渦の発生やこれによる
共振等の生じない改良された原子炉制御棒の保護案内構
造体を提供することを目的とする。As described above, the control rod element 1 is entirely surrounded by the C-shaped sheath 3 and is not directly exposed to the coolant flow. The cavity 7 is defined between the element 1 and the outer peripheral surface. In such a shape, when there is a coolant flow in the circumferential direction as indicated by the arrow below, the tip 5a of the slit 5 cooperates with the sharp edge end 5a.
Vortices V may form in the cavity 7. When such a vortex is generated, the sheath 3 and the control rod element 1 may resonate, interfere with each other, and may be damaged. Therefore, the present invention provides an improved protection guide structure for a reactor control rod, which does not generate a coolant vortex or resonance due to a slit formed in the protection tube surrounding the control rod element. The purpose is to provide the body.
【０００４】[0004]
【課題を解決するための手段】前述のような目的を達成
するため、本発明によれば、細長い制御棒要素を房状に
集合構成した原子炉制御棒を原子炉容器内上方で案内保
護する原子炉制御棒の保護案内構造体は、制御棒要素を
個別に受入れるＣ形断面保護管が複数互いに平行に配置
され、その保護管の断面開口部の隅部を適宜な形状に面
取りして構成されている。According to the present invention, there is provided, in accordance with the present invention, a reactor control rod having a group of elongated control rod elements arranged in a cluster to guide and protect the control rod above a reactor vessel. The protection guide structure for a control rod of a reactor has a configuration in which a plurality of C-shaped cross-section protection tubes for individually receiving control rod elements are arranged in parallel with each other, and the corner of the cross-section opening of the protection tube is chamfered into an appropriate shape. Have been.
【０００５】[0005]
【作用】前記した構成によれば、制御棒要素を取り囲む
保護管に沿って、周方向に向う冷却材流が生じても、断
面開口（スリット）部の隅部が面取りされているので、
冷却材流に剪断流が生せず、渦の発生が抑止される。According to the above construction, even if a coolant flows in the circumferential direction along the protective tube surrounding the control rod element, the corner of the cross-section opening (slit) is chamfered.
No shear flow occurs in the coolant flow, and the generation of vortices is suppressed.
【０００６】[0006]
【実施例】以下、添付の図面を参照して本発明の実施例
を説明する。図１は、原子炉制御棒（図示しない。）の
保護案内構造体１０の平断面を示したもので、外周部に
は、矩形断面の外筒１１が位置し、この中には、比較的
長い長手方向間隔をおいて案内支持板１３が固定されて
いる。この案内支持板１３には、制御棒のスパイダハブ
が通る中心孔１５と、スパイダアームが通るスロット１
７，１９が形成されている。そして、スロット１７，１
９の先端には、制御棒要素が通るＣ形断面保護管２１が
貫通固定されている。スロット１７，１９の途中にある
２つ割の保護管２３も、制御棒要素を取り囲むものであ
るが、本発明の直接の対象ではないので、詳細な説明は
割愛する。図２に、保護管２１の断面が拡大して示され
ているが、説明の都合上、制御棒要素１も示されてい
る。図２から明瞭なように、軸方向にのびたスリット
（案内支持板１３のスロット１７，１９に整列する）２
５を画成する両端部２１ａ，２１ｂは、隅部が丸められ
ている。以上のような構成において、Ｃ形断面保護管２
１は、制御棒要素１を実質的に囲んでおり、軸方向冷却
材流に対し保護すると共に、制御棒の上方からの炉心へ
の挿入時に制御棒要素１を案内する。更に矢印Ｆの方向
に流れ成分をもつ冷却材流が発生しても、両端２１ａ，
２１ｂの隅部は丸められているから、保護管２１の円周
方向流れに対しても剪断流が生ぜず、キャビティ２７に
は渦が発生しない。なお、前記実施例において、保護管
２１の両端２１ａ，２１ｂの隅部を丸めたが、適宜な大
きさの面取りとしても同様の作用効果が期待でき、更
に、両端のみならず一方の端部に、面取りを加え、又は
丸みを形成しても相応の効果は期待できる。Embodiments of the present invention will be described below with reference to the accompanying drawings. FIG. 1 shows a flat cross section of a protection guide structure 10 for a reactor control rod (not shown). An outer cylinder 11 having a rectangular cross section is located on the outer peripheral portion. The guide support plates 13 are fixed at long longitudinal intervals. The guide support plate 13 has a center hole 15 through which the spider hub of the control rod passes and a slot 1 through which the spider arm passes.
7, 19 are formed. And slot 17, 1
A C-shaped protective tube 21 through which the control rod element passes is fixedly penetrated at the tip of the 9. The split protective tube 23 in the middle of the slots 17 and 19 also surrounds the control rod element, but is not a direct object of the present invention, and thus a detailed description is omitted. FIG. 2 shows an enlarged cross section of the protection tube 21, but for convenience of explanation, the control rod element 1 is also shown. As is clear from FIG. 2, a slit extending in the axial direction (aligned with the slots 17 and 19 of the guide support plate 13) 2
The corners of the two end portions 21a and 21b that define 5 are rounded. In the above configuration, the C-shaped protective tube 2
1 substantially surrounds the control rod element 1 and protects it against axial coolant flow and guides the control rod element 1 during insertion into the core from above the control rod. Furthermore, even if a coolant flow having a flow component occurs in the direction of arrow F, both ends 21a,
Since the corner of 21b is rounded, no shear flow is generated even in the circumferential flow of the protection tube 21, and no vortex is generated in the cavity 27. In the above-described embodiment, the corners of both ends 21a and 21b of the protection tube 21 are rounded. However, a similar effect can be expected by chamfering an appropriate size. Even if chamfering or rounding is performed, a corresponding effect can be expected.
【０００７】[0007]
【発明の効果】以上説明したように、本発明によれば、
制御棒要素を取り囲むＣ形断面保護管のスリット画成端
に実質的な面取りを形成したので、円周方向冷却材流に
対し剪断流の発生が抑制され、渦の発生やこれに付ずい
する振動、損傷の発生を防止することができる。As described above, according to the present invention,
Since a substantially chamfer is formed at the slit defining end of the C-shaped protective tube surrounding the control rod element, the generation of shear flow with respect to the circumferential coolant flow is suppressed, and the generation of vortices and the occurrence thereof are prevented. Vibration and damage can be prevented.
【図１】本発明の実施例の平断面図。FIG. 1 is a plan sectional view of an embodiment of the present invention.
【図２】図１の要部拡大断面図。FIG. 2 is an enlarged sectional view of a main part of FIG.
【図３】従来のものの説明図。FIG. 3 is an explanatory view of a conventional device.
１０ 保護案内構造体 ２１ 保護管 ２１ａ 端部 ２１ｂ 端部 ２５ スリット DESCRIPTION OF SYMBOLS 10 Protective guide structure 21 Protective tube 21a End 21b End 25 Slit
───────────────────────────────────────────────────── フロントページの続き (72)発明者 久保 登 兵庫県神戸市兵庫区和田崎町一丁目１番 １号 三菱重工業株式会社 神戸造船所 内 (72)発明者 伊藤 智博 兵庫県高砂市荒井町新浜二丁目１番１号 三菱重工業株式会社 高砂研究所内 (56)参考文献 実開 昭62−88997（ＪＰ，Ｕ) 実開 平３−10294（ＪＰ，Ｕ) (58)調査した分野(Int.Cl.7，ＤＢ名) G21C 7/117 G21C 7/14 ──────────────────────────────────────────────────続 き Continuing on the front page (72) Inventor Noboru Kubo 1-1-1, Wadasaki-cho, Hyogo-ku, Kobe City, Hyogo Prefecture Inside the Kobe Shipyard, Mitsubishi Heavy Industries, Ltd. 2-1-1 1-1 Inside the Takasago Research Laboratory, Mitsubishi Heavy Industries, Ltd. (56) References Japanese Utility Model Sho 62-88997 (JP, U) Japanese Utility Model Utility Model 3-10294 (JP, U) (58) Fields surveyed (Int.Cl) . 7, DB name) G21C 7/117 G21C 7/14
Claims (1)
成した原子炉制御棒を原子炉容器内上方で案内保護する
ものにおいて、前記制御棒要素を個別に受け入れるＣ形
断面保護管が複数互いに平行に配置され、同保護管の断
面開口部の隅部を面取りして形成したことを特徴とする
原子炉制御棒の保護案内構造体。An apparatus for guiding and protecting a reactor control rod having a plurality of elongated control rod elements arranged in a cluster in a reactor vessel above a reactor vessel, wherein a plurality of C-shaped protective tubes for individually receiving the control rod elements are provided. A protection guide structure for a reactor control rod, wherein the protection guide structure is arranged in parallel with each other, and is formed by chamfering a corner of a sectional opening of the protection tube.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP19685794A JP3310787B2 (en) | 1994-08-22 | 1994-08-22 | Reactor control rod protection guide structure |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP19685794A JP3310787B2 (en) | 1994-08-22 | 1994-08-22 | Reactor control rod protection guide structure |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH0862365A JPH0862365A (en) | 1996-03-08 |
| JP3310787B2 true JP3310787B2 (en) | 2002-08-05 |
Family
ID=16364816
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP19685794A Expired - Lifetime JP3310787B2 (en) | 1994-08-22 | 1994-08-22 | Reactor control rod protection guide structure |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JP3310787B2 (en) |
-
1994
- 1994-08-22 JP JP19685794A patent/JP3310787B2/en not_active Expired - Lifetime
Also Published As
| Publication number | Publication date |
|---|---|
| JPH0862365A (en) | 1996-03-08 |
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