JPH056397U - Control rod cluster - Google Patents

Control rod cluster

Info

Publication number
JPH056397U
JPH056397U JP082611U JP8261191U JPH056397U JP H056397 U JPH056397 U JP H056397U JP 082611 U JP082611 U JP 082611U JP 8261191 U JP8261191 U JP 8261191U JP H056397 U JPH056397 U JP H056397U
Authority
JP
Japan
Prior art keywords
stainless steel
control rod
steel pipe
absorbing material
neutron absorbing
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Withdrawn
Application number
JP082611U
Other languages
Japanese (ja)
Inventor
清和 中武
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 JP082611U priority Critical patent/JPH056397U/en
Publication of JPH056397U publication Critical patent/JPH056397U/en
Withdrawn legal-status Critical Current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

  • Particle Accelerators (AREA)

Abstract

(57)【要約】 (修正有) 【目的】 制御棒内の中性子吸収材が、これを被覆して
いるステンレス鋼管の内側に振動接触、またはスエリン
グとステンレス鋼管のクリープの変形による接触で、応
力集中発生部が生じるのを抑制するため。 【構成】 制御棒のステンレス鋼管1で被覆されている
中性子吸収材2の上端部からプレナム部と接する箇所へ
向って傾斜角約5°で長さは上記ステンレス鋼管1の内
径とほぼ等しいテーパー部2aを設けて、制御棒の振動
に伴う中性子吸収材2とステンレス鋼管1との振動接触
あるいはステンレス鋼管1のクリープおよび中性子吸収
材2のスエリングによるステンレス鋼管1と中性子吸収
材2の接触が生じても、ステンレス鋼管1の応力集中発
生部が起こらないように抑制した。
(57) [Summary] (Modified) [Purpose] The neutron absorbing material in the control rod is subjected to stress due to vibration contact with the inside of the stainless steel pipe covering it or deformation due to creep deformation of swelling and stainless steel pipe. To suppress the occurrence of concentrated areas. [Structure] A tapered portion having a tilt angle of about 5 ° from the upper end of a neutron absorber 2 covered with a stainless steel pipe 1 of a control rod toward a portion in contact with a plenum, and having a length substantially equal to the inner diameter of the stainless steel pipe 1. 2a is provided to cause vibration contact between the neutron absorbing material 2 and the stainless steel tube 1 due to vibration of the control rod or contact between the stainless steel tube 1 and the neutron absorbing material 2 due to creep of the stainless steel tube 1 and swelling of the neutron absorbing material 2. Also, it was suppressed so that the stress concentration occurrence part of the stainless steel pipe 1 did not occur.

Description

【考案の詳細な説明】[Detailed description of the device]

【0001】[0001]

【産業上の利用分野】[Industrial applications]

本考案は、制御棒内の中性子吸収材の形状の改良に関するものである。 The present invention relates to improvement of the shape of a neutron absorber in a control rod.

【0002】[0002]

【従来の技術】[Prior Art]

加圧水型原子炉では、出力調整,炉心停止用に、銀・インジゥム・カドミゥム 合金からなる中性子吸収材をステンレス鋼管で被覆した制御棒からなる制御棒ク ラスタを用いている。 制御棒クラスタは、図4に示すように多数本の制御棒10をスパイダーと称す る上部構造体20により結束固定したものである。なお、図中2は中性子吸収材 である。 In a pressurized water reactor, a control rod cluster consisting of a control rod coated with a neutron absorber made of silver, indium and cadmium alloy is coated with a stainless steel tube is used for power adjustment and core shutdown. As shown in FIG. 4, the control rod cluster has a large number of control rods 10 bound and fixed by an upper structure 20 called a spider. In the figure, 2 is a neutron absorber.

【0003】 従来使用されている制御棒は約4m長で径は約10mmであり、その部分図は 図3に示す。従来制御棒は、通常原子炉運転時、炉心内での流水等により振動を 起こしている。この振動により、制御棒の内部ではステンレス鋼管1と中性子吸 収材2の間で、連続的な振動接触が起こる。その結果ステンレス鋼管1は中性子 吸収材2と接触し、中性子吸収材2のないプレナム部5との境界において、局部 的応力集中発生部4を生じ、この応力がある限度を越えると疲労等によりステン レス鋼管が破断に至る恐れがある。A conventionally used control rod has a length of about 4 m and a diameter of about 10 mm, and its partial view is shown in FIG. Conventional control rods normally oscillate due to running water in the core during reactor operation. Due to this vibration, continuous vibration contact occurs between the stainless steel tube 1 and the neutron absorbing material 2 inside the control rod. As a result, the stainless steel pipe 1 comes into contact with the neutron absorbing material 2, and a local stress concentration generating portion 4 is generated at the boundary with the plenum portion 5 where the neutron absorbing material 2 is absent. The stainless steel pipe may be broken.

【0004】 また、炉心内使用において、中性子吸収材2は中性子照射によりスエリングを 起こし、一方ステンレス鋼管は冷却材の外圧並びに中性子照射下のクリープ変形 等により、径が徐々に減小する。その結果ステンレス鋼管1は中性子吸収材2と 接触し、プレナム部5との境界においてやはり局部的な応力集中を受け破断に至 る恐れがある。Further, in the in-core use, the neutron absorber 2 causes swelling by neutron irradiation, while the stainless steel pipe gradually decreases in diameter due to external pressure of the coolant and creep deformation under neutron irradiation. As a result, the stainless steel pipe 1 may come into contact with the neutron absorbing material 2, and at the boundary with the plenum portion 5, the stress may still be locally concentrated, which may lead to fracture.

【0005】[0005]

【考案が解決しようとする課題】[Problems to be solved by the device]

本考案は、出力調整,炉心停止用に、中性子吸収材をステンレス鋼管で被覆し た制御棒のステンレス鋼管への応力の集中を抑制してステンレス鋼管の破断に至 る恐れがあるのを無くすることである。なお、3はプレナムコイルである。 The present invention suppresses the concentration of stress on the stainless steel pipe of the control rod in which the neutron absorber is coated with the stainless steel pipe for power adjustment and core shutdown, and eliminates the risk of the stainless steel pipe breaking. That is. In addition, 3 is a plenum coil.

【0006】[0006]

【課題を解決するための手段】[Means for Solving the Problems]

本考案は、上記の課題を解決するためになされたもので、図1の具体例のよう に、中性子吸収材2の上端部にテーパー部2aを設けた。 同図において、1はステンレス鋼管,2は中性子吸収材,2aは中性子吸収材 のテーパー部,3はプレナムコイルで、図3で示した応力集中発生部4は解消さ れている。 他の手段として中性子吸収材の上端部の形状をテーパー状の代りに球状にして まるめる例も考えられる。 The present invention has been made in order to solve the above problems, and as shown in the specific example of FIG. 1, a taper portion 2a is provided at the upper end portion of the neutron absorber 2. In the figure, 1 is a stainless steel pipe, 2 is a neutron absorbing material, 2a is a tapered portion of the neutron absorbing material, 3 is a plenum coil, and the stress concentration generating portion 4 shown in FIG. 3 is eliminated. As another means, an example in which the shape of the upper end of the neutron absorbing material is rounded instead of being tapered is possible.

【0007】[0007]

【作用】[Action]

中性子吸収材の上端部をテーパー状にしたので、振動により中性子吸収材の上 端部がステンレス鋼管内面に衝突を繰り返しても、またクリープ変形によりステ ンレス鋼管と中性子吸収材上端部が接触しても、応力が集中せず、拡散するよう になる。 Since the upper end of the neutron absorbing material is tapered, even if the upper end of the neutron absorbing material repeatedly collides with the inner surface of the stainless steel pipe due to vibration, the stainless steel pipe and the upper end of the neutron absorbing material contact due to creep deformation. However, the stress does not concentrate, but diffuses.

【0008】[0008]

【実施例】【Example】

図2は実施例で、テーパー部の長さLをステンレス鋼管の内径Dとほぼ等しい 寸法とする。(L≒D) また、テーパー部の角度αは約5°である。 FIG. 2 shows an embodiment, and the length L of the tapered portion is set to be substantially equal to the inner diameter D of the stainless steel pipe. (L≈D) Further, the angle α of the taper portion is about 5 °.

【0009】[0009]

【考案の効果】[Effect of the device]

中性子吸収材の上端部をテーパー状としたので、ステンレス鋼管の応力集中が 抑制され、耐疲労性が向上し、制御棒クラスタの長寿命化に貢献する。 Since the upper end of the neutron absorber is tapered, stress concentration on the stainless steel pipe is suppressed, fatigue resistance is improved, and the life of the control rod cluster is extended.

【図面の簡単な説明】[Brief description of drawings]

【図1】本考案の制御棒クラスタの制御棒における中性
子吸収材上端部の具体例説明図である。
FIG. 1 is an explanatory view of a specific example of an upper end portion of a neutron absorber in a control rod of a control rod cluster of the present invention.

【図2】本考案の制御棒クラスタの制御棒における中性
子吸収材上端部の実施例説明図である。
FIG. 2 is an explanatory view of an embodiment of the upper end portion of the neutron absorber in the control rod of the control rod cluster of the present invention.

【図3】従来の制御棒クラスタの制御棒における中性子
吸収材上端部の説明図である。
FIG. 3 is an explanatory diagram of a neutron absorbing material upper end portion in a control rod of a conventional control rod cluster.

【図4】従来の制御棒クラスタの説明図で、(A)はス
パイダーの上視図,(B)は側面図である。
4A and 4B are explanatory views of a conventional control rod cluster, in which FIG. 4A is a top view of a spider, and FIG. 4B is a side view.

【符号の説明】[Explanation of symbols]

1 ステンレス鋼管 2 中性子吸収材 2a 中性子吸収材のテーパー部 L テーパー部の長さ D ステンレス鋼管の内径 α テーパーの角度 1 stainless steel pipe 2 neutron absorber 2a taper part of neutron absorber L length of taper part D inner diameter of stainless steel pipe α taper angle

Claims (1)

【実用新案登録請求の範囲】 【請求項1】 制御棒クラスタを構成している各制御棒
のステンレス鋼管内の中性子吸収材がその上端部におい
てテーパー状を呈していることを特徴とする制御棒クラ
スタ。
[Claims for utility model registration] [Claim 1] The control rod is characterized in that the neutron absorbing material in the stainless steel pipe of each control rod forming the control rod cluster is tapered at the upper end thereof. cluster.
JP082611U 1991-07-05 1991-07-05 Control rod cluster Withdrawn JPH056397U (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP082611U JPH056397U (en) 1991-07-05 1991-07-05 Control rod cluster

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP082611U JPH056397U (en) 1991-07-05 1991-07-05 Control rod cluster

Publications (1)

Publication Number Publication Date
JPH056397U true JPH056397U (en) 1993-01-29

Family

ID=13779276

Family Applications (1)

Application Number Title Priority Date Filing Date
JP082611U Withdrawn JPH056397U (en) 1991-07-05 1991-07-05 Control rod cluster

Country Status (1)

Country Link
JP (1) JPH056397U (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2009503463A (en) * 2005-07-29 2009-01-29 アレヴァ エンペー ゲゼルシャフト ミット ベシュレンクテル ハフツング Pressurized water reactor control rod

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2009503463A (en) * 2005-07-29 2009-01-29 アレヴァ エンペー ゲゼルシャフト ミット ベシュレンクテル ハフツング Pressurized water reactor control rod
US8295427B1 (en) 2005-07-29 2012-10-23 Areva Np Gmbh Control rod for a pressurized water nuclear reactor

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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: 19951102