JPS587196B2 - control rod - Google Patents

control rod

Info

Publication number
JPS587196B2
JPS587196B2 JP53121565A JP12156578A JPS587196B2 JP S587196 B2 JPS587196 B2 JP S587196B2 JP 53121565 A JP53121565 A JP 53121565A JP 12156578 A JP12156578 A JP 12156578A JP S587196 B2 JPS587196 B2 JP S587196B2
Authority
JP
Japan
Prior art keywords
control rod
sheath
fuel body
stainless steel
stiffener
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
Application number
JP53121565A
Other languages
Japanese (ja)
Other versions
JPS5548692A (en
Inventor
新野毅
盛山武夫
落合兼寛
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.)
Hitachi Ltd
Original Assignee
Hitachi 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 Hitachi Ltd filed Critical Hitachi Ltd
Priority to JP53121565A priority Critical patent/JPS587196B2/en
Publication of JPS5548692A publication Critical patent/JPS5548692A/en
Publication of JPS587196B2 publication Critical patent/JPS587196B2/en
Expired 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

  • Thyristor Switches And Gates (AREA)

Description

【発明の詳細な説明】 本発明は制御棒に係り、特に沸騰水型原子炉に使用する
原子炉燃料体の地震時の変形に追従して変形し、かつ、
適当な剛さと十分な強度をもたせるのに好適な構造の制
御棒に関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a control rod that deforms in accordance with the deformation of a reactor fuel assembly used in a boiling water reactor during an earthquake, and
The present invention relates to a control rod having a structure suitable for providing appropriate rigidity and sufficient strength.

従来の沸騰水型原子炉に使用される制御棒は、第1図、
第2図に示すように構成されていた。
The control rods used in conventional boiling water reactors are shown in Figure 1.
It was constructed as shown in Figure 2.

第1図において、1は十字型のタイロツドで、タイロツ
ド1の十字型の各辺には、第2図に示すように、内部に
中性子吸収材であるボロンカーバイト5が允填してある
ポイズンチューブ6が複数本配列してあり、冷却効果を
増大するだめの複数個の穴7が設けてあるステンレスシ
ース2が根元で溶接によって固定してあり、全体として
も十字型になっている。
In Figure 1, numeral 1 is a cross-shaped tie rod, and each side of the cross shape of tie rod 1 is filled with a poison filled with boron carbide 5, which is a neutron absorbing material, inside, as shown in Figure 2. A stainless steel sheath 2 in which a plurality of tubes 6 are arranged and provided with a plurality of holes 7 for increasing the cooling effect is fixed by welding at the base, and the whole has a cross shape.

そしてステンレスシース2の長手方向の上端には上端固
定板3が、下端には下端固定板4が溶接接合されていて
、十字型が保持されており、全体が一体となった剛構造
となっている。
An upper end fixing plate 3 is welded to the upper end of the stainless steel sheath 2 in the longitudinal direction, and a lower end fixing plate 4 is welded to the lower end of the stainless steel sheath 2 to maintain a cross shape, resulting in an integrated rigid structure. There is.

第3図は原子炉炉心の概略図で、原子炉炉心を支持して
いる円筒状のシュラウド7の内部には数百本の燃料体8
がその上端を上部格子板9で下端を炉心サポート10で
いわゆるピン支持された状態で収納されており、制御棒
案内管11内に納められた制御棒12が燃料体8相互間
の間隙に挿入された構成になっている。
Figure 3 is a schematic diagram of the nuclear reactor core. Inside the cylindrical shroud 7 that supports the reactor core, there are hundreds of fuel bodies 8.
The control rods 12 housed in the control rod guide tubes 11 are inserted into the gaps between the fuel bodies 8. The configuration is as follows.

ところで、第3図に示す原子炉炉心に水平地震力が加わ
った場合、燃料体8は上記したように支持されているた
め振動するが、燃料体8は制御棒12に比較して大きい
重量をもっているので、このとき制御棒12が燃料体8
によって押し曲げられた形で燃料体8相互間の間隙に挿
入されていく。
By the way, when a horizontal seismic force is applied to the nuclear reactor core shown in FIG. At this time, the control rod 12 is connected to the fuel body 8.
The fuel bodies 8 are inserted into the gaps between the fuel bodies 8 in a pressed and bent form.

第4図は原子炉炉心部に水平地震力が加わった場合の制
御棒の変形状態を示した図で、地震力がない場合は、同
図aに示すように、制御棒12が燃料体8相互間の間隙
に変形することなく挿入される。
Figure 4 is a diagram showing the deformation state of the control rods when a horizontal seismic force is applied to the reactor core.When there is no seismic force, the control rods 12 move to the fuel body 8 as shown in figure a. It can be inserted into the gap between them without being deformed.

しかし、水平地震力が加わった場合は同図bに示すよう
に、制御棒12はタイロツド1を中立軸とする面内曲げ
変形をおこした状態で挿入され、中央部ではわずかの変
形でも、ステンンスシース2の外端部においては変形量
が大きくなり、ステンレスシース2の破損をまねきやす
くなる。
However, when a horizontal seismic force is applied, the control rod 12 is inserted with an in-plane bending deformation with the tie rod 1 as the neutral axis, as shown in Figure b. The amount of deformation becomes large at the outer end of the stainless steel sheath 2, which tends to cause damage to the stainless steel sheath 2.

そのだめ、従来、第1図、第2図のタイロツド1とステ
ンレスシース2とを切り離すか、あるいは、第5図に示
すように、ステンレスシース2の外端部に外側に開口す
る切欠き2aを所定間隔で複数個設け、シース2の外端
部の応力緩和をはかり、制御棒12の剛性を低下させ、
燃料体8の地震時の変形に追従しやすいようにすること
が提案されている。
Therefore, conventionally, the tie rod 1 and the stainless steel sheath 2 shown in FIGS. 1 and 2 are separated, or, as shown in FIG. A plurality of rods are provided at predetermined intervals to relieve stress at the outer end of the sheath 2 and reduce the rigidity of the control rod 12.
It has been proposed to make it easier to follow the deformation of the fuel body 8 during an earthquake.

しかしながら、前者においては、切り離されたタイロツ
ド1が地震時の水平加振力を受ける際に、タイロツド1
が独自で激しく振動して曲げ変形を起し、加振と直角方
向のシース2と接触し、シース2を破損させることがあ
る。
However, in the former case, when the separated tie rod 1 receives horizontal excitation force during an earthquake, the tie rod 1
may vibrate violently on its own, cause bending deformation, come into contact with the sheath 2 in a direction perpendicular to the vibration, and damage the sheath 2.

また、後者においては、シース2の応力緩和策としては
非常に有効であるが、制御棒12が曲げ変形を受ける際
、切欠き2aが変形し、燃料体8との接触摩擦の増加を
引き起し、制御棒12の挿入性が阻害される。
In the latter case, although it is very effective as a stress relief measure for the sheath 2, when the control rod 12 undergoes bending deformation, the notch 2a deforms, causing an increase in contact friction with the fuel body 8. However, the insertability of the control rod 12 is hindered.

一方、あまりに柔構造となるため、挿入性に欠けるとい
う問題がある。
On the other hand, since the structure is too flexible, there is a problem in that it lacks insertability.

本発明の目的は、上記した従来技術の欠点をなくし、燃
料体の変形に容易に追従でき、かつ、適当な剛さと十分
な強度をもち、挿入性を良好にできる制御棒を提供する
ことにある。
An object of the present invention is to eliminate the above-mentioned drawbacks of the prior art, and to provide a control rod that can easily follow the deformation of a fuel body, has appropriate stiffness and sufficient strength, and can be easily inserted. be.

本発明の特徴は、断面が十字形で長手方向に所定間隔毎
に外側に開口するように切欠きが設けてあるシースのそ
れぞれの切欠きの間の部分に凸部を設けるようにした点
にある。
A feature of the present invention is that the sheath has a cross-shaped cross section and is provided with notches that open outward at predetermined intervals in the longitudinal direction, and a convex portion is provided between each of the notches. be.

以下本発明を第6図ないし第8図に示した実施例および
第9図を用いて詳細に説明する。
The present invention will be described in detail below with reference to the embodiments shown in FIGS. 6 to 8 and FIG. 9.

第6図は本発明の制御棒の一実施例を示す斜視図、第7
図は第6図のC−C線断面図である。
FIG. 6 is a perspective view showing one embodiment of the control rod of the present invention, and FIG.
The figure is a sectional view taken along line CC in FIG. 6.

第6図、第7図において、第1図、第2図と同一部分は
同じ符号で示し、説明を省略する。
In FIGS. 6 and 7, the same parts as in FIGS. 1 and 2 are designated by the same reference numerals, and their explanation will be omitted.

第1図、第2図と異なるところは、第6図に示すように
、ステンレスシース2の長手方向の外端部に所定間隔毎
に外側に開口するように複数詞の切欠き2aが設けてあ
り、また、それぞれの切欠き2aの間のシース2の内部
には、第7図に示すように、ステイフナ13が固着され
ており、ステイフナ13は第8図に示すように紡錘型に
なっているので、ステンレスシース2の内部にステイフ
ナ13が固着されている部分のシース2の外側にはステ
イフナ13の形状に合った形の凸部14が形成されてい
る。
The difference from FIGS. 1 and 2 is that, as shown in FIG. 6, plural notches 2a are provided at predetermined intervals at the outer end of the stainless steel sheath 2 in the longitudinal direction so as to open outward. Furthermore, a stiffener 13 is fixed inside the sheath 2 between each notch 2a, as shown in FIG. 7, and the stiffener 13 has a spindle shape as shown in FIG. Therefore, a convex portion 14 having a shape matching the shape of the stiffener 13 is formed on the outside of the sheath 2 in a portion where the stiffener 13 is fixed inside the stainless steel sheath 2.

上記したように、本発明の実施例によれば、ステンレス
シース2の長手方向外端部には所定間隔毎に切欠き2a
が設けてあり、また、それぞれの切欠き2aの間には凸
部14が設けてあるので、地震時等の水平外力が原子炉
炉心部に作用したときに、いくつかの有効性を発揮する
As described above, according to the embodiment of the present invention, the stainless steel sheath 2 has cutouts 2a at predetermined intervals at the outer end in the longitudinal direction.
Furthermore, since a convex portion 14 is provided between each notch 2a, it exhibits some effectiveness when a horizontal external force such as during an earthquake acts on the reactor core. .

以下その効果について説明する。The effect will be explained below.

第9図は原子炉炉心部に地震等の水平外力が作用し、燃
料体8が曲げ変形しているときに、燃料体8の間際に制
御棒12が挿入された状態の一例を示した図で、同図a
は燃料体8が曲げ変形していない状態、bは燃料体8が
曲げ変形している状態を示している。
FIG. 9 is a diagram showing an example of a state in which the control rod 12 is inserted just before the fuel body 8 when the fuel body 8 is bent and deformed due to a horizontal external force such as an earthquake acting on the reactor core. So, the same figure a
b shows a state in which the fuel body 8 is not bent and deformed, and b shows a state in which the fuel body 8 is bent and deformed.

燃料体8が第9図aのように外力によって曲げ変形した
場合、制御棒12のステンレスシース2は、上記したよ
うに2面内曲ケ変形を受けるが、シース2の外端部に切
欠き2aが設けてあるので、シース2は燃料体8の変位
に対して挿入時の追従性が良好で、また、シース2の外
端応力は大幅に緩和され、シース2が破損することがな
い。
When the fuel body 8 is bent and deformed by an external force as shown in FIG. 2a, the sheath 2 has good ability to follow the displacement of the fuel body 8 during insertion, and the stress at the outer end of the sheath 2 is greatly alleviated, so that the sheath 2 will not be damaged.

次に、燃料体8と制御棒12との接触形態は、シース2
に凸部14が形成されているので、部分接触となり、制
御棒12の挿入性に大きな影響をおよぼす燃料体8と制
御棒12間の摩擦力が大幅に低減され、同時にステイフ
ナ13は中実構造となっていて、充分な強度を有してい
るので、燃料体8と点接線あるいは線接触するときにも
、燃料体8と制御棒12間に極少の空隙を確実に確保で
き、シース2の切欠き2a部分が制御棒12の挿入時に
燃料体8に当って変形するというようなことは起らない
Next, the form of contact between the fuel body 8 and the control rod 12 is determined by the sheath 2
Since the convex portion 14 is formed on the surface of the fuel body 8, the frictional force between the fuel body 8 and the control rod 12, which causes partial contact and has a large effect on the insertability of the control rod 12, is significantly reduced.At the same time, the stiffener 13 has a solid structure. Since it has sufficient strength, it is possible to secure a very small gap between the fuel body 8 and the control rod 12 even when the fuel body 8 makes point-tangential or line contact with the sheath 2. There is no possibility that the notch 2a is deformed by hitting the fuel body 8 when the control rod 12 is inserted.

また、シース2内にステイフナ13が埋め込んであるの
で、適度の剛性を保持でき、切欠き2aによる柔とステ
イフナ13による剛の組合せによって、制御棒12の挿
入性がさらに良好となる。
Further, since the stiffener 13 is embedded in the sheath 2, it is possible to maintain appropriate rigidity, and the combination of the flexibility provided by the notch 2a and the stiffness provided by the stiffener 13 further improves the insertability of the control rod 12.

このような効果は、第9図に示すような燃料体8に対し
て直角方向の水平外力が作用した場合のみならず、対角
方句の水平外力が作用した場合にも同様に発揮される。
Such an effect is exhibited not only when a horizontal external force in a perpendicular direction is applied to the fuel body 8 as shown in FIG. 9, but also when a horizontal external force in a diagonal direction is applied. .

また、本発明の制御棒は、外形を従来のものとほぼ同一
にできるので、プラント全体に及ぼす悪影響は別にない
Furthermore, since the control rod of the present invention can have an approximately the same external shape as the conventional control rod, there is no adverse effect on the entire plant.

なお、ステンレスシース2の長手方向外端部に設ける切
欠き2aの大きさおよび場所、並びに切欠き2a間に設
ける凸部14の形状、大きさ、位置(ステイフナ13に
よって決まる。
Note that the size and location of the notch 2a provided at the outer end in the longitudinal direction of the stainless steel sheath 2, as well as the shape, size, and position (depending on the stiffener 13) of the convex portion 14 provided between the notches 2a.

)等については、本発明の効果が期待される範囲で適宜
選択できることは特に説明するまでもない。
) etc., it is needless to say that they can be appropriately selected within the range in which the effects of the present invention are expected.

以上説明したように、本発明によれば、燃料体の変形に
容易に追従でき、かつ、適当な剛さと十分な強度をもっ
ているので、挿入性を良好にできるという顕著な効果が
ある。
As explained above, according to the present invention, the fuel body can easily follow the deformation of the fuel body, and has appropriate rigidity and sufficient strength, so it has the remarkable effect of improving insertability.

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

第1図は従来の制御棒の斜視図、第2図は第1図のA−
A線断面図、第3図は原子炉炉心の概略図、第4図は従
来の制御棒が地震時に水平外力を受けた際の変形状況の
説明図、第5図は改良型制御棒の斜視図、第6図は本発
明の制御棒の一実施例を示す斜視図、第7図は第6図の
C−C線断面図、第8図は第7図のステイフナの斜視図
、第9図は、本発明に係る制御棒の燃料体変形時におけ
る挿入性の説明図である。 1・・・タイロツド、2・・・ステンレスシース、5・
・・ボロンカーバイト、6・・・ポイズンチューブ、8
・・・燃料体、12・・・制御棒、2a・・・切欠き、
13・・・ステイフナ、14・・・凸部。
Figure 1 is a perspective view of a conventional control rod, and Figure 2 is A-A in Figure 1.
A-line sectional view, Figure 3 is a schematic diagram of the reactor core, Figure 4 is an explanatory diagram of the deformation state when a conventional control rod receives horizontal external force during an earthquake, and Figure 5 is a perspective view of an improved control rod. 6 is a perspective view showing one embodiment of the control rod of the present invention, FIG. 7 is a sectional view taken along the line CC in FIG. 6, FIG. 8 is a perspective view of the stiffener in FIG. 7, and FIG. The figure is an explanatory diagram of the insertability of the control rod according to the present invention when the fuel body is deformed. 1... tie rod, 2... stainless steel sheath, 5...
...Boron carbide, 6...Poison tube, 8
... fuel body, 12 ... control rod, 2a ... notch,
13... Stiffener, 14... Convex portion.

Claims (1)

【特許請求の範囲】[Claims] 1 断面が十字形で長手方向に所定間隔毎に外側に開口
する切欠きが設けてあるシースと該シース内に装填され
た中性子吸収材とよりなる制御棒において、前記シース
のそれぞれの切欠きの間の部分に凸部が設けてあること
を特徴とする制御棒。
1. In a control rod consisting of a sheath with a cross-shaped cross section and cutouts opening outward at predetermined intervals in the longitudinal direction, and a neutron absorbing material loaded in the sheath, each of the cutouts in the sheath A control rod characterized in that a convex portion is provided between the parts.
JP53121565A 1978-10-04 1978-10-04 control rod Expired JPS587196B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP53121565A JPS587196B2 (en) 1978-10-04 1978-10-04 control rod

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP53121565A JPS587196B2 (en) 1978-10-04 1978-10-04 control rod

Publications (2)

Publication Number Publication Date
JPS5548692A JPS5548692A (en) 1980-04-07
JPS587196B2 true JPS587196B2 (en) 1983-02-08

Family

ID=14814371

Family Applications (1)

Application Number Title Priority Date Filing Date
JP53121565A Expired JPS587196B2 (en) 1978-10-04 1978-10-04 control rod

Country Status (1)

Country Link
JP (1) JPS587196B2 (en)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP4902418B2 (en) * 2007-04-27 2012-03-21 三菱電機株式会社 Circuit breaker mold frame

Also Published As

Publication number Publication date
JPS5548692A (en) 1980-04-07

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