JPS62294995A - Pressure vessel for nuclear reactor - Google Patents
Pressure vessel for nuclear reactorInfo
- Publication number
- JPS62294995A JPS62294995A JP61138199A JP13819986A JPS62294995A JP S62294995 A JPS62294995 A JP S62294995A JP 61138199 A JP61138199 A JP 61138199A JP 13819986 A JP13819986 A JP 13819986A JP S62294995 A JPS62294995 A JP S62294995A
- Authority
- JP
- Japan
- Prior art keywords
- control rod
- drive mechanism
- pressure vessel
- rod drive
- mechanism housing
- 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.)
- Granted
Links
- 230000007246 mechanism Effects 0.000 claims description 50
- 239000000919 ceramic Substances 0.000 claims description 4
- 239000000498 cooling water Substances 0.000 description 8
- 230000008646 thermal stress Effects 0.000 description 7
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 5
- 210000000078 claw Anatomy 0.000 description 4
- 230000037431 insertion Effects 0.000 description 4
- 238000003780 insertion Methods 0.000 description 4
- 238000003466 welding Methods 0.000 description 4
- 238000009835 boiling Methods 0.000 description 3
- 230000006866 deterioration Effects 0.000 description 3
- 230000006835 compression Effects 0.000 description 2
- 238000007906 compression Methods 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 239000000463 material Substances 0.000 description 2
- 229910052770 Uranium Inorganic materials 0.000 description 1
- 239000003795 chemical substances by application Substances 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 238000003384 imaging method Methods 0.000 description 1
- 238000009413 insulation Methods 0.000 description 1
- 230000002093 peripheral effect Effects 0.000 description 1
- 230000009257 reactivity Effects 0.000 description 1
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 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
Abstract
(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.
Description
【発明の詳細な説明】
３、発明の詳細な説明
［発明の目的］
（産業上の利用分野）
本発明は沸騰水型原子炉圧力容器に係り、特に原子炉圧
力容器本体の底部に制御棒駆動機構ハウジングを取り付
けた原子炉圧力容器の改良に関する。Detailed Description of the Invention 3. Detailed Description of the Invention [Object of the Invention] (Industrial Field of Application) The present invention relates to a boiling water reactor pressure vessel, and in particular a control rod installed at the bottom of the reactor pressure vessel body. This invention relates to improvement of a nuclear reactor pressure vessel equipped with a drive mechanism housing.
（従来の技術）
従来の原子炉圧力容器は第３図の断面図に示すように、
原子炉圧力容器本体４の底部には制御棒駆動機構１を収
納した制御棒駆動機構ハウジング３が多数設けられてあ
り、この制御棒駆動機構１により制御棒２の炉心内への
挿脱が調整され、これにより原子炉の出力が制御される
。(Prior art) A conventional nuclear reactor pressure vessel, as shown in the cross-sectional view of Figure 3,
A large number of control rod drive mechanism housings 3 housing control rod drive mechanisms 1 are provided at the bottom of the reactor pressure vessel body 4, and the control rod drive mechanisms 1 adjust the insertion and removal of the control rods 2 into the reactor core. , which controls the power output of the reactor.
しかして、沸騰水型原子炉の制御棒駆動機構１は原子炉
圧力容器４の底部に設けられているため、異物の制御棒
駆動機構１内への降下による摺動部（Ａの劣化防止及び
摺動部材の熱劣化防止のため冷却水を流す溝造としてい
る。However, since the control rod drive mechanism 1 of the boiling water reactor is provided at the bottom of the reactor pressure vessel 4, it is difficult to prevent deterioration of the sliding part (A) due to foreign matter falling into the control rod drive mechanism 1. A groove structure is used to allow cooling water to flow to prevent thermal deterioration of sliding members.
（発明が解決しようとする問題点）
ところで、上記のような沸騰水型原子炉においては、冷
却水の温度は通常５０〜７０℃である。一方、原子炉圧
力容器の通常運転温度は２８５°Ｃであるため、制御棒
駆動機構１を収納する制御棒駆動機構ハウジング３及び
制御棒駆動機構ハウジング３を原子炉圧力容器４に取り
付けるスタブチューブ５の熱応力が高いという欠点があ
った。(Problems to be Solved by the Invention) Incidentally, in the above boiling water reactor, the temperature of the cooling water is usually 50 to 70°C. On the other hand, since the normal operating temperature of the reactor pressure vessel is 285°C, the control rod drive mechanism housing 3 that houses the control rod drive mechanism 1 and the stub tube 5 that attaches the control rod drive mechanism housing 3 to the reactor pressure vessel 4 The disadvantage was that the thermal stress was high.
熱応力が高くなる原因としては、制御棒駆動機構ハウジ
ング３とスタブチューブ５とのクリアランスが小ざいこ
とと、制御棒駆動機、（Ｍハウジング３とスタブチュー
ブ５とのクリアランスの確保は制御棒駆動機構ハウジン
グ３とスタブチューブ５の溶接部のみでおるため、溶接
時の歪により制御棒駆動機構ハウジング３とスタブチュ
ーブ５とが接触すると、原子炉圧力容器４から制御棒駆
動機構ハウジング３への熱伝導が発生し、制御棒駆動機
構ハウジング３の内壁と外壁に大ぎな温度勾配が発生す
ることになる。The reason for the high thermal stress is that the clearance between the control rod drive mechanism housing 3 and the stub tube 5 is small, and the clearance between the control rod drive mechanism housing 3 and the stub tube 5 is secured by the control rod drive mechanism. Since this occurs only at the weld between the mechanism housing 3 and the stub tube 5, if the control rod drive mechanism housing 3 and the stub tube 5 come into contact due to distortion during welding, heat will be transferred from the reactor pressure vessel 4 to the control rod drive mechanism housing 3. Conduction will occur and a large temperature gradient will occur between the inner and outer walls of the control rod drive mechanism housing 3.
このため、前記した温度勾配を小さくし、制御棒駆動機
構ハウジング３及びスタブチューブ５に発生する熱応力
を低減することが望まれていた。Therefore, it has been desired to reduce the temperature gradient described above and reduce the thermal stress generated in the control rod drive mechanism housing 3 and the stub tube 5.
本発明は上記事情に鑑みてなされたもので、その目的は
、原子炉圧力容器のスタブチューブと制御棒駆動機構ハ
ウジングとの熱応力を低減するように構成した制御棒駆
動機構ハウジングの貫通孔を備えた原子炉圧力容器を提
供することにある。The present invention has been made in view of the above circumstances, and its object is to provide a through-hole in a control rod drive mechanism housing configured to reduce thermal stress between the stub tube of a reactor pressure vessel and the control rod drive mechanism housing. An object of the present invention is to provide a nuclear reactor pressure vessel equipped with the following features.
［発明の構成］
（問題点を解決するための手段）
本発明は上記目的を達成するために、原子炉圧力容器本
体に設けた貫通孔の軸方向に突起部を少なくとも２ケ所
設（ブ、この突起部を介して制御棒駆動機構ハウジング
を原子炉圧力容器に取り付けたものである。また、貫通
孔の軸方向に円筒上のスタブチューブを取り付け、この
スタブチューブに突起部を少なくとも１ケ所、また前記
貫通孔にも突起部を少なくとも１ケ所設け、これらの突
起部を介して制御棒駆動機構ハウジングを原子炉圧力容
器に取り付けたものであり、ざらに、前記貫通孔に設け
た突起部をセラミックスで形成したものでおる。[Structure of the Invention] (Means for Solving the Problems) In order to achieve the above object, the present invention provides at least two protrusions in the axial direction of the through hole provided in the reactor pressure vessel body. The control rod drive mechanism housing is attached to the reactor pressure vessel via this protrusion.Also, a cylindrical stub tube is attached in the axial direction of the through hole, and at least one protrusion is attached to the stub tube. The through hole is also provided with at least one protrusion, and the control rod drive mechanism housing is attached to the reactor pressure vessel via these protrusions. It is made of ceramics.
（作 用）
上記の如く構成された原子炉圧力容器においては、突起
部により制御棒駆動機構ハウジングと貫通孔内の外径面
とを接触させることにより制御棒駆動機構ハウジング外
径面と原子炉圧力容器の内径面間にギャップが設けられ
、原子炉圧力容器から制御棒駆動機構ハウジングに熱か
伝わらないため、熱応力低減が可能となる。さらに、制
御棒駆動機構ハウジングを少なくとも２点で支持するこ
とにより撮動剛性が高められる。(Function) In the reactor pressure vessel configured as described above, the control rod drive mechanism housing and the outer diameter surface in the through hole are brought into contact with each other by the protrusion, so that the outer diameter surface of the control rod drive mechanism housing and the reactor reactor are brought into contact with each other. A gap is provided between the inner diameter surfaces of the pressure vessel, and heat is not transferred from the reactor pressure vessel to the control rod drive mechanism housing, making it possible to reduce thermal stress. Furthermore, by supporting the control rod drive mechanism housing at at least two points, imaging rigidity is increased.
（実施例） 本発明の実施例を図面を参照して説明する。(Example) Embodiments of the present invention will be described with reference to the drawings.
第１図は本発明の一実施例の縦断面図でおり、同図に示
すように、原子炉圧力容器本体４の下部には制御棒駆動
機構１が取り付けられ、制御棒駆動機構１の作動により
制御棒２が原子炉炉心部（図示せず）に挿脱し、原子炉
内のウラン燃料の核反応度を調整して原子炉の運転が制
御される。FIG. 1 is a longitudinal sectional view of one embodiment of the present invention. As shown in the figure, a control rod drive mechanism 1 is attached to the lower part of the reactor pressure vessel body 4, and the control rod drive mechanism 1 is operated. The control rods 2 are inserted into and removed from the reactor core (not shown), and the nuclear reactivity of the uranium fuel in the reactor is adjusted to control the operation of the reactor.
原子炉圧力容器本体４の下部には貫通孔８が市けられて
いる。貫通孔８の軸方向に治って円筒状のスタブチュー
ブ５が原子炉圧力容器本体４の内側に溶接１２により取
り付けられている。スタブチューブ５はその端部内側に
向って突起部９を有し、一方、貫通孔８もその一部に突
起部１０を有している。なお、第１図においては突起部
１０は原子炉圧力容器４と同一材料で形成されているが
、第２図に示すように、突起部１０ａを原子炉圧力容器
本体４とは異なる材料、例えばセラミックス等の断熱効
果の優れた材料で形成してもよい。A through hole 8 is formed in the lower part of the reactor pressure vessel body 4 . A cylindrical stub tube 5 extending in the axial direction of the through hole 8 is attached to the inside of the reactor pressure vessel body 4 by welding 12. The stub tube 5 has a protrusion 9 toward the inner side of its end, and the through hole 8 also has a protrusion 10 at a portion thereof. In FIG. 1, the protrusion 10 is made of the same material as the reactor pressure vessel 4, but as shown in FIG. It may be formed of a material with excellent heat insulation effect, such as ceramics.
ところで、制御棒駆動機構ハウジング３は貫通孔８とス
タブチューブ５の中空部に挿入され、突起部９に溶接部
７により取り付けられ、突起部１０で当接して保持され
る。制御棒駆動機構ハウジング３の外周３１と、スタブ
チューブ５の内面５１とは直接接触せずそこには間隙１
１が形成される。By the way, the control rod drive mechanism housing 3 is inserted into the through hole 8 and the hollow part of the stub tube 5, is attached to the protrusion 9 by the welding part 7, and is held in contact with the protrusion 10. The outer periphery 31 of the control rod drive mechanism housing 3 and the inner surface 51 of the stub tube 5 do not directly contact each other, and there is a gap 1 therebetween.
1 is formed.
次に、制御棒駆動機構ハウジング３の内部の構成につい
て説明する。Next, the internal configuration of the control rod drive mechanism housing 3 will be explained.
制御棒駆動機構ハウジング３は円筒で形成され、その内
部に制御棒駆動機構ハウジング３に支持された円筒状の
固定パイプ２０を有している。この固定パイプ２０の外
周に摺動可能に制御棒２と直結したピストンシリンダ２
１が配設されている。このピストンシリンダ２１の周方
向には複数の切欠部２２が設けられ、この切欠部２２は
更にその外周に配設されたキャッチリング２３の爪３０
と係合するよう構成されている。このキャッチリング２
３は制御棒駆動機構ハウジング３に支持された円筒２４
．２５間を上下に摺動するようにその先端部３３は複数
に分割されて構成されている。そして、圧縮バネ２６は
キャッチリング２３と円筒２５の間に設けられ、キャッ
チリング２３を下方に付勢している。The control rod drive mechanism housing 3 is formed of a cylinder, and has a cylindrical fixed pipe 20 supported by the control rod drive mechanism housing 3 inside. A piston cylinder 2 slidably connected directly to the control rod 2 on the outer periphery of the fixed pipe 20
1 is arranged. A plurality of notches 22 are provided in the circumferential direction of this piston cylinder 21, and these notches 22 further include claws 30 of a catch ring 23 disposed on the outer periphery of the notches 22.
configured to engage with. This catch ring 2
3 is a cylinder 24 supported by the control rod drive mechanism housing 3
．． The distal end portion 33 is divided into a plurality of parts so as to be able to slide vertically between 25 and 25. A compression spring 26 is provided between the catch ring 23 and the cylinder 25, and urges the catch ring 23 downward.
次に、先ず、上記の如く構成された本実施例の作用につ
いて説明する。Next, first, the operation of this embodiment configured as described above will be explained.
制御棒駆動機構ハウジング３の外径部３１は貫通孔８の
内面８１およびスタブチューブ５の内面５１に接触せず
、必ず、一定の間隙１１が保たれる。この間隙１１は気
体で満されるためスタブチューブ５の内外面及び制御棒
駆動機構ハウジング３の内外面での温度差を小さく保つ
ことができ、スタブチューブ５及び制御棒駆動機構ハウ
ジング３の熱応力を低減することができる。さらに、突
起部１０をセラミックス等で構成すると、原子炉圧力容
器本体４から制御棒駆動機構ハウジング３への熱伝導を
低く押さえることができる。The outer diameter portion 31 of the control rod drive mechanism housing 3 does not come into contact with the inner surface 81 of the through hole 8 and the inner surface 51 of the stub tube 5, and a constant gap 11 is always maintained. Since this gap 11 is filled with gas, the temperature difference between the inner and outer surfaces of the stub tube 5 and the control rod drive mechanism housing 3 can be kept small, resulting in thermal stress in the stub tube 5 and the control rod drive mechanism housing 3. can be reduced. Furthermore, if the protrusion 10 is made of ceramic or the like, heat conduction from the reactor pressure vessel body 4 to the control rod drive mechanism housing 3 can be kept low.
ところで、原子炉運転時には第１図に示すように制御棒
駆動機構１内には挿入ポート２８から冷却水が円筒２５
の外面と制御棒駆動機構ハウジング３の内面の間を通じ
て矢印２７で示されるように供給される。冷却水を供給
する目的は、炉心内から制御棒駆動機構１内への異物の
降下の防止及び制御棒駆動機構１内の摺動部材の熱劣化
防止のために供給され通常の冷却水の温度は５０〜７０
’Ｃでおる。By the way, during reactor operation, cooling water flows into the control rod drive mechanism 1 from the insertion port 28 into the cylinder 25, as shown in FIG.
and the inner surface of the control rod drive mechanism housing 3 as shown by arrow 27. The purpose of supplying cooling water is to prevent foreign matter from falling from inside the core into the control rod drive mechanism 1 and to prevent thermal deterioration of sliding members in the control rod drive mechanism 1. is 50-70
'C.
先ず、制御棒２を原子炉炉心部に挿入する場合（上方向
への移動）について説明する。First, the case where the control rod 2 is inserted into the reactor core (movement upward) will be described.
挿入ポート２８から冷却水を供給すると、その冷却水は
空間２９に入り、その圧力でピストンシリンダ２１を上
方に押し上げる。この時、切欠部２２は、その形状によ
って、キャッチリング２３を外側に広げ切欠部２２と爪
３０との係合が解かれる。When cooling water is supplied from the insertion port 28, the cooling water enters the space 29, and its pressure pushes the piston cylinder 21 upward. At this time, depending on the shape of the notch 22, the catch ring 23 is expanded outward, and the engagement between the notch 22 and the pawl 30 is released.
そして、ピストンシリンダ２１が適当な位置にきた時、
やはり次の適当な位置にある切欠部２２と爪３０とが係
合し、制御棒２の落下を防止する。Then, when the piston cylinder 21 comes to the appropriate position,
The notch 22 at the next appropriate position engages with the pawl 30 to prevent the control rod 2 from falling.
次に、制御棒２を原子炉炉心部から引扱く場合（下方向
への移動）について説明する。Next, a case in which the control rod 2 is handled from the reactor core (downward movement) will be described.
引火ポート３２から冷却水を供給すると、円筒２４と２
５の間に入り、その水圧でキャッチリング２３を押し上
げる。すると、キャッチリング２３の上端部３３は円筒
２５の端部３４に当接し、爪３０は外側に広がり、爪３
０と切欠部２２の係合は解かれ制御棒２は自重で落下す
る。When cooling water is supplied from the flash port 32, the cylinders 24 and 2
5, and its water pressure pushes up the catch ring 23. Then, the upper end 33 of the catch ring 23 comes into contact with the end 34 of the cylinder 25, the claw 30 spreads outward, and the claw 3
0 and the notch 22 are disengaged, and the control rod 2 falls under its own weight.
［発明の効果］
以上説明したように、本発明によれば、原子炉圧力容器
の貫通孔の内周面に貫通孔の軸方向に少なくとも２ケ所
の突起部を周方向に設け、この突起部により制御棒駆動
機構ハウジングと貫通孔の間に確実に間隙を持たせたの
で、制御棒駆動機構の冷却水温度と原子炉温度に起因す
るスタブチューブ及び制御棒駆動機構ハウジングの熱応
力を大幅に低下でき、原子炉の信頼性をより一層向上さ
せることができる。ざらに、制御棒駆動機構ハウジング
の支持点を複数個とすることができるので、耐震性も向
上させることができる。[Effects of the Invention] As explained above, according to the present invention, at least two protrusions are circumferentially provided on the inner peripheral surface of the through hole of the reactor pressure vessel in the axial direction of the through hole, and the protrusions By ensuring a gap between the control rod drive mechanism housing and the through hole, thermal stress in the stub tube and control rod drive mechanism housing caused by the cooling water temperature of the control rod drive mechanism and the reactor temperature can be greatly reduced. The reliability of the nuclear reactor can be further improved. In general, since the control rod drive mechanism housing can have a plurality of support points, earthquake resistance can also be improved.
第１図は本発明の一実施例の断面図、第２図は本発明の
他の実施例の一部拡大断面図、第３図は本発明が適用さ
れる従来の原子炉圧力容器の断面図である。
１・・・制御棒駆動機構 ２・・・制御棒３・・・制
御棒駆動機構ハウジング
４・・・原子炉圧力容器 ５・・・スタブチューブ７
・・・溶接部 ８・・・貫通孔９．１０・・
・突起部 １１・・・間隙１２・・・溶接
２０・・・固定パイプ２１・・・ピストンシリ
ンダ、２２・・・切欠部２３・・・キャッチリング
２４、２５・・・円筒 ２６・・・圧縮バネ２
７・・・冷水の流れ ２８・・・挿入ポート２９
・・・空間 ３０・・・爪３１・・・外周
３２・・・引扱ボート３３・・・上端部
３４・・・端部５１．８１・・・内面
（８７３３）代理人 弁理士 猪 股 祥 晃（ばか１
名）
第１図
第２図
第３図FIG. 1 is a sectional view of one embodiment of the present invention, FIG. 2 is a partially enlarged sectional view of another embodiment of the present invention, and FIG. 3 is a sectional view of a conventional nuclear reactor pressure vessel to which the present invention is applied. It is a diagram. 1... Control rod drive mechanism 2... Control rod 3... Control rod drive mechanism housing 4... Reactor pressure vessel 5... Stub tube 7
...Welded part 8...Through hole 9.10...
・Protrusion 11...Gap 12...Welding
20... Fixed pipe 21... Piston cylinder, 22... Notch portion 23... Catch ring 24, 25... Cylinder 26... Compression spring 2
7... Cold water flow 28... Insertion port 29
...Space 30...Claw 31...Outer periphery 32...Handling boat 33...Top end 34...End 51.81...Inner surface (8733) Agent Patent attorney Sho Inomata Akira (baka 1)
Figure 1 Figure 2 Figure 3
Claims (3)
貫通孔内に制御棒駆動機構ハウジングを取り付けるよう
にした原子炉圧力容器において、前記貫通孔の軸方向に
突起部を少なくとも２ケ所設け、これらの突起部を介し
て前記制御棒駆動機構ハウジングを前記原子炉圧力容器
に取り付けるようにしたことを特徴とする原子炉圧力容
器。(1) In a reactor pressure vessel in which a through hole is provided at the bottom of the reactor pressure vessel body and a control rod drive mechanism housing is installed in the through hole, projections are provided at at least two locations in the axial direction of the through hole. and the control rod drive mechanism housing is attached to the reactor pressure vessel via these protrusions.
付け、このスタブチューブに突起部を少なくとも１ケ所
、また貫通孔にも突起部を少なくとも１カ所設け、これ
らの突起部を介して制御棒駆動機構ハウジングを原子炉
圧力容器に取り付けている特許請求の範囲第１項記載の
原子炉圧力容器。(2) A cylindrical stub tube is installed in the axial direction of the through hole, and the stub tube is provided with at least one protrusion, and the through hole is also provided with at least one protrusion, and the control rod is inserted through these protrusions. A nuclear reactor pressure vessel according to claim 1, wherein the drive mechanism housing is attached to the reactor pressure vessel.
ている特許請求の範囲第１項記載の原子炉圧力容器。(3) The reactor pressure vessel according to claim 1, wherein the protrusion provided in the through hole is made of ceramic.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP61138199A JPH077089B2 (en) | 1986-06-16 | 1986-06-16 | Reactor pressure vessel |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP61138199A JPH077089B2 (en) | 1986-06-16 | 1986-06-16 | Reactor pressure vessel |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS62294995A true JPS62294995A (en) | 1987-12-22 |
| JPH077089B2 JPH077089B2 (en) | 1995-01-30 |
Family
ID=15216396
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP61138199A Expired - Lifetime JPH077089B2 (en) | 1986-06-16 | 1986-06-16 | Reactor pressure vessel |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH077089B2 (en) |
Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5834092U (en) * | 1981-08-31 | 1983-03-05 | 石川島播磨重工業株式会社 | Through-hole structure for control rod guide tube of reactor pressure vessel |
-
1986
- 1986-06-16 JP JP61138199A patent/JPH077089B2/en not_active Expired - Lifetime
Patent Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5834092U (en) * | 1981-08-31 | 1983-03-05 | 石川島播磨重工業株式会社 | Through-hole structure for control rod guide tube of reactor pressure vessel |
Also Published As
| Publication number | Publication date |
|---|---|
| JPH077089B2 (en) | 1995-01-30 |
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