JPH0448554Y2 - - Google Patents
Info
- Publication number
- JPH0448554Y2 JPH0448554Y2 JP1986140531U JP14053186U JPH0448554Y2 JP H0448554 Y2 JPH0448554 Y2 JP H0448554Y2 JP 1986140531 U JP1986140531 U JP 1986140531U JP 14053186 U JP14053186 U JP 14053186U JP H0448554 Y2 JPH0448554 Y2 JP H0448554Y2
- Authority
- JP
- Japan
- Prior art keywords
- sheath
- cooling water
- tip structure
- tie rod
- control rod
- 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
- 238000003466 welding Methods 0.000 claims description 7
- 238000010521 absorption reaction Methods 0.000 claims description 5
- 239000000498 cooling water Substances 0.000 description 23
- MHAJPDPJQMAIIY-UHFFFAOYSA-N Hydrogen peroxide Chemical compound OO MHAJPDPJQMAIIY-UHFFFAOYSA-N 0.000 description 18
- 239000001301 oxygen Substances 0.000 description 18
- 229910052760 oxygen Inorganic materials 0.000 description 18
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 description 17
- 230000007797 corrosion Effects 0.000 description 15
- 238000005260 corrosion Methods 0.000 description 15
- 230000013011 mating Effects 0.000 description 9
- 238000005336 cracking Methods 0.000 description 8
- 239000000463 material Substances 0.000 description 7
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 7
- 229910001220 stainless steel Inorganic materials 0.000 description 6
- 239000010935 stainless steel Substances 0.000 description 5
- 238000006243 chemical reaction Methods 0.000 description 4
- 239000002826 coolant Substances 0.000 description 4
- 239000007789 gas Substances 0.000 description 4
- 230000008878 coupling Effects 0.000 description 3
- 238000010168 coupling process Methods 0.000 description 3
- 238000005859 coupling reaction Methods 0.000 description 3
- 229910052580 B4C Inorganic materials 0.000 description 2
- 230000002159 abnormal effect Effects 0.000 description 2
- 239000011358 absorbing material Substances 0.000 description 2
- 229910000963 austenitic stainless steel Inorganic materials 0.000 description 2
- INAHAJYZKVIDIZ-UHFFFAOYSA-N boron carbide Chemical compound B12B3B4C32B41 INAHAJYZKVIDIZ-UHFFFAOYSA-N 0.000 description 2
- 238000000354 decomposition reaction Methods 0.000 description 2
- 239000002184 metal Substances 0.000 description 2
- 239000000843 powder Substances 0.000 description 2
- 238000005979 thermal decomposition reaction Methods 0.000 description 2
- 230000001133 acceleration Effects 0.000 description 1
- -1 and moreover Chemical compound 0.000 description 1
- 230000015572 biosynthetic process Effects 0.000 description 1
- 238000009835 boiling Methods 0.000 description 1
- 238000010349 cathodic reaction Methods 0.000 description 1
- 238000001816 cooling Methods 0.000 description 1
- 230000006866 deterioration Effects 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 239000007788 liquid Substances 0.000 description 1
- 238000005272 metallurgy Methods 0.000 description 1
- 230000003647 oxidation Effects 0.000 description 1
- 238000007254 oxidation reaction Methods 0.000 description 1
- 150000002926 oxygen Chemical class 0.000 description 1
- 230000036284 oxygen consumption Effects 0.000 description 1
- 238000003608 radiolysis reaction Methods 0.000 description 1
- 238000006722 reduction reaction Methods 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
- Butt Welding And Welding Of Specific Article (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Description
【考案の詳細な説明】
〔考案の目的〕
（産業上の利用分野）
本考案は軽水炉内で発生する冷却水による腐食
劣化を防止した原子炉用制御棒に関する。[Detailed description of the invention] [Purpose of the invention] (Field of industrial application) The present invention relates to a control rod for a nuclear reactor that prevents corrosion and deterioration due to cooling water generated in a light water reactor.
（従来の技術）
軽水炉、特に沸騰水型原子炉用制御棒は第３図
にその要部を示したように構成されている。(Prior Art) A control rod for a light water reactor, particularly a boiling water reactor, is constructed as shown in FIG. 3.
すなわち、従来の原子炉用制御棒（以下、制御
棒という）は、４枚の縦長のブレード１が十字状
に配列され、このブレード１の上端面に先端構造
材２が設けられ、この先端構造材２の上面にハン
ドル３が取着されている。 That is, in a conventional nuclear reactor control rod (hereinafter referred to as a control rod), four vertically long blades 1 are arranged in a cross shape, and a tip structure member 2 is provided on the upper end surface of the blade 1. A handle 3 is attached to the upper surface of the material 2.
４枚のブレード１は第４図に示したように中性
子吸収棒４を内包するＵ字状のステンレス鋼板の
シース５を有し、このシース５の上端部を先端構
造材２の下端部上に重ね合せて連続スミ肉溶接部
６を介して溶着している。 As shown in FIG. 4, the four blades 1 have a U-shaped stainless steel plate sheath 5 that encloses a neutron absorption rod 4, and the upper end of this sheath 5 is placed over the lower end of the tip structure member 2. They are overlapped and welded via a continuous fillet weld 6.
さらに、シース５は先端構造材２の減厚部２ａ
および中央部のタイロツド７に点溶接部８を介し
て固定されている。また、ブレード１の下端には
図示しない制御棒駆動機構と確実な結合ができる
ように結合ソケツトを有している。 Furthermore, the sheath 5 has a reduced thickness portion 2a of the tip structure member 2.
It is fixed to the tie rod 7 in the center via a spot weld 8. Further, the lower end of the blade 1 has a coupling socket for reliable coupling with a control rod drive mechanism (not shown).
なお、第４図は第３図で示すブレード１の一部
分を拡大して示す側面図である。中性子吸収棒４
は中性子吸収材としてボロンカーバイドの粉末を
ステンレス鋼製細管内に密に充填したものであ
り、この中性子吸収棒４はシース５内に並列配置
されている。なお、ブレード１、先端構造材２お
よびハンドル３などはオーステナイト系ステンレ
ス鋼で形成されている。 Note that FIG. 4 is an enlarged side view of a portion of the blade 1 shown in FIG. 3. Neutron absorption rod 4
A stainless steel thin tube is densely filled with boron carbide powder as a neutron absorbing material, and the neutron absorbing rods 4 are arranged in parallel within a sheath 5. Note that the blade 1, tip structural member 2, handle 3, etc. are made of austenitic stainless steel.
また、シース５には多数の孔９が板厚方向に貫
通して設けられており、これら孔９を通して冷却
材がシース５内に流入し、その内部を冷却材が流
動することにより、制御棒を冷却するように考慮
されている。 In addition, the sheath 5 is provided with a large number of holes 9 passing through it in the thickness direction, and the coolant flows into the sheath 5 through these holes 9, and as the coolant flows inside the sheath 5, the control rod It is considered to be cooling.
（考案が解決しようとする問題点）
一般に、軽水炉の炉心においては冷却水の放射
線分解が起り、(1)式で示したように過酸化水素が
発生する。(Problems to be solved by the invention) Generally, radiolysis of cooling water occurs in the core of a light water reactor, and hydrogen peroxide is generated as shown in equation (1).
2H2Ｏ→H2O2H2 ……(1)
また、この過酸化水素は(2)式で示したように熱
分解し、水と酸素を生成する。 2H 2 O→H 2 O 2 H 2 ...(1) Also, this hydrogen peroxide is thermally decomposed as shown in equation (2) to produce water and oxygen.
H2O2→H2Ｏ＋１／２O2 ……(2)
この熱分解反応は過酸化水素が冷却水中に溶存
するのみではあまり進行しないが、金属の表面に
接触する場合、非常に速くなる。 H 2 O 2 → H 2 O + 1/2 O 2 ...(2) This thermal decomposition reaction does not proceed much if hydrogen peroxide is only dissolved in the cooling water, but it becomes extremely fast when it comes into contact with the metal surface.
このような分解が行なわれる炉心に位置する制
御棒は過酸化水素を含む冷却水と接しており、し
たがつて、その構造において冷却水の流れの停滞
を引き起すような構造部分を有する場合、過酸化
水素の熱分解で生成する酸素が停滞部分の冷却水
の溶存酸素濃度を局部的に高くするか、または酸
素の気相が停滞部分に形成される。 Control rods located in the reactor core where such decomposition takes place are in contact with cooling water containing hydrogen peroxide, and therefore, if they have structural parts that cause stagnation of the flow of cooling water, Oxygen generated by thermal decomposition of hydrogen peroxide locally increases the dissolved oxygen concentration of the cooling water in the stagnation area, or a gas phase of oxygen is formed in the stagnation area.
したがつて、ブレード１内を流動する冷却水中
には過酸化水素が含まれており、しかも、先端構
造材２とのスミ肉溶接部６の下部、さらに先端構
造材２の減厚部２ａおよびタイロツド７との点溶
接部８の近傍には冷却水の流れの停滞部分が形成
されている。すなわち、スミ肉溶接部６では先端
構造材２の減厚部２ａと、シース５の上端部とが
相互に重なり合う合せ面が形成される。同様にタ
イロツド７の点溶接部８では、タイロツド７の軸
方向側端部とシース５の側端部とが重なり合う合
せ面が形成される。 Therefore, the cooling water flowing inside the blade 1 contains hydrogen peroxide, and moreover, hydrogen peroxide is contained in the cooling water flowing inside the blade 1, and the lower part of the fillet weld 6 with the tip structure material 2, as well as the reduced thickness part 2a of the tip structure material 2, and A stagnant portion of the flow of cooling water is formed near the spot weld 8 with the tie rod 7. That is, in the fillet welded portion 6, a mating surface is formed where the reduced thickness portion 2a of the tip structure member 2 and the upper end portion of the sheath 5 overlap with each other. Similarly, at the spot weld 8 of the tie rod 7, a mating surface is formed where the axial side end of the tie rod 7 and the side end of the sheath 5 overlap.
これら重ね合せ面は溶着箇所以外では機械的に
圧接されているだけであるから、微小な間隙が形
成されており、この微小間隙に流入した冷却水に
流れの停滞が発生する。このような冷却水の流れ
の停滞部分では前述したように冷却水の溶存酸素
濃度が局部的に高くなるか、または酸素の気相が
存在することになる。 Since these overlapping surfaces are only mechanically pressed together except at the welded areas, a minute gap is formed, and the flow of cooling water flowing into this minute gap is stagnated. In such a stagnant portion of the cooling water flow, as described above, the dissolved oxygen concentration of the cooling water becomes locally high, or a gas phase of oxygen exists.
溶存酸素濃度が高い場合には腐食加速があり、
高い応力が負荷された非正常な治金組織を持つオ
ーステナイト系ステンレス鋼に応力腐食割れが起
きることが明らかである。したがつて、軽水炉用
制御棒においても、場合によつてはこの応力腐食
割れを招来するおそれがある。 Corrosion accelerates when dissolved oxygen concentration is high;
It is clear that stress corrosion cracking occurs in austenitic stainless steels that have abnormal metallurgy and are subjected to high stress. Therefore, control rods for light water reactors may also suffer from stress corrosion cracking in some cases.
また、気相が形成された場合には気液界面での
腐食加速による不具合のおそれもある。 Furthermore, if a gas phase is formed, there is a risk of problems due to accelerated corrosion at the gas-liquid interface.
第５図は鋭敏化した非正常状態にあるSUS304
ステンレス鋼について応力腐食割れ（SCC）感受
性の290℃純水中の溶存酸素濃度依存性を示した
もので、この図から溶存酸素濃度が高いと応力腐
食割れ感受性が大きくなり、応力腐食割れが発生
することが明らかである。 Figure 5 shows SUS304 in a sensitized and abnormal state.
This figure shows the dependence of the stress corrosion cracking (SCC) susceptibility of stainless steel on the dissolved oxygen concentration in 290°C pure water.This figure shows that when the dissolved oxygen concentration is high, the stress corrosion cracking susceptibility increases and stress corrosion cracking occurs. It is clear that
本考案は上記問題点を解決するためになされた
もので、冷却水の停滞部分を除去して腐食加速を
抑制または軽減させることにより、信頼性のより
向上した原子炉用制御棒を提供することを目的と
する。 The present invention was made to solve the above problems, and aims to provide a control rod for a nuclear reactor with improved reliability by suppressing or reducing corrosion acceleration by removing the stagnant portion of cooling water. With the goal.
（問題点を解決するための手段）
本考案は、従来例の問題点が、連続スミ肉溶接
部６および点溶接部８においては、シース５の上
端部と先端構造材２の下端部とが互いに重なり合
う合せ面が形成される共に、シース５の側端部と
タイロツド７の軸方向側端部とが互いに重なり合
う合せ面が形成され、これら合せ面に冷却水の流
れの停滞が生ずるということに起因する点に鑑み
なされたものであり、次のように構成される。
(Means for Solving the Problem) The present invention solves the problem of the conventional example that, in the continuous fillet weld 6 and the spot weld 8, the upper end of the sheath 5 and the lower end of the tip structure member 2 are A mating surface is formed that overlaps each other, and a mating surface is formed where the side end of the sheath 5 and the axial end of the tie rod 7 overlap each other, and stagnation of the flow of cooling water occurs at these mating surfaces. This was done in consideration of the following factors, and is structured as follows.
中性子吸収棒の複数本を内蔵する複数のシース
を、タイロツド周りに所定形状に配列して結合
し、これらシースの上端に先端構造材を結合する
原子炉用制御棒において、前記先端構造材の下端
と前記各シースの上端との相互、並びに、上記タ
イロツドの軸方向側端と上記シースの側端との相
互をそれぞれ突合せ溶接により結合した。 In a control rod for a nuclear reactor, a plurality of sheaths containing a plurality of neutron absorption rods are arranged in a predetermined shape around a tie rod, and a tip structure member is bonded to the upper end of these sheaths. and the upper end of each sheath, and the axial side end of the tie rod and the side end of the sheath were butt welded.
（作用）
先端構造材およびタイロツドと、シースとの結
合を突合せ溶接により行なつたので、これら結合
部における重ね合せ面が無くなり、微小間隙が無
くなつたので、これら結合部における溶存酸素濃
度が高い冷却水の流れの停滞が解消する。(Function) Since the tip structure material, tie rod, and sheath are joined by butt welding, there are no overlapping surfaces in these joints, and there are no micro gaps, so the dissolved oxygen concentration in these joints is high. Eliminates stagnation in the flow of cooling water.
その結果、局部的な応力腐食割れのおそれが無
くなり、制御棒の信頼性が向上する。 As a result, the risk of localized stress corrosion cracking is eliminated and the reliability of the control rod is improved.
（実施例）
第１図および第２図を参照しながら本考案に係
る原子炉用制御棒の一実施例を説明する。(Example) An example of a control rod for a nuclear reactor according to the present invention will be described with reference to FIGS. 1 and 2.
第２図は本考案の一実施例の上部の斜視図であ
り、図において縦長板状の４枚のブレード１１，
１１，１１，１１が直交十字状に組み立てられ、
その上端には十字状の先端構造材１２が同軸状に
結合されている。 FIG. 2 is a perspective view of the upper part of an embodiment of the present invention.
11, 11, 11 are assembled in an orthogonal cross shape,
A cross-shaped tip structure member 12 is coaxially connected to its upper end.
先端構造材１２の上面には従来例と同様に門形
のハンドル１３が取着されているが、その下半分
の減厚部２ａ（第４図参照）は切欠されている。 A gate-shaped handle 13 is attached to the upper surface of the tip structure member 12 as in the conventional example, but the reduced thickness portion 2a (see FIG. 4) in the lower half thereof is cut out.
各ブレード１１は中性子吸収材であるボロンカ
ーバイドの粉末をステンレス鋼製細管内に密に充
填してなる中性子吸収棒１４の複数本を、Ｕ字状
ステンレス鋼板製の４枚のシース１５内にそれぞ
れ挿入しており、各シース１５の上端面を先端構
造材１２の下端面に突き合せると共に、この突合
せ部のシース１５の外側面と先端構造材１２の外
側面とを面一にして、突合せ溶接１６している。 Each blade 11 has a plurality of neutron absorbing rods 14, which are made by densely filling a stainless steel thin tube with boron carbide powder, which is a neutron absorbing material, inside four sheaths 15 made of U-shaped stainless steel plates. The upper end surface of each sheath 15 is butted against the lower end surface of the tip structure material 12, and the outer surface of the sheath 15 and the outer surface of the tip structure material 12 at this abutting portion are flush with each other and butt welded. I am 16 years old.
したがつて、シース１５の上端と先端構造材１
２の下端とが相互に重なり合う合せ面が解消さ
れ、合せ面による冷却水の流れの停滞部が解消さ
れる。 Therefore, the upper end of the sheath 15 and the tip structure member 1
The mating surfaces where the lower ends of the two overlap each other are eliminated, and the stagnation of the flow of cooling water due to the mating surfaces is eliminated.
また、各シース１５の側端をタイロツド１７の
軸方向側端に突き合せて、シース１５の外側面と
タイロツド１７の外側面とを面一にし、その突合
せ部を突合せ溶接１８している。 Further, the side end of each sheath 15 is butted against the axial side end of the tie rod 17 so that the outer surface of the sheath 15 and the outer surface of the tie rod 17 are flush with each other, and the abutting portions are butt welded 18.
したがつて、シース１５の側端とタイロツド１
７の軸方向側端とが相互に重なり合う合せ面が解
消され、合せ面による冷却水の流れの停滞部が解
消される。 Therefore, the side end of the sheath 15 and the tie rod 1
The mating surfaces where the axial side ends of the parts 7 overlap with each other are eliminated, and the stagnation part of the flow of cooling water due to the mating surfaces is eliminated.
なお、十字状に組み上がつたブレード１１の下
端には制御棒駆動機構と確実な結合ができるよう
に結合ソケツトが配設されている。 A coupling socket is provided at the lower end of the blade 11 assembled in a cross shape so that it can be securely coupled to the control rod drive mechanism.
また、ブレード１１、先端構造材１２およびハ
ンドル１３などはオーステナイト系ステンレス鋼
で形成されている。さらに、シース１５には多数
の孔１９が板厚方向に貫通されており、これら孔
１９を通して冷却材がシース１５内に流入し、冷
却材が流動することにより制御棒を冷却する。 Further, the blade 11, the tip structure member 12, the handle 13, etc. are made of austenitic stainless steel. Further, a large number of holes 19 are penetrated through the sheath 15 in the thickness direction, and a coolant flows into the sheath 15 through these holes 19, and the flow of the coolant cools the control rod.
しかして、従来例においては、過酸化水素を含
む冷却水中の停滞部分では溶存酸素濃度が高くな
るか、さらには酸素の気相が形成するために発生
する。 However, in the conventional example, the concentration of dissolved oxygen increases in the stagnant portion of the cooling water containing hydrogen peroxide, or furthermore, this occurs due to the formation of a gas phase of oxygen.
つまり、腐食反応は金属の酸化、すなわちアノ
ード反応（Ｍ→Mn＋ne）と、これに対応する還
元すなわちカソード反応と、酸素が存在する場合
には酸素消費反応（１／202＋H2Ｏ＋2e→2oH-）
とが対となつて進行する。 In other words, the corrosion reaction consists of the oxidation of metal, that is, the anodic reaction (M→M n +ne), the corresponding reduction, or cathodic reaction, and, in the presence of oxygen, the oxygen consumption reaction (1/20 2 + H 2 O + 2e → 2oH- )
and proceed in pairs.
したがつて、冷却水中の溶存酸素濃度が低くな
れば、腐食反応を抑制または軽減できることにな
る。 Therefore, if the dissolved oxygen concentration in cooling water is lowered, corrosion reactions can be suppressed or reduced.
そこで、本考案の実施例の如く制御棒の先端構
造材１２の下端とシース１５の上端と、またタイ
ロツド１７の軸方向側端とシース１５の側端とを
それぞれ突合せ溶接１６，１８することによつ
て、これら溶接箇所での重ね合せ面を解消するこ
とができる。 Therefore, as in the embodiment of the present invention, the lower end of the control rod tip structure member 12 and the upper end of the sheath 15, and the axial side ends of the tie rod 17 and the side ends of the sheath 15 are butt welded 16 and 18, respectively. Therefore, overlapping surfaces at these welding locations can be eliminated.
この結果、冷却水中に含まれる過酸化水素の分
解により酸素が生成蓄積し、この酸素の腐食加速
のおそれがある冷却水の停滞部分が改善される。 As a result, oxygen is generated and accumulated due to the decomposition of hydrogen peroxide contained in the cooling water, and the stagnant portion of the cooling water where there is a risk of accelerated corrosion due to this oxygen is improved.
なお、上記実施例における突合せ溶接は連続ま
たは断続のいずれかを採用することができる。ま
た、先端構造材１２、タイロツド１７およびシー
ス１５との固定のために一方のみを突合せ溶接す
ることもできる。 Note that the butt welding in the above embodiments can be either continuous or interrupted. Further, in order to fix the tip structure member 12, tie rod 17 and sheath 15, only one of them can be butt welded.
本考案によれば、制御棒の先端構造材およびタ
イロツドと、シースとの結合を突合せ溶接により
行なうので、溶接部における重ね合せ面が解消さ
れて、冷却水の流れの停滞部が解消される。
According to the present invention, since the control rod tip structure member and tie rod are joined to the sheath by butt welding, overlapping surfaces at the welded portion are eliminated, and the stagnation of the flow of cooling water is eliminated.
その結果、溶接酸素濃度が高い冷却水の停滞が
解消し局部的な応力腐食割れの可能性がなく、も
つて、制御棒の信頼性を向上することができる。 As a result, stagnation of cooling water with a high welding oxygen concentration is eliminated, and there is no possibility of localized stress corrosion cracking, thereby improving the reliability of the control rod.
第１図は本考案に係る制御棒の実施例の要部を
一部切欠して示す正面図、第２図は第１図で示す
ブレードの上部の斜視図、第３図は従来の制御棒
の上部を示す斜視図、第４図は第３図で示すブレ
ードの上部を一部切欠して示す正面図、第５図は
溶存酸素濃度に対する応力腐食割れ感受性の依存
性を示す特性図である。
１，１１……ブレード、２，１２……先端構造
材、３，１３……ハンドル、４，１４……中性子
吸収棒、５，１５……シース、６……スミ肉溶接
部、７，１７……タイロツド、８……点溶接部、
１６，１８……突合せ溶接、９，１９……孔。
Fig. 1 is a partially cutaway front view showing the main part of an embodiment of the control rod according to the present invention, Fig. 2 is a perspective view of the upper part of the blade shown in Fig. 1, and Fig. 3 is a conventional control rod. FIG. 4 is a partially cutaway front view of the upper part of the blade shown in FIG. 3, and FIG. 5 is a characteristic diagram showing the dependence of stress corrosion cracking susceptibility on dissolved oxygen concentration. . 1, 11... Blade, 2, 12... Tip structure material, 3, 13... Handle, 4, 14... Neutron absorption rod, 5, 15... Sheath, 6... Fillet weld, 7, 17 ...Tie rod, 8...Spot welding part,
16, 18...butt weld, 9, 19...hole.
Claims (1)
を、タイロツド周りに所定形状に配列して結合
し、これらシースの上端に先端構造材を結合する
原子炉用制御棒において、前記先端構造材の下端
と前記各シースの上端との相互、並びに、上記タ
イロツドの軸方向側端と上記シースの側端との相
互をそれぞれ突合せ溶接により結合したことを特
徴とする原子炉用制御棒。 In a control rod for a nuclear reactor, a plurality of sheaths containing a plurality of neutron absorption rods are arranged in a predetermined shape around a tie rod, and a tip structure member is bonded to the upper end of these sheaths. and an upper end of each of the sheaths, and an axial side end of the tie rod and a side end of the sheath are respectively joined by butt welding.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1986140531U JPH0448554Y2 (en) | 1986-09-16 | 1986-09-16 |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1986140531U JPH0448554Y2 (en) | 1986-09-16 | 1986-09-16 |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS6348193U JPS6348193U (en) | 1988-04-01 |
| JPH0448554Y2 true JPH0448554Y2 (en) | 1992-11-16 |
Family
ID=31047464
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP1986140531U Expired JPH0448554Y2 (en) | 1986-09-16 | 1986-09-16 |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0448554Y2 (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP5373512B2 (en) * | 2009-09-08 | 2013-12-18 | 日立Ｇｅニュークリア・エナジー株式会社 | Reactor control rod |
-
1986
- 1986-09-16 JP JP1986140531U patent/JPH0448554Y2/ja not_active Expired
Also Published As
| Publication number | Publication date |
|---|---|
| JPS6348193U (en) | 1988-04-01 |
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