JPS6371692A - Control rod for nuclear reactor - Google Patents
Control rod for nuclear reactorInfo
- Publication number
- JPS6371692A JPS6371692A JP61215825A JP21582586A JPS6371692A JP S6371692 A JPS6371692 A JP S6371692A JP 61215825 A JP61215825 A JP 61215825A JP 21582586 A JP21582586 A JP 21582586A JP S6371692 A JPS6371692 A JP S6371692A
- Authority
- JP
- Japan
- Prior art keywords
- control rod
- sheath
- nuclear reactor
- rod
- tip
- 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.)
- Pending
Links
- 238000010521 absorption reaction Methods 0.000 claims description 18
- 125000006850 spacer group Chemical group 0.000 claims description 15
- 239000000463 material Substances 0.000 claims description 8
- 229910052580 B4C Inorganic materials 0.000 claims description 5
- INAHAJYZKVIDIZ-UHFFFAOYSA-N boron carbide Chemical compound B12B3B4C32B41 INAHAJYZKVIDIZ-UHFFFAOYSA-N 0.000 claims description 5
- 229910052735 hafnium Inorganic materials 0.000 claims description 3
- VBJZVLUMGGDVMO-UHFFFAOYSA-N hafnium atom Chemical compound [Hf] VBJZVLUMGGDVMO-UHFFFAOYSA-N 0.000 claims description 3
- 239000000498 cooling water Substances 0.000 description 19
- MHAJPDPJQMAIIY-UHFFFAOYSA-N Hydrogen peroxide Chemical compound OO MHAJPDPJQMAIIY-UHFFFAOYSA-N 0.000 description 18
- 230000007797 corrosion Effects 0.000 description 18
- 238000005260 corrosion Methods 0.000 description 18
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 description 16
- 239000001301 oxygen Substances 0.000 description 16
- 229910052760 oxygen Inorganic materials 0.000 description 16
- 238000005336 cracking Methods 0.000 description 9
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 9
- 229910001220 stainless steel Inorganic materials 0.000 description 6
- 239000010935 stainless steel Substances 0.000 description 6
- 238000006243 chemical reaction Methods 0.000 description 4
- 239000011358 absorbing material Substances 0.000 description 3
- 230000001133 acceleration Effects 0.000 description 3
- 230000008878 coupling Effects 0.000 description 3
- 238000010168 coupling process Methods 0.000 description 3
- 238000005859 coupling reaction Methods 0.000 description 3
- 238000000354 decomposition reaction Methods 0.000 description 3
- 239000000843 powder Substances 0.000 description 3
- 230000002159 abnormal effect Effects 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 239000007792 gaseous phase Substances 0.000 description 2
- 239000012071 phase Substances 0.000 description 2
- 238000005979 thermal decomposition reaction Methods 0.000 description 2
- MYMOFIZGZYHOMD-UHFFFAOYSA-N Dioxygen Chemical compound O=O MYMOFIZGZYHOMD-UHFFFAOYSA-N 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
- 239000002826 coolant Substances 0.000 description 1
- 230000006866 deterioration Effects 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 229910001882 dioxygen Inorganic materials 0.000 description 1
- 239000007789 gas Substances 0.000 description 1
- 239000007788 liquid Substances 0.000 description 1
- 229910052751 metal Inorganic materials 0.000 description 1
- 239000002184 metal Substances 0.000 description 1
- 230000003647 oxidation Effects 0.000 description 1
- 238000007254 oxidation reaction Methods 0.000 description 1
- 230000002093 peripheral effect Effects 0.000 description 1
- 238000003608 radiolysis reaction Methods 0.000 description 1
- 238000003466 welding 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
- Vibration Dampers (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
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) [Abstract] This bulletin contains application data before electronic filing, so abstract data is not recorded.
Description
【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 [Object of the Invention] (Industrial Application Field) 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ｆＩＩＩｔＩＩ棒（以下、制
御棒という）は、４枚の縦長のブレード１が直交して十
字状に組立てられ、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。４枚のブレード１は図示しないセン
ターポストと称されるタイロッドに固定されており、ま
たブレード１の下端には図示して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ットを有している。That is, a conventional fIIItII rod for a nuclear reactor (hereinafter referred to as a control rod) has four vertically long blades 1 orthogonally assembled 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 top surface of this tip structure material 2.
is attached. The four blades 1 are fixed to a tie rod (not shown) called a center post, and the lower end of the blade 1 has a coupling socket for secure connection with a control rod drive mechanism (not shown). There is.
なお、４枚のブレード１は第５図に示すようにＵ字状ス
テンレス鋼板のシース７内にて複数本の中性子吸収棒６
をそれぞれ並列配置してなり、これら中性子吸収棒６は
中性子吸収材としてボロンカーバイド粉末４をステンレ
スｕｉ４製細管５内に密に充填してなる。As shown in FIG. 5, the four blades 1 are connected to a plurality of neutron absorption rods 6 within a sheath 7 made of a U-shaped stainless steel plate.
These neutron absorbing rods 6 are formed by densely filling boron carbide powder 4 as a neutron absorbing material into a thin tube 5 made of stainless steel U4.
なお、シース７の上端と先端構造材２とは連続スミ肉溶
接部８により溶着されている。Note that the upper end of the sheath 7 and the tip structure member 2 are welded together by a continuous fillet weld 8.
また、シース７には多数の孔９が板厚方向に貫通されて
おり、これら孔９を通して冷却材がシース７内に流入し
、流動することにより、制御棒を冷却するように工夫さ
れている。Further, the sheath 7 has a large number of holes 9 penetrated in the thickness direction, and a coolant flows into the sheath 7 through these holes 9 and flows to cool the control rod. .
（発明が解決しようとする問題点）
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。(Problem to be solved by the invention) Radiolysis of cooling water occurs in the core of a light water reactor, and (
1) Hydrogen peroxide is generated as shown in the equation.
２Ｈ２０→ ［」２０２＋Ｈ２・・・・・・（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。2H20→ [''202+H2...(1) Also, this hydrogen peroxide is thermally decomposed as shown in equation (2),
Produces water and oxygen.
この熱分解反応は過酸化水素が冷却水中に溶存接触する
場合、非常に速くなる。This thermal decomposition reaction becomes very fast when the hydrogen peroxide comes into contact dissolved in the cooling water.
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、したがって、その
Ｍ４逍において冷却水の流れのＩｒ９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Ｆ９９滞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 core where such decomposition occurs are in contact with cooling water containing hydrogen peroxide, and therefore, if they have a structural part that causes Ir9 stagnation in the flow of cooling water in their M4 rods, Oxygen generated by thermal decomposition of hydrogen peroxide locally increases the dissolved oxygen concentration in the cooling water of the F99 stagnant portion, or an oxygen gas phase is formed in the stagnant portion.
さらに、縦長のブレード１内の幅方向先端部では中性子
吸収棒６とシース７との曲率半径がほぼ１ｉ’ｉ１様で
あり、広い接触部分に冷却水の流れの停滞部分が形成さ
れる。このような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。Further, at the tip in the width direction of the vertically long blade 1, the radius of curvature between the neutron absorption rod 6 and the sheath 7 is approximately 1i'i1, and a stagnation portion of the cooling water flow is formed in the wide contact area. In such a stagnant portion, as described above, the dissolved oxygen concentration of the cooling water becomes locally high, or a gaseous phase of oxygen exists.
溶存酸素Ｃ度が高い場合には旧Ｑ加速があり、高い応力
が負荷された非正常な冶金粗織を持つン１−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。したがって、軽水炉用制御棒においても、場合に
よってはこの応力腐食割れを招来するおそれがある。It is clear that when the dissolved oxygen C degree is high, there is a prior Q acceleration, and that stress corrosion cracking occurs in N1-stenitic stainless steel that has an abnormal metallurgical rough texture and is subjected to high stress. Therefore, in some cases, stress corrosion cracking may occur in control rods for light water reactors as well.
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６図は鋭敏化した非正常状態にある５ＵＳ３ｏ４ステ
ンレス鋼について応力腐食割れ（ＳＣＣ）感受性の２９
０℃純水中の溶存Ｉ！２素濃度依存性を示したもので、
この図から溶存酸素ｆ３ｒｆＸが高いど応力腐食割れ感
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 6 shows the stress corrosion cracking (SCC) susceptibility of 5US3o4 stainless steel in a sensitized abnormal state.
Dissolved I in 0℃ pure water! It shows the dependence on the concentration of two elements,
It is clear from this figure that as the dissolved oxygen f3rfX increases, the stress corrosion cracking susceptibility increases and stress corrosion cracking occurs.
本発明は上記問題点を解決するためになされたもので、
冷却水の流れのＩＪＦ？？ｉ１部分を除去して腐食加速
を抑制または軽減させ、局部的な応力腐食割れを防止す
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 has been made to solve the above problems,
IJF of cooling water flow? ? It is an object of the present invention to provide a control rod for a nuclear reactor with improved reliability by suppressing or reducing corrosion acceleration and preventing local stress corrosion cracking by removing the i1 portion.
〔発明の構成］
（問題点を解決するための手段）
本発明は、中性子吸収棒の複数本を内蔵する複数のシー
スを、タイロッ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ｆ−１８八 峰 １６
７ ＆ ｍ ４１１４１ｍ ４４ｒ Ｉ−−
＋−％ ｌ −−Ｆ Ｊ４ 普１−％、
−１内の幅方向先端部と、この先端部側に配列され
る前記中性子吸収棒との間にスペーサを介在してなるも
のである。[Structure of the Invention] (Means for Solving the Problems) The present invention has a plurality of sheaths each containing a plurality of neutron absorption rods arranged in a predetermined shape around a tie rod and coupled to each other, and the upper ends of these sheaths Tip structure material f-18 Happine 16
7&m 41141m 44r I--
+-% l --F J4 Common 1-%,
A spacer is interposed between the widthwise tip portion of the inside -1 and the neutron absorption rods arranged on the tip side.
（作用）
ブレードを形成するシースの内部幅方向先端部において
、中性子吸収棒との間にスペーサを介在させることによ
りシース内の先端部内壁と先端部側配置の中性子吸収棒
の外周壁との間に間隙が設定され、この間隙に冷却水を
通水することができるので、冷却水の流れの停滞部分を
解８１できる。(Function) At the tip in the internal width direction of the sheath that forms the blade, a spacer is interposed between the neutron absorption rod and the inner wall of the tip inside the sheath and the outer peripheral wall of the neutron absorption rod placed on the tip side. A gap is set in the gap, and cooling water can be passed through this gap, so that stagnation in the flow of cooling water can be resolved.
その結果、冷却水に含まれる過酸化水素の分解により酸
素が生成マＳ積し、このＰＡ素の腐食加速のおそれがあ
る冷却水の流れが促進されるので、局部的な応力腐食割
れを防止し、もって信頼性のより優れた制御棒となる。As a result, oxygen is produced by the decomposition of hydrogen peroxide contained in the cooling water, which accelerates the flow of cooling water that could accelerate corrosion of this PA element, preventing localized stress corrosion cracking. This results in a more reliable control rod.
（実店例）
第１図および第２図を参照しながら本発明に係る原子炉
用制御棒の一実茄例を説朗づ−る。(Example of actual store) An example of a control rod for a nuclear reactor according to the present invention will be explained with reference to FIGS. 1 and 2.
第１図において、符号１１はブレードを示してｔ（ｈ７
のブｌ／ ｋ １ ”ｌ ！＋ ｔ！１Ｖ Ｅ ７”
Ａ ＭＴ ＡＳ 古六ｌ図示してないクイロッドを中
心にして十字状に組立てられている。このブレード１１
の上部には先端構造材１２が、下部には図示してないが
制御棒駆動機構と結合する結合ソケットを右している。In FIG. 1, reference numeral 11 indicates a blade t(h7
Noburi/k 1 ”l !+ t!1V E 7”
A MT AS It is assembled in a cross shape with a Quirod (not shown) at the center. This blade 11
A tip structure member 12 is provided on the upper part of the rod, and a coupling socket (not shown) for coupling with a control rod drive mechanism is provided on the lower part thereof.
先端構造材１２の上面にはハンドル１３が取着されてい
る。ブレード１１は第２図に示すようにＵ字状ステンレ
ス鋼製のシース１７内にて複数本の中性子吸収棒１６を
それぞれ並列配置してなり、これら中性子吸収棒１６は
中性子吸収材としてボロンカーバイド粉末１４をステン
レス鋼製細管１５に充填してなる。A handle 13 is attached to the upper surface of the tip structure member 12. As shown in FIG. 2, the blade 11 is made up of a plurality of neutron absorbing rods 16 arranged in parallel inside a U-shaped stainless steel sheath 17, and these neutron absorbing rods 16 are made of boron carbide powder as a neutron absorbing material. 14 is filled into a stainless steel thin tube 15.
また、このブレード１１はシース１７内の先端部２０と
、この先端部２０側に配置される中性子吸収棒１６ａ、
！？の間に、横断面が円形状の丸棒スペーサ２１が介在
されている。The blade 11 also includes a distal end 20 within the sheath 17, a neutron absorption rod 16a disposed on the distal end 20 side,
! ? A round bar spacer 21 having a circular cross section is interposed between them.
なお、シース１７の上端と先端構造材１２の下端とは連
続スミ肉溶接部１８により溶着され、シース１７には多
数の孔１９が板厚方向に貝通されており、これら孔１゛
９を通して冷ＩＩ水がシース１７内に流入し、流動する
ことにより制御棒を冷却する。The upper end of the sheath 17 and the lower end of the tip structural member 12 are welded together by a continuous fillet weld 18, and the sheath 17 has a large number of holes 19 passed through it in the thickness direction. Cold II water flows into the sheath 17 and cools the control rods by flowing.
しかして、従来例においては、過酸化水素を含む冷却水
の停滞部分では溶存酸素濃度が高くなるか、ざらには酸
素の気相が形成するために発生する。つまり、腐食反応
は金属の酸化、すなわちアノード反応（Ｍ−＋Ｍ ＋
ｎｅ）と、これに対応する還元、すなわら、カソード反
応と、酸素が存在する場合には酸素消費反応（１／２０
２＋ｌ−１２０＋２ｅ→２０Ｈ−）とが対となって進行
する。However, in the conventional example, the concentration of dissolved oxygen becomes high in the stagnant portion of the cooling water containing hydrogen peroxide, or the hydrogen peroxide is generated due to the formation of a gaseous phase of oxygen. In other words, the corrosion reaction is the oxidation of metal, that is, the anodic reaction (M−+M+
ne), the corresponding reduction, i.e., the cathodic reaction, and, in the presence of oxygen, the oxygen-consuming reaction (1/20
2+l-120+2e→20H-) proceed as a pair.
したがって、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、本発明の実施例の如くシース１７内にスペーサ
２１を介在させことによって、シース１７内においてシ
ース１７と中性子吸収棒１０どの広い面積での接触によ
る冷却水の流れ停滞部分がなくなる。この結果、冷却水
に含まれる過酸化水素の分解により酸素が生成蓄積し、
この酸素の店ｉ食加速のおそれがある冷却水の停滞部分
が改善きれる。Therefore, by interposing the spacer 21 within the sheath 17 as in the embodiment of the present invention, there will be no part of the cooling water flow stagnation caused by contact between the sheath 17 and the neutron absorption rod 10 over a large area within the sheath 17. As a result, oxygen is generated and accumulated due to the decomposition of hydrogen peroxide contained in the cooling water.
The stagnation of the cooling water, which may cause the acceleration of oxygen depletion, can be improved.
第３図は本発明の他の実施例の要部のみを示したもので
、第２図と同一部分には同一符号で示し重複する部分の
説明を省略する。FIG. 3 shows only the essential parts of another embodiment of the present invention, and the same parts as in FIG. 2 are denoted by the same reference numerals, and the explanation of the overlapping parts will be omitted.
この第３図の実施例が第２図と異なる点は丸棒スペーサ
２１の代りに横断面が三角形の柱状体スペーサ２２を使
用した点にあり、柱状体スペーサ２２の３辺の外側面外
方に冷却水通水用の間隙が設定される。また、このスペ
ーサ２２の材質はハフニウムからなっており、スペーサ
２２としては高渇水に対する耐食性が優れていることは
勿論のこと、シース１７の先端部内部と中性子吸収棒１
６との接触部の接触腐食を防止する。The difference between the embodiment shown in FIG. 3 and that shown in FIG. 2 is that a columnar spacer 22 with a triangular cross section is used instead of the round bar spacer 21. A gap is set for cooling water to flow through. The material of the spacer 22 is hafnium, and the spacer 22 not only has excellent corrosion resistance against high drought conditions, but also the inside of the tip of the sheath 17 and the neutron absorption rod 1.
6. Prevents contact corrosion at the contact part.
なお、上記実施例における作用効果は第１図および第２
図の実施例とほぼ同様であるので、その説明を省略する
。The effects of the above embodiments are shown in Figures 1 and 2.
Since it is almost the same as the embodiment shown in the figure, its explanation will be omitted.
上記各実施例でシース１７および中性子吸収棒１６との
接触部での接触腐食を防ぐためには、シース１７および
中性子吸収棒１６とは同一系統の材料を選ぶことが好ま
しい。しかしながら、設計の特性を要求される場合には
、これらスペーサ２１．２２を内部に中性子吸収材とし
てのボロンカーバイドを充填した上記同一系統材料の丸
棒、角棒とするか、または耐ｆｆｌ性が優れ、それ自身
の中性子吸収能力を右するハフニウムをスペーサとする
こともできる。In each of the above embodiments, in order to prevent contact corrosion at the contact portion between the sheath 17 and the neutron absorption rod 16, it is preferable to select materials of the same type for the sheath 17 and the neutron absorption rod 16. However, if design characteristics are required, these spacers 21 and 22 may be made of round or square bars made of the same material as above, filled with boron carbide as a neutron absorbing material, or with ffl resistance. The spacer can also be made of hafnium, which has excellent neutron absorption capacity of its own.
また、スペーサ形状はシースと中性子吸収棒との面接触
を避ける観点から、シースおよび中性子吸収棒とは１ユ
または線接触する形状が好ましく、必ずしもその断面は
上部から下部まで均一である必要はない。In addition, from the viewpoint of avoiding surface contact between the sheath and the neutron absorption rod, the spacer shape should preferably be in one unit or line contact with the sheath and the neutron absorption rod, and its cross section does not necessarily have to be uniform from top to bottom. .
木光明によれば、ブレード先端部内でのシースと中性子
吸収棒との広い面積での接触部がなくなり、溶接酸素が
高い冷！ＪＪ水の停滞部分を除去できるので、局部的な
応力腐食割れを防止し、もって制御棒の信頼性を向上さ
せる効果がある。According to Kimitsuaki, the large area of contact between the sheath and the neutron absorption rod within the tip of the blade is eliminated, and the welding oxygen is high. Since the stagnant portion of JJ water can be removed, local stress corrosion cracking can be prevented, thereby improving the reliability of the control rod.
”６１Ｅ’Ａ ｌ −Ａ−ｎ ＩＴＩＩ ｌ−Ｍ ７．
ｒｉ＋ｉヱ梠田ｆｆ、ｌｌ ｍｌ １１ ／Ｉｌ’ｌ
−巾ず六例の要部を示す斜視図、第２図は第１図におけ
るＡ−Ａ矢視方向を切断して示す横断面図、第３図は本
発明の原子炉用ル制御棒の他の実施例を部分的に示す横
断面図、第４図は従来の制御棒の要部を示す斜視図、第
５図は第４図におけるＢ−Ｂ矢視方向を切断して示す横
断面図、第６図は溶存酸素温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・・・ボロンカーバ
イド粉末、５．１５・・・細管、６．１６・・・中性子
吸収棒、７，１７・・・シース、８．１８・・・連続ス
ミ肉溶接部、９．１９・・・孔、２ｏ・・・先端部、２
１．２２・・・スペーサ。
代理人弁理士 則 近 憲 佑
同 三 俣 弘 文＄ｌ飄
県３固”61E'A l -A-n ITII l-M 7.
ri+iヱKakuda ff, ll ml 11 /Il'l
- A perspective view showing the main parts of six examples of width, FIG. 2 is a cross-sectional view taken along the direction of arrow A-A in FIG. 1, and FIG. FIG. 4 is a perspective view showing the main parts of a conventional control rod; FIG. 5 is a cross-sectional view taken along the line B-B in FIG. 4; 6 are characteristic diagrams showing the dependence of stress corrosion cracking susceptibility on dissolved oxygen temperature. 1.11...Blade, 2,12...Tip structural material,
3.13... Handle, 4,14... Boron carbide powder, 5.15... Capillary tube, 6.16... Neutron absorption rod, 7,17... Sheath, 8.18... Continuous fillet weld, 9.19... hole, 2o... tip, 2
1.22...Spacer. Representative Patent Attorney Noriyuki Ken Yudo Hiroshi Mitsumata
Claims (1)
タイロッ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、前記シース内の幅方向先端部と、この先端部側に
配列される前記中性子吸収棒との間にスペーサを介在し
てなることを特徴とする原子炉用制御棒。 ２、スペーサとシースとは同一系統の材質からなること
を特徴とする特許請求の範囲第１項に記載の原子炉用制
御棒。 ３、スペーサはハフニウムまたはボロンカーバイドを充
填してなるものから形成されていることを特徴とする特
許請求の範囲第１項に記載の原子炉用制御棒。[Claims] 1. A plurality of sheaths containing a plurality of neutron absorption rods,
In a nuclear reactor control rod that is arranged and connected in a predetermined shape around a tie rod, and a tip structure member is connected to the upper end of these sheaths, a widthwise tip in the sheath and the neutrons arranged on the side of this tip are provided. A control rod for a nuclear reactor, characterized in that a spacer is interposed between the control rod and the absorption rod. 2. The control rod for a nuclear reactor according to claim 1, wherein the spacer and the sheath are made of the same material. 3. The control rod for a nuclear reactor according to claim 1, wherein the spacer is formed of a material filled with hafnium or boron carbide.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP61215825A JPS6371692A (en) | 1986-09-16 | 1986-09-16 | Control rod for nuclear reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP61215825A JPS6371692A (en) | 1986-09-16 | 1986-09-16 | Control rod for nuclear reactor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS6371692A true JPS6371692A (en) | 1988-04-01 |
Family
ID=16678881
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP61215825A Pending JPS6371692A (en) | 1986-09-16 | 1986-09-16 | Control rod for nuclear reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS6371692A (en) |
-
1986
- 1986-09-16 JP JP61215825A patent/JPS6371692A/en active Pending
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