JP2015206672A - Control rod for nuclear reactor - Google Patents

Control rod for nuclear reactor Download PDF

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JP2015206672A
JP2015206672A JP2014087021A JP2014087021A JP2015206672A JP 2015206672 A JP2015206672 A JP 2015206672A JP 2014087021 A JP2014087021 A JP 2014087021A JP 2014087021 A JP2014087021 A JP 2014087021A JP 2015206672 A JP2015206672 A JP 2015206672A
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control rod
eutectic
neutron
storage
neutron absorption
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JP6296874B2 (en
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研一 吉岡
Kenichi Yoshioka
研一 吉岡
浩志 松宮
Koji Matsumiya
浩志 松宮
菊池 司
Tsukasa Kikuchi
司 菊池
智子 田嶋
Tomoko Tajima
智子 田嶋
水口 浩司
Koji Mizuguchi
浩司 水口
矢板 由美
Yumi Yaita
由美 矢板
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Toshiba Corp
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    • 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
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    • Y02E30/30Nuclear fission reactors

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Abstract

PROBLEM TO BE SOLVED: To provide an accident resistance control rod not being fused earlier than fuel at the time of a severe accident of a nuclear power plant and having neutron absorbers remaining at a reactor core for a long period of time even when being fused and dropping down.SOLUTION: A control rod for a nuclear reactor includes: neutron absorption sections 31 having neutron absorbers; a plurality of housing members 21 housing the neutron absorption sections 31; a coupling member integrating the plurality of housing members 21; and eutectic prevention members 33. Each of the eutectic prevention members 33 is provided between the neutron absorption section 31 and the housing member 21, contains eutectic preventing oxide having neutron absorption effect and high temperature stability and prevents the neutron absorption section 31 and the housing member 21 from being brought into direct contact with each other.

Description

本発明の実施形態は、原子炉用制御棒に関する。   Embodiments described herein relate generally to a reactor control rod.

沸騰水型原子炉の制御棒は、十字形の断面形状を有し、軸方向(鉛直方向)に延びる中央結合部材と、この中央結合部材を中心に4枚の板状のウィングが四方向に広がっている。また、ウィングは、タイロッドの軸方向に延びている。また、中央結合部材の上端部にハンドルが接合され、中央結合部材の下端部には落下速度リミッタを有する下部支持部材が取り付けられている。   The control rod of the boiling water reactor has a cross-shaped cross section, a central coupling member extending in the axial direction (vertical direction), and four plate-like wings around the central coupling member in four directions. It has spread. The wing extends in the axial direction of the tie rod. Further, a handle is joined to the upper end portion of the central coupling member, and a lower support member having a drop speed limiter is attached to the lower end portion of the central coupling member.

それぞれのウィングは、たとえば、BCなどの中性子吸収材を内包しており、中性子吸収材を、オーステナイト系ステンレス鋼製の概略U字形の断面形状を持つシースが覆っている。 Each wing includes, for example, a neutron absorber such as B 4 C, and the neutron absorber is covered with a sheath having a substantially U-shaped cross section made of austenitic stainless steel.

特開2011−174828号公報JP 2011-174828 A 特開2013−246102号公報JP 2013-246102 A

原子力発電所におけるシビアアクシデントでは、冷却材による炉心の冷却が不足し、炉心溶融が生じるような事象が想定される。このような事象においては、炉心燃料のほか、制御棒も溶融落下する。制御棒に使用される炭化ホウ素(BC)は、制御棒の構造材部分(ウィング)に用いられるオーステナイト系ステンレス鋼と共晶を起こして融点が低下し、早期に溶融することが懸念される。 In a severe accident at a nuclear power plant, it is assumed that the core will be melted due to insufficient cooling of the core with coolant. In such an event, the control rods melt and fall in addition to the core fuel. Boron carbide (B 4 C) used for control rods is likely to eutectic with the austenitic stainless steel used for the structural material parts (wings) of the control rods, resulting in a lower melting point and melting at an early stage. The

制御棒の溶融後、原子炉への注水により、原子炉が再び臨界となる「再臨界」事象が考えられる。再臨界は原子炉圧力容器や原子炉格納容器、あるいは原子炉建屋の損傷を引き起こし、放射性物質の環境への放出につながる可能性がある。   After the control rod melts, a “recritical” event can be considered where the reactor becomes critical again due to water injection into the reactor. Recriticality can cause damage to the reactor pressure vessel, the containment vessel, or the reactor building, and can lead to the release of radioactive material to the environment.

図7は、制御棒用の構造材等の融点を示す図である。図7に示したように、オーステナイト系ステンレス鋼の融点は1723Kである。したがって、オーステナイト系ステンレス鋼製の制御棒の融点は、融点が3123KのUOより低い。また、BC自体は融点2723Kであるが、さらに、オーステナイト系ステンレス鋼との共晶によって融点は1500Kまで低下する。このため、炉内の温度状況によっては制御棒が先に溶け落ちる可能性がある。その後、燃料溶融が部分的な範囲に留まり、溶融した燃料によりある高さの炉心が形成され、その後注水により、ある高さで、再臨界が起きる可能性がある。 FIG. 7 is a diagram showing a melting point of a structural material for a control rod. As shown in FIG. 7, the melting point of austenitic stainless steel is 1723K. Therefore, the melting point of the control rod made of austenitic stainless steel is lower than UO 2 having a melting point of 3123K. Further, B 4 C itself has a melting point of 2723 K, and further, the melting point decreases to 1500 K due to the eutectic with austenitic stainless steel. For this reason, there is a possibility that the control rod melts first depending on the temperature in the furnace. Thereafter, fuel melting remains in a partial range, and a core of a certain height is formed by the melted fuel, and then water injection can cause recriticality at a certain height.

また、溶融炉心は崩壊熱の発生により温度が高い。また、燃料形状が崩壊している場合、内部まで冷却するには十分な冷却材の確保が難しい。このため、水は水蒸気として存在する可能性が高い。この場合、核分裂で発生した高速の中性子を、核分裂を起こしやすい熱中性子に減速するための減速材である水素の量が不足しているため、臨界に至る可能性は小さい。一方、時間の経過とともに、崩壊熱は減少するため、炉心溶融から数ヶ月以上も時間が経過した後には、炉内の冷却材は水蒸気ではなく液体の水の状態となってくる。このため、臨界に至る可能性がある。また、初期には存在していた上述の制御棒中のホウ素が時間経過に伴い冷却材とともに流出し、反応度抑制効果が低減することにより臨界となる可能性がある。   Also, the melting core has a high temperature due to the generation of decay heat. Further, when the fuel shape is collapsed, it is difficult to secure a sufficient coolant for cooling to the inside. For this reason, water is likely to exist as water vapor. In this case, the possibility of reaching criticality is low because the amount of hydrogen, which is a moderator for decelerating fast neutrons generated by fission into thermal neutrons that are prone to fission, is insufficient. On the other hand, the decay heat decreases with the passage of time, and therefore, after several months have passed since the melting of the core, the coolant in the furnace becomes liquid water instead of water vapor. This can lead to criticality. In addition, boron in the above-described control rod that was present at the beginning may flow out with the coolant as time passes, and may become critical due to a reduction in the reactivity suppression effect.

そこで、本発明の実施形態は、原子力発電所のシビアアクシデント時に燃料より早期に溶融せず、かつ溶融落下した場合も長期にわたり炉心に中性子吸収材が留まる事故耐性制御棒を提供することを目的とする。   Accordingly, an embodiment of the present invention aims to provide an accident resistance control rod that does not melt earlier than the fuel at the time of a severe accident at a nuclear power plant, and that the neutron absorber remains in the core for a long time even when melted and dropped. To do.

上述の目的を達成するため、本実施形態に係る原子炉用制御棒は、中性子吸収材を有する中性子吸収部と、前記中性子吸収部を内包する複数の収納部材と、前記複数の収納部材を一体化する結合部材と、中性子吸収効果および高温安定性を有する共晶防止用酸化物を含み、前記中性子吸収部と前記収納部材の間に設けられて前記中性子吸収部と前記収納部材との直接的な接触を防止する共晶防止部材と、を備えることを特徴とする。   In order to achieve the above-described object, a reactor control rod according to the present embodiment includes a neutron absorber having a neutron absorber, a plurality of storage members containing the neutron absorber, and the plurality of storage members integrated. And an eutectic-preventing oxide having a neutron absorption effect and high-temperature stability, and is provided between the neutron absorption part and the storage member and directly between the neutron absorption part and the storage member And a eutectic prevention member that prevents unwanted contact.

本発明の実施形態によれば、原子力発電所のシビアアクシデント時に燃料より早期に溶融せず、かつ溶融落下した場合も長期にわたり炉心に中性子吸収材が留まる事故耐性制御棒を提供することができる。   According to the embodiment of the present invention, it is possible to provide an accident resistance control rod in which a neutron absorbing material stays in the core for a long period of time even when it melts and falls at the time of a severe accident at a nuclear power plant and even when melted and dropped.

第1の実施形態による原子炉用制御棒を炉心内に挿入した状態を示す水平断面図である。It is a horizontal sectional view showing the state where the control rod for reactors by a 1st embodiment was inserted in the core. 第1の実施形態による原子炉用制御棒のウィングの構成を示す概念的斜視図である。It is a conceptual perspective view which shows the structure of the wing | wing of the nuclear reactor control rod by 1st Embodiment. 第1の実施形態による原子炉用制御棒のウィングに挿入される中性子吸収部の構成を示す概念的斜視図である。It is a conceptual perspective view which shows the structure of the neutron absorption part inserted in the wing of the control rod for reactors by 1st Embodiment. 第1の実施形態による原子炉用制御棒のウィングの構成を示す図2の第IV−IV矢視概念的縦断面図である。FIG. 4 is a conceptual longitudinal sectional view taken along arrows IV-IV in FIG. 2 showing a configuration of a wing of a nuclear reactor control rod according to the first embodiment. 第2の実施形態による原子炉用制御棒のウィングの構成を示す概念的縦断面図である。It is a notional longitudinal cross-sectional view which shows the structure of the wing | wing of the control rod for reactors by 2nd Embodiment. 第3の実施形態による原子炉用制御棒のウィングの構成を示す概念的縦断面図である。It is a notional longitudinal cross-sectional view which shows the structure of the wing | wing of the control rod for reactors by 3rd Embodiment. 制御棒構造材等の融点を示す図である。It is a figure which shows melting | fusing point of a control-rod structure material.

以下、図面を参照して、本発明の実施形態に係る原子炉用制御棒について説明する。ここで、互いに同一または類似の部分には、共通の符号を付して、重複説明は省略する。   Hereinafter, a control rod for a nuclear reactor according to an embodiment of the present invention will be described with reference to the drawings. Here, the same or similar parts are denoted by common reference numerals, and redundant description is omitted.

[第1の実施形態]
図1は、第1の実施形態による原子炉用制御棒を炉心内に挿入した状態を示す水平断面図である。原子炉用制御棒10は、図示しない炉心内に格子状に配列された四角柱状の燃料集合体1の間隙に鉛直下方から挿入可能に位置決めされている。
[First Embodiment]
FIG. 1 is a horizontal sectional view showing a state in which a nuclear reactor control rod according to a first embodiment is inserted into a core. The nuclear reactor control rod 10 is positioned so that it can be inserted into the gap between the rectangular columnar fuel assemblies 1 arranged in a lattice pattern in a core (not shown) from below.

原子炉用制御棒10は、水平方向および鉛直方向に広がった板状の4つのウィング20と、これらを結合して一体化して鉛直方向に延びる棒状の中央結合部材11とを有する。4つのウィング20は、中央結合部材11を中心に水平方向に十字型に延びている。また、原子炉用制御棒10は、正方形状の4体の燃料集合体1の水平方向のほぼ中央に中央結合部材11が位置し、それぞれのウィング20が互いに隣接する燃料集合体1に挟まれるように配列されている。   The nuclear reactor control rod 10 includes four plate-like wings 20 extending in the horizontal direction and the vertical direction, and a rod-like central coupling member 11 that is coupled and integrated to extend in the vertical direction. The four wings 20 extend in a cross shape in the horizontal direction around the central coupling member 11. Further, in the nuclear reactor control rod 10, a central coupling member 11 is positioned at the substantially horizontal center of four square fuel assemblies 1, and each wing 20 is sandwiched between adjacent fuel assemblies 1. Are arranged as follows.

図2は、原子炉用制御棒のウィングの構成を示す概念的斜視図である。図3は、原子炉用制御棒のウィングに挿入される中性子吸収部の構成を示す概念的斜視図である。また、図4は、図2の第IV−IV矢視概念的縦断面図である。   FIG. 2 is a conceptual perspective view showing the configuration of the wing of the nuclear reactor control rod. FIG. 3 is a conceptual perspective view showing a configuration of a neutron absorbing portion inserted into the wing of the nuclear reactor control rod. FIG. 4 is a conceptual vertical cross-sectional view taken along arrow IV-IV in FIG.

ウィング20は、収納部材21および収納部材21内に収納される中性子吸収部31を有する。収納部材21は、水平断面の外形がU字型形状で、軸方向すなわち、据付状態で鉛直方向に延びている。収納部材21は、たとえば、ウィング20の水平に広がる方向の先端部分を滑らかな曲面にする等、板材から削り出して成形される。   The wing 20 includes a storage member 21 and a neutron absorption part 31 stored in the storage member 21. The storage member 21 has a U-shaped outer shape in a horizontal section, and extends in the axial direction, that is, in the vertical direction in the installed state. The storage member 21 is formed by cutting out from a plate material, for example, by making the tip portion of the wing 20 in a horizontally extending direction a smooth curved surface.

収納部材21には、水平でウィング20の広がり方向に、鉛直方向に互いに間隔をあけて複数の円筒状の収納穴22が形成されている。収納穴22は、中央結合部材11(図1)と結合する側は開放されており、反対側すなわちウィング20が水平方向に広がる側には貫通せず閉じている。収納穴22は、収納部材21にたとえば中央結合部材11と結合する側からの穴加工により形成される。収納部材21の材料は、たとえばオーステナイト系ステンレス鋼である。   The storage member 21 is formed with a plurality of cylindrical storage holes 22 that are horizontally spaced apart from each other in the vertical direction of the wing 20. The storage hole 22 is open on the side coupled to the central coupling member 11 (FIG. 1), and is closed without penetrating on the opposite side, that is, the side where the wing 20 extends in the horizontal direction. The storage hole 22 is formed in the storage member 21 by, for example, drilling from the side that is connected to the central coupling member 11. The material of the storage member 21 is, for example, austenitic stainless steel.

それぞれの収納穴22には、中性子吸収部31が収納されている。中性子吸収部31は、固体であり、円筒形状に形成されている。中性子吸収部31の材料は、たとえば、焼結されたBCである。 A neutron absorbing portion 31 is stored in each storage hole 22. The neutron absorber 31 is solid and is formed in a cylindrical shape. The material of the neutron absorber 31 is, for example, sintered B 4 C.

中性子吸収部31の外面には、共晶防止部材33が設けられている。共晶防止部材33は、中性子吸収部31と収納部材21とが直接に接触することを防止するように配されている。したがって、共晶防止部材33は、必ずしも、中性子吸収部31の外面を完全に覆っている必要はないが、収納部材21の部分的溶融などの可能性を想定すれば完全に覆っていることが好ましい。   A eutectic prevention member 33 is provided on the outer surface of the neutron absorber 31. The eutectic prevention member 33 is arranged so as to prevent the neutron absorbing portion 31 and the storage member 21 from coming into direct contact. Therefore, the eutectic prevention member 33 does not necessarily need to completely cover the outer surface of the neutron absorption part 31, but may completely cover the possibility of partial melting of the storage member 21. preferable.

収納穴22内への共晶防止部材33が設けられた中性子吸収部31の挿入性、および、収納穴22内における共晶防止部材33と収納部材21との接触面積を最小とする観点から、共晶防止部材33と収納部材21との間にはギャップ35が形成されている。ギャップ35を周方向に確保するために図示しないスペーサで共晶防止部材33を固定してもよい。あるいは、スペーサ等を使用せずに、共晶防止部材33を収納穴22上に乗せた状態、すなわち面接触ではなく線接触とすることでもよい。   From the viewpoint of minimizing the insertion property of the neutron absorber 31 provided with the eutectic prevention member 33 in the storage hole 22 and the contact area between the eutectic prevention member 33 and the storage member 21 in the storage hole 22. A gap 35 is formed between the eutectic prevention member 33 and the storage member 21. In order to secure the gap 35 in the circumferential direction, the eutectic prevention member 33 may be fixed with a spacer (not shown). Alternatively, the eutectic prevention member 33 may be placed on the storage hole 22 without using a spacer or the like, that is, a line contact may be used instead of a surface contact.

共晶防止部材33の材料は、中性子吸収効果があること、高温で安定な材料であること、さらにコスト的にも入手可能であることを要件として選定する。   The material of the eutectic prevention member 33 is selected as a requirement that it has a neutron absorption effect, is a material that is stable at high temperatures, and is also available in terms of cost.

共晶防止部材33は、後述する共晶防止部材33用のランタノイド金属あるいはランタノイド酸化物の被膜を、溶射などにより中性子吸収部31の外面に形成させることでもよい。あるいは、共晶防止部材33用のランタノイド酸化物の容器として、中性子吸収部31を収納することでもよい。この場合は、中性子吸収部31は、固体形状に限定されずたとえば粉末状のBCなどでもよい。 The eutectic preventing member 33 may be formed by forming a lanthanoid metal or lanthanoid oxide film for the eutectic preventing member 33 described later on the outer surface of the neutron absorbing portion 31 by thermal spraying or the like. Alternatively, the neutron absorption part 31 may be housed as a lanthanoid oxide container for the eutectic prevention member 33. In this case, the neutron absorber 31 is not limited to a solid shape, and may be, for example, powdered B 4 C.

発明者らは、共晶防止部材33の材料としての候補材について、1150℃のもとで、候補材の酸化物1モルと水蒸気10モルでの熱力学的平衡解析(反応解析)を行い、水蒸気反応後の生成物量のモル数の当初の候補材のモル数(1モル)に対する比を求めた。ここで、1150℃はこの温度以上でBCが水蒸気と反応する温度である。すなわち、BCは1150℃で水蒸気との反応が開始される。 The inventors conducted a thermodynamic equilibrium analysis (reaction analysis) of the candidate material as a material of the eutectic prevention member 33 at 1150 ° C. with 1 mol of the oxide of the candidate material and 10 mol of water vapor. The ratio of the number of moles of the product amount after the steam reaction to the number of moles of the original candidate material (1 mole) was determined. Here, 1150 ° C. is a temperature at which B 4 C reacts with water vapor above this temperature. That is, the reaction of B 4 C with water vapor starts at 1150 ° C.

Cについては、前述のように、水蒸気と反応し10倍以上のモル数の反応生成物が生じたが、希土類元素の一部と、遷移金属の一部は1モルのままで水蒸気と反応しないことがわかった。このように水蒸気と反応しない材料は、具体的には、希土類元素では、候補材としたランタノイド元素(Ln)であるガドリニウム(Gd)、ルテチウム(Lu)、ツリウム(Tm)、エルビウム(Er)、ディスプロシウム(Dy)、ガリウム(Ga)、ユーロピウム(Eu)、およびサマリウム(Sm)のそれぞれの酸化物であり、これらの反応解析の結果は全て1モルのままで水蒸気と反応していなかった。遷移金属としては、水銀(Hg)、ハフニウム(Hf)、カドミウム(Cd)、および銀(Ag)の酸化物についても同様に水蒸気との反応が見られなかった。 As described above, B 4 C reacted with water vapor to produce a reaction product having a molar number of 10 times or more. However, a part of the rare earth element and a part of the transition metal remained at 1 mole, It turns out that it does not react. Specifically, the material that does not react with water vapor is, in the rare earth element, gadolinium (Gd), lutetium (Lu), thulium (Tm), erbium (Er), which are candidate lanthanoid elements (Ln), These oxides were dysprosium (Dy), gallium (Ga), europium (Eu), and samarium (Sm), and the results of these reaction analyzes were all 1 mol and did not react with water vapor. . As transition metals, mercury (Hg), hafnium (Hf), cadmium (Cd), and silver (Ag) oxides did not react with water vapor as well.

これらのうち、Gd、Eu、Dy、Sm、Er、Hf、およびCdは、中性子吸収断面積の大きな核種である。また、これらの酸化物は安定形態であり、したがって、オーステナイト系ステンレス鋼との共晶も生じない材料である。したがって、これらの材料は、入手可能な安定材料である。以下、これらのうち、特に、ランタノイド元素であるGd、Eu、Dy、Sm、Erのそれぞれの酸化物を、共晶防止用酸化物と呼ぶこととする。   Among these, Gd, Eu, Dy, Sm, Er, Hf, and Cd are nuclides having a large neutron absorption cross section. Further, these oxides are in a stable form, and are therefore materials that do not cause eutectic with austenitic stainless steel. These materials are therefore available stable materials. Hereinafter, among these, the oxides of lanthanoid elements Gd, Eu, Dy, Sm, and Er will be referred to as oxides for preventing eutectic.

元素がとりうる最高酸化数は、希土類元素のランタノイド元素ではほとんどが3であり、Hfでは4である。この最高酸化数まで酸素と結合していれば、それ以上の酸化反応は生じないため水蒸気と反応して水素を発生することがないことが反応解析の結果からもわかっている。前述のランタノイド元素の酸化物Ln、Hfの酸化物HfOは融点が2000℃以上であり熱安定性も高い。したがって、水素発生抑制可能な候補材料として最も有効な形態である。 The highest oxidation number that the element can take is almost 3 for lanthanoid elements of rare earth elements and 4 for Hf. From the results of the reaction analysis, it is known that if it is combined with oxygen up to this maximum oxidation number, no further oxidation reaction occurs, so that it does not react with water vapor to generate hydrogen. The above-described lanthanoid element oxide Ln 2 O 3 and Hf oxide HfO 2 have a melting point of 2000 ° C. or higher and high thermal stability. Therefore, it is the most effective form as a candidate material capable of suppressing hydrogen generation.

なお、Sm、Gd、Euの酸化物は、B型と言われる高温型の単斜晶系と、C型と言われる低温型の立方晶系の2つの形態をとりうる。例えばEuは1000℃で相転移が起こり安定相の結晶系が変わる。すなわち、事故による昇温の過程で相転移が起こり、密度が変化すると構造的な破壊を生じる可能性があるため好ましくない。また、Euの原子密度は高温相の方が大きいため高温相の方が制御棒材料としては望ましい。また、1000〜1300℃での相転移は不可逆的であるとわれている。このため、あらかじめ高温型の結晶系とした酸化物を用いることにより、当初より安定な高温相の状態で使用できる。   Note that the oxides of Sm, Gd, and Eu can take two forms: a high-temperature monoclinic system called B-type and a low-temperature cubic system called C-type. For example, Eu undergoes a phase transition at 1000 ° C. and changes the crystal system of the stable phase. That is, phase transition occurs in the process of temperature rise due to an accident, and if the density is changed, structural destruction may occur, which is not preferable. Also, since the atomic density of Eu is higher in the high temperature phase, the high temperature phase is preferable as the control rod material. Moreover, it is said that the phase transition in 1000-1300 degreeC is irreversible. For this reason, it can be used in the state of the stable high temperature phase from the beginning by using the oxide made into the high temperature type crystal system beforehand.

以上の説明のように本実施形態における共晶防止部材33は、材料として、共晶防止用酸化物を有する。   As described above, the eutectic prevention member 33 in the present embodiment has an eutectic prevention oxide as a material.

本実施形態による原子炉用制御棒10においては、高融点でかつ高温で安定な共晶防止用酸化物を有する共晶防止部材33が、中性子吸収部31の外周に配されている。このため、原子炉用制御棒10の周囲温度が上昇した場合であっても、共晶防止部材33が収納部材21と収納部材21内に収納された中性子吸収部31間に介在する状態が持続する。この結果、オーステナイト系ステンレス鋼製の収納部材21と、収納部材21内に収納された中性子吸収部31とが直接接触することがなく、共晶が生じない。したがって、原子炉用制御棒10は、従来よりも高い温度まで、その構成を維持することができる。さらに、事故時の高温水蒸気との反応により水素を発生しない物質を用いることでより安全性の高い原子炉用制御棒10となる。   In the nuclear reactor control rod 10 according to the present embodiment, a eutectic prevention member 33 having an eutectic prevention oxide that has a high melting point and is stable at a high temperature is disposed on the outer periphery of the neutron absorber 31. For this reason, even when the ambient temperature of the nuclear reactor control rod 10 rises, the state in which the eutectic prevention member 33 is interposed between the storage member 21 and the neutron absorbing portion 31 stored in the storage member 21 continues. To do. As a result, the storage member 21 made of austenitic stainless steel and the neutron absorbing portion 31 stored in the storage member 21 are not in direct contact, and no eutectic is generated. Therefore, the configuration of the nuclear reactor control rod 10 can be maintained up to a higher temperature than before. Furthermore, the use of a substance that does not generate hydrogen due to reaction with high-temperature steam at the time of an accident makes the nuclear reactor control rod 10 safer.

また、共晶防止部材33に使用される共晶防止用酸化物は中性子吸収効果を有しており、原子炉用制御棒10の反応度価値をさらに高め、あるいは寿命をさらに延ばすことができる。   Further, the eutectic prevention oxide used for the eutectic prevention member 33 has a neutron absorption effect, and can further increase the reactivity value of the nuclear reactor control rod 10 or further extend the life.

[第2の実施形態]
図5は、第2の実施形態による原子炉用制御棒のウィングの構成を示す概念的縦断面図である。本実施形態は、第1の実施形態の変形である。
[Second Embodiment]
FIG. 5 is a conceptual longitudinal sectional view showing a configuration of a wing of a nuclear reactor control rod according to the second embodiment. This embodiment is a modification of the first embodiment.

本第2の実施形態に係る原子炉用制御棒10においては、共晶防止部材33は、収納部材21に形成されたそれぞれの収納穴22の内面に沿って同心円状に形成されている。共晶防止部材33の径方向の外面の径は、収納穴22の内面の径とほぼ同程度に形成されている。   In the nuclear reactor control rod 10 according to the second embodiment, the eutectic prevention member 33 is formed concentrically along the inner surface of each storage hole 22 formed in the storage member 21. The diameter of the outer surface in the radial direction of the eutectic prevention member 33 is formed to be approximately the same as the diameter of the inner surface of the storage hole 22.

この場合、共晶防止部材33は、たとえば、円筒状の容器形状に成形したものを、収納穴22の内面に沿って挿入することにより設けてもよい。あるいは、ウィング20の外形の鋳型の中に、円筒状の容器形状の共晶防止部材33を互いに間隔をあけて一列に並べて、鋳造によりオーステナイト系ステンレス鋼の収納部材21を成形することによってもよい。   In this case, the eutectic prevention member 33 may be provided, for example, by inserting what is formed into a cylindrical container shape along the inner surface of the storage hole 22. Alternatively, a cylindrical container-shaped eutectic prevention member 33 may be arranged in a line at intervals in a mold having an outer shape of the wing 20, and the austenitic stainless steel storage member 21 may be formed by casting. .

共晶防止部材33の内面と、中性子吸収部31の外面との間には、ギャップ36が形成されている。なお、ギャップの幅は、周角度方向に均一である必要はない。すなわち、共晶防止部材33と中性子吸収部31は一方で接触していてもよい。   A gap 36 is formed between the inner surface of the eutectic prevention member 33 and the outer surface of the neutron absorber 31. Note that the gap width need not be uniform in the circumferential angle direction. That is, the eutectic prevention member 33 and the neutron absorber 31 may be in contact with each other.

中性子吸収部31は共晶防止部材33に比べ熱膨張率が大きい場合、温度上昇の際に中性子吸収部31の熱膨張を共晶防止部材33が拘束することになる。本実施形態においては、中性子吸収部31の外面と共晶防止部材33の内面間にギャップ36を確保することによって、共晶防止部材33によるたが締めにより中性子吸収部31が損壊あるいは崩壊する可能性を排除することができる。   When the thermal expansion coefficient of the neutron absorbing portion 31 is larger than that of the eutectic preventing member 33, the eutectic preventing member 33 restrains the thermal expansion of the neutron absorbing portion 31 when the temperature rises. In the present embodiment, by securing a gap 36 between the outer surface of the neutron absorbing portion 31 and the inner surface of the eutectic preventing member 33, the neutron absorbing portion 31 can be damaged or collapsed by tapping with the eutectic preventing member 33. Sex can be excluded.

[第3の実施形態]
図6は、第3の実施形態による原子炉用制御棒のウィングの構成を示す概念的縦断面図である。本実施形態は、第1または第2の実施形態の変形である。
[Third Embodiment]
FIG. 6 is a conceptual longitudinal sectional view showing a configuration of a wing of a nuclear reactor control rod according to the third embodiment. This embodiment is a modification of the first or second embodiment.

本第3の実施形態に係る原子炉用制御棒10においては、共晶防止部材33は、長手方向に延びた円筒形状である。共晶防止部材33の外面と収納穴22の内面との間には、ギャップ35が形成されている。また、共晶防止部材33の内面と中性子吸収部31の外面の間には、ギャップ36が形成されている。ギャップ35およびギャップ36は、周方向に均一である必要はない。すなわち、共晶防止部材33と収納穴22、共晶防止部材33と中性子吸収部31は、それぞれ一方で接触していてもよい。   In the nuclear reactor control rod 10 according to the third embodiment, the eutectic prevention member 33 has a cylindrical shape extending in the longitudinal direction. A gap 35 is formed between the outer surface of the eutectic prevention member 33 and the inner surface of the storage hole 22. In addition, a gap 36 is formed between the inner surface of the eutectic prevention member 33 and the outer surface of the neutron absorber 31. The gap 35 and the gap 36 do not need to be uniform in the circumferential direction. That is, the eutectic prevention member 33 and the storage hole 22, and the eutectic prevention member 33 and the neutron absorber 31 may be in contact with each other.

中性子吸収部31と収納穴22間にギャップを設けることによって、中性子吸収部31と収納部材21との温度変化による機械的な相互作用を低減し、中性子吸収部31、共晶防止部材33および収納部材21それぞれの構造健全性を向上させることができる。   By providing a gap between the neutron absorber 31 and the storage hole 22, mechanical interaction due to temperature change between the neutron absorber 31 and the storage member 21 is reduced, and the neutron absorber 31, the eutectic prevention member 33 and the storage are reduced. The structural soundness of each member 21 can be improved.

[その他の実施形態]
以上、本発明のいくつかの実施形態を説明したが、これらの実施形態は、例として提示したものであり、発明の範囲を限定することは意図していない。たとえば、実施形態では、ウィング20の収納部材21はたとえば板材から成形され、収納穴22は穴加工により形成される場合を示したが、これには限らない。たとえば、板を曲げてU字型に成形した容器状の収納部材に固体状の中性子吸収部31を並べて収納する構成のウィングでも、本発明は適用できる。
[Other Embodiments]
As mentioned above, although some embodiment of this invention was described, these embodiment is shown as an example and is not intending limiting the range of invention. For example, in the embodiment, the storage member 21 of the wing 20 is formed from, for example, a plate material, and the storage hole 22 is formed by drilling. However, the present invention is not limited to this. For example, the present invention can also be applied to a wing having a configuration in which the solid neutron absorbing portions 31 are stored side by side in a container-shaped storage member formed by bending a plate into a U shape.

また、実施形態では、中性子吸収部31の材料がBCの場合を示したが、これに限定されない。たとえば、金属ハフニウム(Hf)などの場合でもよい。 Further, in the embodiment, the material of the neutron absorbing portion 31 shows the case of B 4 C, but is not limited thereto. For example, metal hafnium (Hf) may be used.

また、各実施形態の特徴を組み合わせてもよい。さらに、これらの実施形態は、その他の様々な形態で実施されることが可能であり、発明の要旨を逸脱しない範囲で、種々の省略、置き換え、変更を行うことができる。   Moreover, you may combine the characteristic of each embodiment. Furthermore, these embodiments can be implemented in various other forms, and various omissions, replacements, and changes can be made without departing from the scope of the invention.

これら実施形態やその変形は、発明の範囲や要旨に含まれると同様に、特許請求の範囲に記載された発明とその均等の範囲に含まれるものである。   These embodiments and their modifications are included in the scope and gist of the invention, and are also included in the invention described in the claims and the equivalents thereof.

1…燃料集合体、10…原子炉用制御棒、11…中央結合部材(結合部材)、20…ウィング、21…シース部(収納部材)、22…収納穴、31…中性子吸収部、33…共晶防止部材、35、36…ギャップ   DESCRIPTION OF SYMBOLS 1 ... Fuel assembly, 10 ... Reactor control rod, 11 ... Central coupling member (coupling member), 20 ... Wing, 21 ... Sheath part (housing member), 22 ... Storage hole, 31 ... Neutron absorption part, 33 ... Eutectic prevention member, 35, 36 ... gap

Claims (6)

中性子吸収材を有する中性子吸収部と、
前記中性子吸収部を内包する複数の収納部材と、
前記複数の収納部材を一体化する結合部材と、
中性子吸収効果および高温安定性を有する共晶防止用酸化物を含み、前記中性子吸収部と前記収納部材の間に設けられて前記中性子吸収部と前記収納部材との直接的な接触を防止する共晶防止部材と、
を備える原子炉用制御棒。
A neutron absorber having a neutron absorber;
A plurality of storage members enclosing the neutron absorber;
A coupling member that integrates the plurality of storage members;
A co-crystal preventing oxide having a neutron absorption effect and high-temperature stability is provided between the neutron absorption part and the storage member to prevent direct contact between the neutron absorption part and the storage member. An anti-crystallizing member;
A control rod for a nuclear reactor.
前記複数の収納部材のそれぞれは、上下方向に延びる軸のまわりに放射状に周方向の間隔をあけて配置されて前記軸の方向および放射方向に広がる平板状であり、
前記結合部材は、前記複数の収納部材を中央で結合する軸方向に延びた棒状である、
ことを特徴とする請求項1に記載の原子炉用制御棒。
Each of the plurality of storage members has a flat plate shape that is radially arranged around an axis extending in the vertical direction and spaced in the circumferential direction and extends in the direction of the axis and the radial direction,
The coupling member has a rod shape extending in the axial direction for coupling the plurality of storage members at the center.
The control rod for a nuclear reactor according to claim 1, wherein:
前記共晶防止用酸化物は、ガドリニウム酸化物、ユーロピウム酸化物、ディスプロシウム酸化物、サマリウム酸化物、エルビウム酸化物の少なくとも一つを含むことを特徴とする請求項1または請求項2に記載の原子炉用制御棒。   The oxide for preventing eutectic includes at least one of gadolinium oxide, europium oxide, dysprosium oxide, samarium oxide, and erbium oxide. Control rod for nuclear reactors. 前記中性子吸収部は固体形状であり、前記共晶防止部材は、前記中性子吸収部の周囲に密着するように形成されていることを特徴とする請求項1ないし請求項3のいずれか一項に記載の原子炉用制御棒。   The said neutron absorption part is a solid shape, The said eutectic prevention member is formed so that it may closely_contact | adhere to the circumference | surroundings of the said neutron absorption part, The Claim 1 thru | or 3 characterized by the above-mentioned. The reactor control rod as described. 前記共晶防止部材は容器状に形成され、前記中性子吸収部は前記容器状の前記共晶防止部材内に収納されていることを特徴とする請求項1ないし請求項3のいずれか一項に記載の原子炉用制御棒。   The said eutectic prevention member is formed in a container shape, The said neutron absorption part is accommodated in the said eutectic prevention member of the said container shape, The Claim 1 thru | or 3 characterized by the above-mentioned. The reactor control rod as described. 前記複数の収納部材のそれぞれには、前記中性子吸収部を収納するための複数の収納穴が形成されており、前記共晶防止部材は、前記収納穴の内面に沿って設けられていることを特徴とする請求項1ないし請求項3のいずれか一項に記載の原子炉用制御棒。   Each of the plurality of storage members is formed with a plurality of storage holes for storing the neutron absorbing portion, and the eutectic prevention member is provided along the inner surface of the storage hole. The control rod for a nuclear reactor according to any one of claims 1 to 3, wherein the control rod is a reactor.
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