JPH0117559B2 - - Google Patents
Info
- Publication number
- JPH0117559B2 JPH0117559B2 JP56155291A JP15529181A JPH0117559B2 JP H0117559 B2 JPH0117559 B2 JP H0117559B2 JP 56155291 A JP56155291 A JP 56155291A JP 15529181 A JP15529181 A JP 15529181A JP H0117559 B2 JPH0117559 B2 JP H0117559B2
- Authority
- JP
- Japan
- Prior art keywords
- zirconium
- hafnium
- control rod
- rod
- neutron
- 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
- QCWXUUIWCKQGHC-UHFFFAOYSA-N Zirconium Chemical compound [Zr] QCWXUUIWCKQGHC-UHFFFAOYSA-N 0.000 claims description 29
- 229910052726 zirconium Inorganic materials 0.000 claims description 29
- 229910052735 hafnium Inorganic materials 0.000 claims description 26
- VBJZVLUMGGDVMO-UHFFFAOYSA-N hafnium atom Chemical compound [Hf] VBJZVLUMGGDVMO-UHFFFAOYSA-N 0.000 claims description 25
- 238000010521 absorption reaction Methods 0.000 claims description 17
- 239000000463 material Substances 0.000 claims description 15
- 229910045601 alloy Inorganic materials 0.000 claims description 14
- 239000000956 alloy Substances 0.000 claims description 14
- 229910052758 niobium Inorganic materials 0.000 claims 1
- 239000010955 niobium Substances 0.000 claims 1
- GUCVJGMIXFAOAE-UHFFFAOYSA-N niobium atom Chemical compound [Nb] GUCVJGMIXFAOAE-UHFFFAOYSA-N 0.000 claims 1
- 238000005253 cladding Methods 0.000 description 8
- 239000011358 absorbing material Substances 0.000 description 6
- 230000000694 effects Effects 0.000 description 3
- 230000005484 gravity Effects 0.000 description 2
- 239000000843 powder Substances 0.000 description 2
- 230000009257 reactivity Effects 0.000 description 2
- 239000000126 substance Substances 0.000 description 2
- 229910001257 Nb alloy Inorganic materials 0.000 description 1
- 239000006096 absorbing agent Substances 0.000 description 1
- 238000009835 boiling Methods 0.000 description 1
- 238000009792 diffusion process Methods 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- GFUGMBIZUXZOAF-UHFFFAOYSA-N niobium zirconium Chemical compound [Zr].[Nb] GFUGMBIZUXZOAF-UHFFFAOYSA-N 0.000 description 1
- 230000008569 process Effects 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 239000002901 radioactive waste Substances 0.000 description 1
- 238000007670 refining Methods 0.000 description 1
- 230000004044 response Effects 0.000 description 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 1
- 239000013585 weight reducing agent Substances 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
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Load-Engaging Elements For Cranes (AREA)
- Separation Using Semi-Permeable Membranes (AREA)
Description
【発明の詳細な説明】 本発明は原子炉用制御棒に係る。[Detailed description of the invention] The present invention relates to a control rod for a nuclear reactor.
従来の沸騰水型原子炉用制御棒は次のように構
成されている。 A conventional boiling water reactor control rod is constructed as follows.
すなわち、中央構造材である十字状断面のタイ
ロツドの各脚に、細長いＵ字状断面のシースを取
付けてウイングを構成し、各ウイング内に数十本
の中性子吸収棒を装填して制御棒としている。而
して、中性子吸収棒はSUSから成る被覆管内に
中性子吸収材であるB4C粉末を充填して構成され
ている。 In other words, a wing is constructed by attaching an elongated sheath with a U-shaped cross section to each leg of a tie rod with a cross-shaped cross section, which is the central structural member, and dozens of neutron absorption rods are loaded into each wing to function as control rods. There is. The neutron absorbing rod is constructed by filling a cladding tube made of SUS with B 4 C powder, which is a neutron absorbing material.
B4C中のＢは中性子を吸収した時、これと反応
してHeガスを発生し被覆管内のガス圧を上昇さ
せる。また、中性子を吸収して生成される物質の
中性子吸収率が小さい。上記の二つのことから
B4C粉末を中性子吸収材とする制御棒は、機械
的、核的に早期に寿命に達する。 When B in B 4 C absorbs neutrons, it reacts with the neutrons to generate He gas and increase the gas pressure inside the cladding tube. In addition, the neutron absorption rate of substances produced by absorbing neutrons is low. From the above two things
Control rods using B 4 C powder as neutron absorbing material reach the end of their mechanical and nuclear lifetimes early.
これに対し、原子炉運転の簡素化、炉心特性の
改良、放射性廃棄物生成量の抑制、原子炉稼動率
の向上等の見地から制御棒の長寿命化が要望され
ている。 In response, there is a desire to extend the life of control rods from the viewpoints of simplifying reactor operation, improving core characteristics, suppressing the amount of radioactive waste generated, and improving reactor operating efficiency.
上記の要望に応じるものとして、長寿命型の中
性子吸収材であるEu2O3、Hf、Ag―In―Cd等を
制御棒の強度の中性子照射を受ける部位または制
御棒全体にわたつて使用したものが開発されてい
る。 In order to meet the above request, long-life neutron absorbing materials such as Eu 2 O 3 , Hf, Ag-In-Cd, etc. were used in the parts of the control rod that are exposed to intense neutron irradiation or throughout the control rod. something is being developed.
ところが上記の長寿命型中性子吸収材は何れも
密度が高く、従つて制御棒の重量が大きくなる。
制御棒が大重量となれば、制御棒落下事故対策の
面や、制御棒駆動装置の余裕等の面で不利であ
り、はなはだしい場合には既設の制御棒駆動装置
を使用できないこととなる。 However, all of the above-mentioned long-life neutron absorbers have a high density, and therefore the weight of the control rod becomes large.
If the control rods become heavy, it is disadvantageous in terms of countermeasures against control rod fall accidents and the margin of the control rod drive device, and in extreme cases, the existing control rod drive device cannot be used.
本発明は上記の事情に基きなされたもので、長
寿命型でしかも軽量な原子炉用制御棒を得ること
を目的としている。 The present invention was made based on the above-mentioned circumstances, and an object of the present invention is to obtain a long-life and lightweight control rod for a nuclear reactor.
本発明に係る原子炉用制御棒は、上述した目的
を達成するためにウイングの少なくとも強度の中
性子照射を受ける部位には、天然ジルコニウムと
同程度のハフニウム濃度を有するジルコニウムを
主成分とする合金から成る被覆管に、ハフニウム
を充填して成る中性子吸収棒を配置し、少なくと
も大重量の構造材は天然ジルコニウムと同程度の
ハフニウム濃度を有するジルコニウムを主成分と
する合金により構成したものである。 In order to achieve the above-mentioned object, the control rod for a nuclear reactor according to the present invention is made of a zirconium-based alloy having a hafnium concentration comparable to that of natural zirconium, in a portion of the wing that receives at least intense neutron irradiation. A neutron absorbing rod filled with hafnium is placed in a cladding tube, and at least the heavy structural material is made of a zirconium-based alloy having a hafnium concentration comparable to that of natural zirconium.
以下、図面につき本発明の詳細を説明する。第
１図乃至第３図において十字状断面のタイロツド
１の各脚には、細長いＵ字状断面のシースをそれ
らの開口部において取付けて十字状のウイング２
が形成してある。また、各ウイング２内には多数
の中性子吸収棒３が装填されており、ウイング２
下端にはスピードリミツタ４を下端にそなえた下
部構造材５が固着され、ウイング上端には上端に
取手６をそなえた上部構造材７が固着されてい
る。 The invention will be explained in detail below with reference to the drawings. In FIGS. 1 to 3, each leg of a tie rod 1 having a cruciform cross section is fitted with an elongated sheath having a U-shaped cross section at its opening to form a cruciform wing 2.
is formed. In addition, a large number of neutron absorption rods 3 are loaded inside each wing 2, and the wing 2
A lower structural member 5 having a speed limiter 4 at the lower end is fixed to the lower end, and an upper structural member 7 having a handle 6 at the upper end is fixed to the upper end of the wing.
上記の中、中性子吸収棒を除き、制御棒の構造
材は全て天然ジルコニウムと同程度のハフニウム
濃度を有するジルコニウムを主成分とする合金で
構成する。 Among the above, except for the neutron absorption rod, all the structural materials of the control rod are composed of an alloy whose main component is zirconium, which has a hafnium concentration comparable to that of natural zirconium.
さらに、中性子吸収棒はハフニウム３ｂをジル
コニウムを主成分とする合金から成る被覆管３ａ
内に充填して構成されている。 Furthermore, the neutron absorption rod has a cladding tube 3a made of an alloy containing hafnium 3b and zirconium as main components.
It is constructed by filling the inside.
上記構成の本発明制御棒においては、ウイング
２を構成するシース、中央構造材であるタイロツ
ド１、先端構造材７、取手６、下部構造材５、ス
ピードリミツタ４等の全ての構造材をまたはジル
コニウムを主成分とする合金で構成している。 In the control rod of the present invention having the above configuration, all the structural members such as the sheath constituting the wing 2, the tie rod 1 which is the central structural member, the tip structural member 7, the handle 6, the lower structural member 5, the speed limiter 4, etc. It is composed of an alloy whose main component is zirconium.
而して、前記の構造材は比重が約6.5ｇ／cm3と
従来の制御棒の構造材料であるSUS（比重約8.0
ｇ／cm3）より小さいので、構造材の全重量を従来
より20％程度減じることができる。 The above-mentioned structural material has a specific gravity of approximately 6.5 g/cm 3 and is similar to SUS (specific gravity approximately 8.0 g/cm 3 ), which is the structural material for conventional control rods.
g/cm 3 ), the total weight of the structural material can be reduced by about 20% compared to conventional materials.
従つて、上記実施例のように、ウイング内に装
填される全中性子吸収棒をハフニウムを吸収材と
するものにしても、制御棒全体の重量増加は従来
型の制御棒の重量に比し、20％程度に押えること
ができる。また、制御棒のウイング先端部やウイ
ング側縁等、特に強度の中性子照射を受ける部位
のみをハフニウム充填の中性子吸収棒とし、他の
部位にはB4C充填の中性子吸収棒とする場合にあ
つては、通常型の制御棒より軽量化することもで
きる。 Therefore, even if all the neutron absorption rods loaded in the wing are made of hafnium as the absorbing material as in the above embodiment, the weight of the entire control rod increases compared to the weight of a conventional control rod. It can be reduced to around 20%. In addition, it is possible to use hafnium-filled neutron absorption rods only in areas that receive particularly strong neutron irradiation, such as the wing tips and wing side edges of control rods, and use B 4 C-filled neutron absorption rods in other areas. Therefore, it can also be lighter than regular control rods.
なお、前記B4C充填中性子吸収棒とハフニウム
充填中性子吸収棒とを混用する場合において、重
量が通常型の制御棒と等しくてよければ、構造材
が軽くなつた分だけハフニウム充填中性子吸収棒
を増加させることができ、反応度効果の向上、寿
命の延長をはかることができる。 In addition, when using the B 4 C-filled neutron absorption rod and the hafnium-filled neutron absorption rod together, if the weight is equal to that of a normal control rod, the hafnium-filled neutron absorption rod can be used to compensate for the lighter structural material. It is possible to increase the reactivity, improve the reactivity effect, and extend the service life.
一方、本発明において使用されている中性子吸
収棒３は、中性子吸収材としてハフニウムを、ま
た被覆管としてジルコニウムを主成分とする合金
を使用している。ジルコニウムとハフニウムとは
物理的、化学的性質が酷似しており、そのため前
記中性子吸収材と被覆管との間で、原子の相互拡
散が生じても両者の健全性を損ねるおそれはな
く、両立性に優れている。 On the other hand, the neutron absorbing rod 3 used in the present invention uses hafnium as a neutron absorbing material and an alloy containing zirconium as a main component as a cladding tube. Zirconium and hafnium have very similar physical and chemical properties, so even if mutual diffusion of atoms occurs between the neutron absorbing material and the cladding, there is no risk of damaging the integrity of both, and they are compatible. Excellent.
なお、ジルコニウムとハフニウムとは天然に共
存し、ジルコニウム精製の過程でハフニウムを分
離除去することは、かなりやつかいで相当の費用
を必要とする。ところが、天然産のジルコニウム
中に含まれるハフニウムの量は約２％であり、ジ
ルコニウム中にこの程度のハフニウムが含まれて
いる時はハフニウム自身の共鳴による自己遮蔽は
なく、被覆管、各構造材共に中性子吸収に関与す
ることとなり、かなりの大きさの中性子吸収効果
の増大がはかられる。従つて、多くの手数と多額
の費用とをかけてジルコニウムからハフニウムを
分離除去する必要はない。 Note that zirconium and hafnium naturally coexist, and separating and removing hafnium in the process of refining zirconium is quite difficult and requires considerable cost. However, the amount of hafnium contained in naturally produced zirconium is approximately 2%, and when zirconium contains this much hafnium, there is no self-shielding due to the resonance of hafnium itself, and the cladding tube and each structural material Both will be involved in neutron absorption, and the neutron absorption effect will be increased considerably. Therefore, it is not necessary to separate and remove hafnium from zirconium by spending a lot of time and money.
従つて、原価の低減をはかることができる。 Therefore, it is possible to reduce the cost.
なお、構造材中多量の中性子照射を受け照射損
傷による脆弱化を生じ易いもの、例えば、取手や
先端構造材等はジルコニウム―ニオブ合金等によ
り構成して、照射による強度低下を防止すればよ
い。 Incidentally, structural materials that are susceptible to irradiation with large amounts of neutrons and become brittle due to radiation damage, such as handles and tip structural materials, may be made of a zirconium-niobium alloy or the like to prevent a decrease in strength due to irradiation.
なお、本発明は上記実施例のみに限定されな
い。例えば制御棒の重量制限があまりきびしくな
ければ、構造材の全てをジルコニウムを主成分と
する合金により構成する必要はなく特に大重量の
もののみをそのようにすればよい。 Note that the present invention is not limited to the above embodiments. For example, if the weight limit of the control rods is not too strict, it is not necessary to make all the structural members from an alloy whose main component is zirconium, and only the particularly heavy ones need to be made of such an alloy.
以上に述べたように本発明に係る原子炉用制御
棒は、少なくとも大重量の構造材を、天然ジルコ
ニウムと同程度のハフニウム濃度を有するジルコ
ニウムを主成分とする合金で形成したから、制御
棒の重量軽減を図ることができ、既存の制御棒駆
動装置をそのまま用いることができる。また、ウ
イング内に配置される中性子吸収棒は、少なくと
も強度の中性子照射を受ける部位には、天然ジル
コニウムと同程度のハフニウム濃度を有するジル
コニウムを主成分とする合金製被覆管内にハフニ
ウムを充填して形成したので、かなりの大きさの
中性子吸収効果の増大が図れ、しかも、ジルコニ
ウムを主成分とする合金には、天然ジルコニウム
と同程度のハフニウム濃度を有するジルコニウム
が用いられるので、多くの手数とコストをかけて
ジルコニウムからハフニウムを分離除去する処理
作業が不要となる等の効果を奏する。 As described above, in the control rod for a nuclear reactor according to the present invention, at least the heavy structural material is formed of an alloy mainly composed of zirconium having a hafnium concentration comparable to that of natural zirconium. Weight reduction can be achieved, and the existing control rod drive device can be used as is. In addition, the neutron absorption rods placed in the wings are filled with hafnium in an alloy cladding tube mainly composed of zirconium, which has a hafnium concentration similar to that of natural zirconium, at least in the parts that receive intense neutron irradiation. As a result, the neutron absorption effect can be significantly increased, and since zirconium with a hafnium concentration comparable to that of natural zirconium is used in alloys containing zirconium as the main component, much labor and cost are required. This has advantages such as eliminating the need for processing operations to separate and remove hafnium from zirconium.
第１図は本発明一実施例の一部を切欠して示す
斜視図、第２図はその横断面図、第３図はその正
面図である。
１…タイロツド、２…ウイング、３…中性子吸
収棒、４…スピードリミツタ、５…下部構造材、
６…取手、７…先端構造材。
FIG. 1 is a partially cutaway perspective view of an embodiment of the present invention, FIG. 2 is a cross-sectional view thereof, and FIG. 3 is a front view thereof. 1... Tie rod, 2... Wing, 3... Neutron absorption rod, 4... Speed limiter, 5... Lower structure material,
6...Handle, 7...Tip structural material.
Claims (1)
ける部位には、天然ジルコニウムと同程度のハフ
ニウム濃度を有するジルコニウムを主成分とする
合金から成る被覆管に、ハフニウムを充填して成
る中性子吸収棒を配置し、少なくとも大重量の構
造材は天然ジルコニウムと同程度のハフニウム濃
度を有するジルコニウムを主成分とする合金によ
り構成したことを特徴とする原子炉用制御棒。 ２ 多量の中性子照射を受ける部位の構造材に
は、ジルコニウムを主成分とする合金内にニオブ
が含まれている特許請求の範囲第１項に記載の原
子炉用制御棒。[Scope of Claims] 1. In the portion of the wing that receives at least intense neutron irradiation, a neutron irradiation tube made of a zirconium-based alloy having a hafnium concentration similar to that of natural zirconium is filled with hafnium. 1. A control rod for a nuclear reactor, in which an absorption rod is arranged, and at least the heavy structural material is made of an alloy containing zirconium as a main component and having a hafnium concentration comparable to that of natural zirconium. 2. The control rod for a nuclear reactor according to claim 1, wherein the structural material of the portion that receives a large amount of neutron irradiation contains niobium in an alloy whose main component is zirconium.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56155291A JPS5855888A (en) | 1981-09-30 | 1981-09-30 | Control rod of reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56155291A JPS5855888A (en) | 1981-09-30 | 1981-09-30 | Control rod of reactor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS5855888A JPS5855888A (en) | 1983-04-02 |
| JPH0117559B2 true JPH0117559B2 (en) | 1989-03-30 |
Family
ID=15602679
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP56155291A Granted JPS5855888A (en) | 1981-09-30 | 1981-09-30 | Control rod of reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS5855888A (en) |
Families Citing this family (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP5376782B2 (en) * | 2007-08-31 | 2013-12-25 | 株式会社東芝 | Reactor control rod and manufacturing method thereof |
| JP2009058447A (en) * | 2007-08-31 | 2009-03-19 | Toshiba Corp | Control rod for reactor |
| JP2010243331A (en) * | 2009-04-06 | 2010-10-28 | Toshiba Corp | Control rod for nuclear reactor |
| JP2011007715A (en) * | 2009-06-29 | 2011-01-13 | Toshiba Corp | Control rod for reactor |
Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5690292A (en) * | 1979-12-24 | 1981-07-22 | Nippon Atomic Ind Group Co | Nuclear reactor control rod |
-
1981
- 1981-09-30 JP JP56155291A patent/JPS5855888A/en active Granted
Patent Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5690292A (en) * | 1979-12-24 | 1981-07-22 | Nippon Atomic Ind Group Co | Nuclear reactor control rod |
Also Published As
| Publication number | Publication date |
|---|---|
| JPS5855888A (en) | 1983-04-02 |
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