JPH03220496A - Control rod of nuclear reactor - Google Patents
Control rod of nuclear reactorInfo
- Publication number
- JPH03220496A JPH03220496A JP2014821A JP1482190A JPH03220496A JP H03220496 A JPH03220496 A JP H03220496A JP 2014821 A JP2014821 A JP 2014821A JP 1482190 A JP1482190 A JP 1482190A JP H03220496 A JPH03220496 A JP H03220496A
- Authority
- JP
- Japan
- Prior art keywords
- hafnium
- control rod
- blade
- thin plates
- gaps
- 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
- 229910052735 hafnium Inorganic materials 0.000 claims abstract description 37
- VBJZVLUMGGDVMO-UHFFFAOYSA-N hafnium atom Chemical compound [Hf] VBJZVLUMGGDVMO-UHFFFAOYSA-N 0.000 claims abstract description 37
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 5
- 238000010521 absorption reaction Methods 0.000 abstract description 9
- 239000002826 coolant Substances 0.000 abstract description 6
- 230000020169 heat generation Effects 0.000 abstract description 2
- 230000003247 decreasing effect Effects 0.000 abstract 1
- 230000003467 diminishing effect Effects 0.000 abstract 1
- 230000008689 nuclear function Effects 0.000 abstract 1
- 229910052580 B4C Inorganic materials 0.000 description 6
- INAHAJYZKVIDIZ-UHFFFAOYSA-N boron carbide Chemical compound B12B3B4C32B41 INAHAJYZKVIDIZ-UHFFFAOYSA-N 0.000 description 6
- 230000000694 effects Effects 0.000 description 3
- 238000004519 manufacturing process Methods 0.000 description 3
- 238000009835 boiling Methods 0.000 description 2
- 238000006243 chemical reaction Methods 0.000 description 2
- 238000005253 cladding Methods 0.000 description 2
- 239000011358 absorbing material Substances 0.000 description 1
- 238000009826 distribution Methods 0.000 description 1
- 239000007789 gas Substances 0.000 description 1
- 239000001307 helium Substances 0.000 description 1
- 229910052734 helium Inorganic materials 0.000 description 1
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 239000000843 powder Substances 0.000 description 1
- 238000004904 shortening 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
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
Description
【発明の詳細な説明】
[産業上の利用分野]
本発明は、沸騰水型原子炉に使用される原子炉制御棒に
係わり、特に核的性能の長寿命化に好適な原子炉制御棒
に関する。Detailed Description of the Invention [Field of Industrial Application] The present invention relates to a reactor control rod used in a boiling water nuclear reactor, and particularly to a reactor control rod suitable for extending the life of nuclear performance. .
[従来の技術]
従来の沸騰水型原子炉に使用される原子炉制御棒は、第
3図の全体斜視図および第4図の横断面図に示すように
、中心部にある断面十字形状の長尺のタイロッド3の各
月4に断面U字形の長手方向にのびたシース5が固定さ
れ、そのシースの内部に中性子吸収棒6を配列した4枚
のブレードで構成される。中性子吸収棒6は長尺細径の
被覆管の内部に中性子吸収材であるボロンカーバイドの
粉末を充填した構造である。ボロンカーバイドは中性子
の照射を受けると(n、α)反応によりヘリウムガスを
生じて、ボロンカーバイド被覆管内の圧力を高める結果
、中性子吸収棒6の破損が起きて、原子炉制御棒の寿命
が短くなる。そこで、長寿命化を図った制御棒として、
例えば特開昭59−17192号公報に記載されたよう
な制御棒のブレードにハフニウムを用いる原子炉制御棒
が提示されている。[Prior Art] A reactor control rod used in a conventional boiling water reactor has a cross-sectional cross-section in the center, as shown in the overall perspective view in Fig. 3 and the cross-sectional view in Fig. 4. A sheath 5 extending in the longitudinal direction and having a U-shaped cross section is fixed to each lug 4 of the long tie rod 3, and is composed of four blades in which neutron absorption rods 6 are arranged inside the sheath. The neutron absorption rod 6 has a structure in which boron carbide powder, which is a neutron absorption material, is filled inside a long and thin cladding tube. When boron carbide is irradiated with neutrons, it generates helium gas through a (n, α) reaction, which increases the pressure inside the boron carbide cladding tube, causing damage to the neutron absorption rod 6 and shortening the life of the reactor control rod. Become. Therefore, as a control rod with a long lifespan,
For example, a nuclear reactor control rod using hafnium in the blade of the control rod as described in Japanese Unexamined Patent Publication No. 59-17192 has been proposed.
[発明が解決しようとする課題]
上記従来技術例では、厚板のハフニウムをブレードとし
て用いるが、ハフニウムは重量が大きい上に非常に高価
であるという問題点があった。また、ハフニウムは(n
、γ)反応型中性子吸収棒であるため、γ線によってハ
フニウム自体が高温になるという問題があった。[Problems to be Solved by the Invention] In the prior art example described above, a thick plate of hafnium is used as the blade, but there are problems in that hafnium is heavy and very expensive. Also, hafnium is (n
, γ) Because it is a reactive neutron absorption rod, there was a problem that the hafnium itself became hot due to γ rays.
本発明の目的は、上記の従来技術の欠点を除き、ハフニ
ウムの使用量の低減化をはかり、廉価で寿命の長い原子
炉制御棒を提供することにある。An object of the present invention is to eliminate the above-mentioned drawbacks of the prior art, reduce the amount of hafnium used, and provide a nuclear reactor control rod that is inexpensive and has a long life.
[課題を解決するための手段]
上記課題を解決するための本発明の原子炉制御棒の構成
は、原子炉炉心を構成し、原子炉出力を制御するための
十字形状ブレードからなる原子炉制御棒において、ブレ
ードの一端は、中央部のタイロッドと嵌合してなり、十
字形状板を形成する複数枚のブレードをハフニウム製薄
板でつくり。[Means for Solving the Problems] The structure of the reactor control rod of the present invention for solving the above problems is a reactor control rod consisting of a cross-shaped blade for configuring the reactor core and controlling the reactor output. In the rod, one end of the blade is fitted with a tie rod in the center, forming a cross-shaped plate made of multiple blades made of thin hafnium plates.
各薄板間に炉水を自在に流動させることができる隙間を
設けるようにしたことである。A gap is provided between each thin plate to allow reactor water to flow freely.
[作用]
複数枚のハフニウム薄板で構成されたフィン構造のブレ
ードは、高価なハフニウムの使用量を減らして原子炉制
御棒の軽量化ならびに低廉化を達成する。また、ブレー
ドの形状をフィン構造に改善することによりハフニウム
の表面積が相対的に増大することから原子炉制御棒の中
性子吸収能力が高まる。さらに、ハフニウム薄板間に設
ける隙間により、その隙間を流れる冷却材はハフニウム
薄板の7発熱を除去する作用を有する。[Function] A blade with a fin structure composed of a plurality of hafnium thin plates reduces the amount of expensive hafnium used, thereby achieving lighter weight and lower cost of the reactor control rod. Furthermore, by improving the shape of the blade to have a fin structure, the surface area of hafnium increases relatively, which increases the neutron absorption capacity of the reactor control rod. Further, due to the gaps provided between the hafnium thin plates, the coolant flowing through the gaps has the effect of removing the heat generated by the hafnium thin plates.
[実施例コ
以下、本発明に係る1実施例を第1図、第2図を用いて
説明する。[Example 1] An example according to the present invention will be described below with reference to FIGS. 1 and 2.
第1図は本発明の原子炉制御棒の全体斜視図、第2図は
同上横断面図である。第2図において、2は薄板のハフ
ニウムで、タイロッド3のタイロッド片4に嵌合させる
。ブレード1はタイロッドの各月において3枚のハフニ
ウム薄板から構成されており、各ハフニウム薄板の間に
冷却材が流動するための隙間が形成されている。FIG. 1 is an overall perspective view of a nuclear reactor control rod according to the present invention, and FIG. 2 is a cross-sectional view of the same. In FIG. 2, 2 is a thin plate of hafnium, which is fitted into the tie rod piece 4 of the tie rod 3. The blade 1 is composed of three hafnium thin plates in each month of the tie rod, and gaps are formed between each hafnium thin plate for the flow of the coolant.
従って、本実施例の制御棒はプレートとして1枚のハフ
ニウム厚板を用いる場合に比べ、ハフニウムの使用量を
約172に減らし、ハフニウム重量を、制御棒1体あた
り約80kgに低減することができる。本実施例のハフ
ニウム重量を約80kgにした場合でも、制御棒は、従
来のボロンカーバイド制御棒の約3倍の寿命を有する。Therefore, in the control rod of this embodiment, the amount of hafnium used can be reduced to about 172, and the weight of hafnium can be reduced to about 80 kg per control rod, compared to the case where one thick hafnium plate is used as the plate. . Even when the hafnium weight of this example is approximately 80 kg, the control rod has a life approximately three times longer than that of a conventional boron carbide control rod.
また、ハフニウム薄板の間に冷却材が存在するため、両
側のハフニウム薄板で吸収されなかった中性子が上記の
冷却材によって減速され、中央のハフニウム薄板におい
て吸収される結果、制御棒の中性子吸収能力が一層向上
される。ハフニウム薄板の隙間を流動する冷却材は、ハ
フニウムの(n、γ)反応で生じる7発熱を除去する作
用をし、7発熱によるハフニウム薄板の熱変形等を防止
する効果を有する。In addition, since there is a coolant between the hafnium thin plates, neutrons that are not absorbed by the hafnium thin plates on both sides are decelerated by the coolant and absorbed by the central hafnium thin plate, which reduces the neutron absorption capacity of the control rod. It will be further improved. The coolant flowing through the gaps between the hafnium thin plates acts to remove the 7 heat generated by the (n, γ) reaction of hafnium, and has the effect of preventing thermal deformation of the hafnium thin plates due to the 7 heat generation.
本実施例の制御棒では、中性子吸収材としてハフニウム
を使用するため、中性子吸収断面積の大きな核種が連鎖
的に生成されることにより、従来のボロンカーバイドに
比べて核的寿命が長くなって制御棒の耐用年数を伸ばす
ことができる。In the control rod of this example, hafnium is used as the neutron absorbing material, so nuclides with a large neutron absorption cross section are generated in a chain manner, resulting in a longer nuclear life than conventional boron carbide, which allows control rods to be controlled using hafnium. It can extend the service life of the rod.
なお、制御棒のブレードに取り付けるハフニウム薄板の
厚さおよび枚数については、原子炉内に設置する制御棒
に要求される出力分布等の制御能力に応じて適宜選定す
ることが可能である。The thickness and number of hafnium thin plates attached to the blades of the control rods can be appropriately selected depending on the control capability such as power distribution required of the control rods installed in the reactor.
さらに、本実施例の制御棒は、製造技術上は、比較的容
易であり、従来例に比べて、加工費1組立費、人件費な
どの魚から、経費低減に効果がある。Furthermore, the control rod of this embodiment is relatively easy to manufacture, and is effective in reducing manufacturing costs, assembly costs, labor costs, etc. compared to the conventional example.
[発明の効果コ
本発明によれば、高価なハフニウムの重量を低減化し、
ハフニウムの表面積を増大させることができるので、経
済性に富み、かつ従来のボロンカーバイドを用いた原子
炉制御棒より核的寿命の長い原子炉制御棒を提供できる
効果がある。[Effects of the Invention] According to the present invention, the weight of expensive hafnium can be reduced,
Since the surface area of hafnium can be increased, it is possible to provide a nuclear reactor control rod that is highly economical and has a longer nuclear life than conventional reactor control rods using boron carbide.
また、従来例と比べて、加工工数が少ないので製造費を
低減化することができる。Furthermore, since the number of processing steps is smaller than in the conventional example, manufacturing costs can be reduced.
第1図は、本発明の実施例の原子炉制御棒の全体斜視図
、第2図は、同上の横断面図、第3図は。
従来例の原子炉制御棒の全体斜視図、第4図は、同上の
横断面図である。
〈符号の説明〉FIG. 1 is an overall perspective view of a nuclear reactor control rod according to an embodiment of the present invention, FIG. 2 is a cross-sectional view of the same, and FIG. 3 is a cross-sectional view of the same. FIG. 4, which is an overall perspective view of a conventional nuclear reactor control rod, is a cross-sectional view of the same as above. <Explanation of symbols>
Claims (1)
十字形状ブレードからなる原子炉制御棒において、ブレ
ードの一端は、中央部のタイロッドと嵌合してなり、十
字形状板を形成する複数枚のブレードをハフニウム製薄
板でつくり、各薄板間に炉水を自在に流動させることが
できる隙間を設けたことを特徴とする原子炉制御棒。1. In a reactor control rod consisting of a cross-shaped blade that constitutes the reactor core and controls the reactor output, one end of the blade is fitted with a tie rod in the center to form a cross-shaped plate. A nuclear reactor control rod characterized in that a plurality of blades are made of hafnium thin plates and gaps are provided between each thin plate to allow reactor water to freely flow.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP2014821A JPH03220496A (en) | 1990-01-26 | 1990-01-26 | Control rod of nuclear reactor |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP2014821A JPH03220496A (en) | 1990-01-26 | 1990-01-26 | Control rod of nuclear reactor |
Publications (1)
Publication Number | Publication Date |
---|---|
JPH03220496A true JPH03220496A (en) | 1991-09-27 |
Family
ID=11871708
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP2014821A Pending JPH03220496A (en) | 1990-01-26 | 1990-01-26 | Control rod of nuclear reactor |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPH03220496A (en) |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US6137854A (en) * | 1997-10-16 | 2000-10-24 | Kabushiki Kaisha Toshiba | Reactor control rod and method of manufacturing the same |
JP2010230607A (en) * | 2009-03-30 | 2010-10-14 | Hitachi-Ge Nuclear Energy Ltd | Control rod |
-
1990
- 1990-01-26 JP JP2014821A patent/JPH03220496A/en active Pending
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US6137854A (en) * | 1997-10-16 | 2000-10-24 | Kabushiki Kaisha Toshiba | Reactor control rod and method of manufacturing the same |
JP2010230607A (en) * | 2009-03-30 | 2010-10-14 | Hitachi-Ge Nuclear Energy Ltd | Control rod |
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