JPH0363590A - Control rod for nuclear reactor - Google Patents
Control rod for nuclear reactorInfo
- Publication number
- JPH0363590A JPH0363590A JP1199411A JP19941189A JPH0363590A JP H0363590 A JPH0363590 A JP H0363590A JP 1199411 A JP1199411 A JP 1199411A JP 19941189 A JP19941189 A JP 19941189A JP H0363590 A JPH0363590 A JP H0363590A
- Authority
- JP
- Japan
- Prior art keywords
- control rod
- europium oxide
- neutron absorption
- nuclear reactor
- 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.)
- Pending
Links
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)
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) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.
Description
【発明の詳細な説明】
〔産業上の利用分野〕
本発明は、原子炉の余剰反応度制御、および、炉停止時
の未臨界性を保障するために用いる原子炉用制御棒に関
する。DETAILED DESCRIPTION OF THE INVENTION [Field of Industrial Application] The present invention relates to a control rod for a nuclear reactor used for controlling excess reactivity of a nuclear reactor and ensuring subcriticality during reactor shutdown.
従来の沸騰水型原子炉には、第２図に示すような構成の
制御棒が用いられてきた。中性子吸収材として、例えば
、炭化ホウ素（ＢａＣ）の粉末をステンレス管に充填し
た中性子吸収棒１をＵ字型断面のシース２とタイロッド
３とを結合して作ったウィング内に装填する。Conventional boiling water nuclear reactors have used control rods configured as shown in FIG. As a neutron absorbing material, for example, a neutron absorbing rod 1 in which a stainless steel tube is filled with powder of boron carbide (BaC) is loaded into a wing made by joining a sheath 2 with a U-shaped cross section and a tie rod 3.
この構成の制御棒は四個の燃料集合体の間に挿入・引抜
自在に設置して使用に供する。制御棒挿入時の中性子照
射量はウィングの先端で急激に増大する。このため、ウ
ィングの先端に位置する吸収棒内のＢ４Ｃは他の部分に
比べて消耗がはげしく制御棒の寿命は先端部の吸収率に
より寿命が決まる。The control rod with this configuration is installed between the four fuel assemblies so that it can be inserted and withdrawn for use. The amount of neutron irradiation when the control rod is inserted increases rapidly at the tip of the wing. For this reason, the B4C in the absorption rod located at the tip of the wing is subject to greater wear than other parts, and the life of the control rod is determined by the absorption rate of the tip.
また、制御棒の挿入方向についてみると制御棒先端部の
中性子前Ｎ量が大きい。Furthermore, in terms of the insertion direction of the control rod, the amount of neutron front N at the tip of the control rod is large.
このような問題点を解決するため、特開昭５９−１９２
９９２号公報に記載のように、ハフニウム（Ｈｆ）棒か
らなる中性子吸収棒を用いることが考えられている。In order to solve these problems, Japanese Unexamined Patent Publication No. 59-192
As described in Japanese Patent No. 992, it has been considered to use a neutron absorption rod made of a hafnium (Hf) rod.
上記、従来技術では、比重の大きなハフニウムを中性子
吸収棒として用いているため、制御棒が重くなり制御棒
駆動装置への負担が大きくなるという問題があった。In the above-mentioned conventional technology, since hafnium, which has a large specific gravity, is used as a neutron absorption rod, there is a problem in that the control rod becomes heavy and the load on the control rod drive device increases.
本発明の目的は軽量、かつ、長寿命で、高反応度価値を
もつ原子炉用制御棒を提供することにある。An object of the present invention is to provide a control rod for a nuclear reactor that is lightweight, has a long life, and has high reactivity value.
上記目的を達成するために、本発明の制御棒は以下のＭ
或をもつ。In order to achieve the above object, the control rod of the present invention has the following M
have a certain
中性子照射量の大きな、制御棒ウィング先端と制御棒上
端の両方、または、いずれか一方において、他の部分に
比べて酸化ユーロピウム（ＥｕＯ３）の混合比の大きい
酸化ユーロピウムと炭化ホウ素の混合物を装填する。Loading a mixture of europium oxide and boron carbide with a higher mixing ratio of europium oxide (EuO3) than in other parts of the control rod wing tip and/or the control rod upper end, which receive a large amount of neutron irradiation. .
第３図は、酸化ユーロピウム（ＥｕＯ３）と炭化ホウ素
（Ｂ４Ｃ）の混合物の比重を、酸化ユーロピウムの混合
比に対して示したものである。酸化ユーロピウムは、炭
化ホウ素の約三倍の比重をもつ。FIG. 3 shows the specific gravity of a mixture of europium oxide (EuO3) and boron carbide (B4C) with respect to the mixture ratio of europium oxide. Europium oxide has a specific gravity about three times that of boron carbide.
これに対し、第４図は同じく酸化ユーロピウムの混合比
を変えたときの反応度価値を示している。On the other hand, FIG. 4 similarly shows the reactivity value when the mixing ratio of europium oxide is changed.
反応度価値は、酸化ユーロピウムの混合比の増加ととも
に増加する。The reactivity value increases with increasing mixing ratio of europium oxide.
上述のことから、本発明の各要素は次のような働きをも
つ。すなわち、中性子照射量の大きい制御棒ウィング先
端部と制御棒挿入方向先端部に、酸化ユーロピウムの混
合比が大きい中性子吸収棒を配置することにより、制御
棒の反応度価値が大きくなる。また、ユーロピウムは、
（ｎｔ γ）反応により中性子を吸収するので、被覆管
の内圧は上昇せず、機械的な寿命も延びる。一方、中性
子照射量の小さな制御棒ウィングの付け根の近くや、制
御棒挿入方向の下部には、炭化ホウ素の混合比が大きい
中性子吸収棒を配置することにより、−様に酸化ユーロ
ピウムを用いた場合に比べて制御棒の重量が軽くなる。From the above, each element of the present invention has the following functions. That is, by arranging neutron absorption rods with a high mixing ratio of europium oxide at the tip of the control rod wing where the amount of neutron irradiation is large and the tip in the control rod insertion direction, the reactivity value of the control rod is increased. Also, europium is
Since neutrons are absorbed by the (nt γ) reaction, the internal pressure of the cladding tube does not increase and the mechanical life is extended. On the other hand, by arranging neutron absorption rods with a high mixing ratio of boron carbide near the base of the control rod wing where the neutron irradiation dose is small and at the bottom of the control rod insertion direction, it is possible to use europium oxide in a similar manner. The weight of the control rod is lighter compared to .
以下、本発明の実施例を第１図により説明する。 Embodiments of the present invention will be described below with reference to FIG.
第１図は、本発明の原子炉用制御棒の横断面図である。FIG. 1 is a cross-sectional view of a control rod for a nuclear reactor according to the present invention.
中性子吸収棒１１〜１３は十字型に伸びた四本のウィン
グ４のそれぞれに二十−本ずつ配置され、Ｕ字型のシー
ス２にっつんでタイロッド３と結合される。Twenty neutron absorption rods 11 to 13 are arranged on each of the four wings 4 extending in a cross shape, and are connected to the tie rod 3 through the U-shaped sheath 2.
特に、中性子照射量の大きいウィングの先端から三本に
は、酸化ユーロピウムのみを充填した中性子吸収棒を配
置する。続く二本には、酸化ユーロピウムと炭化ホウ素
の５０％ずつを混合した中性子吸収材を充填した中性子
吸収棒を配置し、残りの十六本には炭化ホウ素を充填し
た中性子吸収棒を配置する。中性子吸収材を充填する被
覆管にはハフニウムからなる中空管を使用する。ハフニ
ウムはそれ自体（ｎｔ γ）反応による中性子吸収材で
あり、管内に充填された中性子吸収材への中性子照射量
を低減し、制御棒の長寿命化が図れる。In particular, neutron absorption rods filled only with europium oxide are placed at the top three of the wings, which receive a large amount of neutron irradiation. The next two rods will have neutron absorption rods filled with a neutron absorbing material made of a 50% mix of europium oxide and boron carbide, and the remaining 16 rods will have neutron absorption rods filled with boron carbide. A hollow tube made of hafnium is used as the cladding tube filled with the neutron absorbing material. Hafnium itself is a neutron absorbing material that undergoes a (nt γ) reaction, which reduces the amount of neutron irradiation to the neutron absorbing material filled in the tube and extends the life of the control rod.
上記構成の制御棒では、制御棒ウィング先端部に酸化ユ
ーロピウムを充填した中性子吸収棒を配置したことによ
り制御棒の反応度価値が大きくできるとともに、制御棒
ウィングの付け根側には、炭化ホウ素を充填した中性子
吸収率を配置して、制御棒重量の軽量化が可能となる。In the control rod with the above configuration, the reactivity value of the control rod can be increased by placing a neutron absorption rod filled with europium oxide at the tip of the control rod wing, and the base side of the control rod wing is filled with boron carbide. The weight of the control rod can be reduced by arranging the neutron absorption rate.
本発明の第二の実施例を第５図を用いて説明する。第５
図は１本発明の原子炉用制御棒の縦断面図であり、制御
棒ウィング上端側縁部をとりだして示したものである。A second embodiment of the present invention will be described with reference to FIG. Fifth
FIG. 1 is a longitudinal cross-sectional view of a control rod for a nuclear reactor according to the present invention, and shows the upper edge of the control rod wing.
ウィング先端部から三本には第一の実施例と同様、酸化
ユーロピウム２１が充填された中性子吸収棒を配置して
いる。他の中性子吸収棒には、制御棒上端部に酸化ユー
ロピウムと炭化ホウ素を充填し、下部には炭化ホウ素を
充填している。上部に充填した酸化ユーロピウムと炭化
ホウ素の混合物の高さは、ウィング側縁部ほど長い。As in the first embodiment, neutron absorbing rods filled with europium oxide 21 are arranged at the top three of the wings. Other neutron absorption rods have the upper end of the control rod filled with europium oxide and boron carbide, and the lower end filled with boron carbide. The height of the mixture of europium oxide and boron carbide filled in the upper part is longer towards the wing side edges.
このような構成を用いると、中性子照射量の大きなウィ
ング側縁部、および、制御棒先端部に反応度価値の大き
な酸化ユーロピウムを配置でき、制御棒価値が増大する
。また、炭化ホウ素のように中性子を吸収してもヘリウ
ムガスを発生することがなく機械的な寿命が延長できる
。また、中性子照射量の小さな部分には炭化ホウ素を用
いることにより制御棒の重量を軽量化することができる
。If such a configuration is used, europium oxide, which has a high reactivity value, can be placed on the wing side edges, which receive a large amount of neutron irradiation, and at the tip of the control rod, increasing the value of the control rod. In addition, unlike boron carbide, it does not generate helium gas even if it absorbs neutrons, so its mechanical life can be extended. Furthermore, the weight of the control rod can be reduced by using boron carbide in the portion where the amount of neutron irradiation is small.
制御棒の炉内滞在期間が長期化する際には、制御棒の上
端部はすべて酸化ユーロピウムとすることも可能である
。また、酸化ユーロピウムの下に酸化ユーロピウムと炭
化ホウ素の混合物を充填した三領域以上の構成とするこ
ともできる。When the control rod stays in the reactor for a long time, the upper end of the control rod can be entirely made of europium oxide. It is also possible to have a structure of three or more regions in which a mixture of europium oxide and boron carbide is filled under europium oxide.
本発明によれば、軽量、かつ、長寿命で高価値な原子炉
制御棒を提供することができる。According to the present invention, it is possible to provide a nuclear reactor control rod that is lightweight, has a long life, and is of high value.
第１図は、本発明の一実施例の原子炉用制御棒の横断面
図、第２図は従来の制御棒の横断面図、第３図は酸化ユ
ーロピウムの混合比に対する中性子吸収材の比重の変化
を示す特性図、第４図は酸化ユーロピウム混合比に対す
る反応度価値の特性図、第５図は本発明の他の実施例の
原子炉用制御棒の縦断面図である。
ｌ・・・中性子吸収棒、２・・・シース、３・・・タイ
ロッド、４・・・ウィング、５・・・ハンドル、１１・
・・炭化ホウ素入り中性子吸収棒、１２・・・炭化ホウ
素・酸化ユーロピウム混合物入り中性子吸収棒、１３・
・・酸化ユーロピウム入り中性子吸収棒、２１・・・酸
化ユーロピウム、２２・・・酸化ユーロピウムと炭化ホ
ウ素の第２図
第１図
第
３
図
酸化
ユーロピウム混合
毘（′１０）
第
図
Ｏ
Ｏ０
西麦イヒューロピウムラ昆合
叱
（×）Fig. 1 is a cross-sectional view of a nuclear reactor control rod according to an embodiment of the present invention, Fig. 2 is a cross-sectional view of a conventional control rod, and Fig. 3 is a specific gravity of neutron absorbing material with respect to the mixing ratio of europium oxide. FIG. 4 is a characteristic diagram showing the change in reactivity value with respect to the europium oxide mixing ratio, and FIG. 5 is a longitudinal sectional view of a control rod for a nuclear reactor according to another embodiment of the present invention. l... Neutron absorption rod, 2... Sheath, 3... Tie rod, 4... Wing, 5... Handle, 11...
...Neutron absorption rod containing boron carbide, 12...Neutron absorption rod containing boron carbide/europium oxide mixture, 13.
...Neutron absorption rod containing europium oxide, 21...Europium oxide, 22...Europium oxide and boron carbide Figure 2 Figure 1 Figure 3 Europium oxide mixture ('10) Figure O O0 Nishimagi Heuropiumra Kongo scolding (×)
Claims (1)
複数本束ねた原子炉制御棒において、前記中性子吸収材
として酸化ユーロピウム （ＥｕＯ＿３）と炭化ホウ素（Ｂ＿４Ｃ）とを混合して
用い、かつ、酸化ユーロピウムの混合比がウィングの付
け根から前記ウィングの先端に向けて順次大きくなるよ
うにしたことを特徴とする原子炉用制御棒。 ２、被覆管内に中性子吸収材を充填した中性子吸収棒を
複数本束ねた原子炉制御棒において、前記中性子吸収材
として酸化ユーロピウム （ＥｕＯ＿３）と炭化ホウ素（Ｂ＿４Ｃ）とを混合して
用い、かつ、酸化ユーロピウム混合比が制御棒下端部か
ら上端部に向けて順次大きくなるよう構成したことを特
徴とする原子炉制御棒。 ３、酸化ユーロピウム（ＥｕＯ＿３）と炭化ホウ素（Ｂ
＿４Ｃ）の混合比を、中性子吸収棒の軸方向上部に向け
て、順次、大きくなるように構成したことを特徴とする
中性子吸収棒。[Claims] 1. In a nuclear reactor control rod in which a plurality of neutron absorption rods each having a neutron absorption material filled in a cladding tube are bundled, europium oxide (EuO_3) and boron carbide (B_4C) are mixed as the neutron absorption material. 1. A control rod for a nuclear reactor, characterized in that the mixing ratio of europium oxide gradually increases from the root of the wing to the tip of the wing. 2. In a nuclear reactor control rod in which a plurality of neutron absorption rods each having a neutron absorption material filled in a cladding tube are bundled, a mixture of europium oxide (EuO_3) and boron carbide (B_4C) is used as the neutron absorption material, and A nuclear reactor control rod characterized in that the mixture ratio of europium oxide is configured to increase sequentially from the lower end to the upper end of the control rod. 3. Europium oxide (EuO_3) and boron carbide (B
A neutron absorption rod characterized in that the mixing ratio of _4C) is configured to increase sequentially toward the upper part of the neutron absorption rod in the axial direction.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1199411A JPH0363590A (en) | 1989-08-02 | 1989-08-02 | Control rod for nuclear reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1199411A JPH0363590A (en) | 1989-08-02 | 1989-08-02 | Control rod for nuclear reactor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH0363590A true JPH0363590A (en) | 1991-03-19 |
Family
ID=16407358
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP1199411A Pending JPH0363590A (en) | 1989-08-02 | 1989-08-02 | Control rod for nuclear reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0363590A (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| KR20030067343A (en) * | 2002-02-08 | 2003-08-14 | 웨이테크 디벨롭먼트, 인크. | Method and appartus to obtain a substantially accurate digital color image of a subject in a moveable enclosure which provides a controlled lighting environment |
| JP2011038864A (en) * | 2009-08-10 | 2011-02-24 | Hitachi-Ge Nuclear Energy Ltd | Control rod for boiling water nuclear reactor |
-
1989
- 1989-08-02 JP JP1199411A patent/JPH0363590A/en active Pending
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| KR20030067343A (en) * | 2002-02-08 | 2003-08-14 | 웨이테크 디벨롭먼트, 인크. | Method and appartus to obtain a substantially accurate digital color image of a subject in a moveable enclosure which provides a controlled lighting environment |
| JP2011038864A (en) * | 2009-08-10 | 2011-02-24 | Hitachi-Ge Nuclear Energy Ltd | Control rod for boiling water nuclear reactor |
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