JPS5985994A - Control rod - Google Patents
Control rodInfo
- Publication number
- JPS5985994A JPS5985994A JP57195906A JP19590682A JPS5985994A JP S5985994 A JPS5985994 A JP S5985994A JP 57195906 A JP57195906 A JP 57195906A JP 19590682 A JP19590682 A JP 19590682A JP S5985994 A JPS5985994 A JP S5985994A
- Authority
- JP
- Japan
- Prior art keywords
- control rod
- neutron
- spherical
- sheath
- absorbing material
- 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
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】
〔発明の利用分野〕
本発叩の対象は、軽水原子炉（ＬＷＲ）用、とりわけ沸
騰水型原子炉（ＢＷＲＪ用制御棒に係る。DETAILED DESCRIPTION OF THE INVENTION [Field of Application of the Invention] The object of this blasting is related to control rods for light water reactors (LWRs), particularly boiling water reactors (BWRJs).
従来の毎ｕ＃棒は第１図及び第２図に示すようにシース
内に納められた中性子吸収管内に炭化ボロン（Ｂ４Ｃ）
’ｉ充填し、これにより中性子を吸収し原子炉の出力制
御を行っていた。The conventional u# rod has boron carbide (B4C) inside the neutron absorption tube housed in the sheath as shown in Figures 1 and 2.
'i was used to absorb neutrons and control the reactor's output.
しかしながらこのＢ、Ｃは中性子全吸収するとヘリウム
（Ｈｅ）とリチウム（Ｌｉ）とに変わり中性子吸収能力
が無くなるとともに、Ｂ４Ｃ内に′ｆｃまったＨｅによ
り中性子吸収管の機械的寿命をもたらす。However, when these B and C absorb all neutrons, they change to helium (He) and lithium (Li) and lose their neutron absorption ability, and the He accumulated in B4C shortens the mechanical life of the neutron absorption tube.
本発明による制御棒は、従来制御棒に用いられていｆｃ
Ｂ４Ｃをハフニウム（Ｈｆ）やカドミウム（Ｃｄ）等の
（ｎ、γ）材の中性子吸収材に変えこれらを球状又は球
を中空状に形成することによｆ） ｔｌ）長寿命化を狙
らったものである。The control rod according to the present invention has a fc
By changing B4C to a neutron absorbing material of (n, γ) material such as hafnium (Hf) or cadmium (Cd) and forming these into a spherical shape or a hollow sphere, f) tl) Aiming for longer life. It is something that
本発明の制御棒は外形上は従来のものと同一である。す
なわち第１図に示す。ハンドル（１）、シース（３）等
は従来のものと同じままで艮い。The control rod of the present invention is externally the same as the conventional control rod. That is, as shown in FIG. The handle (1), sheath (3), etc. remain the same as the conventional ones.
但しこのシース内は第３図に示すよ！５な、中性子吸収
能力を付つ金属を球状又は、球状を中空にしたもので満
す。さらにシースに穴をあけ減速材が通るようにすると
中性子吸収能力を一層向上できる。密封した場合の減速
材としては灰累でも良い。However, the inside of this sheath is shown in Figure 3! 5. Filled with spherical or hollow spherical metal with neutron absorption ability. Furthermore, by making a hole in the sheath to allow the moderator to pass through, the neutron absorption capacity can be further improved. Ash accumulation may be used as a moderator when sealed.
中性子吸収能力を持つ材料としては、
（ａ） ハフニウム（Ｈｆ）
（リ カドミウム（Ｃｄ）
（Ｃ） 銀・インジウム・カドミウム（Ａｇ・Ｉｎ・
ｃｄ）
合金等の（ｎｓγ）材金属が適している。Materials with neutron absorption ability include (a) Hafnium (Hf) (Licadmium (Cd) (C) Silver, Indium, Cadmium (Ag, In,
(nsγ) material metals such as cd) alloys are suitable.
これらの材料を球状又は、球状を中空にする目的は、
（ａ） 表面積を太きくし、中性子吸収能力全向上（
ｂ） 中性子減速材（水等）と均一に混合させること
により、中性子吸収能力全向上
（Ｃ） 水による冷却効果増大
等が挙けられる。The purpose of making these materials spherical or hollow spherical is to (a) increase the surface area and improve the neutron absorption capacity (
b) By uniformly mixing it with a neutron moderator (water, etc.), the neutron absorption capacity is completely improved (C) The cooling effect of water is increased, etc.
本発明の実施例を第３図に示す。図中のシース（２）と
タイロッド（３）とで囲まれる領域は中性子吸収能力゛
を有する材料を球状又は球を中空にした中性子吸収材（
１）と減速材（水）とで満たす。An embodiment of the invention is shown in FIG. The area surrounded by the sheath (2) and tie rod (3) in the figure is a neutron absorbing material (made of a spherical or hollow sphere made of a material with neutron absorption capacity).
1) and moderator (water).
このＣｎｓ γ）中性子吸収材が、先のシース（２）と
タイロッド（３）で囲まれる体積中に占る割合と制御棒
反応度相対価値との関％を第４図に示す。本図はＨｆｔ
−用いた例で、−図中の制御棒反応度相対価値は同じ外
形寸法を持つ従来制御棒を基準＝１．０とした時の値で
める。本来雄側では中性子吸収材が占る体積率が約１０
％、以上あれば現行制御棒と同程度の制御棒反応度相対
価値を有することが分る。FIG. 4 shows the relationship between the proportion of this Cns γ) neutron absorbing material in the volume surrounded by the sheath (2) and tie rod (3) and the relative value of control rod reactivity. This figure is Hft
- In the example used, - the relative value of control rod reactivity in the figure is determined by the value when a conventional control rod with the same external dimensions is set as reference = 1.0. Originally, on the male side, the volume ratio occupied by neutron absorbing material is about 10
%, it can be seen that the relative value of control rod reactivity is comparable to that of current control rods.
現行制御棒の反応度価値の９０％までを許容したとする
と、上記の中性子吸収材の体積率は５％以上あれば良い
ことになる。Assuming that up to 90% of the reactivity value of the current control rod is allowed, the volume fraction of the above-mentioned neutron absorbing material should be 5% or more.
１（ｆ等の中性子吸収材は大きな中性子吸収能力を有す
る同位体が存在するためＢ４Ｃのように中性子を一度吸
収しても中性子吸収能力が下らずに持続する。さらにＣ
”ｍ γ）反応材であるためヘリウムも発生しない。こ
のため従来の制御棒より長埒命化が期待できる。Neutron absorbing materials such as 1(f) contain isotopes with large neutron absorption ability, so even if they absorb neutrons once, like B4C, the neutron absorption ability continues without decreasing.Furthermore, C
Since it is a reactive material, it does not generate helium. Therefore, it is expected to have a longer lifespan than conventional control rods.
さらに中性子吸収材の占る体積が小さくても現行の制御
棒と同等以上の制御能力？持たせることがで＠ｏ０
本＠明の中性子吸収材の直径が異なる球又は中空状で構
成することも可能である。Furthermore, even if the volume occupied by the neutron absorbing material is small, will it have the same control capability as the current control rod? It is also possible to configure the neutron absorbing material with spheres or hollow shapes with different diameters.
第１図は従来制御棒例の全体図、第２図は従来制御棒の
説明図、第３図は本発明実施例制御棒の説明図、第４図
は中性子吸収材の占る体積率と制御棒反応度相対価値と
の関係図である。
１・・・中性子吸収材、２・・・シース、３・・・タイ
ロッド。
環１区
＄２図
慄３０
第４図
ｏ ｚｏ ４ｏ ｂｏ ｇｏ
ｔｏ。Figure 1 is an overall view of an example of a conventional control rod, Figure 2 is an explanatory diagram of a conventional control rod, Figure 3 is an explanatory diagram of a control rod according to an embodiment of the present invention, and Figure 4 is an illustration of the volume fraction occupied by the neutron absorbing material. It is a relationship diagram with control rod reactivity relative value. 1... Neutron absorbing material, 2... Sheath, 3... Tie rod. Ring 1 ward $2 zu 30 fig. 4 o zo 4o bo go
to.
Claims (1)
あって、この制御棒を構成するシース、タイロッド等の
構造材で囲まれる領域内全球状又は球で中空の形状をし
た中性子能力の大なる材料にて満たしていることを％徴
とする制御棒。 ２、特許請求の範囲第１項において中性子吸収材の満た
される領域内、又はその近傍に減速材としての軽水ｌた
は炭素等の物質が存在していること全特徴とする制御棒
。[Claims] 1. A control rod inserted into the reactor core in a water nuclear reactor, which is entirely spherical or spherical and hollow within the area surrounded by structural members such as a sheath and tie rods that constitute this control rod. A control rod characterized by being filled with a material with a large neutron capacity in the shape of . 2. A control rod according to claim 1, characterized in that a substance such as light water or carbon exists as a moderator in or near the region filled with the neutron absorber.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP57195906A JPS5985994A (en) | 1982-11-10 | 1982-11-10 | Control rod |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP57195906A JPS5985994A (en) | 1982-11-10 | 1982-11-10 | Control rod |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS5985994A true JPS5985994A (en) | 1984-05-18 |
Family
ID=16348948
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP57195906A Pending JPS5985994A (en) | 1982-11-10 | 1982-11-10 | Control rod |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS5985994A (en) |
-
1982
- 1982-11-10 JP JP57195906A patent/JPS5985994A/en active Pending
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