JPS62228194A - Control rod - Google Patents
Control rodInfo
- Publication number
- JPS62228194A JPS62228194A JP61030878A JP3087886A JPS62228194A JP S62228194 A JPS62228194 A JP S62228194A JP 61030878 A JP61030878 A JP 61030878A JP 3087886 A JP3087886 A JP 3087886A JP S62228194 A JPS62228194 A JP S62228194A
- Authority
- JP
- Japan
- Prior art keywords
- control rod
- region
- neutron
- chain type
- absorbing
- 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
- 239000000446 fuel Substances 0.000 claims description 39
- 239000011358 absorbing material Substances 0.000 claims description 31
- 230000004323 axial length Effects 0.000 claims description 19
- 229910052735 hafnium Inorganic materials 0.000 claims description 8
- 239000006096 absorbing agent Substances 0.000 description 25
- 238000010521 absorption reaction Methods 0.000 description 24
- 239000007788 liquid Substances 0.000 description 11
- 125000006850 spacer group Chemical group 0.000 description 7
- 229910052580 B4C Inorganic materials 0.000 description 5
- VBJZVLUMGGDVMO-UHFFFAOYSA-N hafnium atom Chemical compound [Hf] VBJZVLUMGGDVMO-UHFFFAOYSA-N 0.000 description 5
- 238000009835 boiling Methods 0.000 description 4
- 238000010586 diagram Methods 0.000 description 4
- 230000000694 effects Effects 0.000 description 4
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 4
- 230000007423 decrease Effects 0.000 description 3
- 239000007789 gas Substances 0.000 description 3
- 230000037431 insertion Effects 0.000 description 3
- 238000003780 insertion Methods 0.000 description 3
- 230000009257 reactivity Effects 0.000 description 3
- 238000003466 welding Methods 0.000 description 3
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 description 2
- 230000000712 assembly Effects 0.000 description 2
- 238000000429 assembly Methods 0.000 description 2
- 229910052796 boron Inorganic materials 0.000 description 2
- INAHAJYZKVIDIZ-UHFFFAOYSA-N boron carbide Chemical compound B12B3B4C32B41 INAHAJYZKVIDIZ-UHFFFAOYSA-N 0.000 description 2
- 239000000126 substance Substances 0.000 description 2
- 229910052693 Europium Inorganic materials 0.000 description 1
- 230000002411 adverse Effects 0.000 description 1
- 238000005253 cladding Methods 0.000 description 1
- 239000000498 cooling water Substances 0.000 description 1
- OGPBJKLSAFTDLK-UHFFFAOYSA-N europium atom Chemical compound [Eu] OGPBJKLSAFTDLK-UHFFFAOYSA-N 0.000 description 1
- RSEIMSPAXMNYFJ-UHFFFAOYSA-N europium(III) oxide Inorganic materials O=[Eu]O[Eu]=O RSEIMSPAXMNYFJ-UHFFFAOYSA-N 0.000 description 1
- 230000004907 flux Effects 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
- 210000003127 knee Anatomy 0.000 description 1
- 230000001151 other effect Effects 0.000 description 1
- 239000008188 pellet Substances 0.000 description 1
- 239000002574 poison Substances 0.000 description 1
- 231100000614 poison Toxicity 0.000 description 1
- 239000000843 powder Substances 0.000 description 1
- 239000007787 solid Substances 0.000 description 1
- 229910001220 stainless steel Inorganic materials 0.000 description 1
- 239000010935 stainless steel Substances 0.000 description 1
- 230000008961 swelling Effects 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
- Valve Device For Special Equipments (AREA)
- Crystals, And After-Treatments Of Crystals (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、制御棒に係り、特に寿命の長い制御棒に関す
る。DETAILED DESCRIPTION OF THE INVENTION [Field of Industrial Application] The present invention relates to a control rod, and particularly to a control rod with a long life.
［従来の技術］
従来の長寿命型の制御棒は、例えば特開昭５３−７４６
９７号公報に示されるように、制御棒の中でも中性子照
射量の多い上端部あるいはブレードの翼端部に核的・機
械的寿命の長い長寿命型中性子吸収棒を配置したものが
知られている。この制御棒の構成を第１１図に示す。従
来の制御棒は。[Prior Art] A conventional long-life control rod is disclosed in Japanese Patent Application Laid-open No. 53-746, for example.
As shown in Publication No. 97, there are known control rods in which a long-life neutron absorption rod with a long nuclear and mechanical life is placed at the upper end, where the amount of neutron irradiation is high, or at the tip of the blade. . The configuration of this control rod is shown in FIG. Conventional control rod.
ブレードの上端部及び翼端部にハフニウム（Ｈｆ）ある
いはユーロピウム（Ｅｕ）等の長寿命型中性子吸収材６
１を配置し、それ以外の部分にはステンレス鋼製の細長
い被覆管中にボロンカーバイト（８４Ｃ）粉末を充填し
たポイズン管６２を配している。Long-life neutron absorbing material 6 such as hafnium (Hf) or europium (Eu) is used at the upper end of the blade and at the wing tip.
1, and a poison tube 62 in which boron carbide (84C) powder is filled in an elongated cladding tube made of stainless steel is placed in the other part.
［発明が解決しようとする問題点コ
上記従来技術では、長寿命型中性子吸収材が制御棒の一
部にしか用いられておらず、中性子吸収材として長寿命
型中性子吸収材のみを用いた制御棒に比べて寿命が短い
という問題がある。[Problems to be solved by the invention] In the above conventional technology, long-life neutron absorbers are used only in a part of the control rods, and control using only long-life neutron absorbers as neutron absorbers is difficult. The problem is that they have a shorter lifespan than sticks.
この問題を解決するために、制御棒の中性子吸収材をす
べてハフニウム等の長寿命型中性子吸収材にて置替える
ことが考えられる。しかしながら、長寿命型中性子吸収
材は、従来一般に用いられている８４Ｃよりも重く、中
性子吸収材として長寿命型中性子吸収材のみを用いた制
御棒を構成した場合には制御棒の重量が著しく増加し、
制御棒駆動装置による制御棒操作に支障が生じる可能性
がある。In order to solve this problem, it is possible to replace all the neutron absorbing materials in the control rods with long-life neutron absorbing materials such as hafnium. However, long-life neutron absorbers are heavier than the conventionally used 84C, and when a control rod is constructed using only long-life neutron absorbers as the neutron absorber, the weight of the control rod increases significantly. death,
Control rod operation by the control rod drive device may be hindered.
本発明の目的は、寿命が長くてしかも操作性の良い制御
棒を提供することにある。An object of the present invention is to provide a control rod that has a long life and is easy to operate.
［問題点を解決するための手段］
上記目的は、吸収液連鎖型中性子吸収材を燃料集合体の
燃料有効長の１７／２４〜２２／２４の長さにわたって
配置することによって達成できる。[Means for Solving the Problems] The above object can be achieved by arranging the absorbing liquid chain type neutron absorbing material over a length of 17/24 to 22/24 of the effective fuel length of the fuel assembly.
二こで、吸収液連鎖型中性子吸収材とは、中性子吸収反
応により生成される核種あるいはその壊変核種の中にさ
らに中性子を吸収する核種があられれて、中性子吸収効
果の減衰が遅い中性子吸収材を意味する。具体的な物質
としてはＨｆ。2. An absorbing liquid chain type neutron absorbing material is a neutron absorbing material in which neutron absorbing nuclides are added to the nuclides generated by the neutron absorption reaction or their decay nuclides, and the neutron absorption effect decays slowly. means. A specific substance is Hf.
Ｅｕ２ｏ、、Ｔａ−Ｄｙ２０１、及びＡ ｇ −Ｉ ｎ
−Ｃｄ等がある。Eu2o, , Ta-Dy201, and A g -I n
-Cd etc.
［作用コ
吸収液連鎖型中性子吸収材を燃料有効長の１７／２４〜
２２／２４の長さにわたって配置することによる制御棒
重量の軽減と吸収液連鎖型中性子吸収材の使用とにより
、重連の目的を達成できる。[Action absorbing liquid chain type neutron absorbing material from 17/24 of the effective fuel length
By reducing the weight of the control rods by arranging them over a length of 22/24 and by using an absorbing liquid chain type neutron absorber, the purpose of multiplexing can be achieved.
［実施例］
本発明は、以下に示す発明者等による新たな知見に基づ
いてなされたものである。その内容を以下に述べる。[Example] The present invention was made based on new findings by the inventors as shown below. The contents are described below.
中性子吸収材として吸収液連鎖型中性子吸収材のみを中
性子吸収材として用いた長寿命型制御棒における吸収核
連鎖型中性子吸収材領域の軸方向長さと炉停止余裕との
関係を検討した結果、第４図に示す関係を得た。これは
、長寿命型制御棒を多数の燃料集合体を装荷した原子炉
の炉心内に挿入した場合の特性である。横軸は、燃料集
合体の燃料有効長に対する割合である。中性子吸収材と
して長寿命型中性子吸収材のみを用いた場合は、吸収核
連鎖型中性子吸収材領域の軸方向の長さＬａを燃料集合
体の燃料有効長（燃料ペレットが充填されている領域の
軸方向の長さ）の１７／２４より短かくすると炉停止余
裕が減少する。従って、長寿命型制御棒の吸収核連鎖型
中性子吸収領域の軸方向長さＬａは、燃料集合体の燃料
有効長の１７／２４以上にする必要がある。第４図の特
性は、長寿命型中性子吸収材としてＨｆを用いた場合の
特性である。Ｅｕ２Ｏ３，Ｔａ、Ｄ Ｖ ２０． 、
Ａｇ−Ｉ ｎ−Ｃｄ等の吸収液連鎖型中性子吸収材を用
いた場合にも同様な特性が得られる。As a result of examining the relationship between the axial length of the absorbing core chain type neutron absorber region and the reactor shutdown margin in a long-life control rod using only the absorbing liquid chain type neutron absorber as the neutron absorbing material, the following results were obtained. The relationship shown in Figure 4 was obtained. This is a characteristic when long-life control rods are inserted into the core of a nuclear reactor loaded with a large number of fuel assemblies. The horizontal axis is the ratio of the fuel assembly to the effective fuel length. When only a long-life neutron absorber is used as the neutron absorber, the axial length La of the absorbing nuclear chain type neutron absorber region is defined as the effective fuel length of the fuel assembly (the area filled with fuel pellets). If it is made shorter than 17/24 of the axial length (length in the axial direction), the reactor shutdown margin will decrease. Therefore, the axial length La of the absorbing nuclear chain type neutron absorption region of the long-life control rod needs to be 17/24 or more of the effective fuel length of the fuel assembly. The characteristics shown in FIG. 4 are the characteristics when Hf is used as a long-life neutron absorber. Eu2O3, Ta, D V 20. ,
Similar characteristics can be obtained when using an absorbing liquid chain type neutron absorbing material such as Ag-I n-Cd.
また、長寿命型中性子吸収材を燃料集合体の燃料有効長
全体にわたって配置した長寿命型の制御棒を多数の燃料
集合体が装荷された原子炉の炉心内に挿入した場合にお
ける制御棒挿入量と炉心反応度との関係を第５図に示す
。横軸の制御棒挿入量は、燃料集合体の燃料有効長に対
する割合を示している。この長寿命型制御棒を燃料集合
体の燃料有効長の２２／２４よりも多く炉心内に挿入し
ても炉心反応度の変化は著しく小さくなり、燃料有効長
の２２／２４よりも長い部分に存在する吸収液連鎖型中
性子吸収材の中性子吸収能力を有効に活用しているとは
言えない。従って、その中性子吸収能力を有効に利用す
るためには、長寿命型制御棒において吸収液連鎖型中性
子吸収材を配置している領域の軸方向の長さは、燃料集
合体の燃料有効長の２２／２４よりも長くする必要はな
く、その燃料有効長の２２／２４以下でよい。これによ
って、長寿命型制御棒の重量を、燃料有効長全体にわた
って吸収液連鎖型中性子吸収材を配置した場合に比べて
軽減できる。第５図も、吸収液連鎖型中性子吸収材とし
てＨｆを用いたものであるが、Ｅｕ２Ｏ，、Ｔａ、Ｄｙ
２０．、Ａｇ−１ｎ−Ｃｄ等の他の吸収液連鎖型中性子
吸収材を用いても同じ特性が得られる。In addition, the amount of control rod insertion when a long-life control rod with long-life neutron absorbing material arranged over the entire effective fuel length of the fuel assembly is inserted into the core of a reactor loaded with a large number of fuel assemblies. Figure 5 shows the relationship between and core reactivity. The control rod insertion amount on the horizontal axis indicates the ratio to the effective fuel length of the fuel assembly. Even if these long-life control rods are inserted into the reactor core for more than 22/24 of the effective fuel length of the fuel assembly, the change in core reactivity will be significantly small; It cannot be said that the neutron absorption capacity of the existing absorbing liquid chain type neutron absorbing material is effectively utilized. Therefore, in order to effectively utilize the neutron absorption capacity, the axial length of the region in which the absorbing liquid chain type neutron absorber is arranged in the long-life control rod must be equal to the effective fuel length of the fuel assembly. It does not need to be longer than 22/24, and may be 22/24 or less of the fuel effective length. As a result, the weight of the long-life control rod can be reduced compared to the case where the absorbing liquid chain type neutron absorber is arranged over the entire effective length of the fuel. Figure 5 also uses Hf as the absorbing liquid chain type neutron absorbing material, but Eu2O, Ta, Dy
20. The same characteristics can be obtained using other absorbing liquid chain type neutron absorbing materials such as , Ag-1n-Cd, etc.
以上述べた検討結果により、長寿命型制御棒の吸収核連
鎖型中性子吸収材領域の軸方向長さＬａは、燃料集合体
の燃料有効長の１７／２４〜２２／２４にすることが望
しいことがわかった。Based on the above study results, it is desirable that the axial length La of the absorbing nuclear chain type neutron absorber region of the long-life control rod be 17/24 to 22/24 of the effective fuel length of the fuel assembly. I understand.
沸騰水型原子炉の炉心に挿入される本発明の好適な一実
施例である制御棒を第１図〜第３図に基づいて説明する
。DESCRIPTION OF THE PREFERRED EMBODIMENTS A control rod according to a preferred embodiment of the present invention, which is inserted into the core of a boiling water reactor, will be described with reference to FIGS. 1 to 3.
制御棒１０は、横断面が十字形をしており、中心部のタ
イロッド１４を中心に四方に延びた４つのブレード１１
を有している。第１図は、１つのブレード１１の縦断面
を示している。ブレード１１は、タイロッド１４に両端
部が取付けられるＵ字状のシース（ＳＵＳ製）１２及び
シース１２内に設けられた多数の中性子吸収棒１３から
構成される。中性子吸収棒１３は、第２図に示すように
シース１２内に配置され、しかもタイロッド１４に取付
けられたＳＵＳ製の保持部１５Ａ及び１５Ｂの間に配置
されて保持されている。制御棒１０の上端部に位置する
保持部１５Ａの上面に。The control rod 10 has a cross-shaped cross section, and has four blades 11 extending in all directions around a tie rod 14 at the center.
have. FIG. 1 shows a longitudinal section of one blade 11. FIG. The blade 11 is composed of a U-shaped sheath (made of SUS) 12 whose both ends are attached to tie rods 14, and a large number of neutron absorption rods 13 provided within the sheath 12. The neutron absorption rod 13 is disposed within the sheath 12 as shown in FIG. 2, and is further disposed and held between SUS holding parts 15A and 15B attached to the tie rod 14. On the upper surface of the holding part 15A located at the upper end of the control rod 10.
ハンドル２１が取付けられる。中性子吸収棒１３は、Ｈ
ｆの丸棒にて構成される。タイロッド１４の下端は、ベ
ロシティリミッタ１６に取付けられる。A handle 21 is attached. The neutron absorption rod 13 is H
It is composed of a round bar of f. The lower end of the tie rod 14 is attached to a velocity limiter 16.
シース１２の上端は保持部１５Ａに、シース１２の下端
はベロシティリミッタ１６に点溶接にて取付けられる。The upper end of the sheath 12 is attached to the holding portion 15A, and the lower end of the sheath 12 is attached to the velocity limiter 16 by spot welding.
また、シースＩ２は、保持部１５Ｂを被っておりこの保
持部１５Ｂにも点溶接にて取付けられる。保持部１５Ｂ
とベロシティリミッタ１６との間くは、中性子吸収材が
配置されていなく、第３図に示すようにシース１２によ
り囲まれた中空部１７が形成される。Further, the sheath I2 covers the holding part 15B and is also attached to this holding part 15B by spot welding. Holding part 15B
No neutron absorbing material is disposed between the sheath 12 and the velocity limiter 16, and a hollow portion 17 surrounded by the sheath 12 is formed as shown in FIG.
制御棒１０は、その軸方向に吸収核連鎖型中性子吸収材
であるＨｆの丸棒を配置した吸収核連鎖型中性子吸収材
領域１８と、その下方に位置する中性子吸収材が配置さ
れていない領域１９とを有している。吸収核連鎖増中性
子吸収材領域１８の軸方向長さＬａは、燃料集合体の燃
料有効長の１８／２４である。領域１９は、中空部１７
を含む保持部１５Ｂの上面からベロシティリミッタ１６
の上面までの領域である。吸収核連鎖型中性子吸収材領
域１８の軸方向長さＬａと領域１９の軸方向長さＬｂと
を併せた軸方向長さが、従来の制御棒の中性子吸収材充
填領域の軸方向長さに等しく、燃料集合体の燃料有効長
に実質的に等しい。The control rod 10 has an absorbing chain neutron absorber region 18 in which round rods of Hf, which are absorbing chain neutron absorbers, are arranged in the axial direction, and a region located below the region where no neutron absorber is arranged. It has 19. The axial length La of the absorbing nuclear chain multiplier neutron absorber region 18 is 18/24 of the fuel effective length of the fuel assembly. The region 19 is the hollow part 17
Velocity limiter 16 from the top surface of holding part 15B including
This is the area up to the top surface of. The axial length, which is the sum of the axial length La of the absorbing nuclear chain type neutron absorber region 18 and the axial length Lb of the region 19, is equal to the axial length of the neutron absorber filling region of the conventional control rod. equal and substantially equal to the fuel effective length of the fuel assembly.
吸収核連鎖型中性子吸収材領域１８は、中性子吸収材が
配置されていない領域１９よりも制御棒１０の先端側に
位置している。The absorbing nuclear chain type neutron absorbing material region 18 is located closer to the tip of the control rod 10 than the region 19 where no neutron absorbing material is arranged.
シース１２には多数の孔が設けられており、制御棒１０
を原子炉内に設置した時、それらの孔を通して吸収核連
鎖型中性子吸収材領域１８及び中空部１７内に原子炉内
の冷却水が流出入する。The sheath 12 is provided with a large number of holes, and the control rod 10
When installed in a nuclear reactor, cooling water in the reactor flows into and out of the absorption chain type neutron absorbing material region 18 and hollow portion 17 through these holes.
このような本実施例によれば、Ｈｆの密度が１３．３ｇ
／ｃｎ？と８４Ｇの密度２．２ｇ／ａｌよりも著しく大
きいが、Ｈｆ充填域の軸方向長さが燃料有効長の１８／
２４と短かくなっているので、制御棒１０の重量を燃料
有効長全体にハフニウムを配置した場合に比べて軽減で
きる。従って、制御棒１０に対する制御棒駆動装置によ
る良好な操作性が得られる。また、本実施例によれば、
炉停止余裕を満足させることもできる。Ｈｆを用いて中
性子を吸収しているので、ガスが発生しなく中性子吸収
棒１３の機械的寿命が増大し、しかも中性子吸収の核的
寿命も増大する。従来の制御棒のように軸方向の大部分
の領域にＢ４Ｃを配置した場合は、８４Ｃの中性子吸収
によってヘリウムガスが発生するのでＢ４Ｃのスウェリ
ングの助長及びガス圧により中性子吸収棒の機械的寿命
の低下、及び８４Ｃが中性子吸収により中性子を吸収し
ない物質に変わるので核的寿命の低下を招き易い。According to this embodiment, the density of Hf is 13.3 g.
/cn? This is significantly larger than the density of 84G, which is 2.2 g/al, but the axial length of the Hf filling region is 18/1 of the effective fuel length.
24, the weight of the control rod 10 can be reduced compared to when hafnium is arranged over the entire effective fuel length. Therefore, good operability of the control rod 10 by the control rod drive device can be obtained. Furthermore, according to this embodiment,
It is also possible to satisfy the furnace shutdown margin. Since neutrons are absorbed using Hf, no gas is generated and the mechanical life of the neutron absorption rod 13 is increased, and the nuclear life of neutron absorption is also increased. When B4C is placed in most of the axial region like in conventional control rods, helium gas is generated by neutron absorption of 84C, which promotes swelling of B4C and reduces the mechanical life of the neutron absorption rod due to gas pressure. As 84C changes into a substance that does not absorb neutrons due to neutron absorption, the nuclear lifetime tends to decrease.
上記実施例の制御棒１０を適用した沸騰水型原子炉の炉
心の一例を以下に説明する。An example of a core of a boiling water reactor to which the control rod 10 of the above embodiment is applied will be described below.
沸騰水型原子炉の炉心としては、特公昭５７−７３９７
号公報の第３図に示す炉心が考えられている。上記公報
の第３図の炉心構造は、上記公報４カラム、５行〜６男
ラム、下から１１行に述べられた構成になっている。上
記公報の第３図の炉心構造は、原子炉運転中に炉心内に
挿入されて原子炉出力の調節を行う出力調節用制御棒と
、原子炉運転中に炉心から完全に引抜かれて原子炉停止
時に炉心に急速に完全挿入される原子炉停止用制御棒を
有している。出力調節用制御棒も、原子炉停止時に炉心
内に完全に挿入される。出力調節用制御棒及び原子炉停
止用制御棒は、上記公報の第３図に示すように交互に１
つずつ配置され、しかもチェッカボード状に配置されて
いる。As the core of the boiling water reactor,
The reactor core shown in Figure 3 of the publication is being considered. The core structure shown in FIG. 3 of the above publication has the configuration described in column 4, lines 5 to 6, row 11 from the bottom of the publication. The reactor core structure shown in Figure 3 of the above publication consists of power adjustment control rods that are inserted into the reactor core during reactor operation to adjust the reactor output, and power adjustment control rods that are completely pulled out from the reactor core during reactor operation. It has reactor shutdown control rods that are quickly and completely inserted into the reactor core during shutdown. The power adjustment control rods are also fully inserted into the reactor core when the reactor is shut down. The power adjustment control rods and the reactor shutdown control rods are arranged alternately as shown in Figure 3 of the above publication.
They are arranged in a checkerboard pattern.
出力調節用制御棒は、原子炉運転中にほとんど炉心内に
挿入され、中性子が連続的に照射される。The power adjustment control rods are inserted into the reactor core most of the time during reactor operation, and are continuously irradiated with neutrons.
従って、前述した第１図に示す実施例の制御棒１０を、
出力調節用制御棒として用いることが望しい。出力調節
用として用いられた制御棒１０は。Therefore, the control rod 10 of the embodiment shown in FIG.
It is desirable to use it as a control rod for output adjustment. The control rod 10 was used for output adjustment.
原子炉の運転中の出力制御において吸収核連鎖型中性子
吸収材領域１８の軸方向長さＬａ、よりも深く炉心内に
挿入されることはない。しかし原子炉停止時には、領域
１８及び１９が炉心内に挿入される。原子炉停止用制御
棒は、原子炉運転中に炉心から完全に引抜かれているの
で中性子を吸収する割合が少ない。従って、原子炉停止
用制御棒としては、特開昭５７−２５０８０号公報の２
カラム、３〜９行に示す制御棒を用いる。この制御棒は
、十字形のブレード内に８４Ｃを充填した多数の中性子
吸収棒を配置したものであり、吸収核連鎖型中性子吸収
材を有していない。このＢ４Ｃを充填した中性子吸収棒
の軸方向長さは、燃料集合体の燃料有効長と実質的に同
じである。両者の制御棒を操作する制御棒駆動装置の構
造は、同じものである。沸騰水型原子炉の場合、制御棒
駆動装置は、炉心を内蔵する原子炉容器の下部に設置さ
れる。During power control during operation of the nuclear reactor, the absorbing chain type neutron absorbing material region 18 is never inserted deeper into the reactor core than the axial length La of the absorbing chain type neutron absorbing material region 18. However, during reactor shutdown, regions 18 and 19 are inserted into the reactor core. Since the reactor shutdown control rods are completely withdrawn from the reactor core during reactor operation, they absorb only a small percentage of neutrons. Therefore, as a control rod for reactor shutdown, 2 of JP-A No. 57-25080
The control rods shown in columns 3-9 are used. This control rod has a large number of neutron absorbing rods filled with 84C arranged in a cross-shaped blade, and does not have an absorbing nuclear chain type neutron absorbing material. The axial length of the neutron absorption rod filled with B4C is substantially the same as the effective fuel length of the fuel assembly. The structure of the control rod drive device that operates both control rods is the same. In the case of a boiling water reactor, the control rod drive device is installed at the bottom of the reactor vessel containing the reactor core.
制御棒１０の中性子吸収棒１３は、丸棒であるが角棒で
あってもよく、さらには板状にしてもよい。ただし、板
状にした場合には、地震時における炉心内への制御棒の
挿入性が悪くなる。Although the neutron absorption rod 13 of the control rod 10 is a round rod, it may be a square rod or even a plate shape. However, if it is made into a plate shape, it will be difficult to insert the control rod into the reactor core during an earthquake.
本発明の他の実施例の制御棒を第６図及び第７図により
説明する。本実施例の制御棒２５は、制御棒１０の構造
とほとんど同じである。領域１８の軸方向長さＬＬは、
制御棒１０のり、と同じ長さである。異なっている点は
、吸収核連鎖型中性子吸収材領域１８内に、ＳＵＳから
なるスペーサ２６を配置した部分である。制御棒１０の
半径方向における熱中性子束分布は、ブレード１１の中
央部で最も小さいので、中性子の吸収率が最も少なくな
る。従って、制御棒２５は、制御棒１０のブレード１１
内にその翼端に向って配置されたブレード１１中央部の
中性子吸収棒１３（ハフニウム捧）を取除き１代りにス
ペーサ２６を配置したものである。スペーサ２６は、ブ
レード１１内で中性子吸収棒１３の相互に間隙が生じな
いように中性子吸収棒１３を保持している。スペーサ２
６は、軸方向の中央部に中実部が設けられて軸方向の両
端部に中空管部が設けられており、軸方向長さが中性子
吸収棒１３の長さと同じである。本実施例は、ハフニウ
ムが少なくなっているので、制御棒の重量が制御棒１０
よりもさらに低減できる。A control rod according to another embodiment of the present invention will be explained with reference to FIGS. 6 and 7. The control rod 25 of this embodiment has almost the same structure as the control rod 10. The axial length LL of the region 18 is
It is the same length as the control rod 10. The difference is that a spacer 26 made of SUS is arranged within the absorbing nuclear chain type neutron absorbing material region 18. Since the thermal neutron flux distribution in the radial direction of the control rod 10 is smallest at the center of the blade 11, the neutron absorption rate is the smallest. Therefore, the control rod 25 has a blade 11 of the control rod 10.
The neutron absorbing rod 13 (hafnium rod) in the center of the blade 11, which is placed toward the tip of the blade, is removed and a spacer 26 is placed in its place. The spacer 26 holds the neutron absorption rods 13 so that no gaps are formed between the neutron absorption rods 13 within the blade 11. Spacer 2
6 is provided with a solid part at the center in the axial direction and hollow tube parts at both ends in the axial direction, and the length in the axial direction is the same as the length of the neutron absorption rod 13. In this example, since hafnium is reduced, the weight of the control rod is 10
can be further reduced.
他の効果は制御棒１０と同じである。領域１９には、制
御棒１０と同様に中空部１７が形成されている。Other effects are the same as control rod 10. A hollow portion 17 is formed in the region 19 similarly to the control rod 10 .
制御棒２５のブレード１１中央部のスペーサ２６の幅を
狭くしてタイロッド１４に隣接させてその狭くした分の
スペーサ（ＳＵＳ製）２６Ａを配置してもよい。この実
施例が第８図に示す制御棒２７である。本実施例は、タ
イロッド１４に隣接してスペーサ２６Ａを設けているの
で、炉心からの制御棒２７の引抜き操作を行っても、制
御棒２７と対向する燃料集合体のコーナ部に位置する燃
料棒に与えるダメージは小さくなる。制御棒２７は、制
御棒２５と同じ効果も奏する。The width of the spacer 26 at the center of the blade 11 of the control rod 25 may be narrowed, and a spacer 26A (made of SUS) corresponding to the narrowed width may be placed adjacent to the tie rod 14. This embodiment is a control rod 27 shown in FIG. In this embodiment, since the spacer 26A is provided adjacent to the tie rod 14, even if the control rod 27 is withdrawn from the reactor core, the fuel rod located at the corner of the fuel assembly facing the control rod 27 will be removed. The damage dealt will be smaller. The control rod 27 also has the same effect as the control rod 25.
本発明の他の実施例である制御棒３０を第９図に示す。A control rod 30 according to another embodiment of the present invention is shown in FIG.
制御棒３０は、制御棒１０の領域１９の構造を変えたも
のであり、吸収核連鎖型中性子吸収材領域１８の構造は
制御棒１０と同一である。The control rod 30 is obtained by changing the structure of the region 19 of the control rod 10, and the structure of the absorbing nuclear chain type neutron absorbing material region 18 is the same as that of the control rod 10.
制御棒３０の吸収核連鎖型中性子吸収材領域１８の下方
に配置された領域１９Ａは、領域１９と同様にシース１
２にて取囲まれた中空部１７を有している。この領域１
９Ａの中空部１７内に、少数本の中性子吸収棒３１が等
間隔にて配置される。Similar to the region 19, the region 19A disposed below the absorbing nuclear chain type neutron absorber region 18 of the control rod 30 is connected to the sheath 1.
It has a hollow part 17 surrounded by 2. This area 1
A small number of neutron absorption rods 31 are arranged at equal intervals in the hollow part 17 of 9A.
中性子吸収棒３１は、中性子吸収材として吸収核連鎖型
中性子吸収材、Ｂ４Ｃ、ボロン入りのＳ Ｕ Ｓ及びボ
ロン入りのＡＱのうちの１つを用いている。吸収核連鎖
型中性子吸収材領域１８の軸方向長さＬａ及び領域１９
Ａの軸方向長さＬｂは、制御棒１０のそれらに等しい。The neutron absorbing rod 31 uses one of an absorbing nuclear chain type neutron absorbing material, B4C, SUS containing boron, and AQ containing boron as a neutron absorbing material. Axial length La of the absorbing nuclear chain type neutron absorbing material region 18 and region 19
The axial length Lb of A is equal to that of the control rod 10.
領域１９Ａは、原子炉の運転中に炉心から引抜かれてい
るので、原子炉運転中に中性子を吸収することはない。Since the region 19A is extracted from the core during operation of the nuclear reactor, it does not absorb neutrons during operation of the reactor.
従ってこの領域に８４Ｇを充填した短かい中性子吸収棒
を配置しても、制御棒の寿命に悪影響を与えることはな
い。領域１９Ａは、原子炉停止時に炉心内に挿入される
。本実施例は、前述した各実施例に比べて重くなるので
、制御棒の操作性が若干悪くなる。Therefore, even if a short neutron absorption rod filled with 84G is placed in this region, the life of the control rod will not be adversely affected. Region 19A is inserted into the reactor core when the reactor is shut down. Since this embodiment is heavier than the aforementioned embodiments, the operability of the control rod is slightly worse.
本発明の他の実施例である制御棒３５を第１０図に示す
。制御棒３５は、領域１９Ｂを除いて制御棒１０の構成
と同一である。領域１９Ｂは、吸収核連鎖型中性子吸収
材領域１８の下方に配置され、制御棒１０の領域１９の
形状を下方に向って狭くなる形状に変更したものである
。領域１９Ｂも、領域１９と同様にシース１２にて取囲
まれた中空部を有している。この中空部の横断面は下方
に向って減少している。制御棒３５は、制御棒１０と同
様な効果が得られ、さらに領域１９Ａの縦断面形状が減
少するので重量が軽減されて制御棒の操作性が向上する
。A control rod 35 according to another embodiment of the present invention is shown in FIG. Control rod 35 is identical in configuration to control rod 10 except for region 19B. The region 19B is disposed below the absorbing nuclear chain type neutron absorber region 18, and is obtained by changing the shape of the region 19 of the control rod 10 to a shape that becomes narrower toward the bottom. Similarly to the region 19, the region 19B also has a hollow portion surrounded by the sheath 12. The cross section of this hollow part decreases downwards. The control rod 35 provides the same effects as the control rod 10, and furthermore, since the longitudinal cross-sectional shape of the region 19A is reduced, the weight is reduced and the control rod's operability is improved.
シース１２の下端を支持部１５Ｂに点溶接にて取付け、
制御棒１０の領域１９のシース１２を取除いてもよい。Attach the lower end of the sheath 12 to the support part 15B by spot welding,
The sheath 12 in the region 19 of the control rod 10 may be removed.
この場合、支持部１５Ｂより下方のタイロッド１４の部
分を強度上から翼端に向って太くする必要がある。In this case, the portion of the tie rod 14 below the support portion 15B needs to be made thicker toward the wing tip for strength reasons.
［発明の効果］
もに、寿命が長くて操作生の良好な制御棒を得ることが
できる。[Effects of the Invention] In addition, a control rod with a long life and good operability can be obtained.
第１図は本発明の好適な一実施例である制御棒の縦断面
図、第２図は第１図の■−■断面図、第３図は第１図の
■−■断面図、第４図は吸収核連鎖型中性子吸収材領域
の軸方向長さと炉停止余裕との関係を示す特性図、第５
図は制御棒挿入量と炉心反応度との関係を示す特性図、
第６図、第８図〜第１Ｏ図は本発明の他の実施例である
制御棒の構造図、第７図は第６図の■−■断面図、第１
１図は従来の制御棒の構造図である。
１０．２５．３０．３５・・・制御棒、１１・・・ブレ
ード、１２・・・シース、１３・・・中性子吸収棒（Ｈ
ｆ捧）、１４・・・タイロッド、１７・・・中空部、１
８・・・第 ４ 図
ｒＪＩＬ収刹もｆ１襲型中・１呟←表ＭｔＢ４東−（の
中１古Ａ句め長ざ
第 ｒｒｆＥＪ
嬶制御膝神へｉ （金坤入）第 ７０霞FIG. 1 is a vertical cross-sectional view of a control rod according to a preferred embodiment of the present invention, FIG. 2 is a cross-sectional view along the line ■--■ in FIG. 1, and FIG. Figure 4 is a characteristic diagram showing the relationship between the axial length of the absorbing nuclear chain type neutron absorber region and the reactor shutdown margin.
The figure is a characteristic diagram showing the relationship between control rod insertion amount and core reactivity.
6 and 8 to 1O are structural diagrams of control rods according to other embodiments of the present invention, and FIG. 7 is a sectional view taken along the line ■-■ of FIG.
Figure 1 is a structural diagram of a conventional control rod. 10.25.30.35... Control rod, 11... Blade, 12... Sheath, 13... Neutron absorption rod (H
f), 14... Tie rod, 17... Hollow part, 1
8... 4th figure r JIL settlement also f1 attack type middle 1 tweet ← Table MtB4 East - (1st year old A phrase long rrfEJ control knee god i (Kinkon entry) 70th haze
Claims (1)
、前記吸収核連鎖型中性子吸収材が配置される領域の軸
方向の長さを、燃料集合体の燃料有効長の１７／２４〜
２２／２４の範囲にしたことを特徴とする制御棒。 ２、前記吸収核連鎖型中性子吸収材が、Ｈｆ、Ｔａ、Ｅ
ｕ＿２Ｏ＿３、Ｄｙ＿２Ｏ＿３またはＡｇ−Ｉｎ−Ｃｄ
である特許請求の範囲第１項記載の制御棒。 ３、炉心内に挿入されしかも実質的に燃料集合体の燃料
有効長に対応する領域が第１領域と第２領域とに分割さ
れ、前記第２領域よりも制御棒先端側に位置する前記第
１領域に吸収核連鎖型中性子吸収材が配置され、前記第
２領域に中性子吸収材が配置され、前記第１領域の軸方
向長さが前記燃料有効長の１７／２４〜２２／２４であ
る制御棒。 ４、前記吸収核連鎖型中性子吸収材が、Ｈｆ、Ｔａ、Ｅ
ｕ＿２Ｏ＿３、Ｄｇ＿２Ｏ＿３またはＡｇ−Ｉｎ−Ｃｄ
である特許請求の範囲第３項記載の制御棒。[Claims] 1. A control rod having an absorbing nuclear chain type neutron absorbing material, in which the length in the axial direction of the region in which the absorbing nuclear chain type neutron absorbing material is arranged is determined based on the fuel efficiency of the fuel assembly. Long 17/24~
A control rod characterized by having a range of 22/24. 2. The absorbing nuclear chain type neutron absorbing material contains Hf, Ta, E
u_2O_3, Dy_2O_3 or Ag-In-Cd
A control rod according to claim 1. 3. A region inserted into the reactor core and substantially corresponding to the fuel effective length of the fuel assembly is divided into a first region and a second region, and the first region is located closer to the tip of the control rod than the second region. An absorbing nuclear chain type neutron absorbing material is arranged in one region, a neutron absorbing material is arranged in the second region, and the axial length of the first region is 17/24 to 22/24 of the effective fuel length. control rod. 4. The absorbing nuclear chain type neutron absorbing material contains Hf, Ta, E
u_2O_3, Dg_2O_3 or Ag-In-Cd
A control rod according to claim 3.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP61030878A JPS62228194A (en) | 1986-02-17 | 1986-02-17 | Control rod |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP61030878A JPS62228194A (en) | 1986-02-17 | 1986-02-17 | Control rod |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS62228194A true JPS62228194A (en) | 1987-10-07 |
Family
ID=12315992
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP61030878A Pending JPS62228194A (en) | 1986-02-17 | 1986-02-17 | Control rod |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS62228194A (en) |
-
1986
- 1986-02-17 JP JP61030878A patent/JPS62228194A/en active Pending
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