JPS6057288A - Control rod for nuclear reactor - Google Patents

Control rod for nuclear reactor

Info

Publication number
JPS6057288A
JPS6057288A JP58165196A JP16519683A JPS6057288A JP S6057288 A JPS6057288 A JP S6057288A JP 58165196 A JP58165196 A JP 58165196A JP 16519683 A JP16519683 A JP 16519683A JP S6057288 A JPS6057288 A JP S6057288A
Authority
JP
Japan
Prior art keywords
control rod
rod
neutron
neutron absorption
control
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
Application number
JP58165196A
Other languages
Japanese (ja)
Inventor
博見 丸山
肇男 青山
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Hitachi Ltd
Original Assignee
Hitachi Ltd
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Hitachi Ltd filed Critical Hitachi Ltd
Priority to JP58165196A priority Critical patent/JPS6057288A/en
Publication of JPS6057288A publication Critical patent/JPS6057288A/en
Pending legal-status Critical Current

Links

Classifications

    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

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  • Vibration Dampers (AREA)
  • 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】 〔発明の利用分野〕 本発明は、沸騰水型原子炉などで出力分布制御・反応度
制御に用いる制御棒の構成に関する。
DETAILED DESCRIPTION OF THE INVENTION [Field of Application of the Invention] The present invention relates to the structure of a control rod used for power distribution control and reactivity control in a boiling water nuclear reactor or the like.

〔発明の背景〕[Background of the invention]

第1図は、沸騰水型原子炉で用いられている十字形制御
棒である。制御棒1は、制御棒シース2とシース内に′
二翼につき約20本並べられた中性子吸収棒3から構成
されておシ、中性子吸収棒は、第2図に示すように中性
子吸収材である炭化ホウ素(B4C)粉末7とステンレ
ス被覆管6よp成る。
Figure 1 shows a cruciform control rod used in a boiling water reactor. The control rod 1 is connected to the control rod sheath 2 and inside the sheath.
It is composed of about 20 neutron absorption rods 3 arranged in two blades, and the neutron absorption rods are made of boron carbide (B4C) powder 7, which is a neutron absorbing material, and a stainless steel cladding tube 6, as shown in Fig. 2. It consists of p.

B4Cに含まれるホウ素の同位体”Bは、熱中性子に対
して約3800バーンという大きな吸収断面積を有し、
中性子吸収反応 ’0B+n + 7Li +’I(e によジリチウムとヘリウムに変わる。しかし、リチウム
もヘリウムもともに中性子吸収能力が非常に弱いため、
制御棒の中性子吸収能力、すなわち制御棒価値はIOB
の減少とともに急速に低下する。
The boron isotope "B" contained in B4C has a large absorption cross section of about 3800 burns for thermal neutrons,
The neutron absorption reaction '0B+n + 7Li +'I(e) changes into dilithium and helium.However, both lithium and helium have very weak neutron absorption ability, so
The neutron absorption capacity of the control rod, that is, the control rod value is IOB
decreases rapidly as .

沸騰水型原子炉の炉心運用では、制御棒の寿命を制御棒
有効長の1の部分の平均制御棒価値劣化が初期制御棒価
値の10チに到る期間と定義している。すなわち、制御
棒価値劣化が上記の値に達した制御棒は新しい制御棒と
交換される。したがって、制御棒寿命が短いと制御棒交
換体数が多くなり、廃棄物量の増加の一因となるため、
寿命の長い制御棒が望まれている。
In the core operation of a boiling water reactor, the life of a control rod is defined as the period during which the average control rod value deterioration of 1 part of the control rod effective length reaches 10 inches of the initial control rod value. That is, a control rod whose value deterioration reaches the above value is replaced with a new control rod. Therefore, if the control rod life is short, the number of control rods to be replaced will increase, which will contribute to an increase in the amount of waste.
Control rods with long lifespans are desired.

第3図に、第2図のA及びBのB4C棒の中性子吸収率
変化を示す。図に示すように制御棒翼先端の中性子吸収
棒Aでは、10Bの燃焼が速いため中性子吸収率が急速
に減少する。この結果、制御棒の平均制御棒価値劣化も
また速くなる。この点を考慮して、制御棒翼先端部の中
性子吸収棒をハフニウムやユーロピウムなど劣化速度の
遅い中性子吸収材に置き換えた制御棒が日本特許竹開昭
53−74697に提示されている。しかし、B4Cに
比ベハフニウムやユーロピウムは比重がそれぞれ約7倍
、約4倍と重く、シかも非常に高価である。このため、
制御棒の軽量化・低廉化の観点から、これらの使用を制
限し、効果的な134Cとの併用をはかる必要がある。
FIG. 3 shows changes in the neutron absorption rate of the B4C rods A and B in FIG. As shown in the figure, in the neutron absorption rod A at the tip of the control rod blade, the neutron absorption rate decreases rapidly because 10B burns quickly. As a result, the average control rod value deterioration of the control rods is also faster. In consideration of this point, a control rod in which the neutron absorbing rod at the tip of the control rod blade is replaced with a neutron absorbing material with a slow deterioration rate, such as hafnium or europium, is proposed in Japanese Patent No. 53-74697. However, the specific gravity of behafnium and europium is about 7 times and about 4 times heavier than B4C, respectively, and they are also very expensive. For this reason,
From the viewpoint of reducing the weight and cost of control rods, it is necessary to limit the use of these rods and to use them in combination with 134C, which is effective.

上述した日本特許では、ハフニウム等を棒状で使用して
いるため、制御棒寿命到達時において中性子束の低い状
態で燃焼してきた棒の中心部に燃え残シが生じており、
有効に活用されていない。
In the above-mentioned Japanese patent, hafnium, etc. is used in the form of a rod, so when the control rod reaches its end of life, burnt remains are formed in the center of the rod, which has been burned in a low neutron flux state.
Not being used effectively.

〔発明の目的〕[Purpose of the invention]

本発明の目的は、以」二述べた従来技術の欠点・を除き
、制御棒′寿命の長期化を達成するとともに、軽く、し
かも安価な制御棒を提供することにおる。
The object of the present invention is to eliminate the drawbacks of the prior art mentioned above, to prolong the life of the control rod, and to provide a control rod that is light and inexpensive.

〔発明の概要〕[Summary of the invention]

上記の目的を達成するため、本発明の制御棒では中性子
吸収棒を形成する主要な中性子吸収材の他に、中性子吸
収棒の中性子吸収材を低減するための第2の中性子吸収
材を配置し、この中性子吸収材の量を制イl141棒翼
端部で中央部に比べ多く1〜たことを特徴とづる。第2
の中性子吸収材としては、ハフニウム・ユーロピウムな
ど中性子吸収率の減少の遅いもののほか、カドミウム・
A−g−I n −Cd合金やホウ素入りステンレス鋼
などを用いることができる。
In order to achieve the above object, in the control rod of the present invention, in addition to the main neutron absorbing material forming the neutron absorbing rod, a second neutron absorbing material is arranged to reduce the neutron absorbing material of the neutron absorbing rod. It is characterized by controlling the amount of this neutron absorbing material at the tip of the rod blade compared to the center. Second
As neutron absorbing materials, in addition to those whose neutron absorption rate decreases slowly such as hafnium and europium, cadmium and
A-g-I n -Cd alloy, boron-containing stainless steel, etc. can be used.

中性子は燃料棒中の核分裂性物質の核分裂によって生成
し、減速拐によって減速きれながら制御棒に到達する。
Neutrons are generated by fission of fissile material in the fuel rods, and are decelerated by deceleration before reaching the control rods.

第2の中性子吸収材は、制御棒に到達した中性子の一部
を吸収し、中性子吸収棒の中性子照射量を低減する役割
を果す。第4図は、第2の中性子吸収材としてハフニウ
ムシートラ制御棒シースと中性子吸収棒の間に設け、シ
ート厚を増加した場合の中性子吸収棒の中性子吸収率変
化を示す。図より、シート厚を増加させることによp、
中性子吸収棒の中性子吸収量が低下することがわかる。
The second neutron absorbing material absorbs a portion of the neutrons that reach the control rod, and serves to reduce the amount of neutron irradiation of the neutron absorbing rod. FIG. 4 shows the change in neutron absorption rate of the neutron absorption rod when the second neutron absorption material is provided between the hafnium sheetra control rod sheath and the neutron absorption rod and the sheet thickness is increased. From the figure, by increasing the sheet thickness, p,
It can be seen that the neutron absorption amount of the neutron absorption rod decreases.

第5図は、制御棒翼に沿った中性子吸収棒の中性子吸収
率分布である。制御棒翼端部の中性子吸収棒は、制御棒
平均中性子吸収率の1.2〜1.8倍の中性子吸収率を
有する。以上の結果から、ハフニウム使用量を最少にし
て制御棒寿命を長期化するためには、制御棒翼端部のハ
フニウムシート厚を大きくシ、中央部を少なくすればよ
い。すなわち、この対策によシ制御棒翼方向の中性子吸
収率は平坦化され、中性子吸収材は一様に燃焼する。ま
た、ハフニウムをシート状で使用することによシ、表面
積対体積比が増加し燃え残シがなくなシ、有効利用をは
かることができる。
FIG. 5 shows the neutron absorption rate distribution of the neutron absorption rod along the control rod blade. The neutron absorption rod at the control rod blade tip has a neutron absorption rate of 1.2 to 1.8 times the average neutron absorption rate of the control rod. From the above results, in order to minimize the amount of hafnium used and extend the life of the control rod, it is sufficient to increase the thickness of the hafnium sheet at the tip of the control rod and reduce the thickness at the center. That is, this measure flattens the neutron absorption rate in the direction of the control rod blade, and the neutron absorbing material burns uniformly. Furthermore, by using hafnium in sheet form, the surface area to volume ratio increases and there are no residual burn marks, making it possible to use hafnium effectively.

以上説明したように、安価で軽い84Cを用いた制御棒
の長寿命化を達成するためには、10Bの燃焼を抑える
だめの第2の中性子吸収材を配することが有効であシ、
さらに第2の中性子吸収材を次のようにすれは効果的で
ある。
As explained above, in order to extend the life of control rods using cheap and light 84C, it is effective to provide a second neutron absorber to suppress the combustion of 10B.
Furthermore, it is effective to use the second neutron absorber as follows.

(1)制御棒翼・端部の第2の中性子吸収材量を中央部
より多くシ、中性子吸収棒中の吸収材の燃焼を均一化す
る。
(1) The amount of the second neutron absorbing material in the control rod blade/end portion is greater than that in the central portion to make the combustion of the absorbing material in the neutron absorbing rod uniform.

(2)第2の中性子吸収材の表面積対体積比を増し燃え
残りをなくする。
(2) Increase the surface area to volume ratio of the second neutron absorber to eliminate unburnt residue.

〔発明の実施例〕[Embodiments of the invention]

以下、本発明を実施例によってよシ一層詳細に説明する
Hereinafter, the present invention will be explained in more detail with reference to Examples.

第6図は本発明になる原子炉用制御棒の構成図を示す。FIG. 6 shows a configuration diagram of a control rod for a nuclear reactor according to the present invention.

ステンレス鋼の制御棒中央支持材5に浴接された制御棒
シース2の中に21本の中性子吸収棒3が一列に配置さ
れている。本実施例では、制御棒翼先端の中性子吸収棒
と制御棒シースの間隙に第2の中性子吸収材としてノ・
フニウムシート8が配置されてお9、具申央部には/飄
フニウムシートがない構成となっている。第7図は上記
ノ・フニウムシート厚を0.3smとした場合の制御棒
翼方向の中性子吸収率分布を示す。制御棒翼先端部では
、ハフニウムシートによシ約20チ中性子吸収率が低下
し、翼に沿った中性子吸収率の平坦化がはかられている
。本実施例に用いたハフニウムシートは、制御棒全長に
わたって入れた場合でも1枚約280gで、制御棒重量
を約2y4増加させるにすぎない。また、本実施例の制
御棒は、ハフニウムシートがない制御棒に比べ約15%
寿命が長くなる。
Twenty-one neutron absorbing rods 3 are arranged in a row in a control rod sheath 2 that is bath-welded to a control rod central support 5 made of stainless steel. In this example, a second neutron absorbing material is installed in the gap between the neutron absorbing rod at the tip of the control rod blade and the control rod sheath.
A funium sheet 8 is arranged 9, and there is no funium sheet in the central part of the body. FIG. 7 shows the neutron absorption rate distribution in the direction of the control rod blade when the thickness of the neutronium sheet is 0.3 sm. At the tip of the control rod blade, the neutron absorption rate is reduced by about 20 degrees due to the hafnium sheet, and an attempt is made to flatten the neutron absorption rate along the blade. The hafnium sheets used in this example weigh about 280 g each even when inserted over the entire length of the control rod, which only increases the weight of the control rod by about 2y4. In addition, the control rod of this example has approximately 15% less weight than a control rod without a hafnium sheet.
Longer lifespan.

第8図は、上記実施例に示す制御棒の具申央部に軽い材
料から成るシート9を配置し中性子吸収棒の位置ずれを
防止した制御棒である。第9図には、制御捧諷中央部の
中性子吸収棒径を大きくすることによシ位置ずれ防止を
はかった制御棒の実施例を示す。これら実施例では、第
7図に示したもつとも中性子吸収率の大きい中性子吸収
棒、すなわち制御棒真先端の吸収棒をハフニウム棒10
とj7た。
FIG. 8 shows a control rod shown in the above embodiment in which a sheet 9 made of a light material is placed in the center of the rod to prevent the neutron absorption rod from shifting. FIG. 9 shows an embodiment of a control rod in which the diameter of the neutron absorption rod at the center of the control rod is increased to prevent misalignment. In these embodiments, the neutron absorption rod with the highest neutron absorption rate, that is, the absorption rod at the very tip of the control rod, shown in FIG.
and j7.

第10図は、本発明になる原子炉用制御棒の第2の実施
例を示す図でるる。本実施例では、ハフニウムシート厚
をステップ状に変え、制御棒翼端部を厚く、中央部を薄
くした。このように7・フ二つムシート厚を累方向に変
化させることにより第11図に示ず゛ように中性子吸収
棒の中性子吸収率は平坦化される。このような/・フニ
ウムシートを用い、さらに翼先端の吸収棒を・・フニウ
ム棒としたことによシ制御棒寿命は全中性子吸収棒がB
10棒の制御棒に比べ約1.3倍となる。また、第11
図の実施例の7・フニウム使用量は約02W@の一定の
厚さの・・フニウムシートを配置した制御棒と同じであ
るが、ハフニウムシート厚を実施例のように分布させる
ことによシ制御棒寿命は5チ長くなる。したがって、制
御棒翼に沿って第2の吸収材であるハフニウムの量を変
化させることによυ、効果的に制御棒寿命の長期化を実
現できる。なお、本実施例ではノ・フニウムシート厚を
ステップ状に変化させたが連続的に変化させても同様の
効果が得られる。
FIG. 10 is a diagram showing a second embodiment of the control rod for a nuclear reactor according to the present invention. In this example, the hafnium sheet thickness was changed stepwise, so that the control rod blade tip was thicker and the center portion was thinner. By changing the thickness of the 7-frame sheet in the cumulative direction in this manner, the neutron absorption rate of the neutron absorption rod is flattened as shown in FIG. By using such a Fnium sheet and using Fnium rods as the absorption rods at the tip of the blade, the life of the control rods is as long as the total neutron absorption rods are B.
This is approximately 1.3 times the number of control rods with 10 rods. Also, the 11th
Example 7 in the figure: The amount of Hfnium used is a constant thickness of about 0.2 W@... It is the same as the control rod with Hfnium sheets arranged, but it is controlled by distributing the hafnium sheet thickness as in the example. The rod life will be 5 inches longer. Therefore, by varying the amount of hafnium, which is the second absorbing material, along the control rod blade, it is possible to effectively extend the life of the control rod. In this embodiment, the thickness of the no-funium sheet was changed stepwise, but the same effect can be obtained even if the thickness is changed continuously.

〔発明の効果〕〔Effect of the invention〕

以上説明したごとく、本発明によれば少量の第2の中性
子吸収材により中性子吸収棒の中性子照射量を低減でき
、その結果10Bの燃焼を抑えることができるので制御
棒の寿命長期化・軽量化・低廉化を達成できる。さらに
、制御棒寿命が長期化することに伴い、原子炉定期検査
時における制frJu棒交換体数が減少し、廃棄物量の
低減・交換作業時の被ばく量の低減・定期検査期間短縮
によるプラント利用率の向上が可能となる。
As explained above, according to the present invention, the amount of neutron irradiation of the neutron absorbing rod can be reduced by using a small amount of the second neutron absorbing material, and as a result, the combustion of 10B can be suppressed, thereby extending the life span and reducing the weight of the control rod.・Cost reduction can be achieved. Furthermore, as the lifespan of control rods becomes longer, the number of control rods to be replaced during periodic reactor inspections will decrease, reducing the amount of waste, reducing exposure during replacement work, and shortening the period of periodic inspections. This makes it possible to improve the rate.

【図面の簡単な説明】[Brief explanation of the drawing]

第1図は沸騰水型原子炉で用いられている十字形制御棒
を示す斜視図、第2図は第1図の制御棒翼の断面図、第
2(a)図は第2図の一部拡大図、第3図は制御棒真先
端及び中央の中性子吸収棒の中性子吸収率変化グラフ図
、第4図はハフニウムシート厚増加に伴う中性子吸収棒
の中性子吸収率変化グラフ図、第5図は従来の制御棒翼
に沿った中性子吸収棒の中性子吸収率グラフ図、第6図
は本発明の第1実施例になる原子炉用制御棒の一部切欠
表示による全体図、第6(a)図は第6図のx−x’矢
視図、第7図は第6図に示した第1の実施例の制御棒翼
に沿った中性子吸収棒の中性子吸収率グラフ図、第8図
・第9図は第6図に示した第1の実施例の制御棒翼構成
を示した断面図、第10図は本発明になる原子炉用制御
棒の第2の実施例による制御棒翼構成の断面図、第11
図は第10図に示した第2の実施例の制御棒翼に沿った
中性子吸収棒の中性子吸収率を示すグラフ図である。 1・・・制御棒、2・・・制御棒シース、3・・・中性
子吸収棒、4・・・ハンドル、5・・・中央支持材、6
・・・被覆管、7・・・B4C粉末、8・・・吸収材シ
ート、9・・・軽量な材料から成るシート、10・・・
ノ・フニウム棒。 茸、、2CI−)図 充3 図 算 5 図 抑j1坪俸翼方市 −湾痛 算ろ 区 乃− 烹 q 図
Figure 1 is a perspective view of a cruciform control rod used in a boiling water reactor, Figure 2 is a sectional view of the control rod blade in Figure 1, and Figure 2(a) is a cross-sectional view of the control rod blade in Figure 2. Figure 3 is a graph of changes in the neutron absorption rate of the neutron absorption rod at the tip and center of the control rod, Figure 4 is a graph of changes in neutron absorption rate of the neutron absorption rod as the hafnium sheet thickness increases, Figure 5 6 is a graph of the neutron absorption rate of a neutron absorption rod along a conventional control rod blade, FIG. ) is a view taken along the line xx' in FIG. 6, FIG. 7 is a graph of the neutron absorption rate of the neutron absorption rod along the control rod blade of the first embodiment shown in FIG. 6, and FIG.・FIG. 9 is a sectional view showing the configuration of the control rod blade of the first embodiment shown in FIG. 6, and FIG. 10 is a control rod blade according to the second embodiment of the control rod for a nuclear reactor according to the present invention. Sectional view of the configuration, 11th
The figure is a graph showing the neutron absorption rate of the neutron absorption rod along the control rod blade of the second embodiment shown in FIG. DESCRIPTION OF SYMBOLS 1... Control rod, 2... Control rod sheath, 3... Neutron absorption rod, 4... Handle, 5... Central support member, 6
... Cladding tube, 7 ... B4C powder, 8 ... Absorbent sheet, 9 ... Sheet made of lightweight material, 10 ...
No-funium stick. Mushrooms,, 2CI-) 3 diagrams and calculations 5 diagrams

Claims (1)

【特許請求の範囲】 1、多数本の中性子吸収棒を並べて制御棒翼を構成して
なる制御棒において、該中性子吸収材を囲む第2の中性
子吸収材を設け、かつ該中性子吸収材量を制御棒翼に沿
って変化させたことを特徴とする原子炉用制御棒。 2、特許請求の範囲第1項において、制御棒翼端部のみ
に第2の中性子吸収材を設けたことを特徴とする原子炉
用制御棒。 3、特許請求の範囲第1項において、制御棒翼端部の第
2の中性子吸収材量を中央部よシ多くしたことを特徴と
する原子炉用制御棒。
[Claims] 1. In a control rod formed by arranging a large number of neutron absorbing rods to form a control rod blade, a second neutron absorbing material surrounding the neutron absorbing material is provided, and the amount of the neutron absorbing material is A control rod for a nuclear reactor characterized by a change along the control rod blade. 2. A control rod for a nuclear reactor according to claim 1, characterized in that a second neutron absorbing material is provided only at the blade tip of the control rod. 3. A control rod for a nuclear reactor according to claim 1, characterized in that the amount of the second neutron absorbing material at the control rod blade end is greater than that at the center.
JP58165196A 1983-09-09 1983-09-09 Control rod for nuclear reactor Pending JPS6057288A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP58165196A JPS6057288A (en) 1983-09-09 1983-09-09 Control rod for nuclear reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP58165196A JPS6057288A (en) 1983-09-09 1983-09-09 Control rod for nuclear reactor

Publications (1)

Publication Number Publication Date
JPS6057288A true JPS6057288A (en) 1985-04-03

Family

ID=15807658

Family Applications (1)

Application Number Title Priority Date Filing Date
JP58165196A Pending JPS6057288A (en) 1983-09-09 1983-09-09 Control rod for nuclear reactor

Country Status (1)

Country Link
JP (1) JPS6057288A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS627319A (en) * 1986-04-10 1987-01-14 株式会社フジクラ Removal of insulation film for strand insulated conductor
JPS62204192A (en) * 1986-03-05 1987-09-08 株式会社日立製作所 Control rod

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS62204192A (en) * 1986-03-05 1987-09-08 株式会社日立製作所 Control rod
JPS627319A (en) * 1986-04-10 1987-01-14 株式会社フジクラ Removal of insulation film for strand insulated conductor
JPS6232681B2 (en) * 1986-04-10 1987-07-16 Fujikura Cable Works Ltd

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