JPS6196492A - Control rod for nuclear reactor - Google Patents

Control rod for nuclear reactor

Info

Publication number
JPS6196492A
JPS6196492A JP59217589A JP21758984A JPS6196492A JP S6196492 A JPS6196492 A JP S6196492A JP 59217589 A JP59217589 A JP 59217589A JP 21758984 A JP21758984 A JP 21758984A JP S6196492 A JPS6196492 A JP S6196492A
Authority
JP
Japan
Prior art keywords
control rod
neutron
nuclear reactor
absorbing material
pellets
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
JP59217589A
Other languages
Japanese (ja)
Inventor
甲野 啓一
榎戸 裕二
水野 峰雄
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.)
Power Reactor and Nuclear Fuel Development Corp
Original Assignee
Power Reactor and Nuclear Fuel Development Corp
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 Power Reactor and Nuclear Fuel Development Corp filed Critical Power Reactor and Nuclear Fuel Development Corp
Priority to JP59217589A priority Critical patent/JPS6196492A/en
Publication of JPS6196492A publication Critical patent/JPS6196492A/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

Landscapes

  • 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】 く産業上の利用分野〉 この発明は、主として高速中性子を利用ηる原子炉の制
御棒に関し、更に詳しくは中性子吸収能を向上せしめた
制御棒に関づるものである。
[Detailed description of the invention] Industrial application field> This invention mainly relates to a control rod for a nuclear reactor that utilizes fast neutrons, and more specifically to a control rod with improved neutron absorption ability. .

〈従来の技術〉 中性子を利用づる原子炉において、炉の出力制御に使用
するa、II御棒は、一般に、炭化ホウ県ペレット等の
中性子吸収材を被覆管で被覆密封した制御棒ピンを複数
本まとめて構成されている。
<Prior art> In a nuclear reactor that utilizes neutrons, the a and II control rods used to control the reactor output generally consist of a plurality of control rod pins covered with a neutron absorbing material such as carbide pellets and sealed with a cladding tube. The book is organized as a whole.

この明細書で制御棒という用語は、上記した構成を有す
るHill illll棒体合体いうべき制御棒体系を
指すものとして使用される。
In this specification, the term control rod is used to refer to a control rod system that is a combination of Hill and Illll rods having the above-described configuration.

従来の制御棒に使用されてさた中性子吸収材の代表的な
ものは炭化ホウ素であり、ホウ素の同位体のうちホウ素
−10(”B ”)は熱中性子の吸収能力が大きく、ま
た炭化ホウ毒は畠温においてら強度、化学的安定性等の
特性が擾れて、いるため、熱中性子炉である軽水炉等の
制御棒に多く用いられでいる。
A typical neutron absorbing material used in conventional control rods is boron carbide. Of the boron isotopes, boron-10 ("B") has a large ability to absorb thermal neutrons, and boron carbide Poison is often used in control rods of light water reactors, which are thermal neutron reactors, because its properties such as strength and chemical stability deteriorate in the Hatate temperature.

しかしながら、高速中性子炉に、13いては高速中性子
のホウ素−10の吸収は、熱中性子に対するそれの約1
.、’1oooと小さいlこめ、効率良く高速中性子を
吸収させて原子炉を制御するためにはホウ素−10の炭
化ホウ素中の濃度を可能な限り高め(天然ホウ素は B
/Bは約20%であるが、高速炉心制御棒には90%以
上に漠、縮(〕たものが多用されCいる)るか、炉内の
全装荷吊を多くしてやる必要があり、例えば高濃縮、高
密度の炭化ホウ素の使用が余1八なくされている。
However, in fast neutron reactors, the absorption of boron-10 for fast neutrons is approximately 1/2 that for thermal neutrons.
.. In order to efficiently absorb fast neutrons and control the nuclear reactor, the concentration of boron-10 in boron carbide must be as high as possible (natural boron is B
/B is about 20%, but fast core control rods are often used that are more than 90% compressed (C), or it is necessary to increase the total load in the reactor. For example, The use of highly concentrated, high density boron carbide has been eliminated.

また、高速炉で実際に中性子を吸収して利用されるホウ
素−10の比率は、国産高速実験炉「常陽」の場合、i
dJ gO棒の寿命を通じてホウ素10の10%ぐらい
であり、残部は利用されずI7i東されるという不経/
;iな状態−Cあり、海外でもイの事情に大差ない。
In addition, the ratio of boron-10 that actually absorbs neutrons and is used in a fast reactor is i
Throughout the lifespan of the dJ gO rod, approximately 10% of boron 10 is present, and the remainder is not used and is discarded.
;There is an i-state-C, and the situation is not much different from the situation in other countries.

(発明が解決しようとりる問題点) そこでこの発明は、炭化ホウ素の如き中性子吸収材の吸
収能力を増加せしめ、これによって制御棒のil+制御
性(1Lを向上さゼることかでさろと共に、炭化ホウ素
等の使用量を低減させ、あるいはホウ素−10の濃縮度
の低い炭化ホウ素を使用して経済性の而でも優れた原子
炉制御棒を提供づることを目的になされたものである。
(Problems to be Solved by the Invention) Therefore, the present invention increases the absorption capacity of a neutron absorbing material such as boron carbide, and thereby improves the control rod's IL+ controllability (1L). This was done to reduce the amount of boron carbide used or to use boron carbide with a low concentration of boron-10, thereby providing an economically superior nuclear reactor control rod.

〈問題点を解決りるための手段〉 本発明者等は、高速中性子を減速させることによって中
性子吸収材による高速中性子の吸収能力を増加さμるこ
とができること、更に、高速中性子を減速させるために
金属水素化物が効果的に使用でさることを見出し、この
発明を完成させたものである。  ゛ すなわち、この発明による原子炉制御棒は、複数の中性
子吸収材ペレットを被N管内に積重ね密封してなる制御
棒ピンの複数本を制御棒外枠内に配列しで構成される制
御棒の内部に、金属水素化物を主成分とする中性子減速
層を配設したことを特徴とづるものである。。
<Means for Solving the Problems> The present inventors have discovered that the absorption capacity of fast neutrons by a neutron absorbing material can be increased by slowing down fast neutrons, and furthermore, in order to slow down fast neutrons, He discovered that metal hydrides could be effectively used in this process, and completed this invention. In other words, the nuclear reactor control rod according to the present invention is a control rod consisting of a plurality of control rod pins made by stacking and sealing a plurality of neutron absorbing material pellets inside a N tube and arranging them within a control rod outer frame. It is characterized by a neutron moderating layer containing metal hydride as the main component. .

〈実施例) 以下に図面に示した実施例を参照してこの発明を更に説
明する。
<Examples> The present invention will be further described below with reference to examples shown in the drawings.

第1図はこの発明の制御棒10を水平方向に切断した断
面概略図を示すものであり、7本の1IIIJ罪捧ピン
1が制御棒外枠2内に配列されている。各制御棒ピン1
は、例えば炭化ホウ素の如さ中性子吸収材からなるペレ
ット3をジルカロイまたはステンレス鋼等からなる被覆
管4内に積車ねで構成され、被覆管4の両端はプラグ(
図示せず)によって密封されている。各被覆管4の間隙
5は冷却材通路となる。
FIG. 1 shows a schematic horizontal cross-sectional view of a control rod 10 of the present invention, in which seven 1IIIJ pins 1 are arranged in an outer frame 2 of the control rod. Each control rod pin 1
The cladding tube 4 is constructed by loading pellets 3 made of a neutron absorbing material such as boron carbide into a cladding tube 4 made of Zircaloy or stainless steel, and both ends of the cladding tube 4 are fitted with plugs (
(not shown). The gap 5 of each cladding tube 4 serves as a coolant passage.

第1図の実施例にJjいては、制御棒外枠2の内周面に
水素化ジルコニウムの板状体からなる中性子減速層6が
設けられている。
In the embodiment shown in FIG. 1, a neutron moderation layer 6 made of a plate-like zirconium hydride layer is provided on the inner peripheral surface of the control rod outer frame 2.

かJ:うな構造の制ゆ1棒によれば、この制御棒に入射
した中性子は制御棒外枠2を透過し、中性子減速層6で
減速されたのち、間隙5内の冷tJ材を史に透過してm
m管4内の中性子吸収材ペレット3に吸収されることに
なる。
According to the control rod 1 having a curved structure, neutrons incident on this control rod pass through the control rod outer frame 2, are decelerated by the neutron moderation layer 6, and then travel through the cold tJ material in the gap 5. Transparent to m
It will be absorbed by the neutron absorbing material pellet 3 in the m-tube 4.

なお、第1図に示し1ζように、中性子減速層6の内側
および外側にはステンレス鋼からなる被覆材層7 d3
よび8を設けて、中性子減速層が液体金属冷却材に直接
曝され・ないように保護することが好ましい。
In addition, as shown in FIG. 1, a covering material layer 7 d3 made of stainless steel is provided on the inside and outside of the neutron moderation layer 6.
and 8 are preferably provided to protect the neutron moderation layer from direct exposure to the liquid metal coolant.

第2図は、炭化ホウ素ペレットに+5い(”3(n・α
)″Li、吸収反応の起る率をベレッ1へ径方向につい
て調べた結果をグラフに示したものであつ(、従来の炭
化ホウ素ペレットで中性子減速層6を設(〕なかった場
合(第2図の曲線■)では吸収反応率はベレン1〜外表
面では中心よりやや大きい程度であるが、中性子減速層
6を設()た場合(第2図の曲線(≧))(は同じ炭化
ホウ素ペレットでし吸収反応の殆んどはペレット外表面
に近い領域で起り、ペレット中心部での吸収反応は少な
くなり、いわゆる軽水炉でいわれているスキン効果が表
われることがわかる。
Figure 2 shows that boron carbide pellets have +5 ("3(n・α)
)"This is a graph showing the results of investigating the rate of absorption reaction in the radial direction toward the pellet 1 (2). In the curve ■) in the figure, the absorption reaction rate is slightly larger on the outer surface of Belene 1 than on the center, but when the neutron moderation layer 6 is provided () (curve (≧) in Figure 2) (the same boron carbide It can be seen that most of the absorption reactions in the pellets occur in the area close to the outer surface of the pellets, and the absorption reactions in the center of the pellets decrease, resulting in the so-called skin effect in light water reactors.

第2図の曲線■のような反応率分布となれば、ペレット
中心部の炭化ホウ素のホウ素 10′a縮度を下げたり
、更にはペレット中心部の炭化ホウ素を除去して中空と
イ「シ、ペレット全体としての炭化ホウ素の吊を低減さ
せることが可能となる。
If the reaction rate distribution is as shown by curve ① in Figure 2, the degree of condensation of boron 10'a of boron carbide in the center of the pellet can be lowered, or even the boron carbide in the center of the pellet can be removed to form a hollow hole. , it becomes possible to reduce the amount of boron carbide in the pellet as a whole.

この発明で中性I減速り6として用いる金属水素化物と
しては、上記した水素化ジルコニウムの他に、イツトリ
ウム、チタン、ニッケル。
In addition to the above-mentioned zirconium hydride, metal hydrides used as the neutral I moderator 6 in this invention include yttrium, titanium, and nickel.

ランタン、セリウム、ハフニウム等の金属の水素化物、
あるいはこれらの金属の二元もしくは多元合金の水素化
物等も使用できる。また、金属水素化合物を主成分とし
て2石し中性子減速効果を有する物質であれば、金属水
素化物単独の物質でなくてもこの発明における中性子減
速層として使用することができる。
Metal hydrides such as lanthanum, cerium, hafnium, etc.
Alternatively, hydrides of binary or multi-component alloys of these metals can also be used. Furthermore, any substance that has a metal hydride compound as a main component and has a neutron moderation effect can be used as the neutron moderation layer in the present invention even if it is not a metal hydride alone.

原子炉分野における中性子減速材としては、水素を含む
化合物(例えば軽水1−1□O)が最も優れたものとし
て従来から広く用いられているが、。
Compounds containing hydrogen (for example, light water 1-1□O) have been widely used as the best neutron moderator in the field of nuclear reactors.

この発明において減速材として金属水素化物を使用する
理由は、水素を多量に含んでいること、高温における化
学的安定性等の特性が浸れていて炭化ホウ素等の中性子
吸収材との共存使用に耐えること、照θ=I Iff傷
が少ないこと、製ノ当方法が十分確X′rされ(いるこ
と、さらには比較的軽量であることなどが挙げられる。
The reason for using metal hydride as a moderator in this invention is that it contains a large amount of hydrogen and has characteristics such as chemical stability at high temperatures, so it can withstand coexistence with neutron absorbers such as boron carbide. In addition, it has few scratches, the manufacturing method is sufficiently accurate, and it is relatively lightweight.

また、図示の実施例では中性子減速層を制御棒外枠2の
内面に環状に設置したが、制御棒内のその他の個所に設
置することもて−さる。例えば第3図に示したJ、うに
、制御棒ピン1の被覆管4内に積重ねられた中性子吸収
材ベレッ1−3の周囲を、被覆材層17を6覆る中性子
減速層16で包囲してしよい。あるいは第4図に示した
ように、制御棒ピン1のmm管4内に積重ねられた中性
子吸収材ペレット3の間に、被覆材層27で被覆された
中性子減速層26を配設Jることもできる。
Further, in the illustrated embodiment, the neutron moderating layer is installed in an annular manner on the inner surface of the control rod outer frame 2, but it is also possible to install it at other locations within the control rod. For example, in the case of J shown in FIG. Shiyoi. Alternatively, as shown in FIG. 4, a neutron moderating layer 26 covered with a coating layer 27 may be provided between the neutron absorbing material pellets 3 stacked in the mm tube 4 of the control rod pin 1. You can also do it.

〈発明の効果〉 以上説明したようにこの発明によれば、イ1す陣棒内に
金属水素化物を主成分とする中性子減速層を配設して高
速中性子を−り御棒内で減速さ口ることによって、中性
子吸収材の吸収能力を高めてn1lJ御棒の制御性能を
向上させることがCきるとj:(に、高価な中性子吸収
材の使用量の節約F(の澗縮費用の低減化を図ることが
できるため、経済性を高めることもできる。
<Effects of the Invention> As explained above, according to the present invention, (1) a neutron moderation layer containing metal hydride as a main component is provided in the control rod, and fast neutrons are decelerated in the control rod; By increasing the absorption capacity of the neutron absorbing material and improving the control performance of the n1lJ rod, it is possible to save the amount of expensive neutron absorbing material used and reduce the cost of It is also possible to increase the economic efficiency.

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

第1図はこの発明の原子炉111制御棒の実施例を示づ
水平断面概略図であり、第2図は中性子減速層を設δし
た場合と設置しない場合にお(」るペレット径方向反応
率分布を示すグラフであり、第3図および第4図はこの
発明の池の実施1f1におけるa、II tau棒ピン
の縦断面図である。 1・・・制御棒ピン、2・・・−制御棒外枠、3・・・
中性子吸収材ペレット、4・・・被覆管、5・・・間隙
、6.16.26・・・中性子減速層、7.8,17゜
27・・・被覆材層、10・・・制御棒。 1h訂出願人   動力炉・核燃料開発事業団代  理
  人       尾  股  行  雄面    
      荒  木  友之助笥 I 図 笛2[り 第3図 第40
Fig. 1 is a schematic horizontal cross-sectional view showing an embodiment of the nuclear reactor 111 control rod of the present invention, and Fig. 2 shows the radial reaction of pellets with and without a neutron moderation layer. Fig. 3 and Fig. 4 are longitudinal cross-sectional views of the a, II tau rod pins in the pond implementation 1f1 of the present invention. 1... control rod pin, 2... - Control rod outer frame, 3...
Neutron absorbing material pellet, 4... Cladding tube, 5... Gap, 6.16.26... Neutron moderation layer, 7.8, 17゜27... Covering material layer, 10... Control rod . 1h revision applicant: Power Reactor and Nuclear Fuel Development Corporation Representative Yuki Omata Yumen
Araki Tomonosuke 笥 I Zubue 2 [ri Figure 3 Figure 40

Claims (1)

【特許請求の範囲】 1、複数の中性子吸収材ペレットを被覆管内に積重ね密
封してなる制御棒ピンの複数本を制御棒外枠内に配列し
て構成される制御棒の内部に、金属水素化物を主成分と
する中性子減速層を配設したことを特徴とする原子炉制
御棒。 2、前記金属水素化物における金属は、ジルコニウム、
イットリウム、チタン、ニッケル、ランタン、セリウム
、ハフニウムもしくはリチウム、またはこれらの金属の
二元もしくは多元合金である特許請求の範囲第1項記載
の原子炉制御棒。 3、前記中性子減速層は、前記制御棒外枠の内面、前記
中性子吸収材ペレットの表面あるいは積重ねられたペレ
ット間に配設される特許請求の範囲第1項記載の原子炉
制御棒。
[Scope of Claims] 1. A control rod is constructed by arranging a plurality of control rod pins in a control rod outer frame, which are made by stacking and sealing a plurality of neutron absorbing material pellets in a cladding tube. A nuclear reactor control rod characterized by having a neutron moderation layer mainly composed of a chemical compound. 2. The metal in the metal hydride is zirconium,
A nuclear reactor control rod according to claim 1, which is yttrium, titanium, nickel, lanthanum, cerium, hafnium or lithium, or a binary or multi-component alloy of these metals. 3. The reactor control rod according to claim 1, wherein the neutron moderating layer is disposed on the inner surface of the control rod outer frame, on the surface of the neutron absorbing material pellets, or between stacked pellets.
JP59217589A 1984-10-17 1984-10-17 Control rod for nuclear reactor Pending JPS6196492A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP59217589A JPS6196492A (en) 1984-10-17 1984-10-17 Control rod for nuclear reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP59217589A JPS6196492A (en) 1984-10-17 1984-10-17 Control rod for nuclear reactor

Publications (1)

Publication Number Publication Date
JPS6196492A true JPS6196492A (en) 1986-05-15

Family

ID=16706655

Family Applications (1)

Application Number Title Priority Date Filing Date
JP59217589A Pending JPS6196492A (en) 1984-10-17 1984-10-17 Control rod for nuclear reactor

Country Status (1)

Country Link
JP (1) JPS6196492A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS6450991A (en) * 1987-08-21 1989-02-27 Power Reactor & Nuclear Fuel Neutron absorption element

Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5427698A (en) * 1977-08-01 1979-03-01 Hitachi Ltd Control rod of reactor
JPS58156884A (en) * 1982-03-15 1983-09-17 株式会社東芝 Control rod

Patent Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5427698A (en) * 1977-08-01 1979-03-01 Hitachi Ltd Control rod of reactor
JPS58156884A (en) * 1982-03-15 1983-09-17 株式会社東芝 Control rod

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS6450991A (en) * 1987-08-21 1989-02-27 Power Reactor & Nuclear Fuel Neutron absorption element

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