JPS61159190A - Control rod for fast breeder reactor - Google Patents

Control rod for fast breeder reactor

Info

Publication number
JPS61159190A
JPS61159190A JP59280840A JP28084084A JPS61159190A JP S61159190 A JPS61159190 A JP S61159190A JP 59280840 A JP59280840 A JP 59280840A JP 28084084 A JP28084084 A JP 28084084A JP S61159190 A JPS61159190 A JP S61159190A
Authority
JP
Japan
Prior art keywords
control rod
reactor
breeder reactor
beryllium
fast breeder
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
JP59280840A
Other languages
Japanese (ja)
Inventor
正 吉田
和夫 有江
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.)
Toshiba Corp
Nippon Atomic Industry Group Co Ltd
Original Assignee
Toshiba Corp
Nippon Atomic Industry Group Co 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 Toshiba Corp, Nippon Atomic Industry Group Co Ltd filed Critical Toshiba Corp
Priority to JP59280840A priority Critical patent/JPS61159190A/en
Publication of JPS61159190A publication Critical patent/JPS61159190A/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

  • 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】 〔発明の技術分野〕 本発明は高速増殖炉用制御棒に係り、特に、増殖炉スク
ラム時に炉心に挿入される安全棒に内蔵される制御棒ビ
ンを改良した高速増殖炉用制御棒に関する。
Detailed Description of the Invention [Technical Field of the Invention] The present invention relates to a control rod for a fast breeder reactor, and in particular, to a control rod for a fast breeder reactor, which is an improved control rod bin built into a safety rod inserted into the reactor core during a breeder scram. Regarding control rods for reactors.

〔発明の技術的背景とその問題点〕[Technical background of the invention and its problems]

一般に、高速増殖炉に装備される制御棒は、制御棒保護
管内に複数の制御棒ビンを収容してなり、従来の制御棒
ビンは第3図に示すように構成されている。すなわち、
制御棒ビン1はその軸方向中間部内には例えば、ボロン
カーバイト(B4C)等の中性子吸収材2を充填し、そ
の上下には上部プレナム部3と下部プレナム部4とをそ
れぞれ設け、両端は端栓5,5により止栓している。
Generally, a control rod installed in a fast breeder reactor is made up of a plurality of control rod bins housed in a control rod protection tube, and a conventional control rod bin is configured as shown in FIG. 3. That is,
The control rod bin 1 is filled with a neutron absorbing material 2 such as boron carbide (B4C) in its axially intermediate part, and has an upper plenum part 3 and a lower plenum part 4 above and below, respectively. It is stopped by end plugs 5,5.

ところで、制御棒には用途に応じて調整棒と安全棒とが
あり、調整棒は増殖炉の運転制御のために、炉心内へ適
宜挿入され、または引抜かれるように構成されている。
By the way, the control rods include adjustment rods and safety rods depending on the purpose, and the adjustment rods are configured to be inserted into or withdrawn from the reactor core as appropriate to control the operation of the breeder reactor.

これに対し、安全棒は増殖炉スクラム時に炉心に挿入さ
れ増殖炉運転を停止するようになっており、増殖炉の通
常の出力運転時には第4図に示すように炉心6から上方
へ引抜かれた状態にある。すなわち、安全棒としての制
御棒の引抜時には、中性子吸収材2が充填されている制
御棒ビン1の軸方向中間部が上部ブランケット7Aの上
部ないしその上方に亘って位置し、制御棒ビン1の下部
である下部プレナム4は炉心6内上部に滞在する状態に
ある。したがって、制御棒が引抜状態にある炉の運転中
には、制御棒ビン1の下部プレナム部4が常時炉心7内
に滞在していることになる。
On the other hand, the safety rods are inserted into the reactor core during the breeder reactor scram to stop the breeder reactor operation, and are pulled upward from the reactor core 6 during normal output operation of the breeder reactor, as shown in Figure 4. in a state. That is, when a control rod as a safety rod is withdrawn, the axially intermediate portion of the control rod bin 1 filled with the neutron absorbing material 2 is located at or above the upper blanket 7A, and the control rod bin 1 is The lower plenum 4, which is the lower part, remains in the upper part of the core 6. Therefore, during operation of the reactor with the control rods in the withdrawn state, the lower plenum portion 4 of the control rod bin 1 always stays in the reactor core 7.

しかしながら、このような従来の高速増殖炉用制御棒で
は制御棒ビン1の下部プレナム部4については、中性子
を吸収した中性子吸収材2にて生成された分裂生成ガス
を単に貯えるため等に利用されているに過ぎず、中性子
経済的にも反応度的にも何らかの利得を与えるようには
利用されていなかった。
However, in such conventional control rods for fast breeder reactors, the lower plenum part 4 of the control rod bin 1 is used to simply store fission product gas generated by the neutron absorber 2 that has absorbed neutrons. However, it has not been used to provide any benefits in terms of neutron economy or reactivity.

〔発明の目的〕[Purpose of the invention]

本発明は上述した事情を考慮してなされたものであり、
簡単な構成により高速増殖炉内の中性子経済と反応度の
向上を図ることのできる高速増殖炉用制御棒を提供する
ことを目的とする。
The present invention has been made in consideration of the above-mentioned circumstances,
The object of the present invention is to provide a control rod for a fast breeder reactor that can improve the neutron economy and reactivity in the fast breeder reactor with a simple configuration.

〔発明の概要〕[Summary of the invention]

本発明は、従来の制御棒ビンの下部が増殖炉の運転中に
は炉心内に常時滞在しているにも拘らず、炉の中性子経
済および反応度については何ら有効に利用されていない
点に着目してなされたものであり、上記制御棒ビンの下
部に、中性子吸収断面積が小さく、かつ(n、2n)反
応断面積の大きい部材を装填したことを特徴とする。
The present invention solves the problem that although the lower part of the conventional control rod bin always stays in the reactor core during the operation of the breeder reactor, it is not used effectively for the neutron economy and reactivity of the reactor. It is characterized by a member having a small neutron absorption cross section and a large (n, 2n) reaction cross section loaded in the lower part of the control rod bin.

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

以下、本発明に係る高速jt・q、fp用制御棒の一実
施例について図面を参照して説明する。
DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS An embodiment of a control rod for high-speed JT/Q and FP according to the present invention will be described below with reference to the drawings.

第1図は本発明に係る高速増−炉用IIJ御棒の一実施
例に組み込まれる制御棒ビンの構造の一例を一部切り欠
いて示す縦断面図であり、図中符号10は円柱状の制御
棒ビンである。1iljtll棒ビン10は図示しない
制御棒内に複数収容されるものであり、各制御棒ビン1
0の軸方向中間部内にボロンカーバイト等の中性子吸収
材11を充填している。
FIG. 1 is a partially cutaway longitudinal sectional view showing an example of the structure of a control rod bin incorporated in an embodiment of the IIJ control rod for a high speed intensifier according to the present invention. control rod bottle. A plurality of rod bins 10 are housed in a control rod (not shown), and each control rod bin 1
A neutron absorbing material 11 such as boron carbide is filled in the axially intermediate portion of the shaft.

この中性子吸収材11を収容する中性子吸収材収容部1
1Aの上方には上部プレナム部12を、中性子吸収材収
容部11Aの下半部にはベリリウム(Be)をペレット
状に形成したベリリウムペレット13が充填されたベリ
リウムペレット部14が配設されている。このベリリウ
ム(Be)は中性子吸収断面積が小さく、かつ(n、2
n)反応断面積が大きい性質を有し、上部プレナム部1
2は中性子を吸収した中性子吸収材11にて生成された
分裂生成ガスを貯える空間である。制御棒ビン10の上
下両端部は各端栓15,15により止栓されている。
Neutron absorbing material storage section 1 that stores this neutron absorbing material 11
An upper plenum part 12 is provided above 1A, and a beryllium pellet part 14 filled with beryllium pellets 13 formed from beryllium (Be) in the form of pellets is provided in the lower half of the neutron absorbing material storage part 11A. . This beryllium (Be) has a small neutron absorption cross section and (n, 2
n) It has the property of having a large reaction cross section, and the upper plenum part 1
2 is a space for storing the fission product gas generated by the neutron absorbing material 11 that has absorbed neutrons. Both upper and lower ends of the control rod bin 10 are stopped by end plugs 15, 15, respectively.

このように構成された制御棒ビン10は図示しない多角
筒状の制御棒管内に複数収容されて制御棒を構成してお
り、この制御棒は増殖炉スクラム時に炉心16内に挿入
されて増殖炉運転を停止するような安全棒に構成されて
いる。このために、通常の増MP運転時には第2図に示
すように制御棒ビン10は炉心16から引抜かれた状態
にある。
A plurality of control rod bins 10 configured in this manner are housed in a polygonal cylindrical control rod tube (not shown) to constitute a control rod, and the control rods are inserted into the reactor core 16 during the breeder reactor scram and are inserted into the reactor core 16 during the breeder reactor scram. It consists of a safety rod that stops the operation. For this reason, during normal MP increase operation, the control rod bin 10 is in a state of being pulled out from the reactor core 16, as shown in FIG.

この制御棒の引抜き時には制御棒ビン10の中性子吸収
材収容部11Aは炉心16から引抜かれた状態にある。
At the time of withdrawal of this control rod, the neutron absorbing material accommodating portion 11A of the control rod bin 10 is in a state of being withdrawn from the reactor core 16.

この制御棒の引抜き時には1lIIll棒ビン10のベ
リリウムペレット部14が炉心16と、この炉心16周
りを取り囲むブランケット17の上部ブランケット17
Aとに亘って滞在することになる。ベリリウムペレット
部14のベリリウム(Be)は中性子吸収断面積が小さ
く、かつ(n。
When this control rod is withdrawn, the beryllium pellet portion 14 of the 1lIIll rod bin 10 is attached to the reactor core 16 and the upper blanket 17 of the blanket 17 surrounding the reactor core 16.
I will be staying with A. Beryllium (Be) in the beryllium pellet portion 14 has a small neutron absorption cross section and (n).

2n)反応断面積が大きい性質を有するので、ベリリウ
ムの(n、2n)反応を通じて炉内の中性子数は増大さ
れる。
2n) Since beryllium has a large reaction cross section, the number of neutrons in the reactor is increased through the (n, 2n) reaction of beryllium.

また、ベリリウムは中性子吸収材11のボロンカーバイ
ト(84G)に比して正の反応度を有するために、制御
棒が炉心に挿入されたときの負の反応度が相対的に増大
し、安全棒としての制御棒機能の向上を図ることができ
る。
In addition, since beryllium has a positive reactivity compared to boron carbide (84G) of the neutron absorbing material 11, the negative reactivity increases relatively when the control rods are inserted into the reactor core, making it safer. It is possible to improve the function of the control rod as a rod.

一方、III ill棒が炉心16内に挿入さると、制
御棒ビン10の中性子吸収材11Aが炉心16内に滞在
するが、この際ベリリウムペレット部14が下部ブラン
ケット17Bないしその下方へ下降されるので、増殖炉
運転を停止せしめる安全棒としての機能を妨害すること
がない。
On the other hand, when the III ill rod is inserted into the reactor core 16, the neutron absorbing material 11A of the control rod bin 10 stays in the reactor core 16, but at this time, the beryllium pellet portion 14 is lowered into the lower blanket 17B or below it. , it does not interfere with its function as a safety rod to stop the operation of the breeder reactor.

なお、本実施例ではIIJ III棒ビン10の下部に
、ベリリウムペレット13を装填したベリリウムベレッ
ト部14を設けた場合について述べたが、本発明はこれ
に限定されるものではなく、ベリリウム(Be)と同様
に中性子吸収断面積が小さく、かつ(n、2n>反応断
面積の大きい性質を有するものであればよい。また、ベ
リリウムの形状もベレットに限定されず、棒状であって
もよい。
In this embodiment, a case has been described in which the beryllium pellet portion 14 loaded with beryllium pellets 13 is provided at the lower part of the IIJ III rod bottle 10, but the present invention is not limited to this, and beryllium (Be) Similarly, any material having a small neutron absorption cross section and a large reaction cross section (n, 2n>reaction cross section) may be used. Also, the shape of beryllium is not limited to a pellet, and may be rod-shaped.

〔発明の効果〕〔Effect of the invention〕

以上説明したように本発明は、増殖炉スクラム時に炉心
に挿入され内蔵する複数の1lltlll棒ビンを内蔵
してなる高速増殖炉用制m4Iにおいて、上記制御棒ビ
ン内の下部に、中性子吸収断面積が小さく、かつ(n、
2n)反応断面積の大きい部材を装填した。
As explained above, the present invention provides a fast breeder reactor control m4I which is inserted into the reactor core during a breeder scram and has a built-in plurality of 1lltllll rod bins. is small and (n,
2n) A member with a large reaction cross section was loaded.

したがって、本発明によれば制tIl棒ビン下部の<n
、2n)反応を通して炉内の中性子数を増大せしめ、中
性子経済の向上を図ることができる。
Therefore, according to the present invention, <n
, 2n) The number of neutrons in the reactor can be increased through the reaction, and the neutron economy can be improved.

その結果、増殖炉の臨界量を小さくすると共に、核燃料
の増殖比を高めることができる。
As a result, the critical mass of the breeder reactor can be reduced and the breeding ratio of nuclear fuel can be increased.

また、制御棒ビン下部は、中性子吸収材に比して正の反
応度を有するために、制御棒全体としての負の反応度が
相対的に増大し、安全棒としての制御棒機能の向上を図
ることができる。
In addition, since the lower part of the control rod bin has a positive reactivity compared to the neutron absorbing material, the negative reactivity of the control rod as a whole increases relatively, improving the control rod's function as a safety rod. can be achieved.

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

第1図は本発明に係る高速増殖炉用制御棒の一実施例に
組み込まれる制御棒ビンの一例を一部切欠いて示す縦断
面図、第2図は第1図で示す高速増殖炉用制御棒の引抜
時における制御棒ビンの炉心への滞在状態を示す模式図
、第3図は従来の高速増殖炉用制御棒に組み込まれる制
御棒ビンの一例を一部切欠いて示す縦断面図、第4図は
第3図で示す従来例の引抜時における制−棒ビンの炉心
への滞在状態を示す模式図である。 10・・・制御棒ビン、11・・・中性子吸収材、12
・・・上部ブレナム部、1−3・・・ベリリウムベレッ
ト、14・・・ベリリウムベレット部、15・・・端栓
、16・・・炉心、17A・・・上部ブランケット、1
7B・・・下部ブランケット。 第1図 第2図 第3図
FIG. 1 is a partially cutaway vertical sectional view showing an example of a control rod bin incorporated in an embodiment of a fast breeder reactor control rod according to the present invention, and FIG. 2 is a fast breeder reactor control shown in FIG. 1. FIG. 3 is a schematic diagram showing the state in which the control rod bin stays in the reactor core when the rod is withdrawn; FIG. FIG. 4 is a schematic diagram showing the state in which the control rod bin stays in the core during extraction in the conventional example shown in FIG. 3. 10... Control rod bottle, 11... Neutron absorber, 12
... Upper blenheim part, 1-3... Beryllium pellet, 14... Beryllium pellet part, 15... End plug, 16... Core, 17A... Upper blanket, 1
7B...Lower blanket. Figure 1 Figure 2 Figure 3

Claims (1)

【特許請求の範囲】 1、増殖炉スクラム時に炉心に挿入され複数の制御棒ピ
ンを内蔵してなる高速増殖炉用制御棒において、上記制
御棒ピン内の下部に、中性子吸収断面積が小さく、かつ
(n、2n)反応断面積の大きい部材を装填したことを
特徴とする高速増殖炉用制御棒。 2、中性子吸収断面積が小さく、かつ(n、2n)反応
断面積の大きい部材がベリリウム(Be)である特許請
求の範囲第1項に記載の高速増殖炉用制御棒。
[Claims] 1. In a control rod for a fast breeder reactor, which is inserted into the reactor core during a breeder reactor scram and has a plurality of control rod pins, the control rod has a small neutron absorption cross section in its lower part, A control rod for a fast breeder reactor, characterized in that (n, 2n) is loaded with a member having a large reaction cross section. 2. The control rod for a fast breeder reactor according to claim 1, wherein the member having a small neutron absorption cross section and a large (n, 2n) reaction cross section is beryllium (Be).
JP59280840A 1984-12-30 1984-12-30 Control rod for fast breeder reactor Pending JPS61159190A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP59280840A JPS61159190A (en) 1984-12-30 1984-12-30 Control rod for fast breeder reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP59280840A JPS61159190A (en) 1984-12-30 1984-12-30 Control rod for fast breeder reactor

Publications (1)

Publication Number Publication Date
JPS61159190A true JPS61159190A (en) 1986-07-18

Family

ID=17630715

Family Applications (1)

Application Number Title Priority Date Filing Date
JP59280840A Pending JPS61159190A (en) 1984-12-30 1984-12-30 Control rod for fast breeder reactor

Country Status (1)

Country Link
JP (1) JPS61159190A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN104376879A (en) * 2013-08-12 2015-02-25 中国核动力研究设计院 Under-moderated reactor core
US11059189B2 (en) 2016-07-05 2021-07-13 Sony Interactive Entertainment Inc. Arm driving apparatus

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN104376879A (en) * 2013-08-12 2015-02-25 中国核动力研究设计院 Under-moderated reactor core
CN104376879B (en) * 2013-08-12 2017-06-20 中国核动力研究设计院 A kind of deficient moderated reactor reactor core
US11059189B2 (en) 2016-07-05 2021-07-13 Sony Interactive Entertainment Inc. Arm driving apparatus

Similar Documents

Publication Publication Date Title
US4994233A (en) Fuel rod with axial regions of annular and standard fuel pellets
US4777016A (en) Fuel assembly
US5742655A (en) Neutron-absorbent control cluster for a nuclear reactor
US6002735A (en) Nuclear fuel pellet
EP0093901B1 (en) High uranium utilization fuel rod for light water reactors
EP0788117A1 (en) Nuclear fuel pellet
JPS61159190A (en) Control rod for fast breeder reactor
EP0664546A1 (en) Fuel bundle
EP0199197B1 (en) Fuel assembly
JP2565861B2 (en) Fuel assembly for boiling water reactor
EP0613152A1 (en) Mid-enrichment axial blanket for a nuclear reactor fuel rod
JPS59128483A (en) Control rod assembly for fast breeder
JPH07244182A (en) Fuel assembly and reader core
US20240355487A1 (en) Fuel Assembly for Sodium-Cooled Metal Fuel Fast Reactor, Reactor Core, and Manufacturing Method of Fuel Assembly
JPH01263591A (en) Control rod
JPS5948688A (en) Control rod
JP3070756B2 (en) Fuel assembly
JP2509625B2 (en) Core structure of fast breeder reactor
JPS61111493A (en) Method of transporting and storing fuel aggregate
JP3121543B2 (en) Control rods for boiling water reactors and boiling water reactor cores
KR100237136B1 (en) Candu fuel bundle with a low void coefficient
JPS59180388A (en) Nuclear fuel element
JPS61147184A (en) Fuel aggregate
JPS61159191A (en) Control rod for fast breeder reactor
JPS61281993A (en) Fuel assembly