JPH022557B2 - - Google Patents

Info

Publication number
JPH022557B2
JPH022557B2 JP56126204A JP12620481A JPH022557B2 JP H022557 B2 JPH022557 B2 JP H022557B2 JP 56126204 A JP56126204 A JP 56126204A JP 12620481 A JP12620481 A JP 12620481A JP H022557 B2 JPH022557 B2 JP H022557B2
Authority
JP
Japan
Prior art keywords
neutron
cladding tube
neutron absorption
rods
tube
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.)
Expired - Lifetime
Application number
JP56126204A
Other languages
Japanese (ja)
Other versions
JPS5827091A (en
Inventor
Kyoshi Ueda
Tanoshi Sato
Yoshuki Sekiguchi
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 Genshiryoku Jigyo KK
Original Assignee
Toshiba Corp
Nippon Genshiryoku Jigyo KK
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 Genshiryoku Jigyo KK filed Critical Toshiba Corp
Priority to JP56126204A priority Critical patent/JPS5827091A/en
Publication of JPS5827091A publication Critical patent/JPS5827091A/en
Publication of JPH022557B2 publication Critical patent/JPH022557B2/ja
Granted 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

  • Particle Accelerators (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Description

【発明の詳細な説明】 本発明は原子炉用制御棒に係る。[Detailed description of the invention] The present invention relates to a control rod for a nuclear reactor.

原子炉用制御棒は中央構造材に細長いU字状の
シースを取付けて形成した複数箇のウイング内
に、多数の中性子吸収棒を装填して構成されてい
る。前記の中性子吸収棒は一般にステンレス鋼
(SUS)から成る被覆管内に中性子吸収材として
のB4C粉末を充填し、被覆管内に一定間隔で粉末
移動防止用の仕切球を配置して構成されている。
A nuclear reactor control rod is constructed by loading a large number of neutron absorption rods into a plurality of wings formed by attaching an elongated U-shaped sheath to a central structural member. The above-mentioned neutron absorption rod is generally constructed by filling a cladding tube made of stainless steel (SUS) with B 4 C powder as a neutron absorbing material, and arranging partition balls at regular intervals within the cladding tube to prevent powder movement. There is.

中性子吸収棒中のB4Cは中性子を吸収して中性
子吸収能力を次第に失い、またその間 10Bが中
性子と反応してHeガスを発生し被覆管内の圧力
を上昇させる。中性子吸収能力によつて定まる寿
命を核的寿命と言い、管内ガス圧によつて定まる
寿命を機械的寿命と言う。
B 4 C in the neutron absorption rod absorbs neutrons and gradually loses its neutron absorption ability, and during this time 10 B reacts with neutrons to generate He gas and increase the pressure inside the cladding tube. The life determined by the neutron absorption capacity is called the nuclear life, and the life determined by the gas pressure inside the tube is called the mechanical life.

而して、制御棒は一様な中性子照射を受けるも
のではなく、例えば各ウイングの側縁部および上
端部は強度の中性子照射を受け、それら側縁部近
傍および上端部領域の中性子吸収棒内の中性子吸
収材は多量の中性子を吸収するので、他部の中性
子吸収棒より早期に核的寿命に達する。そのた
め、他部の中性子吸収棒は十分核的寿命を残して
いるにも拘らず、制御棒を放射性廃棄物として廃
棄しなければならなかつた。
Therefore, the control rod is not uniformly irradiated with neutrons; for example, the side edges and upper end of each wing are exposed to intense neutron irradiation, and the neutron absorption rods near these side edges and in the upper end area are exposed to strong neutron irradiation. Because the neutron absorbing material absorbs a large amount of neutrons, it reaches its nuclear lifetime earlier than other neutron absorbing rods. As a result, the control rods had to be disposed of as radioactive waste, even though the other neutron absorption rods had sufficient nuclear lifespan left.

本発明は上記の事情に基づきなされたもので、
制御棒全体がほぼ一様に核的寿命に達し、廃棄時
に核的寿命を残存させている部分が殆どない原子
炉用制御棒を得ることを目的としている。
The present invention was made based on the above circumstances, and
The objective is to obtain a control rod for a nuclear reactor in which the entire control rod reaches the end of its nuclear life almost uniformly, and there are almost no parts with nuclear life remaining at the time of disposal.

本発明は制御棒、詳細には制御棒内の中性子吸
収棒の核的寿命についての次のような知見に基づ
く。すなわち、核的寿命の到来は中性子吸収物質
である 10Bの減耗と偏りとに基づく。前記の
中、減耗には中性子との反応による減耗と、中性
子との反応の結果の粉末の性状変化により、被覆
管に有害な影響を及ぼして生じるB4C粉末の消失
とがある。また、偏りについては次の通りであ
る。すなわち、B4C粉末の量に変化がなくても、
粉末の偏りにより、中性子吸収棒内に空隙を生じ
れば、空隙における反応度価値の低下が、粉末の
移動先における高密度化による反応度価値の上昇
を上回るため、結局偏りは核的寿命を短縮させる
こととなる。したがつて、前記の特に高照射を受
ける制御棒の領域の中性子吸収能力を他の領域よ
り大とし、また中性子吸収材と中性子との反応の
結果による被覆管への有害な影響を防止し、中性
子吸収材の偏りを防止すれば、前記目的を達成し
得ることとなる。
The present invention is based on the following findings regarding the nuclear lifetime of control rods, specifically neutron absorbing rods within control rods. That is, the arrival of the nuclear lifetime is based on the depletion and imbalance of 10 B, which is a neutron absorbing material. Among the above, depletion includes depletion due to reaction with neutrons, and loss of B 4 C powder caused by a change in the properties of the powder as a result of reaction with neutrons, which has a detrimental effect on the cladding tube. The bias is as follows. In other words, even if there is no change in the amount of B 4 C powder,
If voids are created in the neutron absorption rod due to powder bias, the decrease in reactivity value in the voids will exceed the increase in reactivity value due to densification at the destination of the powder, so the bias will eventually reduce the nuclear lifetime. It will be shortened. Therefore, the neutron absorption capacity of the area of the control rod that is particularly highly irradiated is made larger than other areas, and the harmful effects on the cladding tube due to the reaction between the neutron absorbing material and the neutrons are prevented, The above objective can be achieved by preventing the neutron absorbing material from being biased.

以下、図面につき本発明の詳細を説明する。第
1図は十字型制御棒1の1つのウイング2のシー
スを除去して示したもので、ウイング2の側縁2
aから1cm〜2cmのウイング側縁領域に配置され
る中性子吸収棒3は第2図に示す如く構成してあ
る。すなわち、B4C、Eu2O3等の粉末を焼結して
成る複数のペレツト4をHf薄肉管5に挿入し、
Hf薄肉管5の両端を縮径してペレツト4を管内
に保持させ、Hf薄肉管5の両端部にはウール状
の詰物6を施して成る単位吸収体7を、有効長全
長にわたりSUSから成る被覆管8内に複数箇充
填して中性子吸収棒3としてある。但し、核中性
子吸収棒3の被覆管8内の単位吸収体7の境界は
同一水準にないようにする。そのためには、各中
性子吸収棒3の被覆管8の最下位および最上位に
挿入充填される単位吸収体7の長さを異らしめ、
中間の単位吸収体7の長さをすべて同一とすれば
よい。
The invention will be explained in detail below with reference to the drawings. FIG. 1 shows the sheath of one wing 2 of the cruciform control rod 1 removed, and the side edge 2 of the wing 2 is shown with the sheath removed.
The neutron absorption rod 3 arranged in the wing side edge region 1 cm to 2 cm from a is constructed as shown in FIG. That is, a plurality of pellets 4 made of sintered powders of B 4 C, Eu 2 O 3 , etc. are inserted into the Hf thin-walled tube 5,
The diameter of both ends of the Hf thin-walled tube 5 is reduced to hold the pellets 4 inside the tube, and the unit absorbent body 7 is made of SUS over the entire effective length by applying wool-like filling 6 to both ends of the Hf thin-walled tube 5. A plurality of rods are filled in the cladding tube 8 to form the neutron absorption rod 3. However, the boundaries of the unit absorbers 7 within the cladding tube 8 of the nuclear neutron absorbing rod 3 should not be at the same level. To do this, the lengths of the unit absorbers 7 inserted and filled into the lowest and highest positions of the cladding tube 8 of each neutron absorption rod 3 are varied,
All of the intermediate unit absorbent bodies 7 may have the same length.

またウイング側縁領域以外に配置される中性子
吸収棒3の挿入先端からに約15cmの上端領域の被
覆管8内にも、上記単位吸収体7と同様に構成し
た単位吸収体10を装填する。
Further, a unit absorber 10 having the same structure as the unit absorber 7 is also loaded into the cladding tube 8 in the upper end region of about 15 cm from the insertion tip of the neutron absorbing rod 3 disposed outside the wing side edge region.

さらに上記ウイング側縁領域以外および上端領
域以外の領域の被覆管8内には中性子吸収材粉末
としてのB4C粉末11を充填する。
Further, B 4 C powder 11 as a neutron absorbing material powder is filled in the cladding tube 8 in areas other than the wing side edge area and the upper end area.

また、B4C粉末11充填部と単位吸収体10充
填部との境界にはウール状の介在物12を配置す
る。また、これらの中性子吸収棒9において、
B4C粉末11充填部と単位吸収体10との境界全
部が同一水準となることがないよう、単位吸収体
10の充填部の長さを長短交互とする。
Further, a wool-like inclusion 12 is arranged at the boundary between the part filled with B 4 C powder 11 and the part filled with unit absorbent body 10. In addition, in these neutron absorption rods 9,
The lengths of the filled parts of the unit absorbent bodies 10 are alternately long and short so that the boundaries between the filled parts of the B 4 C powder 11 and the unit absorbent bodies 10 are not all at the same level.

上記構成に係る原子炉用制御棒においては、高
強度の中性子照射を受けるウイング側縁領域およ
び上端領域にはB4C、Eu2O3のペレツト4をHf薄
肉管5内に挿入して成る単位吸収体7,10を被
覆管8内に充填して形成した中性子吸収棒3,9
が配置されているため、Hfの優れた共鳴吸収能
力によりそれらの部分の中性子吸収能力が高めら
れ、他の部分より早期に核的寿命が到来すること
は防止される。すなわちHfは、中性子を複数回
にわたり吸収しても、なお中性子吸収断面積が大
きな同位体を形成するため、1度の中性子吸収に
よつて吸収能力を喪失するB4Cと比較して中性子
吸収能力が長期間にわたつて持続する。
In the reactor control rod having the above configuration, pellets 4 of B 4 C and Eu 2 O 3 are inserted into the Hf thin-walled tube 5 in the wing side edge region and upper end region which are exposed to high-intensity neutron irradiation. Neutron absorption rods 3 and 9 formed by filling unit absorbers 7 and 10 into a cladding tube 8
are arranged, the excellent resonance absorption ability of Hf increases the neutron absorption ability of those parts, and prevents them from reaching their nuclear lifetimes earlier than other parts. In other words, even if Hf absorbs neutrons multiple times, it still forms an isotope with a large neutron absorption cross section, so it has a lower neutron absorption capacity than B 4 C, which loses its absorption capacity after one neutron absorption. Ability lasts for a long time.

また、B4C、Eu2O3等は固形状のペレツト4と
して充填されているので、粉末の如く経時的に沈
降して偏りを生じることはないので、偏りに基づ
く核的寿命の短縮を生じることはない。さらに、
ペレツト4と被覆管8の内周間にはHf薄肉管5
が介在されるので、ペレツト4と被覆管8とが直
接に接触するおそれはなく、高照射時にB4Cがス
エリングを起こして被覆管に有害な影響を及ぼす
こともなく、これに基づくB4Cの消失もないので
核的寿命の短縮は防止される。
In addition, since B 4 C, Eu 2 O 3 , etc. are packed as solid pellets 4, they do not settle over time and become uneven like powders, so the shortening of the nuclear life due to unevenness is avoided. It will never occur. moreover,
Between the pellet 4 and the inner periphery of the cladding tube 8 is an Hf thin-walled tube 5.
Since the pellets 4 and the cladding tube 8 are interposed, there is no risk of direct contact between the pellets 4 and the cladding tube 8, and B 4 C does not cause swelling during high irradiation and has no harmful effect on the cladding tube. Since there is no loss of C, shortening of the nuclear lifetime is prevented.

また、ウール状の詰物6は、ペレツト4が割れ
た場合にもその微小な破片がHf被覆管5外に脱
落することを防止する機能を有する。したがつて
前記破片が被覆管8とHf薄肉管5との間に入り
込んで局所的応力を発生することもない。
Further, the wool-like filling 6 has a function of preventing minute fragments from falling out of the Hf cladding tube 5 even if the pellet 4 is broken. Therefore, the fragments do not enter between the cladding tube 8 and the Hf thin-walled tube 5 and generate local stress.

また、中性子吸収材をペレツト4とすることに
より被覆管内には小さ空隙が生じるが、ペレツト
4による高密度化とHf薄肉管5の大きな共鳴吸
収能力とにより、ガスプレナムをとつても、従来
より若干の高反応度化を図ることができる。な
お、Eu2O3のペレツトを使用した場合にはその濃
度により反応度価値を調節することができる。
In addition, by using pellets 4 as the neutron absorbing material, small voids are created in the cladding tube, but due to the high density of the pellets 4 and the large resonance absorption capacity of the thin-walled Hf tube 5, even if the gas plenum is used, the cladding is slightly smaller than the conventional one. It is possible to achieve a high degree of reactivity. Note that when Eu 2 O 3 pellets are used, the reactivity value can be adjusted by adjusting their concentration.

さらに、中性子照射によつて生じるB4C、
Eu2O3ペレツト4の性状変化に基づくスエリング
は、Hf薄肉管5と被覆管8との間の小さな空隙
で充分吸収することができる。
Furthermore, B 4 C produced by neutron irradiation,
Swelling caused by changes in the properties of the Eu 2 O 3 pellets 4 can be sufficiently absorbed by the small gap between the Hf thin-walled tube 5 and the cladding tube 8.

また、Hfは重く高価であるが、本発明におい
てはHfの薄肉管を使用しており、しかもHfの中
性子吸収は主としてその表面でなされるのでHf
薄肉管用に使用するHfの量はきわめて少なく、
制御棒の重量の増大、価格の上昇はそれ程著しく
はない。したがつて、従来の制御棒の重量基準で
設計された制御棒駆動装置をそのまま使用して駆
動することができ、従来の制御棒と殆ど違わない
価格で供給することができる。
In addition, Hf is heavy and expensive, but in the present invention, a thin-walled Hf tube is used, and Hf neutron absorption is mainly done on its surface, so Hf
The amount of Hf used for thin-walled pipes is extremely small;
The increase in weight and price of control rods is not so significant. Therefore, a control rod drive device designed based on the weight of conventional control rods can be used as is and can be supplied at a price almost the same as that of conventional control rods.

なお、本発明は上記実施例のみに限定されな
い。例えばウイング側縁領域に配置される中性子
吸収棒であつても高強度の中性子照射を受けるの
は、有効長の上部1/4程度であるから、単位吸収
体の充填はそのウイング側縁上端領域に限つても
よい。
Note that the present invention is not limited to the above embodiments. For example, even if a neutron absorption rod is placed in the wing side edge area, only the upper quarter of the effective length receives high-intensity neutron irradiation, so the filling of the unit absorber is in the upper edge area of the wing side edge. may be limited to.

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

第1図は本発明に係る原子炉用制御棒の一実施
例を示す要部断面図、第2図は第1図に示す中性
子吸収棒の拡大部分断面図である。 2……ウイング、3,9……中性子吸収棒、4
……ペレツト、5……Hf薄肉管、6……ウール
状詰物、7,10……単位吸収体、8……被覆
管、11……B4C粉末、12……ウール状介在
物。
FIG. 1 is a sectional view of a main part showing an embodiment of a control rod for a nuclear reactor according to the present invention, and FIG. 2 is an enlarged partial sectional view of the neutron absorption rod shown in FIG. 1. 2... Wing, 3, 9... Neutron absorption rod, 4
... Pellet, 5 ... Hf thin-walled tube, 6 ... wool-like filling, 7, 10 ... unit absorber, 8 ... cladding tube, 11 ... B 4 C powder, 12 ... wool-like inclusion.

Claims (1)

【特許請求の範囲】[Claims] 1 中央構造材に細長いU字状断面の複数箇のシ
ースを取付けてウイングを形成し、被覆管内に中
性子吸収材を充填して形成した中性子吸収棒を上
記ウイング内に多数装填してなる原子炉用制御棒
において、ウイング側縁領域に配置される中性子
吸収棒の少なくとも上部1/4の側縁上部領域の被
覆管内およびウイング側縁領域以外に配置される
中性子吸収棒の挿入先端から約15cmの上端領域の
被覆管内に、Hf薄肉管内に中性子吸収材ペレツ
トを挿入して成る単位吸収体を充填する一方、上
記側縁上部領域以外および上端領域以外の領域の
被覆管内には中性子吸収材粉末をそれぞれ充填し
たことを特徴とする原子炉用制御棒。
1 A nuclear reactor in which a plurality of sheaths with elongated U-shaped cross sections are attached to a central structural member to form wings, and a large number of neutron absorption rods formed by filling the cladding tube with a neutron absorption material are loaded into the wings. In control rods for control rods, at least the upper 1/4 of the neutron absorption rods placed in the wing side edge area are inside the cladding tube, and approximately 15 cm from the insertion tip of the neutron absorption rods placed outside the wing side edge area. The cladding tube in the upper end region is filled with a unit absorber made by inserting neutron absorbing material pellets into the Hf thin-walled tube, while the cladding tube in regions other than the upper side edge region and the upper end region is filled with neutron absorbing material powder. A nuclear reactor control rod characterized by being filled with each.
JP56126204A 1981-08-12 1981-08-12 Reactor control rod Granted JPS5827091A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP56126204A JPS5827091A (en) 1981-08-12 1981-08-12 Reactor control rod

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP56126204A JPS5827091A (en) 1981-08-12 1981-08-12 Reactor control rod

Publications (2)

Publication Number Publication Date
JPS5827091A JPS5827091A (en) 1983-02-17
JPH022557B2 true JPH022557B2 (en) 1990-01-18

Family

ID=14929284

Family Applications (1)

Application Number Title Priority Date Filing Date
JP56126204A Granted JPS5827091A (en) 1981-08-12 1981-08-12 Reactor control rod

Country Status (1)

Country Link
JP (1) JPS5827091A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US11657393B2 (en) 2019-09-30 2023-05-23 Kddi Corporation Privilege granting method and privilege granting device

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS62129321A (en) * 1985-11-29 1987-06-11 Tokuyama Soda Co Ltd Production of porous sheet
JP5449915B2 (en) * 2009-08-10 2014-03-19 日立Geニュークリア・エナジー株式会社 Control rod for boiling water reactor

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US11657393B2 (en) 2019-09-30 2023-05-23 Kddi Corporation Privilege granting method and privilege granting device

Also Published As

Publication number Publication date
JPS5827091A (en) 1983-02-17

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