JPS6153591A - Control rod - Google Patents
Control rodInfo
- Publication number
- JPS6153591A JPS6153591A JP59175741A JP17574184A JPS6153591A JP S6153591 A JPS6153591 A JP S6153591A JP 59175741 A JP59175741 A JP 59175741A JP 17574184 A JP17574184 A JP 17574184A JP S6153591 A JPS6153591 A JP S6153591A
- Authority
- JP
- Japan
- Prior art keywords
- control rod
- outer tube
- tube portion
- inner tube
- tube part
- 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
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
- Crystals, And After-Treatments Of Crystals (AREA)
- Valve Device For Special Equipments (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、例えばヘリウムのようなガスを冷却材とする
原子炉における出力側り■川の制御棒に関する。DETAILED DESCRIPTION OF THE INVENTION [Technical Field of the Invention] The present invention relates to a control rod on the output side of a nuclear reactor using a gas such as helium as a coolant.
〔発明の技術的背口およびその問題点〕一般に、原子炉
においては、中性子吸収体を充填した制御棒を炉心に挿
脱することによって、炉心の核分裂反応度を制御するに
うにしている。[Technical background of the invention and its problems] Generally, in a nuclear reactor, the nuclear fission reactivity of the reactor core is controlled by inserting and removing control rods filled with neutron absorbers into and from the reactor core.
ところで、上記制御棒としては種々のものかあるが、例
えばガス冷却形原子炉にJ3いては、第4図に示すよう
に、多数の制御棒要素1を111線方向に連結してライ
1フ0−ブ2で吊1:j L/、制御棒案内管3および
炉心4の挿入孔5を冒険させるようにしたものがある。By the way, there are various types of control rods, but for example, in the J3 gas-cooled nuclear reactor, a large number of control rod elements 1 are connected in the 111 line direction to form one life. There is one in which the control rod guide tube 3 and the insertion hole 5 of the reactor core 4 are vented.
このタイプの制御棒の場合には制御棒に可撓性が付与さ
れているため、制御棒案内管3の曲りおよび挿入孔5の
ミスアライメン1−に対しても挿入自由度が大ぎい笠の
利点がある。In the case of this type of control rod, since the control rod is given flexibility, the degree of freedom of insertion is large even against bending of the control rod guide tube 3 and misalignment 1- of the insertion hole 5. There are advantages.
ところが、従来この秤の制御棒にJ3ける各a:I T
h1l捧要索1としては、第5図に示すように、溶接に
よって21i円筒状に形成された被覆管6の外管部6
と内管部6.との間に中性子吸収体7を収容し、内管部
6b内の上部に設けられlこスパイダー8を介して軸方
向に延びるスパイン9に支持さUIcものが採用されて
いる。したがって、これらの制御棒要素からなる制御棒
が、炉の緊急停止を目的と1゛るスクラム時等にJ3い
て急速に炉心の挿入孔に全挿入された場合、挿入孔の壁
面から受【ノる高温の熱輻射および冷W材を介した熱伝
導などにより外管部68が強く加熱され、内管部6.と
の間の温度差が大となって内管部と外管部との連絡部に
熱11i311[:差にもとづく熱応力を生じ、被覆管
6に過大な塑性ひずみが発生することがある。しかも、
このような制御棒の急速挿入は原子炉運転期間中に度々
行なわれることがあり、その都度生じる被覆管6の塑性
ひずみにより制御棒自体の寿命が短縮されることがある
等の問題がある。However, conventionally, the control rod of this scale has each a: I T in J3.
As shown in FIG. 5, the h1l cable 1 is an outer tube portion 6 of a cladding tube 6 formed into a 21i cylindrical shape by welding.
and inner tube part 6. A neutron absorber 7 is accommodated between the neutron absorber 7 and the neutron absorber 7, and a neutron absorber 7 is supported by a spine 9 provided at the upper part of the inner tube part 6b and extending in the axial direction via a spider 8. Therefore, if a control rod consisting of these control rod elements is rapidly fully inserted into the insertion hole of the reactor core during J3 during a scram for the purpose of emergency shutdown of the reactor, the receiving hole will be removed from the wall of the insertion hole. The outer tube portion 68 is strongly heated due to high-temperature thermal radiation and heat conduction via the cold W material, and the inner tube portion 6. The temperature difference between the inner and outer tube parts becomes large, and thermal stress based on the difference in heat 11i311[: is generated in the connecting part between the inner tube part and the outer tube part, and excessive plastic strain may occur in the cladding tube 6. Moreover,
Such rapid insertion of control rods may be performed frequently during the operating period of the nuclear reactor, and there are problems such as the life of the control rods themselves being shortened due to plastic strain of the cladding tube 6 that occurs each time.
本発明はこのよう4【点に鑑み、炉心に急速挿入した場
合に、113いても被覆管に生じる熱応力を軽減でき、
長寿命化を図ることができるようにした制御棒を得るこ
とを目的とする。In view of the above points, the present invention can reduce the thermal stress generated in the cladding tube even if the cladding tube is rapidly inserted into the reactor core.
The objective is to obtain a control rod that can extend its life.
(発明の概要)
本発明は、2単円筒状をなす被覆管の内管部と外管部ど
の間に中性子吸収体を収容して構成された制御棒要素を
複数個連結してなる制御棒において、上記外管部の上下
両端内周面部に周方向に延びる係合片を突設し、その係
合片を前記被覆管の上下両主11ツフ部の外周外端縁部
にそれぞれ係合せしめたことを特徴と1°るものであっ
て、制御棒の急速挿入時等において、内管部に対づ“る
外管・部の相対的伸びを許容せしめ、熱膨張差に起因す
る熱応力の発生を軽減できるようにしたものである。(Summary of the Invention) The present invention provides a control rod formed by connecting a plurality of control rod elements each having a neutron absorber housed between an inner tube portion and an outer tube portion of a cladding tube having a cylindrical shape. In this step, engaging pieces extending in the circumferential direction are provided protrudingly on the inner circumferential surface portions of both upper and lower ends of the outer tube portion, and the engaging pieces are respectively engaged with the outer circumferential outer end edges of the upper and lower main 11 throat portions of the cladding tube. 1°, which allows the relative elongation of the outer tube section with respect to the inner tube section during rapid insertion of control rods, and reduces the heat caused by the difference in thermal expansion. This is designed to reduce stress generation.
以下、第1図乃至第3図を参照して本発明の一実施例に
ついて説明する。Hereinafter, one embodiment of the present invention will be described with reference to FIGS. 1 to 3.
図中、符号10は制御棒要素であって、この制御棒要素
10は、+)1記従来の制御棒と同様に、制御棒要素1
0の中心部を量適ずる金属棒上のスパイン11によって
その複数個が連結され、図示しない制御棒案内管および
炉心の挿入孔内を昇降されるようにしである。In the figure, reference numeral 10 denotes a control rod element, and this control rod element 10 is similar to the conventional control rod described in +) 1.
A plurality of the rods are connected by a spine 11 on a metal rod, which is placed in the center of the rod, and are moved up and down through a control rod guide tube (not shown) and an insertion hole in the reactor core (not shown).
ところで、上記制御I4i要素10は、外管部12 a
J)よび内管部12.から形成された2重円筒状を<
’E 1被覆管12を有し、その被覆管12の内外両管
部間に円筒ベレット状の中性子吸収体13が収容されて
いる。ずなわち、被覆管12の内管部′12bの上下両
端部には、それぞれドーナツ状の上部キャップ14 、
および下部キャップ14bの内周部が溶着されており、
その上部主11ツブ14 a J)よび下部キャップ1
4.の外周外端、 縁部には周方向に延びる切欠き段部
158.15、がそれぞれ形成されている。一方、外管
部128の上下両端内周部には、それぞれ周方向に延び
る係合片16 .16.が突設され、その係台片16,
16.がそれぞれ対応する上下両キVツブ14.14b
の切欠き段部150、15、に係合せしめられ、これに
よって2重円筒状の被覆質12が形成されている。そし
て、上記係合片16 .16.と切欠き段部15 、a
15 との係合によって、内管部12.に対する外管部
12aの軸方向および径方向の熱i眼差による相対的移
動が許容されるようにしである。By the way, the control I4i element 10 has an outer tube portion 12 a
J) and inner tube part 12. The double cylindrical shape formed from <
It has an 'E1 cladding tube 12, and a cylindrical pellet-shaped neutron absorber 13 is housed between the inner and outer tube portions of the cladding tube 12. That is, donut-shaped upper caps 14 are provided at both upper and lower ends of the inner tube part '12b of the cladding tube 12, respectively.
and the inner peripheral part of the lower cap 14b is welded,
Its upper main 11 knob 14 a J) and lower cap 1
4. Notch step portions 158 and 15 extending in the circumferential direction are formed at the outer periphery of the outer edge and the edge thereof, respectively. On the other hand, engagement pieces 16 extending in the circumferential direction are provided on the inner peripheral portions of both upper and lower ends of the outer tube portion 128, respectively. 16. is provided protrudingly, and its retaining piece 16,
16. are the corresponding upper and lower V knobs 14.14b
is engaged with the notch stepped portions 150, 15, thereby forming a double cylindrical covering material 12. Then, the engagement piece 16. 16. and the notch stepped portions 15 , a 15 , the inner tube portion 12 . Relative movement of the outer tube portion 12a in the axial and radial directions due to the thermal eye difference is allowed.
また、被覆管12の内管部12.の上部内面にはスパイ
ダが固設されており、このスパイダ17の中心に形成さ
れた挿通孔17.に前記スパイン11が1=動可能に挿
通され、上記スパイン11に固着された支持部材18を
上記スパイダ17の下面に係合さけることによって、制
御棒要素10を支持するようにしである。なお、図中符
号19は制御棒要素10のスパイン11に対1“る横揺
れを防止づ゛るガイドリング、20は被覆管12の外管
部12.に複数個等角的に固着され、外管部12 が直
接炉心の挿入孔に接触することを防ぎ、冷却材の流路を
確保するためのガイドフィンである。In addition, the inner tube portion 12 of the cladding tube 12. A spider is fixed on the upper inner surface of the spider 17, and an insertion hole 17. is formed in the center of the spider 17. The spine 11 is movably inserted through the spine 11, and the control rod element 10 is supported by engaging the support member 18 fixed to the spine 11 with the lower surface of the spider 17. In addition, the reference numeral 19 in the figure is a guide ring that prevents the control rod element 10 from rolling relative to the spine 11, and the reference numeral 20 is a plurality of guide rings fixed to the outer tube portion 12 of the cladding tube 12 in a conformal manner. These guide fins prevent the outer tube portion 12 from coming into direct contact with the insertion hole of the reactor core and ensure a flow path for the coolant.
しかして、このように構成された制御棒が、図示しない
制御棒駆!I!IJ装置ににつて炉心に対り−る挿入位
置に調節され、炉の出力制御が行なわれる。However, the control rod configured in this way becomes a control rod drive (not shown)! I! The IJ device is adjusted to its inserted position relative to the reactor core, and the output of the reactor is controlled.
ぞして、スクラム時などの緊急時には、制iλl俸が炉
心に全挿入され、炉の運転が停止される。Therefore, in an emergency such as a scram, the control iλl is fully inserted into the reactor core and the reactor operation is stopped.
ところで、このような制御棒の急速挿入口、1には、各
制御棒要素10は炉心の挿入孔の壁面から高温の熱輻射
を受けるとともに、冷lJI祠を介覆る熱伝導により1
渇に加熱され、外管部12.が内管部12bより大き(
熱膨張する。この熱膨服差は被rFi管12の長手方向
つまり軸線方向に顕著に現われるが、径方向にも発生し
、外管部12aGよ内管部12bに対して軸線方向およ
び径方向に相対的伸びが生fる。す゛なわら、本実施例
にL13いては、外管部12aの上下両端部に形成され
た係合片16 .16bが上部キーIツブ14.および
下部キー・ツブ14.の外周外端縁部の切欠き段部15
.15bにそれぞれ係合せしめられているので、その係
合部が、第3図に示すように軸線方向J3よび径方向に
聞くことによって、外管部12 の内管部12.に対す
る薗記相対的伸びが許容される。したがって、熱膨11
1u差に起因する熱応力が、外管部12.ど内管部12
.との連結部に発生り゛ることかなく、塑性ひずみの発
生が大幅に軽減され、制御棒の寿命が短縮されるような
ことが防止される。By the way, in such a control rod rapid insertion port 1, each control rod element 10 receives high temperature heat radiation from the wall surface of the insertion hole of the reactor core, and also receives heat radiation through the cold IJI shrine.
The outer tube part 12. is larger than the inner tube portion 12b (
thermally expands. This thermal expansion difference appears prominently in the longitudinal direction, that is, the axial direction, of the rFi tube 12, but it also occurs in the radial direction, and the outer tube portion 12aG has a relative expansion in the axial and radial directions with respect to the inner tube portion 12b. is born. In other words, in this embodiment, L13 includes engagement pieces 16 . 16b is the upper key I knob 14. and lower key knob 14. Notch step 15 on the outer edge of the outer periphery of
.. 15b, respectively, so that the engaging portions of the outer tube portion 12 and the inner tube portion 12. Relative elongation to Sonoki is allowed. Therefore, the thermal expansion 11
Thermal stress due to the 1u difference is applied to the outer tube portion 12. Inner tube part 12
.. The generation of plastic strain is significantly reduced, and the life of the control rod is prevented from being shortened.
以上説明したように、本発明においては外管部の上下両
端部内周部に周方向に延びる係合片を突設し、その係合
片を被覆管の上下両キトツブ部の外周外端縁部にそれぞ
れ係合せしめたので、内管部に対する外管部の伸びが許
容され、スクラム口・1等にJ5いて制御棒が炉心に急
速挿入されても、内管部と外管部用、4jの熱U5服斧
に起因り゛る熱応力の発生が軽減でき、塑性ひずみの発
生が軽減される1したがって、制御棒の寿命低下を防止
でき、原子炉の稼働率を向上させるとともに、原子炉の
安全性を向上せしめることができる。As explained above, in the present invention, engagement pieces extending in the circumferential direction are provided protrudingly on the inner periphery of both upper and lower ends of the outer tube, and the engagement pieces are attached to the outer periphery of the upper and lower ends of the cladding tube. Since the outer tube section is engaged with the inner tube section, the extension of the outer tube section with respect to the inner tube section is allowed, and even if the control rod is rapidly inserted into the core at J5 at the scram port 1st class, the inner tube section, the outer tube section, and the 4j It is possible to reduce the occurrence of thermal stress caused by the heat of the U5 cap, and the occurrence of plastic strain.1 Therefore, it is possible to prevent a decrease in the life of the control rods, improve the operating rate of the reactor, and improve the reactor safety can be improved.
第1図は本発明の制御棒にJ3ける制御棒要素の縦断面
図、第2図は第1図の制御棒要素の一部省略して示す拡
大図、第3図は外管部伸張時におけ I□
る第2図相当部の縦断面図、第4図はガス冷部形原子炉
の制御棒挿入部の概略組成図、第5図は従来の制(lI
l捧要素の板flJi面図である。
10・・・制御棒要素、11・・・スパイン、12・・
・被覆管、12a・・・外管部、12.・・・内管部、
13・・・中性子吸収体、148・・・上部キャップ、
14・・・下部キャップ、15.15b・・・切欠ぎ段
部、16 .16b・・・係合片。
出本1人代Jg!人 猪 股 h1第1回
64目Fig. 1 is a longitudinal sectional view of a control rod element in J3 of the control rod of the present invention, Fig. 2 is an enlarged view of the control rod element in Fig. 1 with some parts omitted, and Fig. 3 is an enlarged view when the outer tube section is extended. Fig. 4 is a schematic composition diagram of the control rod insertion part of a gas-cooled nuclear reactor, and Fig. 5 is a longitudinal cross-sectional view of the part corresponding to Fig. 2.
It is a board flJi side view of the l dedication element. 10... Control rod element, 11... Spine, 12...
- Cladding tube, 12a... outer tube part, 12. ...Inner tube part,
13... Neutron absorber, 148... Upper cap,
14... Lower cap, 15. 15b... Notch step, 16. 16b...Engagement piece. Demoto Jg! Human boar crotch h1 1st 64th
Claims (1)
中性子吸収体を収容して構成された制御棒要素を複数個
連結してなる制御棒において、上記外管部の上下両端内
周部に周方向に延びる係合片を突設し、その係合片を前
記被覆管の上下両キャップ部の外周外端部にそれぞれ係
合ししめたことを特徴とする、制御棒。 2、係合片は、キャップ部の外周外端縁部に形成された
周方向の切欠き段部に係合せしめられていることを特徴
とする、特許請求の範囲第1項記載の制御棒。[Scope of Claims] A control rod formed by connecting a plurality of control rod elements configured by housing a neutron absorber between an inner tube part and an outer tube part of a cladding tube having a single or double cylindrical shape. In this case, engagement pieces extending in the circumferential direction are provided protrudingly on the inner periphery of both the upper and lower ends of the outer tube part, and the engagement pieces are respectively engaged with the outer periphery outer ends of both the upper and lower cap parts of the cladding tube. A control rod characterized by: 2. The control rod according to claim 1, wherein the engaging piece is engaged with a circumferential notch step formed on the outer edge of the cap portion. .
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP59175741A JPS6153591A (en) | 1984-08-23 | 1984-08-23 | Control rod |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP59175741A JPS6153591A (en) | 1984-08-23 | 1984-08-23 | Control rod |
Publications (1)
Publication Number | Publication Date |
---|---|
JPS6153591A true JPS6153591A (en) | 1986-03-17 |
Family
ID=16001436
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP59175741A Pending JPS6153591A (en) | 1984-08-23 | 1984-08-23 | Control rod |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPS6153591A (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPH01288795A (en) * | 1988-05-17 | 1989-11-21 | Japan Atom Energy Res Inst | Control rod for gas cooled nuclear reactor |
-
1984
- 1984-08-23 JP JP59175741A patent/JPS6153591A/en active Pending
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPH01288795A (en) * | 1988-05-17 | 1989-11-21 | Japan Atom Energy Res Inst | Control rod for gas cooled nuclear reactor |
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