JPH03593B2 - - Google Patents

Info

Publication number
JPH03593B2
JPH03593B2 JP61077786A JP7778686A JPH03593B2 JP H03593 B2 JPH03593 B2 JP H03593B2 JP 61077786 A JP61077786 A JP 61077786A JP 7778686 A JP7778686 A JP 7778686A JP H03593 B2 JPH03593 B2 JP H03593B2
Authority
JP
Japan
Prior art keywords
spacer
guide tube
shield
outer diameter
neutron
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
JP61077786A
Other languages
Japanese (ja)
Other versions
JPS62233788A (en
Inventor
Yoshuki Kasahara
Hideo Machida
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.)
Mitsubishi Heavy Industries Ltd
Original Assignee
Mitsubishi Atomic Power Industries Inc
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 Mitsubishi Atomic Power Industries Inc filed Critical Mitsubishi Atomic Power Industries Inc
Priority to JP61077786A priority Critical patent/JPS62233788A/en
Publication of JPS62233788A publication Critical patent/JPS62233788A/en
Publication of JPH03593B2 publication Critical patent/JPH03593B2/ja
Granted legal-status Critical Current

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

  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Shielding Devices Or Components To Electric Or Magnetic Fields (AREA)

Description

【発明の詳細な説明】 〔産業上の利用分野〕 本発明は原子力発電プラントにおける高速増殖
炉用中性子しやへい体に関するものである。
DETAILED DESCRIPTION OF THE INVENTION [Field of Industrial Application] The present invention relates to a neutron shielding body for a fast breeder reactor in a nuclear power plant.

〔従来の技術〕[Conventional technology]

高速増殖炉は中央部に燃料集合体を多数配置
し、その半径方向外周部に中性子しやへい体を配
置し、炉心からの中性子を反射し、炉内の中性子
束を高めるとともに高速中性子やγ線をしやへい
して周囲の構造体を保護するようになつている。
従来の中性子しやへい体は本出願人が先に出願し
た実願昭60−167991号に示す如く、第4図のハン
ドリングヘツド1とエントランスノズル2の間に
設けられた案内管(六角管)3内に分割型の内部
しやへい体4をスペーサ5を介して積層嵌合す
る。上記スペーサ5は円筒形嵌合部の中間に鍔部
を突設した形状で上記鍔部外周には複数の冷却材
流通用の縦溝が設けてある。
A fast breeder reactor has a large number of fuel assemblies arranged in the center, and neutron shielding bodies arranged on the radial outer periphery to reflect neutrons from the core, increase the neutron flux in the reactor, and reduce fast neutrons and γ It is designed to shield the lines and protect surrounding structures.
The conventional neutron shielding body is a guide tube (hexagonal tube) installed between the handling head 1 and the entrance nozzle 2 in FIG. A split-type internal shield body 4 is stacked and fitted into the interior of the housing 3 with a spacer 5 interposed therebetween. The spacer 5 has a shape in which a flange protrudes from the middle of a cylindrical fitting part, and a plurality of vertical grooves for coolant circulation are provided on the outer periphery of the flange.

〔発明が解決しようとする問題点〕[Problem that the invention seeks to solve]

しかし、その後研究を重ねた結果内部しやへい
体4間の接続部であるスペーサ5上部の空隙6に
ガス溜りが生じると共に内部しやへい体4上面凹
部7には引抜交換時に冷却材であるナトリウムが
滞留し、本来機能であるナトリウムの充填ドレン
が果せない他、放射化(構造材+Na24 a&Na22 a)
レベルが高くなり、燃料取扱設備側に悪影響を及
ぼすことが判明した。
However, as a result of repeated research, gas accumulation occurred in the gap 6 at the top of the spacer 5, which is the connection between the internal shields 4, and a coolant was found in the recess 7 on the upper surface of the internal shield 4 when it was pulled out and replaced. Sodium accumulates, making it impossible to perform its original function of filling and draining sodium, and also causing activation (structural materials + Na 24 a & Na 22 a )
It was found that the level increased and had a negative impact on fuel handling equipment.

又、スペーサ5の外径の鍔部は外周に複数の縦
溝を有し冷却材流路の確保を図り不均一な温度分
布を解消すると共に中間パツド部11の応力緩和
を図つたものであるが、スウエリングにより案内
管(六角管)3内面に局部的に応力集中が発生す
る懸念があることが判つた。
Further, the flange portion of the outer diameter of the spacer 5 has a plurality of vertical grooves on the outer periphery to ensure a coolant flow path, eliminate uneven temperature distribution, and alleviate stress in the intermediate pad portion 11. However, it has been found that there is a concern that stress concentration may occur locally on the inner surface of the guide tube (hexagonal tube) 3 due to swelling.

〔問題点を解決するための手段〕[Means for solving problems]

そのため本発明の高速増殖炉用中性子しやへい
体は、ハンドリングヘツドとエントランスノズル
の間に介在する案内管内に、該案内管内側と所定
の隙間を有する分割型の内部しやへい体を厚肉中
空円筒形スペーサを介して積層嵌合し、該スペー
サの外径を上記内部しやへい体外径より大きく形
成すると共に外周に複数の縦溝を設ける。
Therefore, the neutron shielding body for a fast breeder reactor of the present invention has a thick-walled split-type internal shielding body that has a predetermined gap with the inside of the guide tube within the guide tube interposed between the handling head and the entrance nozzle. They are stacked and fitted via a hollow cylindrical spacer, and the outer diameter of the spacer is larger than the outer diameter of the inner flexible body, and a plurality of vertical grooves are provided on the outer periphery.

〔作用〕[Effect]

積層する内部しやへい体の接続部に厚肉中空円
筒形スペーサを設け、その外周面に複数の縦溝に
よる切欠部を設けることにより、冷却材の流路及
びナトリウム充填ドレンが健全に確保され、内部
しやへい体の偏心による不均一な温度分布が解消
される。又、スペーサを厚肉中空円筒形状にした
事により、スウエリングによる案内管(六角管)
内面への局部的な応力集中が緩和される。
By providing a thick-walled hollow cylindrical spacer at the connection part of the laminated inner shield body, and providing a plurality of vertical grooves on the outer circumferential surface of the spacer, a sound flow path for the coolant and a sodium-filled drain are ensured. , the uneven temperature distribution caused by the eccentricity of the internal shield body is eliminated. In addition, by making the spacer into a thick-walled hollow cylindrical shape, the guide tube (hexagonal tube) can be formed by swelling.
Local stress concentration on the inner surface is alleviated.

〔実施例〕〔Example〕

以下、添付図に基づいて本発明の実施例を詳細
に説明する。
Hereinafter, embodiments of the present invention will be described in detail based on the accompanying drawings.

第1図は本発明の中性子しやへい体の一実施例
の縦断面図、第2図は第1図のA−A線断面図、
第3図は第2図のB−B線断面図である。
FIG. 1 is a longitudinal sectional view of an embodiment of the neutron shielding body of the present invention, FIG. 2 is a sectional view taken along the line A-A in FIG. 1,
FIG. 3 is a sectional view taken along the line B--B in FIG. 2.

ハンドリングヘツド1とエントランスノズル2
の間に介在する案内管(六角管)3から成る外殻
部内に分割型の内部しやへい体9を積層充填し、
積層する内部しやへい体9の接続部にスペーサ8
を配する。図では接続部の嵌合面はそれぞれテー
パー面にしてあるが円筒形でも良い。第2図、第
3図に示すように10はスペーサ8の円筒形外周
部に設けた冷却材流通用の縦溝である。上記スペ
ーサ8は照射レベルに応じたスウエリング挙動を
踏え厚肉な中空円筒形とする。なお高照射レベル
の場合は上記円筒形外周面を太鼓型とすることも
ある。
Handling head 1 and entrance nozzle 2
A split internal shield body 9 is stacked and filled in an outer shell portion consisting of a guide tube (hexagonal tube) 3 interposed between the two.
A spacer 8 is placed at the connection part of the inner shield body 9 to be laminated.
Allocate. In the figure, the fitting surfaces of the connecting portions are respectively tapered surfaces, but they may also be cylindrical. As shown in FIGS. 2 and 3, reference numeral 10 denotes a vertical groove provided in the cylindrical outer circumference of the spacer 8 for flow of coolant. The spacer 8 has a thick hollow cylindrical shape in consideration of swelling behavior depending on the irradiation level. In addition, in the case of a high irradiation level, the cylindrical outer peripheral surface may be shaped like a drum.

第3図に示すように、この実施例では中間パツ
ド部11にスペーサ8を配することにより、炉心
群振動時に加わる横荷重により、中性子しやへい
体案内管3の中間パツド部11付近の応力緩和が
図られると共に炉心変形の可能性が小さくなる。
As shown in FIG. 3, in this embodiment, by disposing a spacer 8 in the intermediate pad part 11, the stress near the intermediate pad part 11 of the neutron shield guide tube 3 is reduced due to the lateral load applied during core group vibration. Relaxation is achieved and the possibility of core deformation is reduced.

〔発明の効果〕〔Effect of the invention〕

以上詳細に説明した本発明の中性子しやへい体
によれば下記の効果を奏する。
The neutron shielding body of the present invention described in detail above provides the following effects.

内部しやへい体をスペーサを介して積層嵌合
することにより、対スウエリング上有効に作用
すると共にスペーサ外周部に設けた縦溝により
冷却材流路の確保が図られ、内部しやへい体の
総片より及び偏心による不均一な温度分布が解
消する。
By stacking and fitting the internal shield bodies through a spacer, it is effective in preventing swelling, and the vertical grooves provided on the outer periphery of the spacer ensure a coolant flow path. Non-uniform temperature distribution caused by the whole piece and eccentricity is eliminated.

ナリウムの充填ドレンが確保でき、ガス溜り
及びナトリウム滞留付着による取出交換時の高
放射化レベルの低減が図れる。
A sodium filling drain can be secured, and the high level of activation caused by gas accumulation and sodium retention and adhesion during removal and replacement can be reduced.

スペーサを厚肉中空円筒形としたので中間パ
ツド部の応力緩和及び案内管内面への応力集中
緩和が図れる。
Since the spacer has a thick hollow cylindrical shape, it is possible to relieve stress in the intermediate pad portion and relieve stress concentration on the inner surface of the guide tube.

単純形状化に伴ない製作性の合理化及び向上
が図れる。
As the shape becomes simpler, manufacturability can be streamlined and improved.

以上の結果により中性子しやへい体としての
長寿命化が図れると共に製作性の向上が図れ
る。
As a result of the above results, it is possible to achieve a longer life as a neutron shielding body and to improve manufacturability.

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

第1図は本発明の中性子しやへい体の一実施例
の縦断面図、第2図は第1図のA−A線断面図、
第3図は第2図のB−B線断面図、第4図は従来
の中性子しやへい体の縦断面図である。 1……ハンドリングヘツド、2……エントラン
スノズル、3……案内管、4,9……内部しやへ
い体、5,8……スペーサ、10……縦溝。
FIG. 1 is a longitudinal sectional view of an embodiment of the neutron shielding body of the present invention, FIG. 2 is a sectional view taken along the line A-A in FIG. 1,
3 is a sectional view taken along the line B--B in FIG. 2, and FIG. 4 is a longitudinal sectional view of a conventional neutron shield. DESCRIPTION OF SYMBOLS 1... Handling head, 2... Entrance nozzle, 3... Guide tube, 4, 9... Internal shield body, 5, 8... Spacer, 10... Vertical groove.

Claims (1)

【特許請求の範囲】[Claims] 1 ハンドリングヘツドとエントランスノズルの
間に介在する案内管内に、該案内管内側と所定の
隙間を有する分割型の内部しやへい体を厚肉中空
円筒形スペーサを介して積層嵌合し、該スペーサ
の外径を上記内部しやへい体外径より大きく形成
すると共に外周に複数の縦溝を設けたことを特徴
とする高速増殖炉用中性子しやへい体。
1. A split-type internal shield body having a predetermined gap with the inside of the guide tube is stacked and fitted into the guide tube interposed between the handling head and the entrance nozzle via a thick-walled hollow cylindrical spacer, and the spacer A neutron shield for a fast breeder reactor, characterized in that the outer diameter of the inner shield is larger than the outer diameter of the inner shield, and a plurality of longitudinal grooves are provided on the outer periphery.
JP61077786A 1986-04-04 1986-04-04 Neutron shielding body for fast breeder reactor Granted JPS62233788A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP61077786A JPS62233788A (en) 1986-04-04 1986-04-04 Neutron shielding body for fast breeder reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP61077786A JPS62233788A (en) 1986-04-04 1986-04-04 Neutron shielding body for fast breeder reactor

Publications (2)

Publication Number Publication Date
JPS62233788A JPS62233788A (en) 1987-10-14
JPH03593B2 true JPH03593B2 (en) 1991-01-08

Family

ID=13643653

Family Applications (1)

Application Number Title Priority Date Filing Date
JP61077786A Granted JPS62233788A (en) 1986-04-04 1986-04-04 Neutron shielding body for fast breeder reactor

Country Status (1)

Country Link
JP (1) JPS62233788A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
KR101447434B1 (en) * 2008-09-09 2014-10-13 주성엔지니어링(주) Solar cell, method and apparatus for fabrication of the solar cell

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN102176328B (en) * 2011-01-27 2013-01-23 郑州双辐射线防护器材有限公司 Neutron protective body plug and material thereof

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
KR101447434B1 (en) * 2008-09-09 2014-10-13 주성엔지니어링(주) Solar cell, method and apparatus for fabrication of the solar cell

Also Published As

Publication number Publication date
JPS62233788A (en) 1987-10-14

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