JPH0132478B2 - - Google Patents

Info

Publication number
JPH0132478B2
JPH0132478B2 JP54137823A JP13782379A JPH0132478B2 JP H0132478 B2 JPH0132478 B2 JP H0132478B2 JP 54137823 A JP54137823 A JP 54137823A JP 13782379 A JP13782379 A JP 13782379A JP H0132478 B2 JPH0132478 B2 JP H0132478B2
Authority
JP
Japan
Prior art keywords
tube
rectifier
mounting plate
core
insulating ring
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
Application number
JP54137823A
Other languages
Japanese (ja)
Other versions
JPS5661690A (en
Inventor
Shigeru Kishi
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
Original Assignee
Tokyo Shibaura Electric 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 Tokyo Shibaura Electric Co Ltd filed Critical Tokyo Shibaura Electric Co Ltd
Priority to JP13782379A priority Critical patent/JPS5661690A/en
Publication of JPS5661690A publication Critical patent/JPS5661690A/en
Publication of JPH0132478B2 publication Critical patent/JPH0132478B2/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

  • Monitoring And Testing Of Nuclear Reactors (AREA)

Description

【発明の詳細な説明】 本発明は原子炉の炉心上部機構の構成部品であ
る炉心上部整流装置の構造改良に関するものであ
る。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a structural improvement of a core upper rectifier which is a component of the upper core mechanism of a nuclear reactor.

一般にナトリウム冷却高速増殖炉においては、
運転監視あるいは異常診断のため各炉心燃料出口
部に温度計や流量計等の炉心出口計装を設置し、
これを炉心上部機構で支持する構造が採用されて
いる。
In general, in sodium-cooled fast breeder reactors,
Core outlet instrumentation such as thermometers and flow meters is installed at each core fuel outlet for operation monitoring or abnormality diagnosis.
A structure is adopted in which this is supported by the upper core mechanism.

原子炉全体での位置関係を第1図に示す。原子
炉容器1の中に炉心2があり、その真上に炉心上
部機構3があつてしやへいプラグ4に支えられて
いる。炉心上部機構3の中には制御棒駆動機構5
(以下CRDと略す)と、温度計、流量計等を収納
した多数の計装ウエル6があつて、計装ウエル下
端囲りには炉心出口計装を精度よく行なうための
炉心上部整流装置7が設置されている。
Figure 1 shows the positional relationship of the entire reactor. There is a reactor core 2 in a reactor vessel 1, and a core upper mechanism 3 is placed directly above it and supported by a shield plug 4. A control rod drive mechanism 5 is located inside the core upper mechanism 3.
(hereinafter abbreviated as CRD), there are many instrumentation wells 6 that house thermometers, flowmeters, etc., and around the lower end of the instrumentation well there is a core upper rectifier 7 for accurate core exit instrumentation. is installed.

ところで、従来の炉心上部整流装置、第2図に
示すように各炉心燃料(図示せず)の真上に設置
された整流筒8と、これを保持る整流筒取付板9
と、整流筒取付板を懸下する支持パイプ10と支
持パイプ内にはめ込まれCRDを案内するCRD案
内管11と、構造物の熱衝撃応力を緩和するため
のサーマルライナ12とから成立つている。整流
筒8の内部には計装ウエル6の下端部が挿入され
ており、整流筒により整流されかつ隣接した炉心
燃料あるいは制御棒集合体から隔離された流れの
温度や流速を測定できるようになつている。この
整流筒8は炉心燃料直上での厳しい温度ゆらぎ条
件に耐えるため、高温強度が優れた材料Alloy
718を使用しており、整流筒取付板9との結合は
異材溶接を避けるため、取付板9の穴に整流筒8
を嵌合させネジ結合で取付板9をかさみ込む構造
を採用している。
By the way, as shown in FIG. 2, the conventional core upper rectifier includes a rectifier tube 8 installed directly above each core fuel (not shown) and a rectifier tube mounting plate 9 that holds this.
It consists of a support pipe 10 for suspending the rectifying cylinder mounting plate, a CRD guide pipe 11 fitted into the support pipe for guiding the CRD, and a thermal liner 12 for relieving the thermal shock stress of the structure. The lower end of the instrumentation well 6 is inserted into the straightening tube 8, so that the temperature and flow velocity of the flow rectified by the straightening tube and isolated from the adjacent core fuel or control rod assembly can be measured. ing. In order to withstand the severe temperature fluctuation conditions directly above the core fuel, this straightening tube 8 is made of alloy material with excellent high-temperature strength.
718 is used, and in order to avoid dissimilar metal welding when joining the rectifier tube mounting plate 9, the rectifier tube 8 is inserted into the hole of the mounting plate 9.
A structure is adopted in which the mounting plate 9 is fitted over the mounting plate 9 by screw connection.

しかし、整流筒8内には炉心燃料から流出した
高温ナトリウム20が流れるのに対し、CRD案
内管11内には制御棒集合体から流出した低温ナ
トリウム21が流れるので、整流筒取付板9の整
流筒貫通穴とCRD案内管貫弾穴との間には大き
な温度差が生じ、高い熱応力のためクリープ疲労
破損する恐れがあつた。
However, while the high-temperature sodium 20 flowing out from the core fuel flows into the straightening tube 8, the low-temperature sodium 21 flowing out from the control rod assembly flows into the CRD guide tube 11. There was a large temperature difference between the cylinder through hole and the CRD guide tube through hole, and there was a risk of creep fatigue failure due to high thermal stress.

本発明は上記点に鑑してなされたもので、整流
装置の構造を改良することによつて整流筒取付板
の熱応力を低減させ、強度的に十分保証された整
流装置を得るとが目的である。
The present invention has been made in view of the above points, and an object of the present invention is to reduce the thermal stress of the rectifying tube mounting plate by improving the structure of the rectifying device, and to obtain a rectifying device whose strength is sufficiently guaranteed. It is.

以下図面を参照して本発明の一実施例を説明す
る。第3図、第4図は第2図に示した従来案とほ
ぼ同一構成であるが、整流筒8と整流筒取付板9
との間に整流筒を囲むように別体構造の断熱リン
グ13を設ける点が異なつている。この断熱リン
グ13は取付板9と同じ材質、同じ板厚であり、
また取付板9の穴径が下側で小さくなるよう穴に
段が付いているのでその段付部で断熱リング13
の重量を支えるようになつている。つまり断熱リ
ング13は整流筒取付板9に機械的にはめ合され
る構造になつている。従つて両者の間には微小な
間隙が存在するので各々独立に熱膨張することが
できる。
An embodiment of the present invention will be described below with reference to the drawings. 3 and 4 have almost the same configuration as the conventional plan shown in FIG.
The difference is that a heat insulating ring 13 of a separate structure is provided to surround the rectifying cylinder between the two. This insulation ring 13 is made of the same material and has the same thickness as the mounting plate 9,
In addition, since the hole in the mounting plate 9 is stepped so that the hole diameter becomes smaller on the lower side, the insulating ring 13
It is designed to support the weight of In other words, the heat insulating ring 13 is mechanically fitted to the rectifier tube mounting plate 9. Therefore, since a minute gap exists between the two, each can thermally expand independently.

ここで断熱リングは取付板と同じ材料であり、
熱を遮断する機能は無いが取付板と別体構造に設
けることによつて熱歪および熱応力の影響を断ち
切る作用を有するので、本明細書においてはこの
名称を用いている。
Here the insulation ring is the same material as the mounting plate,
This name is used in this specification because although it does not have the function of blocking heat, it has the effect of cutting off the effects of thermal strain and stress by providing it in a separate structure from the mounting plate.

本願においては上記した通り整流筒の周囲に断
熱リングを設け、この断熱リングの周囲に間隙を
おいて整流筒取付板を設けた構成としている。従
つて断熱リングおよび整流筒取付板はそれぞれあ
る程度自由に熱膨張し、また熱変形することによ
つて熱応力を軽減することができる。
In the present application, as described above, a heat insulating ring is provided around the rectifying tube, and a rectifying tube mounting plate is provided around the heat insulating ring with a gap therebetween. Therefore, the heat insulating ring and the rectifier tube mounting plate can thermally expand freely to some extent and deform thermally, thereby reducing thermal stress.

なお、断熱リングの機質は取付板と異なつてい
てもさしつかえなく、熱膨張差の問題がなければ
できる限り熱伝導率の小さい材料が望ましい。ま
た、断熱リングを中空にして、その中を真空ある
いは不活性ガスとして、熱伝導率を下げることも
可能である。先の実施例では整流筒まわりに断熱
リングを設けたが、CRD案内管の周囲に断熱リ
ングを設けてもよいし、またその双方に設けても
よい。断熱リング自身の熱応力を下げるため、こ
れを多層リングに分割してもよい。
Note that the nature of the heat insulating ring may be different from that of the mounting plate, and it is desirable to use a material with as low thermal conductivity as possible as long as there is no problem with the difference in thermal expansion. It is also possible to lower the thermal conductivity by making the heat insulating ring hollow and filling it with vacuum or inert gas. In the previous embodiment, a heat insulating ring was provided around the rectifying cylinder, but a heat insulating ring may be provided around the CRD guide tube, or may be provided on both sides. To reduce the thermal stress of the insulating ring itself, it may be divided into multilayer rings.

以上説明のように、本発明の炉心上部整流装置
は、整流筒と整流筒取付板との間に別体構造に断
熱リングを設けることにより、整流筒取付板に生
ずる温度差を小さくすることができる。
As explained above, the core upper rectifier of the present invention can reduce the temperature difference that occurs in the rectifier tube mounting plate by providing a separate heat insulating ring between the rectifier tube and the rectifier tube mounting plate. can.

すなわち、第4図において、従来の温度差が
T1―T3であるのに対し、本発明では温度差がT2
―T3と小さくなる。熱応力は一般にσ=
αEΔT/2(1―ν)(ここでσ:熱応力、α:熱膨張
係 数、E:縦弾性係数、ν:ボアソン比、ΔT:温
度差)で計算され、σ,E,νはほぼ一定なの
で、σは板厚等に関係なく、ΔTに比例すること
になる。したがつて、温度差が小さくなければ、
これに比例して熱応力も低くなり、強度的に十分
保証された整流装置を得ることができる。
In other words, in Figure 4, the conventional temperature difference is
T 1 - T 3 , whereas in the present invention the temperature difference is T 2
- T becomes smaller than 3 . Thermal stress is generally σ=
Calculated as αEΔT/2(1−ν) (where σ: thermal stress, α: coefficient of thermal expansion, E: modulus of longitudinal elasticity, ν: Boisson's ratio, ΔT: temperature difference), and σ, E, and ν are almost constant. Therefore, σ is proportional to ΔT, regardless of plate thickness, etc. Therefore, unless the temperature difference is small,
Thermal stress also decreases in proportion to this, making it possible to obtain a rectifying device with sufficient strength guaranteed.

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

第1図は原子炉全体立面図、第2図は従来の炉
心上部整流装置を示す立面図、第3図は本発明の
一実施例を示す立面図、第4図は本発明の一実施
例を示す平面図である。 7……炉心上部整流装置、8……整流筒、9…
…整流筒取付板、10……支持パイプ、11……
CRD案内管、13……断熱リング。
Fig. 1 is an elevational view of the entire reactor, Fig. 2 is an elevational view showing a conventional upper core rectifier, Fig. 3 is an elevational view showing an embodiment of the present invention, and Fig. 4 is an elevational view showing an embodiment of the present invention. FIG. 2 is a plan view showing an example. 7... Core upper rectifier, 8... Rectifier tube, 9...
... Rectifier cylinder mounting plate, 10 ... Support pipe, 11 ...
CRD guide pipe, 13...Insulation ring.

Claims (1)

【特許請求の範囲】[Claims] 1 制御棒駆動機構用案内管と、そのまわりに配
列された整流筒とを保持する剛な管板構造を備え
た炉心上部整流装置において、制御棒駆動機構用
案内管もしくは整流筒と管板との間に別体構造の
断熱リングを設けたことを特徴とする炉心上部整
流装置。
1. In a core upper rectifier equipped with a rigid tube plate structure that holds a control rod drive mechanism guide tube and a rectifier tube arranged around it, the control rod drive mechanism guide tube or rectifier tube and tube plate are A reactor core upper rectifier characterized by having a separate structure heat insulating ring provided between the core.
JP13782379A 1979-10-26 1979-10-26 Flow regulator in upper core Granted JPS5661690A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP13782379A JPS5661690A (en) 1979-10-26 1979-10-26 Flow regulator in upper core

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP13782379A JPS5661690A (en) 1979-10-26 1979-10-26 Flow regulator in upper core

Publications (2)

Publication Number Publication Date
JPS5661690A JPS5661690A (en) 1981-05-27
JPH0132478B2 true JPH0132478B2 (en) 1989-06-30

Family

ID=15207676

Family Applications (1)

Application Number Title Priority Date Filing Date
JP13782379A Granted JPS5661690A (en) 1979-10-26 1979-10-26 Flow regulator in upper core

Country Status (1)

Country Link
JP (1) JPS5661690A (en)

Family Cites Families (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS54130788A (en) * 1978-03-31 1979-10-11 Toshiba Corp Nuclear reactor

Also Published As

Publication number Publication date
JPS5661690A (en) 1981-05-27

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