JPS607386A - Upper mechanism of core of fast breeder reactor - Google Patents
Upper mechanism of core of fast breeder reactorInfo
- Publication number
- JPS607386A JPS607386A JP58114229A JP11422983A JPS607386A JP S607386 A JPS607386 A JP S607386A JP 58114229 A JP58114229 A JP 58114229A JP 11422983 A JP11422983 A JP 11422983A JP S607386 A JPS607386 A JP S607386A
- Authority
- JP
- Japan
- Prior art keywords
- core
- reactor
- guide tube
- fast breeder
- plug
- 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
- 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]
本発明は液体ナトリウムのような))り体金属を冷却材
として使用する高速増作“1炉の炉心」一部12M 4
f4に関する。[Detailed Description of the Invention] [Technical Field of the Invention] The present invention relates to a high-speed expansion "1 reactor core" part 12M 4 using solid metal such as liquid sodium as a coolant.
Regarding f4.
[発明の技術的背景とその問題点]
高速増殖炉は冷却材として液(ホナ1−リウムのような
熱転率の高い液体金属を採用している。[Technical background of the invention and its problems] A fast breeder reactor uses a liquid (a liquid metal with a high heat conversion rate such as honalium) as a coolant.
第1図は、従来の高速増殖炉の縦断面図てあり同図に示
すにうに、原子炉容器′1は冷7JI月1j給管2およ
び冷fJI材流出管3を備え内部に冷JJI 444か
収容され−Cいる。この1皇子炉容器1内には支111
Ii4造物5に支持されて炉心6が設置されるととb
(、Z、原子炉容器1の上部開口部に間転プラグ7が
設(]られ、この回転プラグ7を貫通して炉心上部機構
8が前記炉心6の上方に重設されている。この炉心上部
機(148には、複数重の制till捧駆動敗構采内管
9と、炉心6の燃わ1集合体各々の出口流!i)、出口
温度を測定する流量泪、温度計を内包づる多数の51装
ウェル10が5父回されている。31、Iど回中入ブラ
グ7と冷却材4との間の空間にはカバーガス12が充填
されている。なd3、炉心6の出口の冷Nj月流れを整
流するために整流格子板11が前記案内管9の下端に配
設されている。FIG. 1 is a longitudinal sectional view of a conventional fast breeder reactor. As shown in the figure, the reactor vessel '1 is equipped with a cold JJI 444 feed pipe 2 and a cold fJI material outflow pipe 3. It is accommodated in -C. There are 111 supports in this 1 Prince reactor vessel 1.
When the core 6 is installed supported by the Ii4 structure 5, b
(,Z, An intermittent plug 7 is provided at the upper opening of the reactor vessel 1 (), and a core upper mechanism 8 is superimposed above the core 6 through the rotary plug 7. The upper machine (148 includes multiple till control drive structure internal tubes 9, outlet flow of each burner assembly of the core 6!i), a flow rate for measuring the outlet temperature, and a thermometer. A large number of 51 wells 10 are installed 5 times.The space between the plug 7 and the coolant 4 is filled with cover gas 12. A rectifying grid plate 11 is disposed at the lower end of the guide tube 9 to rectify the cold Nj flow at the outlet.
また炉心上部11 <M 8は、第2図に拡大して示さ
れるように゛、円筒状本体13の内部に扁平な案内板1
5が設けられ、これに制御棒駆動機(111を収納する
制御棒案内管9が装着されるとともに、円筒状本体13
の上部に連接された大径の継胴部14上縁に、遮蔽蓋体
16が複数の取付部(117ににり固着された(14造
となっている。In addition, the core upper part 11<M8 has a flat guide plate 1 inside the cylindrical main body 13, as shown in an enlarged view in FIG.
5 is provided, to which a control rod guide tube 9 that houses a control rod drive machine (111) is attached, and a cylindrical main body 13
The shielding lid 16 is fixed to the upper edge of the large-diameter joint body 14 connected to the upper part of the body by means of a plurality of attachment parts (117).
前記計装ウェル1oは、炉心上部機構8の下端から円筒
状本体13内で数組に束ねられ各々計装ウェル某内管1
8の内部を通り炉心上部機構8の上方へ導かれている。The instrumentation wells 1o are bundled into several sets within the cylindrical body 13 from the lower end of the core upper mechanism 8, and each instrumentation well has a certain inner pipe 1.
8 and is guided above the core upper mechanism 8.
このような炉心上部は構8においては、例えば計装ウェ
ル10等が破損した場合この補修のために炉心上部は横
8全体を回転プラグ7から取外づ必要がある。甜装ウェ
ル10内の流量泪 、ン品度計は通常故障時の交換のた
め計装ウェル19から引扱き可能であるが、万一引抜き
がひきないどガ]心上部機構8全体を取外ゴことになる
。このように機器破損または故障時に炉心上部1m i
M 8全体を引抜きメンテナンス作業を行うようになる
と、その作業型は増大して修復するまでには長時間かか
り、このためプラン1〜運転稼動率に影v!lを勺える
どともに、作業中の被曝量も多い等の不具合が/lヂる
ことになる。In such an upper core structure 8, if the instrumentation well 10 or the like is damaged, for example, it is necessary to remove the entire lateral 8 of the upper core from the rotating plug 7 for repair. The quality meter can normally be removed from the instrumentation well 19 for replacement in the event of a failure, but in the unlikely event that it fails to pull out, the entire center upper mechanism 8 can be removed. It's going to be a big deal. In this way, in the event of equipment damage or failure, the upper 1 m i
When the entire M8 is pulled out and maintenance work is performed, the work size increases and it takes a long time to repair it, which affects Plan 1 - operation availability v! In addition to this, there are also problems such as high radiation exposure during work.
[発明の目的]
本発明は、上記事情に鑑みC’+1されたもので、その
目的は、計装ウェル等の破714 nlのメンテナンス
性を大幅に向]−シた高j虫増殖炉の炉心−1一部1m
4ft1+を提供づるにある。[Objective of the Invention] The present invention has been made C'+1 in view of the above circumstances, and its purpose is to significantly improve the maintainability of instrumentation wells, etc. Core-1 part 1m
We offer 4ft1+.
[発明の概要]
本発明は、上記目的を達成するために原子炉容器の上部
間口部を閉塞する回転プラグを肖通し、前記原子炉容器
内の炉心の上方に垂設される畠速増殖炉の炉心上部機構
において、前記原子炉容器内に配設された燃料集合体お
よび制御棒から成る炉心の配列と対応した多数の計装ウ
ェル案内筒iJ3よひ制御棒駆動機4ia案内管からな
る炉心上部本体を前記炉心上方に設け、かつ前記各案内
管の上部には各々の案内管単独に取外しが可能なしゃへ
いプラグを設けるように構成したものである。そして前
記各案内管は断面六角形1円形あるいはその池適当な形
状の柱状管を有するものである。[Summary of the Invention] In order to achieve the above object, the present invention provides a Hatake breeder reactor that is installed vertically above a core in a reactor vessel through a rotary plug that closes the upper opening of the reactor vessel. In the upper core mechanism of the reactor, the core is composed of a large number of instrumentation well guide tubes iJ3 and control rod drive machines 4ia guide tubes corresponding to the core arrangement consisting of fuel assemblies and control rods arranged in the reactor vessel. An upper main body is provided above the reactor core, and a shielding plug is provided above each of the guide tubes and is detachable from each guide tube. Each of the guide tubes has a hexagonal cross section, a circular cross section, or a columnar tube having an appropriate shape.
[発明の実施例] 本発明の一実施例を図面を参照して説明Jる。[Embodiments of the invention] An embodiment of the present invention will be described with reference to the drawings.
なお第1図および第2図と同一1鮨所には同一符号をI
jjJ l、て説明する。The same 1 sushi place as in Figures 1 and 2 is designated with the same code.
jjJ l, I will explain.
第3図は、本発明に係る炉心上部機構の縦断面図である
。同図において、回転プラグ7は図示しない炉心、冷I
J材4およびカバーガス12等を収容した図示しない原
子炉容器の上部開口部に設【プられており、この回転プ
ラグ7の中央部を貫通して炉心上部BM Ji/+ 8
が図示しない炉心の上方に垂設されている。FIG. 3 is a longitudinal sectional view of the upper core mechanism according to the present invention. In the same figure, the rotary plug 7 is connected to a reactor core (not shown), a cold I
It is installed in the upper opening of the reactor vessel (not shown) that accommodates J material 4, cover gas 12, etc., and penetrates through the center of this rotary plug 7 to connect the upper core BM Ji/+ 8.
is installed vertically above the reactor core (not shown).
この炉心上部機構8は、複数本の制御棒駆動(幾IM
19を支持案内するための制御棒駆動機構案内管9おJ
:び炉心を構成づ”る各燃i!′31集合体の出口流量
および出口温度を測定J−るための流m it (13
J、ひ渇度泪を収容づる多数(通常は数百本)の甜装ウ
ェル10を支持案内覆るためのH1装つJ−ル案内管1
8からなる炉心上部本体20ど、流量、渇1α測定条件
から要求される炉心用L](1)冷月1月流れを整流づ
るために設【プられる整流板11ど、各h1装ウェル案
内管18の上方空間に各々単独に設(Jられる多数のし
ゃへいプラグ21どから114成され(いる。This core upper mechanism 8 has a plurality of control rod drives (several IM
Control rod drive mechanism guide tube 9 for supporting and guiding 19
Flow m it (13
J-L guide tube 1 equipped with H1 for supporting, guiding and covering a large number (usually several hundred) of welding wells 10 that accommodate thirsty wells.
8, the core upper body 20, etc., the flow rate, the core L required from the thirst 1α measurement conditions; (1) the rectifying plate 11 installed to rectify the cold flow; There are 114 shielding plugs 21, each of which is individually installed in the space above the pipe 18.
第4図は第3図の八−へ線に沿う炉心−1一部本体の部
分断面図であり、制御棒駆動機構案内管9ど計装ウェル
10を収容する4装ウェル案内↑゛118はそれぞれ円
管、六角性の組合l!(ある。さらに、この断面構造は
第5図に示覆ごとく制1111 (’i・案内?−9を
六角へとしてもよい。また、その他制御忰案内管9およ
び計装ウェル案内↑へ18を共に円?τ構成にしてもよ
い。FIG. 4 is a partial sectional view of a part of the main body of the reactor core 1 taken along the line 8 in FIG. A combination of circular tubes and hexagons, respectively! (In addition, this cross-sectional structure can be changed to a hexagonal shape as shown in FIG. Both may have a circular ?τ configuration.
第6図は第3図のし15へいプラグ21回りの拡大断面
図で、4装ウェル案内管18の上端には各々単独にし1
bへいプラグ21が設【ノられ、このし−Ibへいプラ
グ21に計装ウェル10が貫通している。FIG. 6 is an enlarged cross-sectional view of the area around the plug 21 in FIG.
A b-hole plug 21 is provided, and an instrumentation well 10 passes through the Ib-hole plug 21.
第7図は第3図の整流格子板11部分の拡大断面図で制
御棒案内管9の下端は整流格子板11と一体組立414
造である。FIG. 7 is an enlarged cross-sectional view of the rectifying grid plate 11 portion in FIG.
It is constructed.
以上のように構成された本発明の炉心上部機構において
は、計装ウェル10が損傷した際の補修、交換作業には
損傷した当該計装ウェル案内性18の上部に設けられた
しヤへいプラグ21だけを計装つ1ル10と一体で引扱
くことができるので、メンテナンスを行う部分は、この
当該部分だ()で淡みメンテナンスづる範囲を局限する
ことができる。In the upper core mechanism of the present invention configured as described above, when the instrumentation well 10 is damaged, repair or replacement work is carried out using a drain plug provided above the damaged instrumentation well guide 18. Since only the instrument 21 can be handled as one unit with the instrument 10, the maintenance area can be limited to this part ().
しかも、しをへいプラグ21の引抜時に使用づる放射線
防御キャスクは小型で済みいずれのしやへいプラグにも
兼用することができる。Moreover, the radiation protection cask used when pulling out the shield plug 21 is small and can be used for any shield plug.
また、計装ウェル案内管18は各燃料集合体に1対1に
対応してその上方に垂設されているため他の計装システ
ム、例えば燃料ビン破損を検出Jる破損燃オ′」検出計
を設置すれば各燃利集合体毎に単独にその破損が検出可
能になる専科々の用i1に対して有効なものとなる。In addition, since the instrumentation well guide pipe 18 is vertically installed above each fuel assembly in one-to-one correspondence, other instrumentation systems, such as those used to detect fuel bottle damage, can also be used to detect damaged combustion. If a meter is installed, damage can be detected independently for each fuel assembly, making it effective for specialized applications i1.
さらに、地震時にお【プる制御棒挿入1り畦土からも炉
心上部1a lf4は、水平方向地震時その]一端の変
位相を極力少なくづる必要がある。このため水\11方
向荷重に対づる炉心上部機構の剛性を高くづる必要があ
り、本発明による炉心上部機構の炉心上部本体は断面全
体に渡り六角形状管おにび円形状管の組合せ構造である
から、従来の外161円質(14j閏に比べその剛性を
遥かに高くづることがて゛きる。Furthermore, it is necessary to minimize the phase shift of one end of the upper core 1a lf4 from the ridged ground during an earthquake when the control rods are inserted in the horizontal direction. For this reason, it is necessary to increase the rigidity of the core upper mechanism against the water\11 direction load, and the core upper body of the core upper mechanism according to the present invention has a combination structure of hexagonal tubes and circular tubes over the entire cross section. Because of this, it is possible to make the rigidity much higher than the conventional outer 161-yen (14-jen).
[発明の効果]
本発明ににれば、メンテナンス部を局限化−Cきること
から作業員の被曝■を(氏減りるどとしに各部のメンテ
ナンス時の作業量9作業明間か少く1くでき、したがっ
てプラント稼働率を大幅tJ上41’ることがCぎる。[Effects of the Invention] According to the present invention, since the maintenance department is localized and the radiation exposure of the workers is reduced, the amount of work during maintenance of each part is reduced by 9 hours or less. Therefore, it is possible to significantly increase the plant operating rate by 41'.
また、炉心上部機構の水平方向荷重に対りる剛性が高い
ため、地震時の制till枠挿入性能はその信頼性を大
きく、しかも、独立して設りた4装つJ−構案内管は破
損燃料検出器等の他の削具システムに対してもそのまま
有効に利用できる等の種々の効果を有する。In addition, because the upper core mechanism has high rigidity against horizontal loads, the control frame insertion performance during earthquakes is highly reliable, and the four independently installed J-structure guide pipes are It has various effects such as being able to be effectively used as is for other cutting tool systems such as a damaged fuel detector.
第1図は従来の高速増殖炉の縦断面図、第2図は第1図
の部分拡大断面図、第3図は本発明の一実施例の縦断面
図、第4図は第3図のA−A線に沿う横断面図、第5図
は第4図の他の実施例の横断面図、第6図は第3図のし
ゃへいプラグ部分の拡大n面図、第7図は第3図の整流
格子板部分の拡大断面図である。
1・・・原子力j容器 4・・・冷却材6・・・炉心
7・・・回転プラグ
8・・・炉心上部機構
9・・・制御棒駆動□構案内管
10・・・計装ウェル 11・・・整流格子板12・・
・jjバーガス 13・・・円筒上本体1 G ・・・
遮蔽蓋 1本
18・・・計装つ1ル案内筈
19・・・制御棒駆動1幾椙 20・・・炉心上部本体
21・・・しゃへいプラグ
代J睨(ブl理士則近憲佑((J
第 1 図
か1名)
第 2 図
第3図
第4図
第 5 図
第 6 図
第 7 図
/(?
−一//FIG. 1 is a longitudinal sectional view of a conventional fast breeder reactor, FIG. 2 is a partially enlarged sectional view of FIG. 1, FIG. 3 is a longitudinal sectional view of an embodiment of the present invention, and FIG. FIG. 5 is a cross-sectional view of another embodiment shown in FIG. 4, FIG. 6 is an enlarged n-side view of the shielding plug shown in FIG. 3, and FIG. 7 is a cross-sectional view taken along line A-A. FIG. 3 is an enlarged cross-sectional view of the rectifying grid plate portion shown in the figure. 1...Nuclear J vessel 4...Coolant 6...Core
7... Rotating plug 8... Core upper mechanism 9... Control rod drive □ Structure guide tube 10... Instrumentation well 11... Rectifier grid plate 12...
・jj bargas 13...Cylindrical upper body 1 G...
1 shielding lid 18...Instrumentation 1 guide 19...Control rod drive 1 number 20...Core upper body 21...Shieling plug cost (J Figure 1 or 1 person) Figure 2 Figure 3 Figure 4 Figure 5 Figure 6 Figure 7/(? -1//
Claims (2)
貫通し、前記原子炉容器内の炉心の上方に垂設される高
速増殖炉の炉心上部機4j4において、前記原子炉容器
内に配設された燃料集合体および制御棒から成る炉心の
配列と対応した多数の案内管からなる炉心上部本体を前
記炉心上方に設け、かつ前記各案内管の上部には各々の
案内管単独に取外しが可能なしゃへいプラグを設けるよ
うに構成したことを特徴とする高速増殖炉の炉心上部機
構。(1) In the upper core machine 4j4 of a fast breeder reactor, which passes through a rotating plug that closes the upper opening of the reactor vessel and is installed vertically above the reactor core in the reactor vessel, A core upper body consisting of a large number of guide tubes corresponding to the array of the installed fuel assemblies and control rods is provided above the reactor core, and each guide tube can be individually removed at the upper part of the guide tube. An upper core mechanism of a fast breeder reactor, characterized in that it is configured to be provided with a possible shielding plug.
案内管である特許請求の範囲第1項記載の高速増殖炉の
炉心上部機構。 く3)案内管は断面六角形または円形の柱状管である特
許請求の範囲第1項記載の高速増殖炉の炉心上部機構。(2) The upper core mechanism of a fast breeder reactor according to claim 1, wherein the guide tube is a cutting tool well guide tube and a control rod drive mechanism guide tube. 3) The upper core mechanism of a fast breeder reactor according to claim 1, wherein the guide tube is a columnar tube with a hexagonal or circular cross section.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58114229A JPS607386A (en) | 1983-06-27 | 1983-06-27 | Upper mechanism of core of fast breeder reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58114229A JPS607386A (en) | 1983-06-27 | 1983-06-27 | Upper mechanism of core of fast breeder reactor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS607386A true JPS607386A (en) | 1985-01-16 |
Family
ID=14632471
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP58114229A Pending JPS607386A (en) | 1983-06-27 | 1983-06-27 | Upper mechanism of core of fast breeder reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS607386A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US10322003B2 (en) | 2015-06-30 | 2019-06-18 | Depuy Ireland Unlimited Company | Modular taper seal and method for orthopaedic prosthetic hip assembly |
-
1983
- 1983-06-27 JP JP58114229A patent/JPS607386A/en active Pending
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US10322003B2 (en) | 2015-06-30 | 2019-06-18 | Depuy Ireland Unlimited Company | Modular taper seal and method for orthopaedic prosthetic hip assembly |
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