JPS6220519B2 - - Google Patents
Info
- Publication number
- JPS6220519B2 JPS6220519B2 JP54083480A JP8348079A JPS6220519B2 JP S6220519 B2 JPS6220519 B2 JP S6220519B2 JP 54083480 A JP54083480 A JP 54083480A JP 8348079 A JP8348079 A JP 8348079A JP S6220519 B2 JPS6220519 B2 JP S6220519B2
- Authority
- JP
- Japan
- Prior art keywords
- control rod
- coolant
- flow rate
- rod element
- reactor
- 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
Links
- 239000002826 coolant Substances 0.000 claims description 29
- 230000007246 mechanism Effects 0.000 claims description 21
- 239000008358 core component Substances 0.000 description 5
- 239000000446 fuel Substances 0.000 description 5
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 description 4
- 230000037431 insertion Effects 0.000 description 4
- 238000003780 insertion Methods 0.000 description 4
- 229910052708 sodium Inorganic materials 0.000 description 4
- 239000011734 sodium Substances 0.000 description 4
- 230000002411 adverse Effects 0.000 description 2
- 230000000903 blocking effect Effects 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 230000009257 reactivity Effects 0.000 description 2
- 230000008646 thermal stress Effects 0.000 description 2
- 230000009471 action Effects 0.000 description 1
- 230000000712 assembly Effects 0.000 description 1
- 238000000429 assembly Methods 0.000 description 1
- 230000036541 health Effects 0.000 description 1
- 230000001771 impaired effect Effects 0.000 description 1
- 230000002452 interceptive effect Effects 0.000 description 1
- 230000000149 penetrating effect Effects 0.000 description 1
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)
Description
【発明の詳細な説明】
本発明は、高速増殖炉に使用される制御棒集合
体に係り、特に、上・下に可動な制御棒と炉心支
持板に固定される制御棒案内管との間に冷却材流
量を制限する伸縮可能な流量調整機構を設けた制
御棒集合体に関する。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a control rod assembly used in a fast breeder reactor, and in particular, to a control rod assembly used in a fast breeder reactor. This invention relates to a control rod assembly equipped with an extendable flow rate adjustment mechanism that limits the flow rate of coolant.
従来、制御棒と制御棒案内管との隙間（外側流
路）には、制御棒が原子炉の反応度調節等で移動
しても常に流量を制限する様な流量調整機構は設
置されていなかつた。従つて、制御棒内を流れ、
制御棒要素から熱を奪つて高温となつた冷却材
と、制御棒の外側流路と流れる低温の冷却材とが
制御棒出口付近で合流し、制御棒出口温度として
は低い温度となつていた。このため、隣接する燃
料集合体出口冷却材温度との間に大きな差が生
じ、炉心上方に設置される炉心上部機構の整流格
子部には、狭い範囲に大きな温度差がつくため大
きな熱応力を発生させることとなり、原子炉の健
全性に悪影響を与えていた。 Conventionally, there was no flow rate adjustment mechanism installed in the gap between the control rod and the control rod guide tube (outer flow path) that would always limit the flow rate even if the control rod moved to adjust the reactivity of the reactor. Ta. Therefore, the flow inside the control rod,
The high-temperature coolant that took heat from the control rod elements and the low-temperature coolant flowing through the control rod's outer flow path merged near the control rod exit, resulting in a low control rod exit temperature. . As a result, a large temperature difference occurs between the outlet coolant temperature of adjacent fuel assemblies, and the rectifying grid section of the upper core mechanism installed above the reactor core is subject to large thermal stress due to the large temperature difference in a narrow range. This had an adverse effect on the health of the reactor.
本発明は、上記問題点に対してなされたもの
で、制御棒出口冷却材温度を上昇させ隣接の燃料
集合体出口冷却材温度との温度差を制御棒の位置
にかかわらず常に小さく出来かつ制御棒動作のス
ムースな制御棒集合体を提供することを目的とし
ている。 The present invention has been made to solve the above-mentioned problems, and it is possible to increase the temperature of the control rod outlet coolant, thereby constantly reducing the temperature difference between the control rod outlet coolant temperature and the outlet coolant temperature of an adjacent fuel assembly, regardless of the position of the control rod. The purpose is to provide a control rod assembly with smooth rod movement.
以下、図面を参照して本発明の例について説明
する。 Examples of the present invention will be described below with reference to the drawings.
始めに、本発明の構成を説明する。 First, the configuration of the present invention will be explained.
第１図は原子炉の縦断面図である。この図にお
いて符号１は、原子炉容器、２は原子炉容器１の
下部に設置される原子炉容器入口ノズルを示す。
原子炉容器１の内部には制御棒集合体９、燃料集
合体１０等の炉心構成要素が収納され、この炉心
構成要素を搭載、支持するために炉心支持板３が
設けられる。４はこれら炉心構成要素を横方向に
支持する炉心槽であり、炉心構成要素の上方には
炉心上部機構５がしやへいプラング７を貫通して
設置される。また炉心上部機構５の下部には冷却
材の流れを調整する整流格子６が設置される。さ
らに炉心内を通過した冷却材が流出するための原
子炉容器出口ノズル８が、前記原子炉容器に取り
付けられる。 FIG. 1 is a longitudinal cross-sectional view of the nuclear reactor. In this figure, reference numeral 1 indicates a reactor vessel, and 2 indicates a reactor vessel inlet nozzle installed at the bottom of the reactor vessel 1.
Reactor core components such as a control rod assembly 9 and a fuel assembly 10 are housed inside the reactor vessel 1, and a core support plate 3 is provided to mount and support these core components. Reference numeral 4 denotes a core barrel that supports these core components in the lateral direction, and a core upper mechanism 5 is installed above the core components by penetrating through a shield plunger 7. Further, a rectifying grid 6 is installed at the bottom of the upper core mechanism 5 to adjust the flow of coolant. Furthermore, a reactor vessel outlet nozzle 8 is attached to the reactor vessel, through which the coolant that has passed through the reactor core flows out.
尚、前記制御棒集合体９は、周囲を燃料集合体
１０により包囲される配置となる。 The control rod assembly 9 is surrounded by a fuel assembly 10.
第２図は本発明の一実施例による制御棒集合体
９である。この制御棒集合体９は炉心支持板に挿
入され冷却材を流入させる下部のエントランスノ
ズル１１と、制御棒要素１５を内部に収納する制
御棒案内管１２と、制御棒案内管１２上方に連設
されるハンドリングヘツド１３とから構成され
る。また、前記制御棒要素１５を制御棒駆動機構
で移動させるために連結部材１６を設ける。制御
棒要素１５の下部には制御棒内部へ冷却材を流入
させる入口オリフイス１７、さらに制御棒外部へ
冷却材を流出させる出口オリフイス１８を設け
る。 FIG. 2 shows a control rod assembly 9 according to one embodiment of the present invention. The control rod assembly 9 includes a lower entrance nozzle 11 that is inserted into the core support plate and allows coolant to flow in, a control rod guide tube 12 that houses the control rod elements 15 inside, and a control rod guide tube 12 that is connected above the control rod guide tube 12. and a handling head 13. Further, a connecting member 16 is provided for moving the control rod element 15 by a control rod drive mechanism. At the bottom of the control rod element 15, an inlet orifice 17 is provided to allow coolant to flow into the control rod, and an outlet orifice 18 is provided to allow the coolant to flow out of the control rod.
第３図は、第２図の制御棒集合体９の連結部材
１６部を拡大して示す縦断面図である。第３図に
示すように制御棒要素の外側流路を制限するため
のリング状の流路閉塞板１９を前記連結部材１６
と案内管１２間に設置し、これを制御棒の上・下
移動にかかわらず常に外側流路に保持するバネ２
０を閉塞板１９上方に設ける。この流路閉塞板と
バネで制御棒要素の外側流路を制限する流量調整
機構を構成している。 FIG. 3 is an enlarged vertical cross-sectional view of the connecting member 16 of the control rod assembly 9 of FIG. 2. FIG. As shown in FIG.
A spring 2 is installed between the control rod and the guide tube 12 and keeps it in the outer flow path regardless of whether the control rod moves up or down.
0 is provided above the closing plate 19. The flow passage blocking plate and the spring constitute a flow rate adjustment mechanism that restricts the outer flow passage of the control rod element.
第４図は、第３図に示した流量調整機構の他の
実施例であり外側流路上端部に帯状の弾性体２１
を使用した伸縮自在な流量調整機構を設置したも
のである。 FIG. 4 shows another embodiment of the flow rate adjustment mechanism shown in FIG.
It is equipped with a telescopic flow rate adjustment mechanism using.
第５図は、第３図の流量調整機構の他の実施例
を示し、外側流路上部に、リング状部材を嵌合せ
た嵌合せ型の伸縮自在な流量調整機構２２を設置
したものである。 FIG. 5 shows another embodiment of the flow rate adjustment mechanism shown in FIG. 3, in which a fit-type telescopic flow rate adjustment mechanism 22 fitted with a ring-shaped member is installed above the outer flow path. .
さらに第６図は、第３図の流量調整機構の他の
実施例を示したもので外側流路上部にベローズシ
ール２３を取付けた伸縮自在な流量調整機構を示
している。 Furthermore, FIG. 6 shows another embodiment of the flow rate adjustment mechanism shown in FIG. 3, and shows a telescopic flow rate adjustment mechanism in which a bellows seal 23 is attached to the upper part of the outer flow path.
次に作用を説明する。 Next, the action will be explained.
原子炉冷却材であるナトリウムは、原子炉容器
入口ノズル２より流入し、炉心支持板４の下部か
ら炉心構成要素内を通つて上部へ流出する。炉心
出口の直上には、炉心上部機構５の整流格子６が
あつて、冷却材は、この中を通つて上部プレナム
に流出し、原子炉出口ノズル８を通つて原子炉容
器外へ出る。制御棒集合体９において冷却材は、
炉心支持板４の下部からエントランスノズル１１
を通つて流入し、エントランスノズルを出たとこ
ろで、制御棒内部を流れるものと、外側流路を流
れるものとに分かれ、上方で、制御棒出口オリフ
イス１８から出た冷却材と外側流路を流れた冷却
材とは合流してハンドリングヘツド１３を通つて
上方へ流出する。 Sodium, which is a reactor coolant, flows in through the reactor vessel inlet nozzle 2 and flows out from the lower part of the core support plate 4 through the core components to the upper part. Immediately above the core outlet is a straightening grid 6 of the core upper mechanism 5, through which the coolant flows out into the upper plenum and exits the reactor vessel through the reactor outlet nozzle 8. In the control rod assembly 9, the coolant is
Entrance nozzle 11 from the bottom of core support plate 4
When it exits the entrance nozzle, it is divided into the coolant that flows inside the control rod and the coolant that flows through the outer flow path. The coolant flows upward through the handling head 13.
従つて制御棒出口温度は、制御棒内部を流れ制
御棒要素１５から熱を奪つて高温となつた冷却材
と、外側流路を流れた低温の冷却材との混合割合
により決まる。 Therefore, the control rod exit temperature is determined by the mixing ratio of the coolant that flows inside the control rod and becomes high temperature by removing heat from the control rod element 15, and the low temperature coolant that flows through the outer flow path.
本発明の制御棒集合体においては、外側流路を
流れる低温の冷却材流量を制限して制御棒集合体
出口冷却材温度を上昇させることができる。 In the control rod assembly of the present invention, the flow rate of the low temperature coolant flowing through the outer flow path can be restricted to increase the temperature of the control rod assembly outlet coolant.
つまり、第３図における流量調整機構にあつて
は外側流路の流量は流路閉塞板１９により制限さ
れる。流路閉塞板１９は制御棒要素１５が原子炉
反応度制御あるいは緊急炉停止といつた時に移動
しても追随して動く様、弾性体２０により常に下
方向に押しつけられている。このため制御棒要素
１５本体には常に下向きの力が加わつており、制
御棒緊急挿入時には制御棒要素を下向きに加速す
る。 That is, in the flow rate adjustment mechanism shown in FIG. 3, the flow rate of the outer flow path is restricted by the flow path closing plate 19. The passage blocking plate 19 is always pressed downward by an elastic body 20 so that it can follow the movement of the control rod element 15 during reactor reactivity control or emergency reactor shutdown. For this reason, a downward force is always applied to the main body of the control rod element 15, and the control rod element is accelerated downward when the control rod is urgently inserted.
第４図に示す構造においては、弾性体２１その
ものが流路を制限する。弾性体２１は帯状である
ため常に重なり合つて流路を制限出来る。また、
この弾性体２１は制御棒要素１５に対し常に下向
きの力が加わる様な形としており、制御棒緊急挿
入時にも加速力となつて有利に働く。 In the structure shown in FIG. 4, the elastic body 21 itself limits the flow path. Since the elastic bodies 21 are band-shaped, they always overlap to restrict the flow path. Also,
The elastic body 21 is shaped so that a downward force is always applied to the control rod element 15, and it works advantageously as an accelerating force even when the control rod is inserted in an emergency.
第５図に示す構造においては、流量調整機構２
２の伸縮自在なリング同志の嵌め合わせにより流
路を制限する。リングの形状については、挿入に
対して緊急挿入時の制御棒移動時にその支障とな
らない様になつている。また冷却材ナトリウムに
ついても挿入時にはリング状の隙間から上部へ漏
れ出るので、下部の圧力が上つて支障となること
はない。 In the structure shown in FIG.
The flow path is restricted by fitting the two telescopic rings together. The shape of the ring is such that it does not interfere with the movement of the control rod during emergency insertion. Furthermore, when the coolant sodium is inserted, it leaks to the upper part through the ring-shaped gap, so the pressure at the lower part does not increase and cause problems.
第６図に示す構造においては、冷却材ナトリウ
ムは伸縮自在なベローズシール２３により流路を
制限される。制御棒の移動に際しては、ベローズ
２３自体の弾性により制御棒には下向きの力がか
かり、緊急挿入時には、制御棒が先に落下するた
め、制御棒とベローズシール２３の間に隙間が出
来、この隙間から冷却材ナトリウムが漏れるた
め、下部の圧力により緊急挿入の支障となること
はない。 In the structure shown in FIG. 6, the flow path of the coolant sodium is restricted by a retractable bellows seal 23. When moving the control rod, a downward force is applied to the control rod due to the elasticity of the bellows 23 itself, and in the event of emergency insertion, the control rod will fall first, creating a gap between the control rod and the bellows seal 23. Since coolant sodium leaks from the gap, the pressure at the bottom will not interfere with emergency insertion.
以上説明したように本発明による制御棒集合体
は制御棒要素の動作に追従して伸縮可能な流量調
節機構を備えているので制御棒が移動してもこれ
に追従して外側流路の流量を制限出来かつ制御棒
の動きを妨げることがない。従つて制御棒出口温
度を常に高くすることが出来るので、隣接の燃料
集合体出口冷却材温度との温度差を小さく出来
る。 As explained above, the control rod assembly according to the present invention is equipped with a flow rate adjustment mechanism that can expand and contract in accordance with the movement of the control rod elements, so even if the control rods move, the flow rate in the outer flow path is adjusted accordingly. can be restricted without interfering with the movement of the control rod. Therefore, since the control rod outlet temperature can be kept high, the temperature difference between the control rod outlet coolant temperature and the adjacent fuel assembly outlet coolant temperature can be reduced.
このため炉心上部機構整流格子に発生する熱応
力が小さくできるので原子炉の構造健全性を向上
させることができる。また、制御棒集合体の主要
機能の１つである緊急制御棒挿入に関しては、悪
影響を与えないため機能を損うことはない。 Therefore, the thermal stress generated in the rectifying grid of the upper core mechanism can be reduced, and the structural integrity of the reactor can be improved. Furthermore, the insertion of emergency control rods, which is one of the main functions of the control rod assembly, does not have any adverse effects, so the function is not impaired.
第１図は原子炉の縦断面図、第２図は本発明の
一実施例による制御棒集合体の縦断面図、第３図
ないし第６図は第２図の制御棒集合体の流量調整
機構の他の実施例を示した縦断面図である。
１１……エントランスノズル、１２……制御棒
案内管、１５……制御棒要素、１９……流路閉塞
板、２０……バネ、２１……帯状の弾性体、２２
……嵌合せ型流量調整機構、２３……ベローズシ
ール。
FIG. 1 is a vertical cross-sectional view of a nuclear reactor, FIG. 2 is a vertical cross-sectional view of a control rod assembly according to an embodiment of the present invention, and FIGS. 3 to 6 are flow rate adjustment of the control rod assembly shown in FIG. FIG. 7 is a vertical cross-sectional view showing another embodiment of the mechanism. DESCRIPTION OF SYMBOLS 11... Entrance nozzle, 12... Control rod guide tube, 15... Control rod element, 19... Channel closing plate, 20... Spring, 21... Band-shaped elastic body, 22
...Fitting type flow rate adjustment mechanism, 23...Bellows seal.
Claims (1)
と、このエントランスノズルに固定される制御棒
案内管と、この制御棒案内管に連設されるハンド
リングヘツドと、前記制御棒案内管内を上下動す
る上下端に冷却材流路を有した制御棒要素と、こ
の制御棒要素の上部に形成されて制御棒駆動機構
と連結する連結部材と、制御棒要素の上部とハン
ドリングヘツドの下部との間に介挿されて、制御
棒要素の外側を通つて上方へ流れる冷却材の流量
を制限する制御棒要素の動作に追従して伸縮可能
な流量調整機構とを具備してなる制御棒集合体。1. An entrance nozzle inserted into the core support plate, a control rod guide tube fixed to the entrance nozzle, a handling head connected to the control rod guide tube, and an upper and lower end that moves up and down within the control rod guide tube. A control rod element having a coolant flow path in the control rod element, a connecting member formed at the upper part of the control rod element and connected to the control rod drive mechanism, and interposed between the upper part of the control rod element and the lower part of the handling head. and a flow rate adjustment mechanism that is extendable and retractable in accordance with the operation of the control rod element and that limits the flow rate of coolant flowing upward through the outside of the control rod element.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP8348079A JPS568595A (en) | 1979-07-03 | 1979-07-03 | Control rod assembly |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP8348079A JPS568595A (en) | 1979-07-03 | 1979-07-03 | Control rod assembly |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS568595A JPS568595A (en) | 1981-01-28 |
| JPS6220519B2 true JPS6220519B2 (en) | 1987-05-07 |
Family
ID=13803622
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP8348079A Granted JPS568595A (en) | 1979-07-03 | 1979-07-03 | Control rod assembly |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS568595A (en) |
Families Citing this family (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS58121797A (en) * | 1982-01-08 | 1983-07-20 | Mitsui Petrochem Ind Ltd | Production of dicarboxylic acid |
| JPS6024191A (en) * | 1983-07-16 | 1985-02-06 | Showa Shell Sekiyu Kk | Preparation of citric acid by fermentation |
| JPS6156991A (en) * | 1984-08-28 | 1986-03-22 | 株式会社東芝 | Control rod aggregate |
Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5241438A (en) * | 1976-07-29 | 1977-03-31 | Toshiko Hori | Door of overlapped storage type |
-
1979
- 1979-07-03 JP JP8348079A patent/JPS568595A/en active Granted
Patent Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5241438A (en) * | 1976-07-29 | 1977-03-31 | Toshiko Hori | Door of overlapped storage type |
Also Published As
| Publication number | Publication date |
|---|---|
| JPS568595A (en) | 1981-01-28 |
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