JPS5944687A - Reactor core structural element - Google Patents

Reactor core structural element

Info

Publication number
JPS5944687A
JPS5944687A JP57155355A JP15535582A JPS5944687A JP S5944687 A JPS5944687 A JP S5944687A JP 57155355 A JP57155355 A JP 57155355A JP 15535582 A JP15535582 A JP 15535582A JP S5944687 A JPS5944687 A JP S5944687A
Authority
JP
Japan
Prior art keywords
control rod
tube
coolant
fuel
rod guide
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
Application number
JP57155355A
Other languages
Japanese (ja)
Inventor
鈴木 聖夫
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
Nippon Genshiryoku Jigyo KK
Nippon Atomic Industry Group Co Ltd
Original Assignee
Nippon Genshiryoku Jigyo KK
Tokyo Shibaura Electric Co Ltd
Nippon Atomic Industry Group 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 Nippon Genshiryoku Jigyo KK, Tokyo Shibaura Electric Co Ltd, Nippon Atomic Industry Group Co Ltd filed Critical Nippon Genshiryoku Jigyo KK
Priority to JP57155355A priority Critical patent/JPS5944687A/en
Publication of JPS5944687A publication Critical patent/JPS5944687A/en
Pending 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

  • Devices And Processes Conducted In The Presence Of Fluids And Solid Particles (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〕 本発明は高速増珀炉の炉心構成要素に関する。[Detailed description of the invention] [Technical field of invention] The present invention relates to core components of a fast smelting reactor.

〔発明の技術的背景〕[Technical background of the invention]

尚速増夕向炉では燃料集合体、制御棒集合体等の炉心構
成要素に対する1次冷却材の流量を・各炉心構成要素の
発熱iの割合に応じて配分し、各炉心構成要素の除熱を
行なうようにしている。
In a direct-to-air reactor, the flow rate of primary coolant to core components such as fuel assemblies and control rod assemblies is distributed according to the proportion of heat generation i of each core component, and the removal of each core component is I'm trying to heat it up.

ところが、例えば制御棒集合体の場合、1体の制御棒集
合体に配分された1次冷却材のうち40〜60係が制御
棒保護管の外側を流れ、これは除熱に寄与しない無駄流
量となる。
However, in the case of a control rod assembly, for example, 40 to 60 of the primary coolant distributed to one control rod assembly flows outside the control rod protection tube, and this is a waste flow that does not contribute to heat removal. becomes.

このため制御棒集合体出口部の冷却利温展は周辺の燃料
集合体出口部の冷却材温度に比べて低くなシ(極端な場
合は200 ℃程度も低くなる)、炉心上部機構の熱応
力が大きくなる等、原子炉の健全性が害されるおそれが
あった。
For this reason, the cooling temperature at the exit of the control rod assembly is lower than the coolant temperature at the exit of the surrounding fuel assemblies (as much as 200°C lower in extreme cases), and the thermal stress of the upper core mechanism is low. There was a risk that the integrity of the reactor would be damaged, such as the increase in the size of the reactor.

〔発明の目的〕[Purpose of the invention]

本発明はこのような事情にもとづいてなされたもので、
その目的は、制御棒保護管の外側を流れる1次冷却材の
有効利用を図り、出口部における冷却材温度を高め、周
辺の燃料集合体出口部の冷却材温度との差を減少させて
原子炉の健全性を維持することにある。
The present invention was made based on these circumstances, and
The purpose of this is to effectively utilize the primary coolant flowing outside the control rod protection tube, increase the coolant temperature at the outlet, reduce the difference in coolant temperature at the outlet of the surrounding fuel assemblies, and The purpose is to maintain the health of the furnace.

〔発明の概快〕[Summary of the invention]

不発明に係る炉心構成要素は、ラッ・9管と制御棒案内
管との間に筒状空間を設け、かつ制御棒案内管の周壁に
は複数の冷却相流通孔を設け、前記筒状空間内には複数
の燃料要素を収納して構成される。
The reactor core component according to the invention is such that a cylindrical space is provided between the rack 9 tube and the control rod guide tube, and a plurality of cooling phase flow holes are provided in the peripheral wall of the control rod guide tube, and the cylindrical space is provided with a plurality of cooling phase flow holes. It is configured to house multiple fuel elements inside.

〔発明の実施例〕[Embodiments of the invention]

以下、本発明の一実施例を図面を奈照して説明する。 Hereinafter, one embodiment of the present invention will be described with reference to the drawings.

第1図は炉心構成要素の縦断+fu図、第2図は@1図
の■−■断面図であって、図中1は六角筒状のラッパ管
である。このラッノ←#1は、他の燃料集合体(図示せ
ず〕の外形と同一外形を呈しておシ、その下端部にはエ
ントランスノズル3が取着され、このエントランスノズ
ル3は炉心支持部5に上方よυ挿入支持されるように構
成されている。
FIG. 1 is a vertical +fu view of the core components, and FIG. 2 is a cross-sectional view taken along the line ■-■ of FIG. This fuel assembly #1 has the same external shape as that of other fuel assemblies (not shown), and an entrance nozzle 3 is attached to its lower end. It is configured to be inserted and supported upwardly.

ラッパ管lの内部には、このラッパ管lとの間に筒状空
間7を存してtljlJ御棒菜内前9が配置されている
。この制御俸案内官9の胸壁には多数の冷却材流通孔1
1が、周方向及び軸方向にそれぞれ等間隔に穿設芒れて
いる。
Inside the trumpet tube 1, a tljlJ inner tube 9 is disposed with a cylindrical space 7 between the trumpet tube 1 and the trumpet tube 1. A large number of coolant distribution holes 1 are provided in the parapet of this control salary guide 9.
1 are perforated at equal intervals in the circumferential direction and the axial direction.

前記筒状空間7の下部位故には燃料要素支持板13が設
けられ、この支持板13の上方には適宜の間隔をあけて
複数の燃料要素支持グリッド15が設けられている。そ
して筒状空間7の内部には、これらの燃料要素支持板1
3及び燃料要素支持グリッド15に支持されて複数の燃
料要素17が周方向に配置されている。
A fuel element support plate 13 is provided at the bottom of the cylindrical space 7, and above the support plate 13, a plurality of fuel element support grids 15 are provided at appropriate intervals. Inside the cylindrical space 7, these fuel element support plates 1 are provided.
3 and a fuel element support grid 15, a plurality of fuel elements 17 are arranged in the circumferential direction.

また、前記制御棒案内管9の内部には制御棒集合体19
が昇降自在に配置され1いる。この制御棒集合体19は
、制御棒集合体2ノの内部に複数の中性子吸収材要素2
3を収納した構成のもので、保護管21の上端は制?i
ll棒鹿動杆25を介して制御棒駆動機構(図示せず)
に連結され、制@1棒駆動機栴に枢動されて制御棒案内
管9内を外陣動作するように構成されている0前記ラツ
パ管1の上端部には吊上げ用のハンドリングヘッド27
が取着されている。
Furthermore, a control rod assembly 19 is provided inside the control rod guide tube 9.
are arranged so that they can be raised and lowered freely. This control rod assembly 19 has a plurality of neutron absorbing material elements 2 inside the control rod assembly 2.
3 is stored, and the upper end of the protection tube 21 is restricted. i
Control rod drive mechanism (not shown)
A handling head 27 for lifting is attached to the upper end of the control rod guide tube 9.
is attached.

以上の如く構成された炉心構成要素によれは、エントラ
ンスノズル3よシ流入した1次冷却材29の流路力、エ
ントランスノズル29を通過した後、3つに分岐する。
With the core components configured as described above, the flow path force of the primary coolant 29 flowing through the entrance nozzle 3 branches into three after passing through the entrance nozzle 29.

第1の流路29には保護管2ノ内の下部よシ中性子吸収
拐扱素23に山って上昇し、中性子吸収材要素23を除
熱した後、冷却材流;a (Ll)よシ筒状空間7へ流
出し、ラツ・ぐ管1の上端よシ流出する。
In the first flow path 29, a coolant flow flows from the lower part of the protection tube 2 to the neutron absorbing element 23 and rises, and after removing heat from the neutron absorbing element 23, a coolant flow; It flows out into the cylindrical space 7 and out through the upper end of the ratchet tube 1.

また第2の流路29Bは制御棒案内管9と保護管21と
の間の隙間を上昇し、保護管21を外部よシ除熱する。
Further, the second flow path 29B ascends through the gap between the control rod guide tube 9 and the protection tube 21, and removes heat from the protection tube 21 to the outside.

そして第3の流路29Cは筒状窒間都7内を上昇し、燃
料要素17の除熱全行なうOなお、第2の流% 29 
Bは条内管9に設けられた冷却相流通孔1ノ紫通って逸
亘、第3のI/lL路29Cに合勇しし、燃料吸糸17
の除熱に寄与することになる。
The third flow path 29C rises within the cylindrical nitrogen pipe 7 and completely removes heat from the fuel element 17.The second flow path 29C
B passes through the cooling phase flow hole 1 provided in the inner pipe 9, connects to the third I/L path 29C, and connects to the fuel suction thread 17.
This will contribute to heat removal.

L タフ>Xって、エントランスノズル3よシ流入した
1次冷却材29はすべて中1住子吸収制要素23X保祿
管21又は燃料依索17の除熱に寄与することになシ、
ラッパ管1の上端よシ流出するまでに、かなシの面部に
なる。
L Tough >
By the time it flows out from the upper end of the trumpet tube 1, it becomes a round surface.

そこで、このような構成された炉心構成要素の出口部(
すなわちラッ・ぐ管Jの上部)における冷却材29の温
度T。utは次式で表わされることになる。
Therefore, the exit section (
In other words, the temperature T of the coolant 29 at the top of the cooling pipe J). ut will be expressed by the following equation.

ただし〜Tin  :  エントランスノズル流入部温
度 PCB  ’  中性子吸収材要素発熱量Pfuel:
  燃料要素発熱量 Psus :  保護管、ラッパ管元熱量W : 1炉
心構成要素に対する配 分流量 α : 比例係数 これに対して、従来の制御棒集合体ではラツz! Vf
t内に燃料要素が配置抗されていないので、出口部の冷
却拐温匿T。utは である0そして、燃別要素元熱蛍Pfuelは中性子吸
収材要素発熱量P。Rや保護省、ラツノ9管発熱量p8
uFIよりはるかに大であることから、ToutはTo
utよシはる刀1に^温となること、明らかである。し
かも中性子吸収材要素23の発熱量PcRは制御棒集合
体19を引抜くにしたがって低下し、全引抜時には全挿
入時の1/10程度となるので、従来の制御棒集合体で
は全引抜時における出口部冷却材温度がかなシ低下する
ことになるが、不実施例の構成では制御棒集合体19の
引抜量に応じて燃料要素17の発熱’L Pfuel 
は々 逆に増加することにνるので、制御棒集合体19の引抜
によって出口部冷却材の温度が低下することはない。そ
して燃料要素17の数を増やすことによって、出口部冷
却材温度を周辺の燃料集合体出口部における冷却材温度
に近づけることができ、その温度差を50℃程度とする
こともできる。
However, ~Tin: Entrance nozzle inlet temperature PCB' Neutron absorber element calorific value Pfuel:
Fuel element calorific value Psus: Protective tube, wrapper tube original heat value W: Distributed flow rate for one core component α: Proportionality coefficient On the other hand, in the conventional control rod assembly, Ratz! Vf
Since the fuel element is not placed within T, the outlet section is cooled and heat-sealed. ut is 0, and the combustion element source Pfuel is the neutron absorber element calorific value P. R, Ministry of Protection, Ratsuno 9 tube calorific value p8
Tout is much larger than uFI, so Tout is To
It's obvious that UT Yoshiharu Katana 1 will be warm. Moreover, the calorific value PcR of the neutron absorber element 23 decreases as the control rod assembly 19 is withdrawn, and when fully withdrawn it is about 1/10 of that when fully inserted. Although the outlet coolant temperature will drop slightly, in the configuration of the non-embodiment, the heat generation of the fuel element 17 will increase depending on the amount of withdrawal of the control rod assembly 19.
On the contrary, the temperature of the outlet coolant does not decrease due to withdrawal of the control rod assembly 19. By increasing the number of fuel elements 17, the outlet coolant temperature can be brought closer to the coolant temperature at the outlet of the surrounding fuel assembly, and the temperature difference therebetween can be made about 50°C.

〔発明の効果〕〔Effect of the invention〕

以上、実施例にもとついて評述したように、本発明によ
れは、ラッパ管と制御棒案内管との間に筒秋空[i4]
を設け、かつ制御棒案内管の周壁には複数の冷却材流通
孔を設け、前記筒状空間内に複数の燃料要素を収納する
ことに′よシ、ル制御棒保護管の外側を流れる1次冷却
相の有効利起 用が図4、出口部における冷却材温度が尚められて周辺
の燃料集合体出口部の冷却材温度との差を減少させて原
子炉の健全性を維持することができる炉心構成要素を提
供できるものである。
As described above based on the embodiments, according to the present invention, there is a tube fall air [i4] between the trumpet tube and the control rod guide tube.
In addition, a plurality of coolant flow holes are provided in the peripheral wall of the control rod guide tube, and in order to store a plurality of fuel elements in the cylindrical space, coolant flowing outside the control rod protection tube is provided. As shown in Figure 4, the effective use of the next cooling phase reduces the temperature difference between the coolant at the outlet of the surrounding fuel assemblies and the coolant temperature at the outlet of the surrounding fuel assemblies, thereby maintaining the integrity of the reactor. It is possible to provide core components that can be used.

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

図は本発明の一実施例を示すもので、果1図は炉心構成
要素の縦1面図、第2図は第1図の■−■断面図である
。 1・・・ラッパ管、3・・・エントランスノズル、7・
・・筒状空間、9・・・制御棒案内管、1ノ・・・冷却
材流通孔、12・・・燃料要素、19・・・制御棒集合
体・2ノ・・・制御棒保護管、23・・・中性子吸収材
要素、29・・・1次冷却材。 出願人代理人  弁理士 鈴 江 武 診4 第2図
The figures show one embodiment of the present invention, in which Figure 1 is a vertical plan view of the core components, and Figure 2 is a sectional view taken along the line 1--2 of Figure 1. 1...Trumpet tube, 3...Entrance nozzle, 7.
... Cylindrical space, 9... Control rod guide tube, 1 No.... Coolant flow hole, 12... Fuel element, 19... Control rod assembly, 2 No.... Control rod protection tube , 23... Neutron absorber element, 29... Primary coolant. Applicant's agent Patent attorney Takeshi Suzue Examination 4 Figure 2

Claims (1)

【特許請求の範囲】[Claims] 下端部にエントランスノズルを取着したラッパ管と、周
壁に複数の冷却材流通孔を有し前記ラッパ管との間に筒
状空間′(I:任してラッパ管内に配置された制御棒案
内管と、前記筒状空間内に収納された複数の燃料要素と
、中性子吸収劇を内蔵して前記制御棒案内管のPI部に
配置され制御棒駆動截構に、駆動されて制御棒案内管内
を昇l14!動作する制御棒集合体とを具備したことを
特徴とする炉心構成要素。
A cylindrical space '(I: a control rod guide disposed inside the trumpet tube) is formed between a trumpet tube with an entrance nozzle attached to its lower end and a trumpet tube having a plurality of coolant flow holes in the peripheral wall. A tube, a plurality of fuel elements housed in the cylindrical space, and a neutron absorber are disposed in the PI section of the control rod guide tube and are driven in the control rod guide tube. A reactor core component characterized in that it comprises a control rod assembly that moves and operates.
JP57155355A 1982-09-07 1982-09-07 Reactor core structural element Pending JPS5944687A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP57155355A JPS5944687A (en) 1982-09-07 1982-09-07 Reactor core structural element

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP57155355A JPS5944687A (en) 1982-09-07 1982-09-07 Reactor core structural element

Publications (1)

Publication Number Publication Date
JPS5944687A true JPS5944687A (en) 1984-03-13

Family

ID=15604088

Family Applications (1)

Application Number Title Priority Date Filing Date
JP57155355A Pending JPS5944687A (en) 1982-09-07 1982-09-07 Reactor core structural element

Country Status (1)

Country Link
JP (1) JPS5944687A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2006337215A (en) * 2005-06-02 2006-12-14 Toshiba Corp Fast reactor

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2006337215A (en) * 2005-06-02 2006-12-14 Toshiba Corp Fast reactor

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