JPS5930473Y2 - Core support device in fast breeder reactor - Google Patents

Core support device in fast breeder reactor

Info

Publication number
JPS5930473Y2
JPS5930473Y2 JP1979097784U JP9778479U JPS5930473Y2 JP S5930473 Y2 JPS5930473 Y2 JP S5930473Y2 JP 1979097784 U JP1979097784 U JP 1979097784U JP 9778479 U JP9778479 U JP 9778479U JP S5930473 Y2 JPS5930473 Y2 JP S5930473Y2
Authority
JP
Japan
Prior art keywords
flow rate
coolant
core support
support device
pressure
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
JP1979097784U
Other languages
Japanese (ja)
Other versions
JPS5625295U (en
Inventor
清 池田
Original Assignee
株式会社東芝
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 株式会社東芝 filed Critical 株式会社東芝
Priority to JP1979097784U priority Critical patent/JPS5930473Y2/en
Publication of JPS5625295U publication Critical patent/JPS5625295U/ja
Application granted granted Critical
Publication of JPS5930473Y2 publication Critical patent/JPS5930473Y2/en
Expired 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

【考案の詳細な説明】 本考案は液体金属を冷却材とした高速増殖炉の炉心支持
装置に関する。
[Detailed Description of the Invention] The present invention relates to a core support device for a fast breeder reactor using liquid metal as a coolant.

高速増殖炉の炉心支持装置は、一般に、第1図および第
2図に示すような構造とされている。
A core support device for a fast breeder reactor generally has a structure as shown in FIGS. 1 and 2.

すなわち、原子炉容器1の下部には冷却材の入口配管2
が、また上部には冷却材の出口配管3がそれぞれ形成さ
れて釦り、これらの両配管2,3の上下方向における中
間位置には炉心支持装置4の炉心支持板5が水平方向に
張設されている。
That is, a coolant inlet pipe 2 is installed at the bottom of the reactor vessel 1.
However, coolant outlet pipes 3 are formed in the upper part and are buttoned, and a core support plate 5 of a core support device 4 is horizontally stretched between the pipes 2 and 3 in the vertical direction. has been done.

そして、この炉心支持板5の下方には箱体6が連設され
ており、この箱体6内に水平方向に張設された隔壁1に
より箱体6の内部を高圧冷却材室8と低圧冷却材室9と
に仕切っている。
A box body 6 is connected below this core support plate 5, and a partition wall 1 stretched horizontally within this box body 6 connects the inside of the box body 6 with a high-pressure coolant chamber 8 and a low-pressure coolant chamber 8. It is partitioned into a coolant chamber 9.

前記炉心支持板5には、後述する燃料集合体10用の多
数の開口11.11・・・が形成されて訃り、各開口1
1の下方の高圧冷却材室8には各開口11と連通ずる多
数の流量調整管12.12・・・が固定されている。
The core support plate 5 is formed with a large number of openings 11, 11, .
A large number of flow rate adjusting pipes 12, 12, .

渣た、前記隔壁7にも各流量調整管12と同軸的な多数
の開口13.13・・・が形成されている。
Additionally, a large number of openings 13, 13, .

炉心燃料集合体、ブランケット燃料集合体、制御棒、反
射体などからなる前記燃料集合体10のエントランスノ
ズル14は、前記炉心支持板5の開口11を介して流量
調整管12内に挿入され、下端が隔壁7の開口13から
低圧冷却材室9内に臨んで支持されている。
The entrance nozzle 14 of the fuel assembly 10, which is composed of a core fuel assembly, a blanket fuel assembly, a control rod, a reflector, etc., is inserted into the flow rate adjustment tube 12 through the opening 11 of the core support plate 5, and the lower end is supported facing into the low pressure coolant chamber 9 from the opening 13 of the partition wall 7.

オた、第2図に詳示するように、箱体6の高圧冷却室8
の外周には円周方向に多数の冷却材流入口15.15・
・・が形成されている。
Additionally, as shown in detail in FIG. 2, the high-pressure cooling chamber 8 of the box body 6
There are many coolant inlets 15, 15 and 15 in the circumferential direction on the outer periphery of the
... is formed.

そして、入口配管2から炉容器1内に導入された冷却材
は前記冷却材流入口15から高圧冷却材室8を介して燃
料集合体10内を重力の方向と逆方向に流れて出口配管
3から排出されるが、燃料集合体10内を流れる冷却材
の圧力損失による上方への力が燃料集合体100重量よ
り大きいため燃料集合体10が浮上する傾向にある。
The coolant introduced into the reactor vessel 1 from the inlet pipe 2 flows from the coolant inlet 15 through the high-pressure coolant chamber 8 in the fuel assembly 10 in a direction opposite to the direction of gravity, and flows into the outlet pipe 3. However, since the upward force due to the pressure loss of the coolant flowing within the fuel assembly 10 is greater than the weight of the fuel assembly 100, the fuel assembly 10 tends to float.

このため、従来から、第3図に示すように、流量調整管
12の冷却材通過用のオリフィス孔16.16・・・に
合致するように燃料集合体10のエントランスノズル1
4に横孔17,17・・・を形成して、これらの横孔1
7から冷却材を燃料集合体10内に導くとともに、前述
したように、高圧冷却材室8の下方に低圧冷却材室9を
連通し、燃料集合体10を水圧的に保持している。
For this reason, conventionally, as shown in FIG.
Horizontal holes 17, 17... are formed in 4, and these horizontal holes 1
7 into the fuel assembly 10, and as mentioned above, the low pressure coolant chamber 9 is communicated with the lower part of the high pressure coolant chamber 8, and the fuel assembly 10 is held hydraulically.

ところで、流量調整管12のオリフィス孔16は各流量
調整管12ごとに異なっており、冷却材流入口15から
高圧冷却材室8に流入した冷却材は、核熱設計に基づい
た冷却材流量を各燃料集合体10に配分して内部の燃料
ピン18,18・・・の発熱を冷却する。
By the way, the orifice hole 16 of the flow rate adjustment tube 12 is different for each flow rate adjustment tube 12, and the coolant flowing into the high pressure coolant chamber 8 from the coolant inlet 15 has a coolant flow rate based on the nuclear thermal design. The heat generated by the internal fuel pins 18, 18, . . . is cooled by distributing it to each fuel assembly 10.

昔たζ炉容器1の内側に配列された燃料集合体10に流
量配分される冷却材は、外側に配列された燃料集合体1
0田の流量調整管12の相互の間隙を、一部は付近の流
量調整管12に流入しながら内側に向って数mの流速で
流れ、高圧冷却材室8のすべての流量調整管12に流量
配分される。
In the past, the flow rate of the coolant distributed to the fuel assemblies 10 arranged inside the reactor vessel 1 was distributed to the fuel assemblies 1 arranged outside.
It flows inward at a flow rate of several meters through the gaps between the flow rate adjustment pipes 12 in the high-pressure coolant chamber 8, with some of it flowing into the nearby flow rate adjustment pipes 12, and flows into all the flow rate adjustment pipes 12 in the high-pressure coolant chamber 8. Flow rate is distributed.

この流量調整管12の管群の間隙を流れる冷却材により
、流速と列数に比例した圧力損失を生じるため、内側に
なるに従って圧力が低下する。
The coolant flowing through the gaps between the tube groups of the flow rate adjustment tubes 12 causes a pressure loss proportional to the flow velocity and the number of rows, so the pressure decreases as it moves toward the inside.

この高圧冷却材室8内を流れる冷却材の圧力損失により
生じる圧力分布は流量配分上の誤差となる。
The pressure distribution caused by the pressure loss of the coolant flowing in the high-pressure coolant chamber 8 causes an error in flow rate distribution.

な釦、高速増殖炉の熱出力の増加に伴ない燃料集合体1
00本数も増加するが、これにより冷却材の流量配分上
の誤差も増大する。
button, fuel assembly 1 due to increase in thermal output of fast breeder reactor
00, but this also increases the error in the flow rate distribution of the coolant.

本考案は、前述した従来のものにおける欠点を除去し、
冷却材の流量配分上の誤差を減少させ、全燃料集合体を
ほぼ等温となるように冷却し得るようにした炉心支持装
置を提供することを目的としてなされたもので、各流量
調整管の冷却材の衝突する位置に、該流量調整管の軸線
方向に延在する邪魔板を突設し、流量調整管表面の境介
層の剥離を遅らせて調整管の背後の後流を小さくし、圧
力損失を減少し、これにより、高圧冷却材室の圧力分布
を小サクシて流量配分上の誤差を減少したものである。
The present invention eliminates the drawbacks of the conventional ones mentioned above,
The purpose of this system is to provide a core support device that reduces errors in coolant flow distribution and cools all fuel assemblies to an almost isothermal state. A baffle plate extending in the axial direction of the flow rate adjustment tube is installed at the location where the material collides with the flow rate adjustment tube to delay the separation of the boundary layer on the surface of the flow rate adjustment tube, thereby reducing the wake behind the adjustment tube and reducing the pressure. This reduces losses, thereby reducing the pressure distribution in the high-pressure coolant chamber and reducing errors in flow distribution.

以下、本考案を第4図および第5図に示す実施例により
説明する。
The present invention will be explained below with reference to the embodiments shown in FIGS. 4 and 5.

な釦、第1図トよび第2図について既述した炉心支持装
置の全体の構成には変化がないので、従来のものと変化
のある要部のみについて説明する。
Since there is no change in the overall configuration of the core support device already described with reference to FIGS. 1 and 2, only the main parts that are different from the conventional device will be described.

第4図A、Bは本考案の第1実施例を示すものあり、流
量調整管12の外周の冷却材の衝突する位置、すなわち
冷却材が流れてくる方向に向って流量調整管12の軸線
方向に一対の邪魔板19゜19が突設され、これらの邪
魔板19.19はほぼ20°の角度をもって位置してい
る。
FIGS. 4A and 4B show the first embodiment of the present invention, and the axis of the flow rate adjustment tube 12 is shown at the collision position of the coolant on the outer periphery of the flow rate adjustment tube 12, that is, in the direction in which the coolant flows. A pair of baffle plates 19.19 are provided projecting in the direction, and these baffle plates 19.19 are positioned at an angle of approximately 20°.

前述した構成によれば、第5図に示すように、流量調整
管12の前面に、槍の穂先のような冷却材の停滞部分a
を生ずる。
According to the above-described configuration, as shown in FIG.
will occur.

また、邪魔板19.19の背部訟よび流量調整管12の
背部に渦す、cを生じ、さらに単純円管の場合に較べて
管12の外表面における境界層の剥離が遅れるため、流
量調整管12の背部に生ずる後流が小さくなる。
In addition, swirls are generated at the back of the baffle plate 19, 19 and the back of the flow rate adjustment tube 12, and the separation of the boundary layer on the outer surface of the tube 12 is delayed compared to the case of a simple circular tube, so the flow rate is adjusted. The wake generated at the back of the tube 12 is reduced.

したがって、流量調整管12は、冷却材の停滞部分a1
大小多数の渦す、c>よび乱流境界層に対する包絡面と
しての仮想楕円柱dに置き換えられ、抵抗が明瞭に減少
し、冷却材の圧力損失は小さくて済む。
Therefore, the flow rate adjustment pipe 12 has a stagnant portion a1 of the coolant.
It is replaced by a virtual elliptical cylinder d as an envelope surface for a large and small number of vortices, c>, and a turbulent boundary layer, the resistance is clearly reduced, and the pressure loss of the coolant is small.

よって、冷却材の流量配分上の誤差は小さく、各燃料集
合体10を均一に冷却することができる。
Therefore, the error in the flow rate distribution of the coolant is small, and each fuel assembly 10 can be uniformly cooled.

な釦、前述した抵抗減少の理論は、昭和31年8月発行
の機械学会論文集の第570頁ないし第575頁に詳細
に示されている。
The theory of resistance reduction mentioned above is explained in detail on pages 570 to 575 of the Proceedings of the Japan Society of Mechanical Engineers, published in August 1955.

第6図A、Bは本考案の第2実施例を示すものであり、
流量調整管12の外周の冷却材の衝突する位置に軸線方
向に延在する1枚の邪魔板12を突設したものである。
6A and 6B show a second embodiment of the present invention,
A baffle plate 12 extending in the axial direction is provided at a position on the outer periphery of the flow rate adjusting pipe 12 where the coolant collides with the baffle plate 12 .

このような構成によってもある程度の効果が得られる。A certain degree of effect can also be obtained with such a configuration.

以上説明したように、本考案に係る高速増殖炉における
炉心支持装置は、各流量調整管の軸線方向に延在する邪
魔板を突設したので、高圧冷却材室内の圧力損失を減少
させ、各燃料集合体に流入する冷却材の流量配分上の誤
差を減少せしめ、高速増殖炉の運転性能および健全性の
向上をはかることができるという優れた効果を奏する。
As explained above, the core support device for a fast breeder reactor according to the present invention has a protruding baffle plate extending in the axial direction of each flow rate adjustment tube, so that the pressure loss in the high pressure coolant chamber is reduced, and each This has the excellent effect of reducing errors in the flow rate distribution of coolant flowing into the fuel assembly, and improving the operational performance and integrity of the fast breeder reactor.

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

第1図は一般的な炉心支持装置を示す半部の縦断面図、
第2図は第1図の要部を拡大して示す横断面図、第3図
は従来の炉心支持装置の流量調整管の近傍を1部側面で
示す縦断面図、第4図Aは本考案に係る炉心支持装置の
第1実施例を示す流量調整管の近傍の一部縦断面図、第
4図Bは第4図AのIV−IV線による断面図、第5図
は第4図の炉心支持装置の抵抗の減少理論を説明するた
めの概念図、第6図Aは本考案に係る炉心支持装置の第
2実施例を示す正面図、第6図Bは第6図AのVl−V
l線による断面図である。 1・・・・・・原子炉容器、4・・・・・・炉心支持装
置、6・・・・・・箱体、8・・・・・・高圧冷却材室
、9・・・・・・低圧冷却材室、10・・・・・・燃料
集合体、12・・・・・・流量調整管、14・・・・・
・エントランスノズル、15・・・・・・冷却材流入口
、19・・・・・・邪魔板。
Figure 1 is a longitudinal cross-sectional view of a half part showing a general core support device;
Figure 2 is an enlarged cross-sectional view of the main part of Figure 1, Figure 3 is a vertical cross-sectional view partially showing the vicinity of the flow rate adjustment tube of a conventional core support device, and Figure 4A is a main part of the main part. FIG. 4B is a cross-sectional view taken along the line IV-IV of FIG. 4A, and FIG. FIG. 6A is a front view showing a second embodiment of the core support device according to the present invention, and FIG. -V
FIG. 1...Reactor vessel, 4...Core support device, 6...Box, 8...High pressure coolant chamber, 9...・Low pressure coolant chamber, 10...Fuel assembly, 12...Flow rate adjustment pipe, 14...
- Entrance nozzle, 15... Coolant inlet, 19... Baffle plate.

Claims (1)

【実用新案登録請求の範囲】[Scope of utility model registration request] 燃料集合体のエントランスノズルが挿入される多数の流
量調整管を備え側方に冷却材の流入口が形成された高圧
冷却材室と、この高圧冷却材室の下方に隔壁を介して形
成された低圧冷却材室とを有するものに釦いて、前記各
流量調整管の前記冷却材の衝突する位置に、該流量調整
管の軸線方向に延在する邪魔板を突設したことを特徴と
する高速増殖炉における炉心支持装置。
A high-pressure coolant chamber with a large number of flow rate adjustment pipes into which the entrance nozzle of the fuel assembly is inserted and a coolant inlet on the side, and a partition wall formed below this high-pressure coolant chamber. a low-pressure coolant chamber, and a baffle plate extending in the axial direction of each flow rate adjusting tube is provided protrudingly at a position where the coolant collides with each of the flow rate adjusting tubes. Core support device in a breeder reactor.
JP1979097784U 1979-07-16 1979-07-16 Core support device in fast breeder reactor Expired JPS5930473Y2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP1979097784U JPS5930473Y2 (en) 1979-07-16 1979-07-16 Core support device in fast breeder reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP1979097784U JPS5930473Y2 (en) 1979-07-16 1979-07-16 Core support device in fast breeder reactor

Publications (2)

Publication Number Publication Date
JPS5625295U JPS5625295U (en) 1981-03-07
JPS5930473Y2 true JPS5930473Y2 (en) 1984-08-30

Family

ID=29330568

Family Applications (1)

Application Number Title Priority Date Filing Date
JP1979097784U Expired JPS5930473Y2 (en) 1979-07-16 1979-07-16 Core support device in fast breeder reactor

Country Status (1)

Country Link
JP (1) JPS5930473Y2 (en)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS6069514U (en) * 1983-10-14 1985-05-17 日新電機株式会社 closed switchboard

Also Published As

Publication number Publication date
JPS5625295U (en) 1981-03-07

Similar Documents

Publication Publication Date Title
US5203405A (en) Two pass shell and tube heat exchanger with return annular distributor
US4039377A (en) Nuclear boiler
JP2013053620A (en) Multi-tube type heat exchanger
JPS5930473Y2 (en) Core support device in fast breeder reactor
CN211234072U (en) Cooling device
CN108895864B (en) Baffle assembly and shell-and-tube heat exchanger comprising such an assembly
JPS59191897A (en) Multitubular heat exchanger
JP2937423B2 (en) Tank type fast breeder reactor
JP4301604B2 (en) Pressurized water reactor
JPS643992Y2 (en)
JPS6337880B2 (en)
CN213335695U (en) Rotational flow fin tube cooler
JPS629199A (en) Heat exchanger
JPH0740865Y2 (en) Heat exchanger
JPS5836079Y2 (en) Reactor
JPH04299299A (en) Intermediate heat exchanger for fast breeder reactor
JPS58217192A (en) Heat exchanger
JPH05203388A (en) Straight-tube type shell and tube heat exchanger
JP2963586B2 (en) Steam generator
JPS6019948Y2 (en) regiator
JPS5883193A (en) Heat exchanger
JPH04361195A (en) Tank type fast breeder reactor
JPH0578721B2 (en)
JP2928516B2 (en) Fuel assembly
JPS60188750A (en) Hot-water boiler