JPS5941557B2 - nuclear fuel assembly - Google Patents

nuclear fuel assembly

Info

Publication number
JPS5941557B2
JPS5941557B2 JP52056216A JP5621677A JPS5941557B2 JP S5941557 B2 JPS5941557 B2 JP S5941557B2 JP 52056216 A JP52056216 A JP 52056216A JP 5621677 A JP5621677 A JP 5621677A JP S5941557 B2 JPS5941557 B2 JP S5941557B2
Authority
JP
Japan
Prior art keywords
coolant
fuel assembly
nuclear fuel
liquid metal
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
Application number
JP52056216A
Other languages
Japanese (ja)
Other versions
JPS53141885A (en
Inventor
光夫 若松
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 JP52056216A priority Critical patent/JPS5941557B2/en
Publication of JPS53141885A publication Critical patent/JPS53141885A/en
Publication of JPS5941557B2 publication Critical patent/JPS5941557B2/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

  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)

Description

【発明の詳細な説明】 本発明は液体金属冷却材を使用する原子炉における核燃
料集合体に関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to nuclear fuel assemblies in nuclear reactors using liquid metal coolant.

既に提案されているこの種の原子炉に使用される液体金
属冷却材は、原子炉容器内に装填された各核燃料集合体
の個々の発熱量の異なることを考慮して流量配分を行い
、原子炉内における熱の交換効率を均一にしかも効率を
よくすると共に、各核燃料集合体内の燃料ピンの耐融等
の生じないように構成されている。
The liquid metal coolant used in this type of reactor, which has already been proposed, has a flow rate distribution that takes into account the different calorific values of each nuclear fuel assembly loaded in the reactor vessel. It is configured to make the heat exchange efficiency within the reactor uniform and to improve the efficiency, and to prevent melting of the fuel pins in each nuclear fuel assembly.

即ち、既に提案されている液体金属冷却材を使用する原
子炉、例えば高速増殖炉は、第1図乃至第3図に示され
るように、回転プラグaを有する原子炉容器すの下部に
液体金属冷却材の供給口C1y c2を設け、上記原子
炉容器すの炉心構造物dを水平に設置し、この炉心構造
物dの流量調節孔eを有する各連結管fに各核燃料集合
体gのエントランスノズルg1 を着脱自在に挿着し、
曲刃、上記炉容器すの冷却材の供給口CI+02に連通
ずる高圧プレナムhからの冷却材を炉心構造物dの下部
に設けられた整流多孔板d1 を通して下部プレナムi
に圧送し、しかる後、これを上記流量調節孔eから各エ
ントランスノズルg1内へIN、入L、この各エントラ
ンスノズルg1へ流入した冷却材を各核燃料集合体gの
燃料ピンj内を通過させることにより、熱交換し、これ
を上記炉容器すの上部側壁に設けられた冷却材の各吐出
口に1.に2から外部へ流出して熱交換して仕事をした
後、再び、上記冷却材の供給口C1+C2へ還流するよ
うになっている。
That is, in a nuclear reactor that uses a liquid metal coolant that has already been proposed, such as a fast breeder reactor, as shown in FIGS. Coolant supply ports C1y and C2 are provided, the core structure d of the reactor vessel is installed horizontally, and the entrance of each nuclear fuel assembly g is connected to each connecting pipe f having the flow rate adjustment hole e of the reactor core structure d. Insert the nozzle g1 removably,
The curved blade directs the coolant from the high-pressure plenum h, which communicates with the coolant supply port CI+02 of the reactor vessel, through the lower plenum i through the rectifying perforated plate d1 provided at the lower part of the core structure d.
After that, the coolant is injected into each entrance nozzle g1 from the flow rate adjustment hole e, and the coolant flowing into each entrance nozzle g1 is passed through the fuel pin j of each nuclear fuel assembly g. This exchanges heat and supplies it to each outlet of the coolant provided on the upper side wall of the furnace vessel. After that, the coolant flows out from the coolant 2 and performs work by exchanging heat, and then returns to the coolant supply ports C1 and C2.

尉」ち、上記原子炉に使用される液体金萬による冷却材
は、上記各連結管fの流量調節孔eの開口数、大きさ、
形状、及び流量を上記各エントランスノズルg1の各オ
リフィスによって調節するようになっている関係上、上
記炉心構造物dの上支持板d2の上S[合部lは球面座
を形成しており、これにより冷却材の漏洩現象を少なく
押えるようにしである。
The liquid metal coolant used in the reactor is determined by the opening aperture and size of the flow rate adjustment hole e of each connecting pipe f,
Since the shape and flow rate are adjusted by each orifice of each entrance nozzle g1, the upper S [junction l] of the upper support plate d2 of the core structure d forms a spherical seat, This is intended to minimize the phenomenon of coolant leakage.

上記下支持板d3の下部嵌合部mは冷却材の流体圧によ
って核燃料集合体gのエントランスノズルg1 を偏倚
し、これに起因して冷却材の適正流量発作が損われ、炉
容器す内の流量配分か不均一なものとなり、熱の交換効
率を低下し、しかも各核燃料集合体g間に温度差を生じ
、この核燃料集合体gが熱変形や燃料ピンjに異常力ロ
熱を起すおそれがある。
The lower fitting part m of the lower support plate d3 biases the entrance nozzle g1 of the nuclear fuel assembly g due to the fluid pressure of the coolant, which impairs the proper flow rate of the coolant and causes the inside of the reactor vessel to deviate. The flow distribution becomes uneven, reducing the heat exchange efficiency and creating a temperature difference between the nuclear fuel assemblies g, which may cause thermal deformation of the nuclear fuel assemblies g and abnormal heat generation in the fuel pins j. There is.

そこで、上述した点を防止するために、第2図に示され
るように、エントランスノズルg1 の下部嵌合部mに
至る各連結管fを長くして冷却材の通過時の摩擦損失を
大きくしたり、又第3図に示されるように、エントラン
スノズルg1 と下部嵌合部mの間隙を小さくするこ
とが提案されているけれども、これらの各手段は、いず
れも各核燃料集合体gの装荷性が悪くなるばかりでなく
、上記エントランスノズルg1の下端部が階かでも熱変
形するおそれがあり、これに起因して各核燃料集合体g
が炉心構造物dの各上・下嵌合部d、mから引き抜けな
くなるおそれがある。
Therefore, in order to prevent the above-mentioned problem, as shown in Fig. 2, each connecting pipe f leading to the lower fitting part m of the entrance nozzle g1 is lengthened to increase the friction loss when the coolant passes through. It has also been proposed to reduce the gap between the entrance nozzle g1 and the lower fitting part m, as shown in FIG. Not only will this deteriorate, but the lower end of the entrance nozzle g1 may also be thermally deformed, causing each nuclear fuel assembly g
may not be able to be pulled out from the upper and lower fitting parts d and m of the core structure d.

本発明は、上述した点に鑑み、液体金属冷却材を使用す
る原子炉において、炉心構造物の上・下支持板に上・下
眠合部を設け、これに挿着される核燃料集合体のエント
ランスノズルの下端開口部に抜は落ちないようにして摺
動自在に嵌装された漏洩防止部材を上記下嵌合部に上記
液体金属冷却材の圧力で圧接し得るようにし、これによ
り下に合部から液体金属冷却材の漏洩を確実に阻止して
熱の交換効率を向上するようにすると共に、燃料集合体
の装填、抜き取り等の取扱い操作を円滑に行えるように
したことを目的とする核燃料集合体を提供するものであ
る。
In view of the above-mentioned points, the present invention provides a nuclear reactor using a liquid metal coolant with upper and lower sleeping parts on the upper and lower support plates of the core structure, and a nuclear fuel assembly inserted into the sleeping parts. A leak prevention member slidably fitted into the lower end opening of the entrance nozzle so as not to fall off can be brought into pressure contact with the lower fitting part by the pressure of the liquid metal coolant, and thereby The purpose is to reliably prevent liquid metal coolant from leaking from joints to improve heat exchange efficiency, and to facilitate handling operations such as loading and unloading fuel assemblies. It provides nuclear fuel assemblies.

以下、本発明を図示の一実施例について説明する。Hereinafter, the present invention will be described with reference to an illustrated embodiment.

第4図及び第5図において、符号1は、液体金属冷却材
を使用する原子炉における炉心構造物であって、この炉
心構造物1の上・下支持板2,3は流量調節孔4を有す
る連結管5によって連結されており、この連結管5の開
口部に位置する上記上・下支持板2,3には球面上・下
眠合部6,7か設けられている。
In FIGS. 4 and 5, reference numeral 1 denotes a core structure in a nuclear reactor that uses liquid metal coolant, and upper and lower support plates 2 and 3 of this core structure 1 have flow rate adjustment holes 4. The upper and lower supporting plates 2 and 3 located at the opening of the connecting tube 5 are provided with spherical upper and lower mating portions 6 and 7, respectively.

父上記上支持板2の上投合部6には燃料ピン8を収納し
た燃料集合体9のエントランスノズル10が投合して挿
着されてオリ、このエントランスノズル10の中程には
各オリフィス11が上記流量調節孔4からの冷却材を流
入し得るようになっている。
An entrance nozzle 10 of a fuel assembly 9 containing a fuel pin 8 is inserted into the upper injection part 6 of the upper support plate 2, and each orifice 11 is inserted in the middle of the entrance nozzle 10. Coolant can flow in from the flow rate adjustment hole 4.

又、上記エントランスノズル10の下端開口部10aに
は、第5図に拡大して示されるように鍔部12が形成さ
れており、しかもこの下端開口部10aにはストッパ1
3aを有する漏洩防止部材13が抜は落ちないようにし
て摺動自在に嵌装されている。
Further, a flange 12 is formed at the lower end opening 10a of the entrance nozzle 10, as shown in an enlarged view in FIG.
The leakage prevention member 13 having 3a is slidably fitted in such a manner that it does not fall out.

又この漏洩防止部材13の下部13bは上記下投合部7
に上記オリフィス11から流入した液体金属冷却材の圧
力で圧接し、この下投合部7との接合面から液体金属冷
却材が漏洩しないようになっている。
Further, the lower part 13b of this leakage prevention member 13 is connected to the lower part 7.
The pressure of the liquid metal coolant flowing in from the orifice 11 presses against the lower injection part 7 to prevent the liquid metal coolant from leaking from the joint surface with the lower injection part 7.

即ち、上」己エントランスノスル10のオリフィス11
から流入しだ液体金属冷却材の圧力Peは上合己下歌合
部7の吐圧プレナムがわの冷却材の圧力PL よりも
大きい圧力で押圧しているから、この上記圧力PeとP
L との差圧が大きくなればなるほど、冷却材の漏洩防
止効果を向上し得るようになっている。
That is, the orifice 11 of the upper self-entrance nostle 10
Since the pressure Pe of the liquid metal coolant flowing from the upper and lower joints 7 is greater than the pressure PL of the coolant against the discharge pressure plenum of the upper and lower joints 7, the above pressures Pe and P
The larger the differential pressure with L, the more effective the leakage prevention effect of the coolant can be.

次に、第6図及び第7図に示される実施例は、本発明の
曲の実施例であって、これはエントランスノズル10の
鍔部12とストッパ13aとの間隙14内にガスを充填
したンール環体15を介装し、これにより冷却材が摺動
眠合部から漏洩するのを阻止するようにしたものである
Next, the embodiment shown in FIGS. 6 and 7 is an embodiment of the music of the present invention, in which the gap 14 between the flange 12 of the entrance nozzle 10 and the stopper 13a is filled with gas. A ring ring 15 is interposed therebetween to prevent the coolant from leaking from the sliding sleeping area.

次に、第8図に示される実施例はエントランスノズル1
0の段部10bと上記ストッパ13aとの間に伸張性の
はね16を介装し、このはね16の弾力と冷却材の内圧
とによって下に合部7に漏洩防止部材13を圧接し得る
ようにしだものである。
Next, the embodiment shown in FIG.
An extensible spring 16 is interposed between the stepped portion 10b of No. 0 and the stopper 13a, and the elasticity of the spring 16 and the internal pressure of the coolant press the leakage prevention member 13 downwardly to the joint portion 7. It's just something you get.

さらに又、第9図に示される本発明の実施例は、漏洩防
止部材13の下部13bに扁平な段部13cを設け、こ
れにより扁平な下投合部7に圧接し、これにより冷却材
の漏洩を防止するようにしたものである。
Furthermore, in the embodiment of the present invention shown in FIG. 9, a flat step part 13c is provided at the lower part 13b of the leakage prevention member 13, and this makes pressure contact with the flat lower part 7, thereby causing leakage of coolant. It is designed to prevent this.

又、第10図に示される本発明の曲の実施例は、エント
ランスノズル10の下端開口部10aと漏洩防止部材1
3とを伸縮する金属製のベロース17によって連結した
ものであり、実質的には、上述した具体例と同一内容を
なすものである。
Furthermore, the embodiment of the song of the present invention shown in FIG.
3 are connected by a metal bellows 17 that expands and contracts, and is substantially the same as the specific example described above.

さらに又、第11図に示される本発明の曲の実施例は、
第10図に示す実施例の変形例であって、これU、ベロ
ース17の外周に円筒状の保護カバー18を設けたもの
であり、実質的には上述した実施例と同一内容をなすも
のである。
Furthermore, the embodiment of the song of the present invention shown in FIG.
This is a modification of the embodiment shown in FIG. 10, in which a cylindrical protective cover 18 is provided around the outer periphery of the bellows 17, and is substantially the same as the embodiment described above. be.

以上述べたように本発明によれば、液体金属冷却材を使
用する原子炉において、炉心構造物1の上・下支持板2
,3に上・下眠合部6,7を設け、これに挿着される燃
料集合体9のエントランスノズル10の下端開口部10
aに抜は落ちないようにして摺動自在に嵌装された漏洩
防止部材13を上記下に合部7に液体金属冷却材の圧力
で圧接し得るようになっているので、冷却材の適正流量
分布か得られると共に、熱変形や異常加熱を起すおそれ
もなくなり、さらに構成も簡素であるから、取扱い操作
も容易である等の優れた効果を有する。
As described above, according to the present invention, in a nuclear reactor using a liquid metal coolant, the upper and lower support plates 2 of the core structure 1
, 3 are provided with upper and lower sleeping parts 6, 7, and a lower end opening 10 of the entrance nozzle 10 of the fuel assembly 9 inserted therein.
The leakage prevention member 13, which is slidably fitted in the hole a and not falling, can be pressed to the joint 7 below by the pressure of the liquid metal coolant, so that the appropriate coolant is used. It has excellent effects such as obtaining a good flow rate distribution, eliminating the risk of thermal deformation or abnormal heating, and also being simple in structure and easy to handle.

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

第1図乃至第3図は既に提案されている原子炉に使用さ
れる核燃料集合体を説明するための各図、第4図は本発
明による核燃料集合体部分断面図、第5図は本発明の要
部のみを示す拡大断面図、第6図乃至第11図は本発明
の曲の実施例を示す図である。 1・・・炉心構造物、2,3・・・上・下支持板、6゜
7・・・上・下嵌合部、9・・・燃料集合体、10・・
・エントランスノスル、13・・・漏洩防止部材。
1 to 3 are diagrams for explaining nuclear fuel assemblies used in nuclear reactors that have already been proposed, FIG. 4 is a partial sectional view of a nuclear fuel assembly according to the present invention, and FIG. 5 is a diagram illustrating the present invention. FIGS. 6 to 11 are enlarged sectional views showing only the main parts of the music piece, and FIGS. DESCRIPTION OF SYMBOLS 1... Core structure, 2, 3... Upper and lower support plates, 6°7... Upper and lower fitting parts, 9... Fuel assembly, 10...
・Entrance nostle, 13...Leakage prevention member.

Claims (1)

【特許請求の範囲】[Claims] 1 液体金属冷却材を使用する原子炉において、この原
子炉の炉心構造物の上・下支持板に設けられたテーパー
面を有する上・下眠合部と、この上投合部に投合するよ
うに形成された燃料集合体のエントランスノズルと、こ
のエントランスノズルの下端開口部に抜は落ちないよう
にして摺動自在に眠装されしかも上記下嵌合部に上記液
体金属冷却材の圧力で圧接し得るように設けられた漏洩
防止部材とよりなる核燃料集合体。
1. In a nuclear reactor that uses liquid metal coolant, upper and lower coupling parts with tapered surfaces are provided on the upper and lower support plates of the core structure of this reactor, and The entrance nozzle of the formed fuel assembly and the lower end opening of this entrance nozzle are fitted so as to be slidable so as not to fall, and are pressed against the lower fitting part by the pressure of the liquid metal coolant. A nuclear fuel assembly comprising a leakage prevention member provided to obtain a leakage prevention member.
JP52056216A 1977-05-16 1977-05-16 nuclear fuel assembly Expired JPS5941557B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP52056216A JPS5941557B2 (en) 1977-05-16 1977-05-16 nuclear fuel assembly

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP52056216A JPS5941557B2 (en) 1977-05-16 1977-05-16 nuclear fuel assembly

Publications (2)

Publication Number Publication Date
JPS53141885A JPS53141885A (en) 1978-12-11
JPS5941557B2 true JPS5941557B2 (en) 1984-10-08

Family

ID=13020899

Family Applications (1)

Application Number Title Priority Date Filing Date
JP52056216A Expired JPS5941557B2 (en) 1977-05-16 1977-05-16 nuclear fuel assembly

Country Status (1)

Country Link
JP (1) JPS5941557B2 (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS60212722A (en) * 1984-04-06 1985-10-25 Sasaki Celluloid Kogyosho:Kk Decoration working method to frame of spectacles
JPS62139698U (en) * 1986-02-28 1987-09-03

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2963473B1 (en) * 2010-07-27 2012-09-07 Areva Np METHOD FOR CONTROLLING POSITIONS OF NUCLEAR FUEL ASSEMBLIES WITHIN A NUCLEAR REACTOR HEART AND CORRESPONDING CONTROL ASSEMBLY
CN105280247B (en) * 2015-10-14 2018-02-02 上海核工程研究设计院 A kind of new the pipe sleeve pipe connecting structure being automatically positioned and assemble method

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS60212722A (en) * 1984-04-06 1985-10-25 Sasaki Celluloid Kogyosho:Kk Decoration working method to frame of spectacles
JPS62139698U (en) * 1986-02-28 1987-09-03

Also Published As

Publication number Publication date
JPS53141885A (en) 1978-12-11

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