JP2958047B2 - Fuel assembly - Google Patents
Fuel assemblyInfo
- Publication number
- JP2958047B2 JP2958047B2 JP2102823A JP10282390A JP2958047B2 JP 2958047 B2 JP2958047 B2 JP 2958047B2 JP 2102823 A JP2102823 A JP 2102823A JP 10282390 A JP10282390 A JP 10282390A JP 2958047 B2 JP2958047 B2 JP 2958047B2
- Authority
- JP
- Japan
- Prior art keywords
- fuel assembly
- pad
- tube
- fuel
- horizontal member
- 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 - Fee Related
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)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Description
【発明の詳細な説明】 ［産業上の利用分野］ 本発明は高速増殖炉に係わり、とくに炉心の反応度の
制御性向上に好適な燃料集合体、およびそれらで構成し
た炉心に関する。Description: BACKGROUND OF THE INVENTION The present invention relates to a fast breeder reactor, and more particularly to a fuel assembly suitable for improving the controllability of the reactivity of a core, and a core composed of the same.
［従来の技術］ 原子炉の炉心の半径方向の膨張により、炉心の反応度
が減少することが、例えば、三木良平著、「高速増殖
炉」、日刊工業新聞、p101〜105（昭和50.9）において
論じられている。[Related Art] Reactivity of a reactor core due to radial expansion of a reactor core is reduced, for example, as described in Ryohei Miki, “Fast Breeder Reactor”, Nikkan Kogyo Shimbun, pp. 101-105 (Showa 50.9). Is being discussed.
従来、高速増殖炉の燃料集合体は、前出「高速増殖
炉」に記載のように、核燃料物質を被覆管に封入して多
数束ねた燃料棒束とこれを取り囲むラッパ管、燃料棒束
より上方にある冷却材流出部、燃料棒束の下方にある冷
却材流入部、および燃料集合体上端部と燃料棒領域のす
ぐ上のラッパ管側面に配置した荷重パッド（夫々、上部
パッド、中間パッドと称す。）からなっていた。この場
合、炉心の半径方向膨張の主要な原因は、冷却材温度上
昇に伴う炉心支持板の熱膨張により燃料集合体の相互間
の間隔が増体することによる。Conventionally, a fuel assembly of a fast breeder reactor is, as described in the above-mentioned `` fast breeder reactor '', composed of a bundle of fuel rods in which nuclear fuel material is enclosed in a cladding tube and bundled, a wrapper tube surrounding the bundle, and a bundle of fuel rods. Coolant outflow above, coolant inflow below the bundle of fuel rods, and load pads located on the side of the wrapper tube just above the fuel assembly top and fuel rod area (top pad, middle pad, respectively) ). In this case, the main cause of the radial expansion of the core is that the interval between the fuel assemblies increases due to the thermal expansion of the core support plate accompanying the increase in the coolant temperature.
［発明が解決しようとする課題］ 上記従来技術では、炉心内温度が急激に上昇した場合
に、冷却材と炉心支持板の間の熱伝達が小さいために炉
心支持板の熱膨張に時間を要する。したがって、炉心に
流入する冷却材の流量の増減による冷却材の温度変化に
対する炉心の半径方向膨張の応答性は鈍く、迅速な反応
度制御ができないという問題があった。[Problems to be Solved by the Invention] In the above-described conventional technique, when the temperature in the core rises rapidly, heat transfer between the coolant and the core support plate is small, so that it takes time for the thermal expansion of the core support plate. Therefore, the response of the radial expansion of the core to the temperature change of the coolant due to the increase and decrease of the flow rate of the coolant flowing into the core is slow, and there is a problem that rapid reactivity control cannot be performed.
本発明の目的は、冷却材の温度変化に対する炉心の半
径方向膨張の応答性を高めることにより、迅速な反応度
の制御を達成することにある。SUMMARY OF THE INVENTION It is an object of the present invention to achieve quick reactivity control by increasing the responsiveness of radial expansion of a reactor core to a change in coolant temperature.
［課題を解決するための手段］ 上記課題を解決するための本発明の燃料集合体の構成
は、核燃料物質を充填した複数個の燃料棒を取囲み、上
方に中間パッド、上部パッドを備えたラッパ管と、冷却
材流入部および流出部からなる燃料集合体において、上
記中間パッドないし上部パッドはラッパ管の内側方向に
突出する水平部材とラッパ管の外側方向に突出する突出
部材からなり、炉心上部のラッパ管の内側の上記中間パ
ッドと上部パッドの水平部材間に配設され、１端はいず
れかのパッド部材の水平部材に拘束され、他の１端は上
記と対抗するパッド部材の水平部材に係合する垂直部材
とをそなえ、いずれかのパッドの上記水平部材はラッパ
管壁を貫通して半径方向に移動自在であるように構成し ［作用］ 本発明に係る燃料集合体の作用について第２図
（ａ），（ｂ）を用いて説明する。[Means for Solving the Problems] The structure of the fuel assembly of the present invention for solving the above problems surrounds a plurality of fuel rods filled with nuclear fuel material, and includes an intermediate pad and an upper pad above. In a fuel assembly comprising a wrapper pipe and a coolant inlet and outlet, the intermediate pad or upper pad comprises a horizontal member projecting inwardly of the wrapper pipe and a projecting member projecting outwardly of the wrapper pipe. The horizontal pad of the upper pad is disposed between the intermediate pad and the horizontal member of the upper pad, one end of which is constrained by the horizontal member of one of the pad members, and the other end of the horizontal member of the pad member opposed to the above. A vertical member engaging with the member is provided, and the horizontal member of one of the pads is configured to be able to move radially through the trumpet tube wall. [Operation] The operation of the fuel assembly according to the present invention To There a second view (a), is described with reference to (b).
第２図（ａ），（ｂ）は、燃料集合体の上端部分の上
部パッド部の部分断面図である。ラッパ管４の内側に、
下端部が拘束された垂直部材16があり、その上端部は、
パッド９（9A,9B）に係合されている。ラッパ管４の貫
通孔がラッパ管壁を鋭角に切断した形状をなしている。FIGS. 2A and 2B are partial cross-sectional views of an upper pad portion at an upper end portion of the fuel assembly. Inside the trumpet tube 4,
There is a vertical member 16 whose lower end is restrained, and its upper end is
It is engaged with the pad 9 (9A, 9B). The through hole of the trumpet tube 4 has a shape obtained by cutting the trumpet tube wall at an acute angle.
第２図（ａ）は、原子炉が定格運転時の状態を示すも
のである。いま、急に冷却材温度が上昇した場合を想定
する。第２図（ｂ）に示すように、下端部が拘束されて
いる垂直部材16は、熱膨張により軸方向（上方）に膨張
し、パッド９の9A部を押上げるが、この時、ラッパ管４
の尖頭部が、てこ運動の支点となって突起状の9Bを下方
に引下げる作用をする。このようにして隣接する燃料集
合体の突起同志が相互に押合うことにより、燃料集合体
間の間隔が拡がり、炉心は半径方向に膨張するようにな
る。FIG. 2 (a) shows the state of the reactor during rated operation. Now, assume that the coolant temperature suddenly rises. As shown in FIG. 2 (b), the vertical member 16 whose lower end is constrained expands in the axial direction (upward) due to thermal expansion, and pushes up the 9A portion of the pad 9. 4
The point of the sword serves as a fulcrum of the lever movement and acts to lower the protruding 9B downward. In this manner, the protrusions of the adjacent fuel assemblies press against each other, so that the interval between the fuel assemblies increases, and the core expands in the radial direction.
冷却材と前記垂直部材の間の熱伝達はきわめて大きい
ため、冷却材の温度変化に対する炉心の半径方向の膨張
の応答性は高くなり、反応度の迅速な制御が可能とな
る。Since the heat transfer between the coolant and the vertical member is extremely large, the responsiveness of the radial expansion of the reactor core to the temperature change of the coolant is high, and the reactivity can be quickly controlled.
［実施例］ 以下本発明の実施例を第１図〜第７図を用いて説明す
る。Embodiment An embodiment of the present invention will be described below with reference to FIGS. 1 to 7.
第１図（ａ）は、本発明の第１実施例に係る燃料集合
体と炉心支持板構造の部分断面図、第１図（ｂ）は、第
１図（ａ）のＡ−Ａ線切断の水平断面図である。FIG. 1 (a) is a partial cross-sectional view of a fuel assembly and a core support plate structure according to a first embodiment of the present invention, and FIG. 1 (b) is a sectional view taken along line AA of FIG. 1 (a). FIG.
第１図（ａ），（ｂ）において、２は、燃料集合体、
４は、ラッパ管、６は、ラッパ管上部の冷却材流出部、
８は、燃料棒束、９は、上部パッド、10は、中間パッ
ド、12は、ラッパ管冷却材流入部、14は、炉心支持板、
16は、中空円筒（垂直部材）、18は、固定部材、20は、
開口である。1 (a) and 1 (b), reference numeral 2 denotes a fuel assembly,
4 is a trumpet tube, 6 is a coolant outlet at the top of the trumpet tube,
8 is a fuel rod bundle, 9 is an upper pad, 10 is an intermediate pad, 12 is a trumpet tube coolant inlet, 14 is a core support plate,
16 is a hollow cylinder (vertical member), 18 is a fixed member, 20 is
It is an opening.
第１図（ａ），（ｂ）の構成は、燃料集合体２は、核
燃料物質を充填した燃料棒束８と、これを取り囲むラッ
パ管４、ラッパ管上部に配置された冷却材流出部６、ラ
ッパ管下部に配置された冷却材流入部12とからなる。1 (a) and 1 (b), the fuel assembly 2 is composed of a fuel rod bundle 8 filled with nuclear fuel material, a wrapper pipe 4 surrounding the fuel rod bundle 8, and a coolant outflow portion 6 arranged above the wrapper pipe. And a coolant inflow section 12 arranged at the lower part of the trumpet tube.
燃料集合体２は、冷却材流入部は12を介して、炉心支
持板14に片持ち梁状に取り付けられ、通常状態では隣接
する燃料集合体と、第１図Ａ−ＡおよびＢ−Ｂで互いに
軽く接触するように配置されている。この接触は、ラッ
パ管の外側面に設けた上部パッド９および中間パッド10
を介してなされる。The fuel assembly 2 is attached to the core support plate 14 in a cantilever manner through the coolant inflow portion 12, and in a normal state, the fuel assembly 2 is adjacent to the fuel assembly in FIGS. 1A-A and BB. They are arranged to be in light contact with each other. This contact occurs between the upper pad 9 and the intermediate pad 10 provided on the outer surface of the wrapper tube.
Made through.
本実施例は、燃料集合体２の上端部分に、ラッパ管の
外側面を貫通して半径方向に突出する機構を設けた点に
特徴がある。This embodiment is characterized in that a mechanism is provided at the upper end portion of the fuel assembly 2 so as to protrude in the radial direction through the outer surface of the trumpet tube.
すでに第２図（ａ）、（ｂ）によって発明したよう
に、この突出機構は、ラッパ管の上端部側面に所定角度
毎に設けた開口20からラッパ管４の内側方向に突出する
水平部材9Aと、前記水平部材の外端部と一体化された垂
直な突起部材9B（水平部材と垂直な突起部材は上部パッ
ド９を構成する）と、ラッパ管の内側面に沿って、ラッ
パ管中心軸方向に延びた中空円筒16および前記中空円筒
の下端を固定するための部材18からなる。前記水平部材
9Aは前記中空円筒16の上端に拘束されているが、ラッパ
管には固定されていない。したがって、上部パッド９
は、前記中空円筒16の上端が軸方向に変位するにつれ
て、前記開口20を支点とする「てこ運動」を行う。これ
により、上部パッド９は燃料集合体の半径方向に突出す
ることになる。As shown in FIGS. 2 (a) and 2 (b), the projecting mechanism comprises a horizontal member 9A projecting inward from the wrapper tube 4 from an opening 20 provided at a predetermined angle on the side surface of the upper end of the wrapper tube. A vertical projecting member 9B integrated with the outer end of the horizontal member (the projecting member perpendicular to the horizontal member constitutes an upper pad 9); and a center axis of the trumpet tube along the inner surface of the trumpet tube. It comprises a hollow cylinder 16 extending in the direction and a member 18 for fixing the lower end of the hollow cylinder. The horizontal member
9A is constrained by the upper end of the hollow cylinder 16, but is not fixed to the trumpet tube. Therefore, the upper pad 9
Performs a “lever motion” with the opening 20 as a fulcrum as the upper end of the hollow cylinder 16 is displaced in the axial direction. As a result, the upper pad 9 projects in the radial direction of the fuel assembly.
前記中空円筒16の上端の変位は、熱膨張の差異により
生じる。すなわち、中空円筒16は、ラッパ管の材料より
も大きな熱膨張率を有する材料からなる。例えば、中空
円筒16はオーステナイト鋼からなるのに対しラッパ管は
フェライト鋼からなる。オーステナイト鋼はフェライト
鋼の約２倍の熱膨張率を有する。The displacement of the upper end of the hollow cylinder 16 is caused by a difference in thermal expansion. That is, the hollow cylinder 16 is made of a material having a larger coefficient of thermal expansion than the material of the wrapper tube. For example, the hollow cylinder 16 is made of austenitic steel, while the trumpet tube is made of ferritic steel. Austenitic steels have a coefficient of thermal expansion about twice that of ferritic steels.
原子炉を定格運転中は、冷却材温度は一定の範囲内に
あり、上部パッド９は「てこ運動」をしない。冷却材の
流量が減少するような事象を仮想した場合、燃料集合体
において冷却材の温度が上昇すると、前記中空円筒とラ
ッパ管の熱膨張差により、てこの原理にしたがって上部
パッド９は、半径方向に突出し、隣接する燃料集合体の
上部パッド同士が押し合うため、燃料集合体間の間隔が
増大する。これは、炉心が径方向に膨張したことであ
り、これにより反応度が低減される。したがって、本実
施例によれば、急激な冷却材流量喪失や余熱源喪失とい
った要因に対して受動的に安全な原子炉を提供できる可
能性が高くなる。During rated operation of the reactor, the coolant temperature is within a certain range and the upper pad 9 does not "lever". If the temperature of the coolant in the fuel assembly rises in a hypothetical event that the flow rate of the coolant decreases, the upper pad 9 has a radius according to the leverage principle due to the difference in thermal expansion between the hollow cylinder and the wrapper tube. Since the upper pads of the fuel assemblies protrude in the direction and the upper pads of the adjacent fuel assemblies press against each other, the distance between the fuel assemblies increases. This is due to the radial expansion of the core, which reduces the reactivity. Therefore, according to the present embodiment, there is a high possibility that a reactor that is passively safe against factors such as a sudden loss of the coolant flow rate and a loss of the residual heat source can be provided.
つぎに、第３図（ａ）、（ｂ）および第４図（ａ）、
（ｂ）によって、本発明の第２実施例を説明する。Next, FIGS. 3 (a) and (b) and FIG. 4 (a),
(B) A second embodiment of the present invention will be described.
第３図（ａ）は、本発明の第２実施例に係る燃料集合
体と炉心支持板構造の部分断面図、第３図（ｂ）は第３
図（ａ）のＡ−Ａ線切断の水平断面図、第４図（ａ）、
（ｂ）は、同上の作用を説明する説明図である。FIG. 3A is a partial cross-sectional view of a fuel assembly and a core support plate structure according to a second embodiment of the present invention, and FIG.
FIG. 4 (a) is a horizontal sectional view taken along the line AA in FIG.
(B) is an explanatory view explaining an operation same as the above.
第２実施例が、第１実施例と異なる点は、燃料集合体
２の燃料領域の直ぐ上部に配置した中間パッド10の個所
に第１実施例と同様な突出機構を設けたことである。The second embodiment is different from the first embodiment in that a projecting mechanism similar to that of the first embodiment is provided at an intermediate pad 10 disposed immediately above the fuel region of the fuel assembly 2.
第３図および第４図の符号はすべて第１図と同様であ
る。3 and 4 are the same as those in FIG.
第４図（ａ）は、原子炉定格運転時の状態であり、同
図（ｂ）は、温度上昇時の状態を示したものである。FIG. 4 (a) shows a state at the time of reactor rated operation, and FIG. 4 (b) shows a state at the time of temperature rise.
本実施例の場合の作用の原理は、第２図（ａ）、
（ｂ）に説明したものと同様で、ただ、熱膨張による作
用力の方向が、上方から下方へ向って作用する点のみが
異なる。The principle of operation in the case of this embodiment is shown in FIG.
As in the case of (b), the only difference is that the direction of the acting force due to thermal expansion acts from above to below.
したがって、第２実施例によって、第１実施例と同様
な効果が期待できる。Therefore, the second embodiment can expect the same effects as the first embodiment.
第５図（ａ）は、本発明の第３実施例に係る燃料集合
体と炉心支持板構造の部分断面図、同図（ｂ）は、第５
図（ａ）のＡ−Ａ線切断の水平断面図である。FIG. 5 (a) is a partial cross-sectional view of a fuel assembly and a core support plate structure according to a third embodiment of the present invention, and FIG.
FIG. 2 is a horizontal sectional view taken along line AA of FIG.
第５図の符号は、第３図と全く同様であり、中空円筒
の内側に炭化硼素22を新しく設けたものである。The reference numerals in FIG. 5 are exactly the same as those in FIG. 3, except that boron carbide 22 is newly provided inside the hollow cylinder.
第３実施例では、第２実施例（第３図）で用いた中空
円筒16の内側に、炭化硼素等の中性子吸収物質を主成分
とする中性子吸収領域22を設けたことが特徴である。The third embodiment is characterized in that a neutron absorbing region 22 mainly composed of a neutron absorbing substance such as boron carbide is provided inside the hollow cylinder 16 used in the second embodiment (FIG. 3).
このことにより、第１実施例および第２実施例と同様
な効果を得ることができるほかに、軸方向の中性子しゃ
へい能力が増大するという効果が付加されることにな
る。As a result, in addition to the effects similar to those of the first and second embodiments, the effect of increasing the neutron shielding ability in the axial direction is added.
第６図は、本発明の第４実施例に係る燃料集合体の中
間パッド部で切断した水平断面図である。FIG. 6 is a horizontal cross-sectional view of a fuel assembly according to a fourth embodiment of the present invention, taken along an intermediate pad portion.
第２〜第３実施例において、正六面体のラッパ管の各
面中間パッド部にそれぞれ突出機構を設けていたが、本
実施例において、一面おきに、三面（六面ではなく）に
ついてのみ突出機構を設けるようにしたものである。In the second and third embodiments, the protruding mechanism is provided on each surface intermediate pad portion of the regular hexahedral trumpet tube. However, in the present embodiment, the protruding mechanism is provided on every other surface only on three surfaces (not on six surfaces). Is provided.
第４実施例の効果は、突出機構の数を半減することに
より生産効率の向上をはかることができるのみならず、
前実施例と同様に炉心の半径方向膨張の応答性を高める
ことに寄与することができる。The effect of the fourth embodiment is that not only can the production efficiency be improved by halving the number of projecting mechanisms,
As in the previous embodiment, it is possible to contribute to improving the response of the radial expansion of the core.
第７図は、本実施例に基づいて構成した燃料集合体の
炉内配置平面図である。第７図において、30は、炉心燃
料集合体、31は、ブランケット集合体である。本炉心構
成では、炉心燃料集合体30には、第４実施例（第６図）
に示したものを用いた。この場合には、隣接する２体の
集合体において、突出機構のある中間パッドと、従来例
の固定された中間パッドとが接触するような配置をとる
ことになるが、これでも、炉心の半径方向膨張の応答性
を高める役割を果すことができる。但し、ブランケット
燃料集合体に関しては、炉心の周辺方向に位置して、反
応度への寄与は小さいことから、従来通りのパッドの燃
料集合体を使用する。FIG. 7 is a plan view of the inside of a furnace of a fuel assembly constituted based on this embodiment. In FIG. 7, 30 is a core fuel assembly, and 31 is a blanket assembly. In this core configuration, the core fuel assembly 30 includes the fourth embodiment (FIG. 6).
Was used. In this case, an arrangement is made such that the intermediate pad having the protruding mechanism and the fixed intermediate pad of the conventional example are in contact with each other in the two adjacent aggregates. It can play a role of increasing the responsiveness of directional expansion. However, the blanket fuel assembly is located in the peripheral direction of the reactor core and has a small contribution to the reactivity. Therefore, the fuel assembly of the conventional pad is used.
また、炉心上部に設けた垂直部材の形状は、ラッパ管
中心軸と同軸の円筒状でもよく、正六角柱状でもよい。
さらに垂直部材の材料は、ラッパ管材料よりも熱膨張率
の高いものがよく、将来ラッパ管はフェライト鋼になる
可能性を考慮して、オーステナイト系のオーステナイト
鋼などが有望である。Further, the shape of the vertical member provided at the upper part of the core may be a cylindrical shape coaxial with the central axis of the trumpet tube, or a regular hexagonal column shape.
Further, the material of the vertical member is preferably a material having a higher coefficient of thermal expansion than the material of the wrapper tube, and in view of the possibility that the wrapper tube will become ferritic steel in the future, austenitic austenitic steel or the like is promising.
［発明の効果］ 本発明によれば、高速増殖炉において、冷却材の急激
な温度変化に対する炉心の半径方向膨張の応答性が高く
なり、反応度の迅速な制御が可能となる。[Effects of the Invention] According to the present invention, in a fast breeder reactor, responsiveness of radial expansion of a reactor core to a rapid temperature change of a coolant becomes high, and quick control of reactivity becomes possible.
したがって、冷却材流量喪失や除熱源喪失といった急
激な変化に対して、即時応答して、安全側に制御できる
事故時の安全性を強調した炉心を提供することができ
る。Therefore, it is possible to provide a reactor core that emphasizes safety at the time of an accident that can be controlled to a safe side in an immediate response to a sudden change such as a loss of a coolant flow rate or a loss of a heat removal source.
第１図（ａ）は、本発明の第１実施例の燃料集合体の部
分断面図、第１図（ｂ）は、同上のＡ−Ａ断面図、第２
図（ａ）、（ｂ）は、第１実施例の作用を示す説明図、
第３図（ａ）は、本発明の第２実施例の燃料集合体の部
分断面図、第３図（ｂ）は同上のＡ−Ａ断面図、、第４
図（ａ）、（ｂ）は、第２実施例の作用説明図、第５図
（ａ）は、本発明の第３実施例の燃料集合体の部分断面
図、第５図（ｂ）は、同上のＡ−Ａ断面図、第６図は、
本発明の第４実施例の燃料集合体の水平断面図、第７図
は、第４実施例の燃料集合体で構成した炉心平面図であ
る。 ＜符号の説明＞ ２……燃料集合体、４……ラッパ管、６……ラッパ管冷
却材流出部、８……燃料棒束、９……上部パッド、10…
…中間パッド、12……ラッパ管冷却材流入部、14……炉
心支持板、16……中空円筒（垂直部材）、18……固定部
材、20……開口、22……中性子吸収領域、30……炉心燃
料集合体、31……ブランケット集合体。FIG. 1 (a) is a partial sectional view of a fuel assembly according to a first embodiment of the present invention, FIG. 1 (b) is a sectional view taken along line AA in FIG.
(A), (b) is an explanatory view showing the operation of the first embodiment,
FIG. 3 (a) is a partial sectional view of a fuel assembly according to a second embodiment of the present invention, FIG. 3 (b) is a sectional view taken along the line AA in FIG.
5 (a) and (b) are explanatory views of the operation of the second embodiment, FIG. 5 (a) is a partial sectional view of a fuel assembly of a third embodiment of the present invention, and FIG. FIG. 6 is a sectional view taken along the line AA in FIG.
FIG. 7 is a horizontal sectional view of a fuel assembly according to a fourth embodiment of the present invention, and FIG. 7 is a plan view of a core constituted by the fuel assembly according to the fourth embodiment. <Explanation of reference numerals> 2 ... fuel assembly, 4 ... trumpet tube, 6 ... trumpet tube coolant outlet, 8 ... fuel rod bundle, 9 ... upper pad, 10 ...
... Intermediate pad, 12 ... Wrapper tube coolant inlet, 14 ... Core support plate, 16 ... Hollow cylinder (vertical member), 18 ... Fixed member, 20 ... Opening, 22 ... Neutron absorption area, 30 …… Core fuel assemblies, 31 …… Blanket assemblies.
───────────────────────────────────────────────────── フロントページの続き (56)参考文献 特開 昭48−73693（ＪＰ，Ａ) 特開 昭59−187285（ＪＰ，Ａ) 特開 昭63−308597（ＪＰ，Ａ) 特開 昭63−195590（ＪＰ，Ａ) 特開 昭55−132988（ＪＰ，Ａ) (58)調査した分野(Int.Cl.6，ＤＢ名) G21C 3/30 ──────────────────────────────────────────────────続 き Continuation of the front page (56) References JP-A-48-73693 (JP, A) JP-A-59-187285 (JP, A) JP-A-63-308597 (JP, A) 195590 (JP, A) JP-A-55-132988 (JP, A) (58) Fields investigated (Int. Cl. 6 , DB name) G21C 3/30
Claims (8)
囲み、上方に中間パッド、上部パッドを備えたラッパ管
と、冷却材流入部および流出部からなる燃料集合体にお
いて、上記中間パッドないし上部パッドはラッパ管の内
側方向に突出する水平部材とラッパ管の外側方向に突出
する突出部材からなり、炉心上部のラッパ管の内側の上
記中間パッドと上部パッドの水平部材間に配設され、１
端はいずれかのパッド部材の水平部材に拘束され、他の
１端は上記と対抗するパッド部材の水平部材に係合する
垂直部材とをそなえ、いずれかのパッドの上記水平部材
はラッパ管壁を貫通して半径方向に移動自在であるよう
に構成したことを特徴とする燃料集合体。1. A fuel assembly, comprising a plurality of fuel rods filled with the fuel substance, a trumpet tube having an intermediate pad and an upper pad provided above, and a coolant inflow portion and an outflow portion, the fuel assembly comprising: The pad or upper pad includes a horizontal member protruding inwardly of the wrapper tube and a protruding member protruding outwardly of the wrapper tube, and is disposed between the intermediate pad and the horizontal member of the upper pad inside the wrapper tube above the core. And 1
One end is constrained by the horizontal member of one of the pad members, the other end has a vertical member engaging the horizontal member of the opposing pad member, and the horizontal member of one of the pads is a trumpet tube wall. A fuel assembly characterized in that the fuel assembly is configured to be movable in a radial direction through the fuel assembly.
いずれかのパッドは、ラッパ管側面に所定角度毎に設け
た開口を通る水平部材と、前記水平部材の外端に１体化
された突出部材からなることを特徴とする燃料集合体。2. The fuel assembly according to claim 1, wherein any one of the pads is formed as a horizontal member passing through an opening provided at a predetermined angle on a side surface of the wrapper tube, and is integrated into an outer end of the horizontal member. A fuel assembly comprising a projected member.
を、燃料棒領域のすぐ上部のラッパ管側面に設けたこと
を特徴とする燃料集合体。3. The fuel assembly according to claim 1, wherein the pad is provided on a side surface of the flapper tube immediately above the fuel rod region.
燃料集合体上端部のラッパ管側面に設けたことを特徴と
する燃料集合体。4. The method according to claim 1, wherein the opening is
A fuel assembly provided on the side of a wrapper tube at the upper end of the fuel assembly.
の熱膨張率が、ラッパ管の熱膨張率よりも大きいことを
特徴とする燃料集合体。5. The fuel assembly according to claim 1, wherein a thermal expansion coefficient of the vertical member is larger than a thermal expansion coefficient of the flared tube.
の形体が、ラッパ管中心軸と同軸の中空円筒であること
を特徴とする燃料集合体。6. The fuel assembly according to claim 1, wherein the shape of the vertical member is a hollow cylinder coaxial with the center axis of the wrapper tube.
の形体が、ラッパ管中心軸と同軸の中空正六角柱である
ことを特徴とする燃料集合体。7. The fuel assembly according to claim 1, wherein the shape of the vertical member is a hollow regular hexagonal column coaxial with the center axis of the trumpet tube.
１体以上装荷してなることを特徴とする原子炉の炉心。8. A nuclear reactor core comprising at least one fuel assembly according to any one of claims 1 to 7.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP2102823A JP2958047B2 (en) | 1990-04-20 | 1990-04-20 | Fuel assembly |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP2102823A JP2958047B2 (en) | 1990-04-20 | 1990-04-20 | Fuel assembly |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH04212094A JPH04212094A (en) | 1992-08-03 |
| JP2958047B2 true JP2958047B2 (en) | 1999-10-06 |
Family
ID=14337744
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP2102823A Expired - Fee Related JP2958047B2 (en) | 1990-04-20 | 1990-04-20 | Fuel assembly |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JP2958047B2 (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN109830315B (en) * | 2019-01-29 | 2022-08-02 | 哈尔滨工程大学 | Expanded nuclear reactor core |
-
1990
- 1990-04-20 JP JP2102823A patent/JP2958047B2/en not_active Expired - Fee Related
Also Published As
| Publication number | Publication date |
|---|---|
| JPH04212094A (en) | 1992-08-03 |
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