JPS6039194B2 - nuclear fuel assembly - Google Patents

nuclear fuel assembly

Info

Publication number
JPS6039194B2
JPS6039194B2 JP52129728A JP12972877A JPS6039194B2 JP S6039194 B2 JPS6039194 B2 JP S6039194B2 JP 52129728 A JP52129728 A JP 52129728A JP 12972877 A JP12972877 A JP 12972877A JP S6039194 B2 JPS6039194 B2 JP S6039194B2
Authority
JP
Japan
Prior art keywords
fuel
fuel assembly
nuclear fuel
nuclear
fuel element
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
JP52129728A
Other languages
Japanese (ja)
Other versions
JPS5464287A (en
Inventor
厚治 蛭川
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 JP52129728A priority Critical patent/JPS6039194B2/en
Publication of JPS5464287A publication Critical patent/JPS5464287A/en
Publication of JPS6039194B2 publication Critical patent/JPS6039194B2/en
Expired legal-status Critical Current

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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

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  • Monitoring And Testing Of Nuclear Reactors (AREA)

Description

【発明の詳細な説明】 本発明は沸騰軽水型原子炉用の核燃料集合体特に軸方向
の出力分布を適正化した核燃料棒に関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a nuclear fuel assembly for a boiling light water reactor, particularly to nuclear fuel rods with optimized axial power distribution.

沸騰水型原子炉の炉心は、多数の棒状燃料要素を整列配
置し、複数のスべ−サにて燃料要素間隔を保持し、上下
端をタイプレートで束ねて、燃料東としたものに、燃料
束冷却用の冷却材流路を確保するチャンネルボックスを
かぶせて核燃料集合体となし多数垂直列に並べたもので
ある。
The core of a boiling water reactor consists of a large number of rod-shaped fuel elements arranged in a row, the spacing between the fuel elements maintained by a plurality of spacers, and the upper and lower ends tied together with a tie plate to form the fuel east. A large number of nuclear fuel assemblies are arranged in vertical rows by covering them with a channel box to secure a coolant flow path for cooling the fuel bundle.

そして、4体の核燃料集合体に1体の割合で、4体の核
燃料集合体に囲まれたチャンネルボックス外の漏洩流路
に十字形制御棒を配置し、炉心下部より挿入できる様に
なっている。
Then, a cruciform control rod was placed in the leakage passage outside the channel box surrounded by the four nuclear fuel assemblies, one in every four nuclear fuel assemblies, so that they could be inserted from the bottom of the reactor core. There is.

沸騰軽水型原子炉では、この制御棒を使用して、炉心の
反応度制御と出力分布制御を行っている。
In boiling light water reactors, these control rods are used to control the reactivity and power distribution of the reactor core.

沸騰軽水型原子炉の燃料集合体内では下部よりボィドが
発生し、上方に行くに従ってボィド量が増すため、出力
分布は第1図に示す様にボトムピークの形になる。
In the fuel assembly of a boiling light water reactor, voids occur from the bottom, and the amount of voids increases as you move upward, so the power distribution takes the form of a bottom peak, as shown in Figure 1.

これを改善して下部での出力を抑えるために現在初装荷
燃料には、下方に可燃毒物(od)を添加している。し
かし、現在のGd添加濃度では燃料の燃焼が進んだ時点
では下部の出力分布のピークが大きくなり過ぎるため、
深挿入の制御榛と、浅挿入の制御榛を適当なパターンで
配置して、深挿入制御棒で主として反応度制御を行い、
浅挿入の制御陣で下部の出力ピークを抑えている。この
様に浅挿入制御榛を使用すると、パターン交換時、浅挿
入制御棒を全引抜する場合に、制御棒先端部附近の局所
熱出力及びその増加率が大きくて操作が複雑になったり
、困難になる場合がある。
In order to improve this and suppress the output in the lower part, burnable poison (OD) is currently added to the lower part of the initially loaded fuel. However, with the current concentration of Gd added, the peak of the power distribution at the bottom becomes too large once the combustion of the fuel has progressed.
By arranging deep insertion control rods and shallow insertion control rods in an appropriate pattern, the deep insertion control rods mainly control the reactivity.
The shallow insertion control layer suppresses the output peak at the bottom. If shallow insertion control rods are used in this way, when the shallow insertion control rod is completely withdrawn during pattern exchange, the local heat output near the control rod tip and its increase rate are large, making operation complicated and difficult. It may become.

これを改善して、浅挿入制御榛を使用せず深制御棒だけ
で、反応度制御と核燃料集合体の鞠方向出力分布制御が
できる様に、最近核燃料集合体のほぼ中央から下方の出
力分布のピークを下げる方法として、燃料要素の下半分
に上半分より低濃縮の燃料を用いた核燃料集合体や濃縮
度を上半分と下半分で変えるかわり、一様平均濃縮度で
ああるが、上下で可燃毒物の濃度を変えて下半分の可燃
毒物の濃度を高くした核燃料集合体が提案されている。
By improving this, it is now possible to control the reactivity and the power distribution in the direction of the nuclear fuel assembly using only deep control rods without using shallow insertion control rods. As a method of lowering the peak of the fuel element, instead of using a nuclear fuel assembly in which the lower half of the fuel element is enriched less than the upper half or changing the enrichment between the upper and lower halves, a uniform average enrichment is used, but the upper and lower A nuclear fuel assembly has been proposed in which the concentration of burnable poisons in the lower half is increased by changing the concentration of burnable poisons.

この両方の提案とも各々点を有している。上下で平均濃
縮度を変える場合、製作時に充填べレットの混合という
ミスを誘発しやすい事である。この事は可燃毒物の濃度
を変化させる場合にも言える。この上可燃毒物の添加濃
度を、燃料要素完成後非破壊検査で測定するのは困難を
伴う。特に2〜3%以上になると感度曲線が悪くなり著
しく精度が落ちてくる。又、多数本の燃料要素に複数種
の燃料を充填する作業は作業工程を煩雑にし生産性が悪
い。
Both proposals have their points. When changing the average concentration between the upper and lower parts, it is easy to cause mistakes in mixing the filled pellets during production. This also applies when changing the concentration of burnable poisons. Furthermore, it is difficult to measure the concentration of combustible substances by non-destructive testing after the fuel element is completed. In particular, when it exceeds 2 to 3%, the sensitivity curve worsens and the accuracy drops significantly. Further, filling a large number of fuel elements with a plurality of types of fuel complicates the work process and reduces productivity.

本発明の目的は上記護事情に鑑みでなされたもので軸方
向出力分布の最適化能力をそれ自身が有する核燃料集合
体を得ることにある。以下に図面を参照して本発明の実
施例を示す。
The object of the present invention was made in view of the above-mentioned circumstances, and is to obtain a nuclear fuel assembly which itself has the ability to optimize the axial power distribution. Embodiments of the present invention will be described below with reference to the drawings.

第2図に示す如く本発明の核燃料集合体は、複数本の燃
料要素1を正方格子状に配置し、上下端部を上部タイプ
レート2と下部タイプし−ト3で結束し、中間には複数
個設けられたスベーサ4にて、燃料要素間隔を保持する
構造の燃料束にチャンネル4をかぶせたものである。第
1の実施例の特徴はこの燃料集合体に第3図に示す様な
燃料要素■を第6図に斜線で示す制御榛側の3コーナー
に組み込む事にある。
As shown in FIG. 2, the nuclear fuel assembly of the present invention has a plurality of fuel elements 1 arranged in a square lattice, the upper and lower ends of which are bound by an upper tie plate 2 and a lower tie plate 3, and a A plurality of spacers 4 are provided to cover a fuel bundle having a structure in which the fuel element spacing is maintained. The feature of the first embodiment is that fuel elements (2) as shown in FIG. 3 are incorporated into the fuel assembly at three corners on the control arm side shown by diagonal lines in FIG. 6.

この燃料要素は円筒のジルコニウム合金の被覆管11に
、ほぼ中央から上方にのみ円柱状燃料べレット12を充
填し、燃料べレット12が充填されている部分の上下端
を上部端栓13と中間部端栓14で密封し、その下方に
続く中空部分の最下端に下部端栓15を設ける。更に中
間部端栓14の少し下方に劣却材流出口穴16を、下部
端栓16の少し上方に冷却材流入口穴17をそれぞれ設
け、中空部分を矢印の方向に冷却材が流れる様にする。
本実施例において、第3図の様な燃料要素■のかわりに
第4図の様な燃料要素■を組み込んでも良い。この燃料
要素は、円筒のジルコニウム合金製の被覆管11に、ほ
ぼ中央から上方にのみ円柱状の燃料べレット12を充填
し、中央から下方には円柱、円筒、コイル状の反射材又
は減速材20を充填する。
In this fuel element, a cylindrical zirconium alloy cladding tube 11 is filled with cylindrical fuel pellets 12 only upward from approximately the center. A lower end plug 15 is provided at the lowest end of the hollow portion continuing below the end plug 14 for sealing. Furthermore, a waste material outlet hole 16 is provided slightly below the intermediate end plug 14, and a coolant inlet hole 17 is provided slightly above the lower end plug 16, so that the coolant flows through the hollow portion in the direction of the arrow. do.
In this embodiment, a fuel element (2) as shown in FIG. 4 may be incorporated in place of the fuel element (2) as shown in FIG. In this fuel element, a cylindrical zirconium alloy cladding tube 11 is filled with cylindrical fuel pellets 12 only upward from approximately the center, and cylindrical, cylindrical, or coil-shaped reflectors or moderators are filled downward from the center. Fill 20.

反射材又は減速材としてはべりリウム金属、酸化ベリリ
ウム、黒鉛等が考えられるが、被覆管材料及び燃料べレ
ットと両立性のあるものを考える。本実施例では円柱形
状の場合を第4図に示す。又本実施例で用いる反射材又
は減速材にGdなどの可燃毒物を添加する事も考えられ
る。次に第2の実施例を示す。この核燃料集合体の特徴
は第4図に示す様な燃料要素B′を第6図に斜線で示す
制御榛側3コーナーに組み込む事にある。この燃料要素
B′は円筒のジルコニウム合金製の被覆管11に、ほぼ
中央から上方にのみ円柱状の燃料べレット12を充填し
、中央から下方には円柱、円筒、又はコイル状のジルコ
ニウム合金又はステンレス鋼20′を充填する。第2の
実施例において燃料要素に充填するジルコニウム合金又
はステンレス鋼にGd等の可燃毒物を添加してもよいし
、第5図の示す様な下方部が中空の燃料要素◎にしても
良い。第3の実施例を示す。
Possible reflective materials or moderators include beryllium metal, beryllium oxide, graphite, etc., which are compatible with the cladding material and the fuel pellet. In this embodiment, the case of a cylindrical shape is shown in FIG. It is also conceivable to add a burnable substance such as Gd to the reflective material or moderator used in this embodiment. Next, a second example will be shown. The feature of this nuclear fuel assembly is that fuel elements B' as shown in FIG. 4 are assembled in the three corners of the control beam side shown by diagonal lines in FIG. 6. In this fuel element B', a cylindrical zirconium alloy cladding tube 11 is filled with cylindrical fuel pellets 12 only upward from the center, and cylindrical, cylindrical, or coiled zirconium alloy or cylindrical fuel pellets 12 are filled downward from the center. Fill with stainless steel 20'. In the second embodiment, a burnable substance such as Gd may be added to the zirconium alloy or stainless steel filled in the fuel element, or the fuel element may have a hollow lower part as shown in FIG. A third example is shown.

本実施例は、第2の実施例と同り様に、コーナーに位贋
する燃料要素のうち3本(制御榛側のコーナーを含む3
本)に第4図に示すよ燃料要素B′を組み込んだ上、更
に核燃料集合体の中央部に第3図に示す燃料要素■を第
7図に示すように組み込む事を特徴としている。本発明
の第1から第3の実施例において、核燃料集合体全体の
平均濃縮度を0.71〜4.2%程度として、下方部分
には装荷量を減じて、それによる平均濃縮度の減少分を
0.1〜0.4%程度とするのが沸騰水型原子炉用の燃
料のK的の鼠方向分布上よい。又、核燃料集合体の燃焼
初期の過剰反応度を抑える目的で、炉心有効長にわたり
単一濃縮度の燃料が充填されている燃料要素の一本又は
複数本に0.5〜lOW%のCb酸化物を全長にわたっ
て一様に添加すると良い。
In this embodiment, as in the second embodiment, three of the fuel elements to be replaced at the corner (including the corner on the control side side
In addition to incorporating the fuel element B' shown in FIG. 4 into the nuclear fuel assembly, the fuel element B' shown in FIG. 3 is further installed in the center of the nuclear fuel assembly as shown in FIG. 7. In the first to third embodiments of the present invention, the average enrichment of the entire nuclear fuel assembly is set to about 0.71 to 4.2%, and the loading amount is reduced in the lower part, thereby reducing the average enrichment. It is best to set the amount of K to about 0.1 to 0.4% in terms of the horizontal distribution of K in fuel for boiling water reactors. In addition, in order to suppress excessive reactivity at the initial stage of combustion of a nuclear fuel assembly, one or more fuel elements filled with fuel of a single enrichment over the effective length of the reactor core are oxidized with 0.5 to 1OW% of Cb. It is best to add the substance uniformly over the entire length.

この時この燃料要素の配置は核燃料集合体内の局所出力
ピークを考慮する必要がある。次に本発明の作用効果を
述べる。
At this time, the arrangement of the fuel elements must take into account local power peaks within the nuclear fuel assembly. Next, the effects of the present invention will be described.

沸騰水型原子炉では、燃料集合体冷却チャンネル内の藤
方向ボィド率分布が第1図に示す様に上方に行く程大き
くなっているため、核燃料集合体積断面の平均濃縮度が
軸万向に一様で、叢物濃度が軸万向に一様か、含まれて
いない場合核燃料集合体の軸方向出力分布は第1図のよ
うに下方ピークになる。
In a boiling water reactor, the void fraction distribution in the vertical direction in the fuel assembly cooling channel increases as it goes upward, as shown in Figure 1, so the average enrichment of the nuclear fuel assembly volume cross section increases in the vertical direction. If the nucleation concentration is uniform in all axial directions or is not included, the axial power distribution of the nuclear fuel assembly will have a downward peak as shown in FIG.

この下方ピークが極端に突出しない様制御するには、下
方のKの(無限増倍率)が小さくなる様核燃料集合体に
使用する燃料の濃縮度を下方だけ下げるとか、下方だけ
濃度の高い可燃毒物を添加すればよい。他の方法として
は、下方の燃料濃縮度は下げなし、で、燃料装荷量を減
少させ実質的に平均濃縮度を下げる事が考えられる。
In order to control this downward peak so that it does not become extremely prominent, it is possible to reduce the enrichment of the fuel used in the nuclear fuel assembly only in the downward direction so that the (infinite multiplication factor) of K in the downward direction becomes small, or to reduce the enrichment of the fuel used in the nuclear fuel assembly only in the downward direction. All you have to do is add. Another method would be to reduce the fuel loading without lowering the lower fuel enrichment, thereby substantially lowering the average enrichment.

この考えに立つのが本発明である。燃料東の下方部の燃
料装荷量を減少させる方法としては、単純には燃料べレ
ットを下方に充填しないで、中空にした燃料要素を用い
れば良い。
The present invention is based on this idea. As a method of reducing the amount of fuel loaded in the lower part of the fuel east, it is sufficient to simply use a hollow fuel element instead of filling the fuel pellet downward.

しかし、中空にした場合、被覆管の破損による中空部へ
の水の侵入による核特性の変化等が考えられうるので、
中空にする代わりに積極的に冷却材を流したり、適当な
材料を充填する方が良い。以下に核燃料集合体に水、B
e,C,Zr合金、S瓜304等を充填した特珠燃料要
素を複数本組み込んで、燃料装荷量を下げた場合の効果
を述べる。(尚、本発明で特珠燃料要素■の様な被覆管
内に部分的に水を流す燃料要素の水が流れる部分を特定
して「waにrrod」と呼ぶ事にする。)この時、燃
料のかわりにこの様な燃料要素を組み込むのであるが、
他の燃料の濃縮度は固定したままとする。waにrro
dを核燃料集合体の最外周におけば、本数が増せば核燃
料集合体のKのは減少する。
However, if it is made hollow, there is a possibility that the nuclear properties may change due to water entering the hollow part due to damage to the cladding.
Instead of making it hollow, it is better to actively flow coolant or fill it with a suitable material. Below, water is added to the nuclear fuel assembly, B
The effect of lowering the fuel loading amount by incorporating a plurality of Tokuju fuel elements filled with e, C, Zr alloy, Smelt 304, etc. will be described. (In addition, in the present invention, the part where water flows partially in the cladding tube of a fuel element such as the special fuel element (■) is specified and called "wa to rrod".) At this time, the fuel Instead, such a fuel element is incorporated,
The enrichments of other fuels remain fixed. wa to rro
If d is placed at the outermost periphery of the nuclear fuel assembly, as the number increases, K of the nuclear fuel assembly will decrease.

しかし核燃料集合体の横断面中央部に配置すると第8図
に示す如く増加してピークを経て減少する。肌terr
odのかわりに反射材や減速材とし茂金属又は酸化ベリ
リウム、黒鉛を充填した燃料要素を用いる場合も言える
。但し黒鉛は中性子の自由行程が大きいので中央部に配
しても第8図に示すようにK功の増加には寄与しない。
ジルコニウム合金又はステンレス鋼を充填した燃料要素
を組み込む場合、配置によって程度は異なるのが第9図
に示す如くKのは低下する。
However, if it is placed at the center of the cross section of the nuclear fuel assembly, it increases, peaks, and then decreases as shown in FIG. skin terr
This also applies to the case where a fuel element filled with a reflective material or a moderator, such as Toshige metal, beryllium oxide, or graphite, is used instead of od. However, since graphite has a large free path for neutrons, even if it is placed in the center, it will not contribute to increasing K-gon as shown in FIG.
When incorporating a fuel element filled with zirconium alloy or stainless steel, K decreases to varying degrees depending on the location, as shown in FIG.

この様に濃縮度を下げるとか、Wなどの可燃亨物等の添
加濃度を増加する以外の、燃料装荷量を下げる事によっ
ても下方部のKのを低下させて下方の出力ピークを抑え
る事ができる。このことを利用し、かつ下方部の核燃料
集合体横断面の局所出力ピークをできるだけ小さくする
よう本発明で用いる特殊な燃料要素の配置及び、燃料要
素中の下方部に充填する材料を選択する必要がある。又
、本発明に使用する特珠な燃料要素は、燃料要素1本の
上下で濃縮度が異なるとか、G材などの可燃毒物濃度に
差があるという様な構造ではないため、燃料要素製作時
充填物の混合とか、充填長さの計測ミス等を誘発せず、
充填物の外観で明確に区別して製作できる。又、燃料要
素完成後の非破壊検査においても、X線又は核分裂r線
、中性子線の計測により容易に検査できる。本発明は、
核燃料集合体の下方部の燃料装荷量を減少させる事によ
って、下方部の出力ピークを抑える働きをしている。
In addition to lowering the enrichment or increasing the additive concentration of combustible substances such as W, it is also possible to reduce the K in the lower part and suppress the lower output peak by lowering the fuel loading. can. Taking advantage of this, it is necessary to select the special arrangement of the fuel elements used in the present invention and the material to be filled in the lower part of the fuel element in order to minimize the local power peak in the cross section of the nuclear fuel assembly in the lower part. There is. In addition, the special fuel element used in the present invention does not have a structure in which the enrichment level differs between the upper and lower parts of one fuel element, or the concentration of burnable substances such as G material differs, so there are Does not cause mixing of fillings or mistakes in measuring filling length, etc.
The filling can be manufactured by clearly distinguishing it by its appearance. Furthermore, non-destructive inspection after completion of the fuel element can be easily performed by measuring X-rays, nuclear fission r-rays, or neutron beams. The present invention
By reducing the amount of fuel loaded in the lower part of the nuclear fuel assembly, it works to suppress the output peak in the lower part.

又、一本の燃料要素中に複数の濃縮度燃料を充填する事
を避けている。しかし、本発明により他の効果も考えら
れる。本発明の第一の実施例において、黒鉛を燃料要素
の下方部に充填したものを使用した場合制御綾側3コー
ナー部の燃料の出力ピークを低下させる事ができる。又
、第二、第三の実施例においては更に大きく制御榛側3
コーナー部の燃料要素の出力を下る事ができる。これに
より、制御陣移動時の出力変化量を減じて制御榛移動速
度を速める事ができ、ひいては稼動率の向上に寄与でき
る。特に第三の実施例では、下方部分だけ肌terro
dである特珠燃料要素を中央部に持ち、制御樺側の3コ
ーナー部には下方部分に中性子吸収体(ジルカロイやS
us等)を含む特珠燃料要素を持っているので、積極的
に核燃料集合体内の横断面内での局所ピークを中央部に
持ってこようとしている事になり、制御榛移動時の出力
変化量を大きく減じる事になる。更に、本発明の第1〜
3の実施例において、下方部に燃料以外の物を充填する
侍珠燃料要素は、制御綾側の3コーナー部又は中央部と
しているが、これは原子炉内で燃料東の出力を監視する
計装系が第4のコーナー部にあるため、これの計測精度
を落さないためである。
It also avoids filling multiple enrichment fuels into a single fuel element. However, other effects are also possible with the invention. In the first embodiment of the present invention, when graphite is used in the lower part of the fuel element, the output peak of the fuel at the three corners on the control trailing side can be reduced. In addition, in the second and third embodiments, the control side 3
It is possible to reduce the output of the fuel element at the corner. As a result, it is possible to reduce the amount of change in output when the control group moves and increase the movement speed of the control beam, which in turn can contribute to improving the operating rate. In particular, in the third embodiment, only the lower part has skin terro.
It has a special fuel element (d) in the center, and a neutron absorber (Zircaloy or S
Since the fuel element has a special fuel element that includes (US, etc.), it is actively trying to bring the local peak in the cross section of the nuclear fuel assembly to the center, and the amount of output change during control comb movement. will be significantly reduced. Furthermore, the first to
In Embodiment 3, the samurai fuel element whose lower part is filled with things other than fuel is located at the 3 corners on the control side or at the center, but this is a part of the fuel element that monitors the output of the fuel east in the reactor. This is because the measurement accuracy is not compromised since the mounting system is located at the fourth corner.

次に本発明の更に他の実施例を説明する。Next, still another embodiment of the present invention will be described.

■ 本発明の第1から第3までの実施例では、各燃料要
素内では燃料の濃縮度は一様であるとした。
(2) In the first to third embodiments of the present invention, it is assumed that the fuel enrichment is uniform within each fuel element.

しかし、炉心の中性子経済上、有効炉心長の上下端に1
5〜30伽程度他の部分よりK的の低い燃料を配置する
と効率が良い事がわかつている。従って本発明の中にも
この効用を取り入れる。これが第10図に示す第4の実
施例である。この実施例では、炉心有効長にわたって燃
料が充填されている燃料要素については、上下端の短い
部分的15〜30肌に天然ウラン又は劣化ウランを充填
し、上方にのみ燃料が充填されている燃料要素には本数
が少ないので、一様の濃縮度のままとするか、上端の短
い部分のみ天然又は劣化ウランを充填する。■ 本発明
の第1から第4の実施例では上方部にのみ燃料が充填さ
れている特殊燃料要素では、燃料充填部分の長さが統一
されて、核燃料集合体の中に組み込まれている。
However, due to the neutron economy of the reactor core, 1 at the upper and lower ends of the effective core length
It is known that efficiency is good if fuel with a lower K value is placed in the other parts by about 5 to 30 degrees. Therefore, this effect is incorporated into the present invention. This is the fourth embodiment shown in FIG. In this example, for fuel elements filled with fuel over the effective length of the core, short partial 15 to 30 skins at the upper and lower ends are filled with natural uranium or depleted uranium, and the fuel element is filled with fuel only in the upper part. Since the number of elements is small, either the enrichment remains uniform or only a short section at the top is filled with natural or depleted uranium. (2) In the first to fourth embodiments of the present invention, in the special fuel element whose upper portion is only filled with fuel, the length of the fuel-filled portion is unified and the element is incorporated into the nuclear fuel assembly.

このため、この境界部分で第12図に示す如く出力分布
に大きな段差が生じ、燃料東の出力を監視する中性子計
装の精度上不利である。そこで、第11図に様に、持珠
燃料要素の燃料充填部分の長さを各々かえてやる事によ
り、第12図B曲線の如くなめらかな出力分布になる。
Therefore, as shown in FIG. 12, a large step occurs in the output distribution at this boundary, which is disadvantageous in terms of accuracy of the neutron instrumentation that monitors the output of the fuel east. Therefore, by changing the lengths of the fuel-filled portions of the holding fuel elements as shown in FIG. 11, a smooth output distribution as shown by the curve B in FIG. 12 can be obtained.

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

第1図は本発明の核燃料集合体と従来の核燃料集合体と
の軸万向のボィド分布と出力分布を示す説明図、第2図
は本発明の核燃料集合体の一実施例を示す縦断面図、第
3図乃至第5図は燃料要素の縦断面図、第6図、第7図
は核燃料集合体の横断面図、第8図、第9図は本発明の
効果を示す説明図、第10図、第11図は本発明の他の
実施例を示す説明図、第12図は本発明の燃料東軸万向
出力分布を示す説明図である。 1・・・・・・燃料要素、2・…・・上部タイプレート
、3・・・・・・下部タイプレート、4・・・・・・ス
ベーサ、11・・・・・・・・・被覆管、12・・・・
・・燃料べレット、14…・・・中間部端栓。 第1図 第7図 第2図 第3図 第4図 第5図 第6図 第9図 第8図 第10図 第11図 第12図
FIG. 1 is an explanatory diagram showing the void distribution and power distribution in all axial directions of a nuclear fuel assembly of the present invention and a conventional nuclear fuel assembly, and FIG. 2 is a longitudinal section showing an embodiment of the nuclear fuel assembly of the present invention. 3 to 5 are longitudinal sectional views of the fuel element, FIGS. 6 and 7 are cross sectional views of the nuclear fuel assembly, and FIGS. 8 and 9 are explanatory diagrams showing the effects of the present invention. FIGS. 10 and 11 are explanatory diagrams showing other embodiments of the present invention, and FIG. 12 is an explanatory diagram showing the fuel east axis universal power distribution of the present invention. 1...Fuel element, 2...Upper tie plate, 3...Lower tie plate, 4...Subasa, 11......Coating Tube, 12...
...Fuel pellet, 14...Middle end plug. Figure 1 Figure 7 Figure 2 Figure 3 Figure 4 Figure 5 Figure 6 Figure 9 Figure 8 Figure 10 Figure 11 Figure 12

Claims (1)

【特許請求の範囲】 1 格子状に整列配置された複数本の燃料要素と、この
燃料要素の上下端を結束する上部タイプレート及び下部
タイプレートと、前記燃料要素間の間隔を規制する数個
のスペーサと、前記燃料要素全てを覆うチヤンネルとか
ら構成された核燃料集合体において、前記燃料要素の数
本は上方と下方とに分割されその上方のみに核分裂物質
が充填され下方は中空又は減速材、反射材、中性子吸収
材の内の一部材が充填されている特珠燃料要素であるこ
とを特徴とする核燃料集合体。 2 特珠燃料要素の上方と下方との分割は中間部に設け
られた中間部端栓で行われ、下方に充填される減速材は
特珠燃料要素の下端に穿設された冷却水入口孔から導か
れ、前記特珠燃料要素の中間部に設けられた中間部端栓
の下方に穿設された冷却水出口孔より排出される水であ
ることを特徴とする特許請求の範囲第1項記載の核燃料
集合体。 3 減速材及び反射材はベリリウム金属、酸化ベリリウ
ム、黒鉛の内の一部材であることを特徴とする特許請求
の範囲第1項記載の核燃料集合体。 4 中性子吸収材はジルコニウム合金、ステンレス鋼の
内の一部材であることを特徴とする特許請求の範囲第1
項記載の核燃料集合体。 5 特珠燃料要素は核燃料集合体の角部に配置されてい
ることを特徴とする特許請求の範囲第1項記載の核燃料
集合体。
[Claims] 1. A plurality of fuel elements arranged in a grid, an upper tie plate and a lower tie plate that bind the upper and lower ends of the fuel elements, and several tie plates that regulate the spacing between the fuel elements. In a nuclear fuel assembly composed of a spacer and a channel that covers all of the fuel elements, several of the fuel elements are divided into an upper part and a lower part, and only the upper part is filled with fissile material, and the lower part is hollow or filled with moderator. A nuclear fuel assembly characterized in that it is a special fuel element filled with one of the following: a reflective material, and a neutron absorbing material. 2 The upper and lower parts of the Toju fuel element are separated by an intermediate end plug provided in the middle, and the moderator charged in the lower part is supplied through the cooling water inlet hole drilled at the lower end of the Toju fuel element. Claim 1, characterized in that the water is led from the fuel element and discharged from a cooling water outlet hole drilled below an intermediate end plug provided in the intermediate part of the fuel element. The nuclear fuel assembly described. 3. The nuclear fuel assembly according to claim 1, wherein the moderator and the reflective material are one of beryllium metal, beryllium oxide, and graphite. 4. Claim 1, characterized in that the neutron absorbing material is a member of zirconium alloy or stainless steel.
Nuclear fuel assembly as described in section. 5. The nuclear fuel assembly according to claim 1, wherein the special fuel element is arranged at a corner of the nuclear fuel assembly.
JP52129728A 1977-10-31 1977-10-31 nuclear fuel assembly Expired JPS6039194B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP52129728A JPS6039194B2 (en) 1977-10-31 1977-10-31 nuclear fuel assembly

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP52129728A JPS6039194B2 (en) 1977-10-31 1977-10-31 nuclear fuel assembly

Publications (2)

Publication Number Publication Date
JPS5464287A JPS5464287A (en) 1979-05-23
JPS6039194B2 true JPS6039194B2 (en) 1985-09-04

Family

ID=15016721

Family Applications (1)

Application Number Title Priority Date Filing Date
JP52129728A Expired JPS6039194B2 (en) 1977-10-31 1977-10-31 nuclear fuel assembly

Country Status (1)

Country Link
JP (1) JPS6039194B2 (en)

Families Citing this family (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5877686A (en) * 1981-11-02 1983-05-11 株式会社東芝 Nuclear fuel assembly
JPS58182585A (en) * 1982-04-19 1983-10-25 株式会社東芝 Fuel assembly
JPS5938684A (en) * 1982-08-27 1984-03-02 株式会社東芝 Fuel assembly of reactor
FR2535508B1 (en) * 1982-10-27 1986-07-04 Framatome Sa NUCLEAR REACTOR WITH IMPROVED YIELD
JPS59171886A (en) * 1983-03-18 1984-09-28 株式会社日立製作所 Fuel rod
JPH0636048B2 (en) * 1986-09-24 1994-05-11 東京電力株式会社 Fuel assembly

Also Published As

Publication number Publication date
JPS5464287A (en) 1979-05-23

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