JPH06102385A - Fuel assembly and reactor core - Google Patents

Fuel assembly and reactor core

Info

Publication number
JPH06102385A
JPH06102385A JP4249502A JP24950292A JPH06102385A JP H06102385 A JPH06102385 A JP H06102385A JP 4249502 A JP4249502 A JP 4249502A JP 24950292 A JP24950292 A JP 24950292A JP H06102385 A JPH06102385 A JP H06102385A
Authority
JP
Japan
Prior art keywords
fuel
rods
rod
water
burnable
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
JP4249502A
Other languages
Japanese (ja)
Inventor
Yoko Ishibashi
洋子 石橋
Tadao Aoyama
肇男 青山
Junichi Koyama
淳一 小山
Riyouji Masumi
亮司 桝見
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.)
Hitachi Ltd
Original Assignee
Hitachi 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 Hitachi Ltd filed Critical Hitachi Ltd
Priority to JP4249502A priority Critical patent/JPH06102385A/en
Publication of JPH06102385A publication Critical patent/JPH06102385A/en
Pending 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)

Abstract

PURPOSE:To reduce the output at the time of a low flow of a core by arranging burnable poisonous rods more than a half of the total burnable poisonous rods across one fuel rod to the water rods. CONSTITUTION:Twelve burnable poisonous fuel rods 2 corresponding to 75% of the total of 16 are arranged at positions across one fuel rod 1 against water rods 3. Since the poisonous fuel rods 2 are arranged across the fuel rods 1, they can be prevented from being affected by the neutron spectrum change due to the height change of the liquid level of the water rods 3. Many poisonous fuel rods 2 are arranged on the second layer from the outermost layer of a fuel assembly having high thermal neutron flux, and burnable poisons can be effectively burnt regardless of the height change of the liquid level in the water rods 3. When this fuel assembly is used to reduce the output at the time of a low flow of a core coolant, the output reducing effect can be improved by about 3%. When the spectrum shift operation is performed with this fuel assembly, the burnable poisons can be effectively burnt at the cycle initial stage when the liquid level height in the water rods 3 is made low for operation.

Description

【発明の詳細な説明】Detailed Description of the Invention

【0001】[0001]

【産業上の利用分野】本発明は、沸騰水型原子炉の燃料
集合体及び、この燃料集合体を装荷した炉心に係り、特
に、炉心冷却水流量低下時の出力低減効果を増大する燃
料集合体に関する。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a fuel assembly for a boiling water reactor and a core loaded with the fuel assembly, and more particularly to a fuel assembly for increasing the output reduction effect when the core cooling water flow rate is reduced. Regarding the body

【0002】[0002]

【従来の技術】従来の沸騰水型原子炉用燃料集合体は、
特開昭54−121389号公報に記載されているように、中性
子の減速を促進させるために冷却水のみが流れる管(以
下、水ロッドと称する)をもつ燃料集合体を炉心内に装
荷している。水ロッドの採用により、熱中性子束の分布
が平坦化できるとともに、ウラン原子に対する水素原子
の数を増大でき、炉心に装荷された核燃料を有効に利用
できる。
2. Description of the Related Art A conventional boiling water reactor fuel assembly is
As described in Japanese Patent Laid-Open No. 54-121389, a fuel assembly having a pipe (hereinafter, referred to as a water rod) through which only cooling water flows in order to accelerate deceleration of neutrons is loaded in a core. There is. By adopting the water rod, the distribution of thermal neutron flux can be flattened, the number of hydrogen atoms with respect to uranium atoms can be increased, and the nuclear fuel loaded in the core can be effectively used.

【0003】しかし、更に核燃料物質の有効利用を図る
には、核燃料物質の燃焼にともなって炉心内の水素原子
数を変えるスペクトルシフト運転が有効である。
However, in order to further effectively utilize the nuclear fuel material, it is effective to perform a spectrum shift operation in which the number of hydrogen atoms in the core is changed with the combustion of the nuclear fuel material.

【0004】特開昭57−125390号公報及び特開昭57−12
5391号公報は、低速中性子吸収水押棒及びこの水押棒よ
りも反応度価値の大きいステンレンス鋼で構成される中
速中性子吸収棒を設け、これらの水押棒の炉心への挿入
量を制御して炉心内の冷却水量を調整することを述べて
おり、特開昭61−38589号公報は、水ロッド内にウラン
235濃度の低い燃料棒を設置し、この燃料棒のウラン
235の消失前後における水ロッド内のボイド量の変化
を利用することを述べている。また、特開昭63−73187
号公報は、炉心冷却水流量を調節することによって、可
動部なしで管内の減速材液面高さを変化させることので
きる水ロッドを提案している。この水ロッドは、炉心冷
却材流量変化による冷却材中のボイド率変化に、水ロッ
ド管内の減速材量変化が加わるので、大きなスペクトル
シフト効果を得ることができる。その結果、取出燃焼度
が増大し核燃料物質をより有効に利用できるようにな
る。この、炉心流量により水ロッド管内の液面高さを変
化させることのできる水ロッドを使用した燃料集合体に
おける可燃性毒物入り燃料棒の利用方法として、水ロッ
ドに可燃性毒物入り燃料棒を隣接して配置することによ
り、水ロッド内のボイド率の急減時における反応度を抑
制する方法が特開平1−162189 号公報及び、特開平2−2
49995 号公報に記載されている。これは、炉心の圧力や
流量が急激に増大する過渡時に、水ロッド内の液面が急
激に上昇してボイド率が下がり、中性子減速効果が急増
して大きな正の反応度が炉心に投入されたときに、水ロ
ッドに隣接して配置された可燃性毒物により反応度を抑
制できるようにするものである。
JP-A-57-125390 and JP-A-57-12
No. 5391 gazette is provided with a medium speed neutron absorbing rod composed of a slow neutron absorbing water pushing rod and a stainless steel having a reactivity value higher than that of the water pushing rod, and controlling the amount of insertion of these water pushing rods into the core. JP-A-61-38589 discloses that a fuel rod having a low concentration of uranium 235 is installed in the water rod, and the water rod before and after the uranium 235 disappears in the fuel rod is disclosed. It describes that the change in the void amount inside is used. In addition, JP-A-63-73187
The publication proposes a water rod capable of changing the moderator liquid level height in the pipe without moving parts by adjusting the core cooling water flow rate. In this water rod, a change in the void ratio in the coolant due to a change in the core coolant flow rate is added to the change in the amount of moderator in the water rod tube, so that a large spectrum shift effect can be obtained. As a result, the take-out burnup is increased and the nuclear fuel material can be used more effectively. As a method of using a burnable poison-bearing fuel rod in a fuel assembly using a water rod that can change the liquid level height in the water rod tube depending on the core flow rate, the burnable poison-bearing fuel rod is adjacent to the water rod. A method of suppressing the reactivity when the void ratio in the water rod sharply decreases by arranging them in such a manner is disclosed in JP-A-1-162189 and JP-A-2-2.
It is described in Japanese Patent Publication No. 49995. This is because during a transient increase in core pressure and flow rate, the liquid level in the water rod rises sharply, the void fraction decreases, the neutron moderating effect increases sharply, and a large positive reactivity is injected into the core. In this case, the reactivity can be suppressed by the burnable poison disposed adjacent to the water rod.

【0005】[0005]

【発明が解決しようとする課題】上記従来技術の水ロッ
ドは、炉心冷却材流量を制御することで水ロッド管内の
液面高さが変化する。すなわち、管内液面高さは炉心冷
却材流量を増大させると上昇し、減少させると下降す
る。一方、冷却材である水は、中性子減速効果を持つの
で、水ロッド管内の液面の上昇は、原子炉炉心の反応度
を増大す。従って、炉心冷却材流量を増して水ロッド管
内の液面を上昇させることにより、核分裂製物質の燃焼
によって起きた反応度の損失を補償することができる。
このため、出力運転中の原子炉炉心の反応度を制御する
ために、炉心に挿入して反応度を制御する制御棒を挿入
する必要がなくなる。すなわち、制御棒挿入のない炉心
流量制御のみによる運転が可能となる。また、運転サイ
クルの前半には、原子炉の余分な反応度を抑えて、適切
なレベルに反応度を維持するため、炉心流量を少なくし
て水ロッド管内の液面を低い位置に保つことになる。し
たがって、燃料の上部領域では水ロッド管内のボイド率
が100%となるので、中性子の減速は十分でなく、ウ
ラン238のプルトニウムへの転換が促進される。この
ように、運転サイクルの前半には、燃料上部領域でプル
トニウムの蓄積を図り、また後半に、炉心流量の増大に
より水ロッド管内の液面を上昇させて中性子減速効果を
高めて、プルトニウムを燃焼させることができ、核燃料
物質の有効利用が図れる。
In the above-mentioned conventional water rod, the liquid level height in the water rod tube is changed by controlling the core coolant flow rate. That is, the liquid level in the pipe rises when the core coolant flow rate is increased, and falls when it is decreased. On the other hand, since water as a coolant has a neutron moderating effect, an increase in the liquid level in the water rod tube increases the reactivity of the reactor core. Therefore, by increasing the core coolant flow rate and raising the liquid level in the water rod tube, it is possible to compensate for the loss of reactivity caused by the combustion of the fission product.
Therefore, in order to control the reactivity of the reactor core during power operation, it is not necessary to insert a control rod that is inserted into the core to control the reactivity. That is, the operation can be performed only by controlling the core flow rate without inserting the control rod. Also, in the first half of the operation cycle, in order to suppress the excess reactivity of the reactor and maintain the reactivity at an appropriate level, it is necessary to reduce the core flow rate and keep the liquid level in the water rod pipe at a low position. Become. Therefore, in the upper region of the fuel, the void ratio in the water rod tube becomes 100%, so the moderation of neutrons is not sufficient and the conversion of uranium 238 to plutonium is promoted. Thus, in the first half of the operation cycle, plutonium is accumulated in the upper fuel region, and in the latter half, the liquid level in the water rod tube is increased by increasing the core flow rate to enhance the neutron moderating effect and burn plutonium. It is possible to effectively use the nuclear fuel material.

【0006】また、上記従来技術の水ロッドの使用方法
として、通常運転時には管内が満水となるようにして従
来の水ロッドと同じように機能させ、炉心流量低下時に
水ロッド管内の液面高さが下がるように使うことで、炉
心低流量時にウラン原子数に対する水素原子数の比を小
さくして反応度の低減効果を大きくし、炉心の出力を下
げることにより安定性を向上する方法が考えられる。
Further, as a method of using the water rod of the above-mentioned prior art, the inside of the water rod is filled with water during normal operation so that it functions like the conventional water rod, and when the core flow rate decreases, the liquid level in the water rod pipe rises. It is possible to improve the stability by reducing the ratio of the number of hydrogen atoms to the number of uranium atoms at the time of low core flow to increase the reactivity reduction effect and lowering the core output. .

【0007】しかし、燃料集合体中には図2のように燃
焼初期の余剰反応を抑制する可燃性毒物入り棒が配置さ
れているため、図3に示されているように、可燃性毒物
の影響の大きい燃焼初期において、水ロッド内の液面高
さが低減し、水ロッド内がボイドした状態となると可燃
性毒物に吸収される中性子の割合も減り、反応度が増大
してしまうという問題がある。このため、図4に示した
ように可燃性毒物の有る燃料集合体が存在するサイクル
初期には、炉心低流量時の水ロッド内液面低下による反
応度低減の効果が打ち消されて小さくなってしまうとい
う問題がある。本発明の目的は、炉心流量により中性子
減速効果を変えることのできる水ロッドを用いた燃料集
合体において、炉心低流量時の出力を低減できる燃料集
合体を提供することである。
However, as shown in FIG. 3, since the rod containing burnable poisons for suppressing the excess reaction at the initial stage of combustion is arranged in the fuel assembly, as shown in FIG. In the early stage of combustion, which has a large effect, the height of the liquid surface in the water rod decreases, and if the water rod becomes void, the proportion of neutrons absorbed by the burnable poison also decreases and the reactivity increases. There is. Therefore, as shown in FIG. 4, in the early stage of the cycle in which the fuel assembly containing the burnable poison exists, the effect of reducing the reactivity due to the decrease in the liquid level in the water rod at the time of the low core flow rate is canceled and becomes small. There is a problem that it ends up. An object of the present invention is to provide a fuel assembly using a water rod capable of changing the neutron moderating effect depending on the core flow rate, and capable of reducing the output at a low core flow rate.

【0008】[0008]

【課題を解決するための手段】上記目的は、核燃料物質
を充填した複数の燃料棒と、複数の可燃性毒物入り棒及
び、炉心流量により管内の液面高さを変えることのでき
る水ロッドを有する燃料集合体において、可燃性毒物入
り棒総数の50%より多い可燃性毒物入り棒を、前記水
ロッドとの間に1本の燃料棒を挟んで配置することによ
り達成される。ここで、2本以上の燃料棒を挟んだ位置
に配置すると、可燃性毒物入り棒を置く位置の自由度が
少なくなり、制御棒に影響のある位置や、可燃性毒物入
り棒どうしが隣接した位置に配置されるようになる。
The above object is to provide a plurality of fuel rods filled with a nuclear fuel substance, a plurality of burnable poison-bearing rods, and a water rod capable of changing the liquid level in the tube depending on the core flow rate. In the fuel assembly of the present invention, it is achieved by arranging more than 50% of the total number of burnable poison-bearing rods in the burnable poison-bearing rod with one fuel rod sandwiched between the rod and the water rod. If two or more fuel rods are placed between them, the degree of freedom of the position for placing the burnable poison-bearing rods is reduced, and the control rods are affected or the burnable poison-bearing rods are adjacent to each other. Will be placed in position.

【0009】[0009]

【作用】水ロッド内に水が充満されているときと、水が
抜けたときでは水ロッドに隣接する燃料棒位置での熱中
性子束が他の位置に比べて大きく変化する。このため、
その位置に配置された可燃性毒物入り棒の、水ロッド内
ボイド率の変化による吸収効果変化への影響は大きく、
水ロッドから1燃料棒分隔てて配置された燃料棒に比べ
て約3倍変わる。このため、可燃性毒物入り棒の半数よ
り多くを、水ロッドに直接隣接しないように燃料棒を挟
んで配置することで、図5に示すように、水ロッド内の
ボイド率が変化した時の、燃焼初期における可燃性毒物
により反応度が上がる効果が低減される。
The thermal neutron flux at the position of the fuel rod adjacent to the water rod greatly changes when the water rod is filled with water and when the water is drained, compared with other positions. For this reason,
The burnable poison-filled rod placed at that position has a large effect on the change in the absorption effect due to the change in the void ratio in the water rod,
The change is about three times as much as the fuel rods placed one fuel rod apart from the water rods. Therefore, by disposing more than half of the burnable poison-containing rods with the fuel rods sandwiched so as not to be directly adjacent to the water rod, as shown in FIG. 5, when the void ratio in the water rod changes. , The effect of increasing reactivity due to combustible poisons in the early stage of combustion is reduced.

【0010】[0010]

【実施例】以下に本発明の実施例を説明する。EXAMPLES Examples of the present invention will be described below.

【0011】図1に本発明の第1の実施例を示す。図
中、1は核燃料物質を充填した燃料棒、2は可燃性毒物
を添加した可燃性毒物入り燃料棒、3は冷却材流量によ
り管内の液面高さを変えることのできる水ロッドであ
る。可燃性毒物入り燃料棒の本数は16本でそのうちの
75%である12本が水ロッドに対して1燃料棒を挟ん
だ位置に配置されている。このように、可燃性毒物入り
燃料棒の多くを水ロッドに直接隣接しないように燃料棒
を挟んで配置することで、可燃性毒物入り燃料棒が水ロ
ッドの液面高さの変化にともなう中性子スペクトル変化
の影響を受けないようにできる。また、本実施例の燃料
集合体では可燃性毒物入り燃料棒の多くが熱中性子束の
高い集合体最外層から2層目に配置されているため、水
ロッド内の液面高さの変化によらず可燃性毒物を有効に
燃焼できる。この燃料集合体を、炉心冷却材低流量時の
出力低減のために使用した場合、従来の燃料集合体より
も約3%,出力低減効果を向上することができる。これ
により、炉心安定性が増大し燃料の装荷量を増やすこと
ができるため、使用済燃料の発生体数を低減することが
できる。また、この燃料集合体を用いてスペクトルシフ
ト運転を行った場合、水ロッド内の液面高さを低下させ
て運転を行うサイクル初期において、熱中性子スペクト
ルの硬い水ロッド隣接位置に可燃性毒物が配置されてい
ないため、可燃性毒物を有効に燃焼させることができ
る。このため、燃焼度を伸ばすことができ、従来の集合
体よりも省ウラン効果を1%向上することができる。
FIG. 1 shows a first embodiment of the present invention. In the figure, 1 is a fuel rod filled with a nuclear fuel substance, 2 is a fuel rod containing a burnable poison added with a burnable poison, and 3 is a water rod capable of changing the liquid level in the pipe depending on the flow rate of the coolant. The number of burnable poison-bearing fuel rods is 16, and 75% of the fuel rods, 12 rods, are arranged at positions where one fuel rod is sandwiched between water rods. In this way, by placing many of the burnable poison-bearing fuel rods so that they are not directly adjacent to the water rods, the burnable poison-bearing fuel rods are arranged so that the neutrons associated with changes in the liquid level of the water rods are It is possible to avoid the influence of the spectrum change. Further, in the fuel assembly of the present embodiment, most of the burnable poison-containing fuel rods are arranged in the second layer from the outermost layer of the assembly having a high thermal neutron flux, so that there is a change in the liquid level in the water rod. It can burn burnable poisons effectively. When this fuel assembly is used for reducing the output when the core coolant flow rate is low, the output reducing effect can be improved by about 3% as compared with the conventional fuel assembly. As a result, core stability is increased and the amount of fuel loaded can be increased, so that the number of spent fuel generators can be reduced. Further, when the spectrum shift operation is performed using this fuel assembly, in the early stage of the cycle in which the liquid level in the water rod is lowered, the burnable poison is present at the position adjacent to the hard water rod in the thermal neutron spectrum. Since it is not arranged, the burnable poison can be effectively burned. Therefore, the burnup can be extended, and the uranium saving effect can be improved by 1% as compared with the conventional aggregate.

【0012】図6に本発明の第2の実施例を示す。図中
1は核燃料物質を充填した燃料棒、2は可燃性毒物入り
燃料棒、3は冷却材流量により管内の液面高さを変える
ことのできる水ロッドである。第2の実施例では、水ロ
ッドの領域が燃料棒9本分と大きいため、水ロッド内の
水位変化による中性子スペクトルの変化がさらに大きく
なり、スペクトルシフト効果を増大できる。この実施例
の場合、すべての可燃性毒物入り燃料棒が水ロッドから
2層目の位置に燃料棒1本を挟んで配置されているた
め、水ロッド管内の液面高さ変化による可燃性毒物の吸
収量変化への影響はほとんどなくなる。このため、スペ
クトルシフト効果の大きな水ロッドに対しても、燃焼初
期における中性子スペクトル変化の効果が十分保たれ
る。
FIG. 6 shows a second embodiment of the present invention. In the figure, 1 is a fuel rod filled with a nuclear fuel substance, 2 is a fuel rod containing burnable poisons, and 3 is a water rod whose liquid level in the pipe can be changed by the flow rate of the coolant. In the second embodiment, since the area of the water rod is as large as nine fuel rods, the change in the neutron spectrum due to the change in the water level in the water rod is further increased, and the spectrum shift effect can be increased. In the case of this embodiment, all the fuel rods containing burnable poisons are arranged at the position of the second layer from the water rod with one fuel rod sandwiched between them. Therefore, the burnable poisons due to the change in the liquid level in the water rod pipe are placed. Has almost no effect on the change in absorption. Therefore, the effect of changing the neutron spectrum at the early stage of combustion is sufficiently maintained even for a water rod having a large spectrum shift effect.

【0013】図7は、本発明第3の実施例で、第1の実
施例の変形である。この実施例は、燃焼集合体配列が1
0×10の格子であり、図中1は核燃料を充填した燃料
棒、2は可燃性毒物入り燃料棒、3は炉心冷却材流量に
より管内の液面高さを変えることのできる水ロッドであ
る。この例は、燃料集合体配列が増えたことにより、可
燃性毒物入り燃料棒を配置できる位置の自由度が大きく
なる。本実施例では、可燃性毒物入り燃料棒の70%が
水ロッドと1燃料棒を挟んだ位置に配置されている。
FIG. 7 shows a third embodiment of the present invention, which is a modification of the first embodiment. In this embodiment, the combustion assembly array is 1
It is a grid of 0 × 10, in the figure, 1 is a fuel rod filled with nuclear fuel, 2 is a fuel rod containing burnable poisons, and 3 is a water rod capable of changing the liquid level in the tube depending on the core coolant flow rate. . In this example, since the fuel assembly arrangement is increased, the degree of freedom in the position where the burnable poison-bearing fuel rod can be arranged is increased. In this embodiment, 70% of the fuel rods containing burnable poisons are arranged at a position sandwiching the water rod and one fuel rod.

【0014】図8は、本発明の第4の実施例である。燃
料集合体配列は14×14であり、図中1は燃料棒、2
は可燃性毒物入り燃料棒、3と4は水ロッド、5はチャ
ンネルボックスである。大型格子であるため水ロッド本
数が8本となっている。8本の水ロッドのうち図中4で
示した5本は、定格運転時に核燃料物質の燃焼に合わせ
て水位が変わるスペクトルシフト運転用の水ロッドであ
り、図中、3で示した4本は、定格運転時には管内が満
水となる従来の水ロッドと同じに働き、炉心流量低下時
に管内の液面高さが下がる水ロッドである。炉心低流量
時の水ロッド管内液面高さと出力低減効果の増大量の関
係は、水ロッド内液面がある高さ以下となるとほとんど
変化しなくなる。このため、スペクトルシフト用に管内
液面高さが変わるように調整された水ロッドでは、定格
運転中に管内の水位が下がっているため、低流量時にさ
らに液面高さが下がっても、出力低減に大きな効果を出
すことが難しい。本実施例では、二種類の水ロッドを使
用することで、スペクトルシフト運転により燃料を有効
に燃焼できるとともに、炉心冷却材低流量時の出力低減
の増大も可能な燃料集合体を提供している。80%の可
燃性毒物入り燃料棒が、水ロッドに直接隣接しない位置
に燃料棒を1本挟んで配置されているため、サイクル初
期の炉心冷却水低流量時にも可燃性毒物により出力低減
効果が妨げられることがなく、定格運転時には可燃性毒
物が有効に燃焼するため、核燃料物質の有効利用を促進
することができる。
FIG. 8 shows a fourth embodiment of the present invention. The fuel assembly arrangement is 14 × 14, where 1 is a fuel rod and 2 is a fuel rod.
Is a fuel rod containing burnable poison, 3 and 4 are water rods, and 5 is a channel box. Since it is a large grid, the number of water rods is eight. Of the eight water rods, five shown by 4 in the figure are water rods for spectrum shift operation in which the water level changes according to the combustion of the nuclear fuel material during rated operation, and the four shown by 3 in the figure are A water rod that works in the same way as a conventional water rod in which the pipe is full of water during rated operation, and the liquid level in the pipe decreases when the core flow rate decreases. The relationship between the liquid level in the water rod pipe and the increase amount of the power reduction effect at the time of low core flow rate hardly changes when the liquid level in the water rod becomes lower than a certain height. For this reason, with a water rod that is adjusted to change the liquid level in the pipe for spectrum shifting, the water level in the pipe is lowered during rated operation. It is difficult to have a great effect on reduction. In the present embodiment, by using two types of water rods, a fuel assembly that can effectively burn fuel by spectrum shift operation and that can also increase output reduction at low core coolant flow rate is provided. . Since 80% of fuel rods containing burnable poisons are placed not directly adjacent to the water rods with one fuel rod sandwiched between them, burnable poisons can reduce the output even when the core cooling water flow rate is low at the beginning of the cycle. Since the burnable poison is effectively burned during the rated operation without being hindered, the effective use of the nuclear fuel material can be promoted.

【0015】図9は、本発明の第5の実施例で、燃料集
合体上部領域での可燃性毒物入り燃料棒配置が、本発明
の第1の実施例で示したように、半数より多い可燃性毒
物入り燃料棒が水ロッドに直接隣接しない配置となって
おり、水ロッドに非沸騰水が存在する集合体の下部は従
来の可燃性毒物入り燃料棒の配置となっている。これに
より、炉心冷却水低流量時に水ロッド内の液面が変化し
ボイド状態となる炉心上部では、液面高さ変化による、
可燃性毒物の反応度低減効果への影響が減少し、水ロッ
ド内が非沸騰水である集合体下部では、熱中性子スペク
トルの軟らかい位置に可燃性毒物入り燃料棒が配置され
るようになるため、可燃性毒物のサイクル初期における
反応度抑制効果を維持できる。
FIG. 9 shows a fifth embodiment of the present invention, in which the burnable poison-bearing fuel rod arrangement in the upper region of the fuel assembly is larger than half as shown in the first embodiment of the present invention. The burnable poison-bearing fuel rod is arranged not to be directly adjacent to the water rod, and the lower part of the assembly where non-boiling water exists in the water rod is the conventional burnable poison-bearing fuel rod. As a result, the liquid level in the water rod changes at the time of low flow rate of the core cooling water, and in the upper part of the core where it becomes a void state, due to the liquid level height change,
Since the influence of the burnable poison on the reactivity reduction effect is reduced, the fuel rod containing the burnable poison will be placed at the soft position of the thermal neutron spectrum in the lower part of the assembly where the water rod is non-boiling water. , The effect of suppressing the reactivity of the burnable poison in the early stage of the cycle can be maintained.

【0016】上記実施例の可燃性毒物入り燃料棒に添加
される可燃性毒物には、ガドリニア,ボロン,ジスプロ
シウムなどがある。
The burnable poisons added to the fuel rods containing burnable poisons in the above-mentioned embodiment include gadolinia, boron, dysprosium and the like.

【0017】[0017]

【発明の効果】本発明によれば、炉心冷却材流量低下時
における燃料の反応度を有効に抑制して、出力を低減す
る効果を約3%高めることができ、炉心の安定性を向上
できる。これにより、燃料の炉心への装荷量を増大して
使用済み燃料の発生体数を低減することができる。
According to the present invention, the reactivity of the fuel when the core coolant flow rate is reduced can be effectively suppressed, and the effect of reducing the output can be increased by about 3%, and the stability of the core can be improved. . This makes it possible to increase the amount of fuel loaded into the core and reduce the number of spent fuel generators.

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

【図1】本発明の第1の実施例の燃料集合体の断面図。FIG. 1 is a sectional view of a fuel assembly according to a first embodiment of the present invention.

【図2】従来の燃料集合体における可燃性毒物配置の一
例を示す断面図。
FIG. 2 is a sectional view showing an example of arrangement of burnable poisons in a conventional fuel assembly.

【図3】従来の燃料集合体における、水ロッド内ボイド
率が0%(水)から100%(蒸気)に変わったときの
反応度変化量の燃焼変化を示す特性図。
FIG. 3 is a characteristic diagram showing a combustion change of the reactivity change amount when the void ratio in the water rod changes from 0% (water) to 100% (steam) in the conventional fuel assembly.

【図4】サイクル初期における炉心に装荷された燃料の
可燃性毒物の有無を示す特性図。
FIG. 4 is a characteristic diagram showing the presence or absence of combustible poisons in the fuel loaded in the core at the beginning of the cycle.

【図5】本発明の燃料集合体における、水ロッド内ボイ
ド率が0%(水)から100%(蒸気)に変わったとき
の反応度変化量の燃焼変化を示す特性図。
FIG. 5 is a characteristic diagram showing the combustion change of the reactivity change amount when the void ratio in the water rod changes from 0% (water) to 100% (steam) in the fuel assembly of the present invention.

【図6】本発明の第2の実施例の燃料集合体を示す断面
図。
FIG. 6 is a sectional view showing a fuel assembly according to a second embodiment of the present invention.

【図7】本発明の第3の実施例の燃料集合体を示す断面
図。
FIG. 7 is a sectional view showing a fuel assembly according to a third embodiment of the present invention.

【図8】本発明の第4の実施例の燃料集合体を示す断面
図。
FIG. 8 is a sectional view showing a fuel assembly according to a fourth embodiment of the present invention.

【図9】本発明の第5の実施例の燃料集合体を示す断面
図。
FIG. 9 is a sectional view showing a fuel assembly according to a fifth embodiment of the present invention.

【符号の説明】[Explanation of symbols]

1…燃料棒、2…可燃性毒物入り棒、3…水ロッド、4
…水ロッド、5…チャンネルボックス。
1 ... Fuel rod, 2 ... Burnable poison containing rod, 3 ... Water rod, 4
… Water rod, 5… Channel box.

───────────────────────────────────────────────────── フロントページの続き (72)発明者 桝見 亮司 茨城県日立市森山町1168番地 株式会社日 立製作所エネルギー研究所内 ─────────────────────────────────────────────────── ─── Continuation of the front page (72) Inventor Ryoji Masumi 1168 Moriyama-cho, Hitachi-shi, Ibaraki Prefectural Energy Research Institute

Claims (5)

【特許請求の範囲】[Claims] 【請求項1】核燃料を充填した複数の燃料棒及び、可燃
性毒物を添加した複数の可燃性毒物入り棒及び、冷却材
の一部が流入し、前記冷却材の流量により管内の液面高
さを変えることのできる水ロッドから構成される燃料集
合体において、前記可燃性毒物入り棒の総数の50%よ
り多くが、前記水ロッドとの間に1本の燃料棒を挟んだ
位置に配置されていることを特徴とする燃料集合体。
1. A plurality of fuel rods filled with nuclear fuel, a plurality of rods containing burnable poisons added with burnable poisons, and a part of a coolant flow in, and the liquid level in the pipe is increased by the flow rate of the coolant. In a fuel assembly composed of variable water rods, more than 50% of the total number of burnable poison-containing rods is arranged at a position where one fuel rod is sandwiched between the rod and the water rod. The fuel assembly is characterized by being
【請求項2】軸方向上部2分の1以上で前記可燃性毒物
入り棒の配置が、請求項1の構成となっている領域が存
在する燃料集合体。
2. A fuel assembly in which there is a region in which the disposition of the burnable poison-bearing rods has an arrangement according to claim 1 in the axial upper half or more.
【請求項3】請求項1または2の燃料集合体を少なくと
も一体装荷した原子炉炉心。
3. A nuclear reactor core in which the fuel assembly according to claim 1 or 2 is at least integrally loaded.
【請求項4】請求項1または2において、前記可燃性毒
物入り棒は可燃性毒物が核燃料中に添加されている可燃
性毒物入り燃料棒である燃料集合体。
4. The fuel assembly according to claim 1, wherein the rod containing burnable poison is a fuel rod containing burnable poison added to a nuclear fuel.
【請求項5】請求項1または2において、前記可燃性毒
物入り棒は可燃性毒物が核燃料を充填した燃料棒の被覆
間中に添加されている燃料集合体。
5. The fuel assembly according to claim 1 or 2, wherein the burnable poison-containing rod is added with a burnable poison in a space between claddings of a fuel rod filled with nuclear fuel.
JP4249502A 1992-09-18 1992-09-18 Fuel assembly and reactor core Pending JPH06102385A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP4249502A JPH06102385A (en) 1992-09-18 1992-09-18 Fuel assembly and reactor core

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP4249502A JPH06102385A (en) 1992-09-18 1992-09-18 Fuel assembly and reactor core

Publications (1)

Publication Number Publication Date
JPH06102385A true JPH06102385A (en) 1994-04-15

Family

ID=17193924

Family Applications (1)

Application Number Title Priority Date Filing Date
JP4249502A Pending JPH06102385A (en) 1992-09-18 1992-09-18 Fuel assembly and reactor core

Country Status (1)

Country Link
JP (1) JPH06102385A (en)

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