JPH0555836B2 - - Google Patents

Info

Publication number
JPH0555836B2
JPH0555836B2 JP58095547A JP9554783A JPH0555836B2 JP H0555836 B2 JPH0555836 B2 JP H0555836B2 JP 58095547 A JP58095547 A JP 58095547A JP 9554783 A JP9554783 A JP 9554783A JP H0555836 B2 JPH0555836 B2 JP H0555836B2
Authority
JP
Japan
Prior art keywords
fuel
rods
burnable poison
gadolinia
lower half
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 - Lifetime
Application number
JP58095547A
Other languages
Japanese (ja)
Other versions
JPS59220674A (en
Inventor
Shino Yoshioka
Yuzuru Nagano
Kazutaka Hida
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 JP58095547A priority Critical patent/JPS59220674A/en
Publication of JPS59220674A publication Critical patent/JPS59220674A/en
Publication of JPH0555836B2 publication Critical patent/JPH0555836B2/ja
Granted 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

  • Fuel-Injection Apparatus (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Description

【発明の詳細な説明】 〔発明の技術分野〕 本発明は主として沸騰水型原子炉に用いられる
燃料集合体に関する。
DETAILED DESCRIPTION OF THE INVENTION [Technical Field of the Invention] The present invention relates primarily to a fuel assembly used in a boiling water nuclear reactor.

〔発明の技術的背景〕[Technical background of the invention]

一般に、沸騰水型原子炉には第1図および第2
図に示す燃料集合体が装架されている。
In general, boiling water reactors are shown in Figures 1 and 2.
The fuel assembly shown in the figure is installed.

この燃料集合体は、上部タイプレート1と下部
タイプレート2との間に、複数本の燃料棒3と複
数本の可燃性毒物入燃料棒4(符号Gを付してあ
る。)と2本のウオータロツド5(符号Wを付し
てある。)とを、第2図に示すように8行8列の
正方格子状に配列し、中間部の数箇所をスペーサ
6により支持して形成されており、チヤンネルボ
ツクス7内に収容されている。そして、燃料集合
体は第2図に示すように断面十字形の制御棒8に
沿つて炉心内に装荷される。
This fuel assembly includes a plurality of fuel rods 3, a plurality of burnable poison-containing fuel rods 4 (designated with the symbol G), and two fuel rods between an upper tie plate 1 and a lower tie plate 2. Water rods 5 (marked with the symbol W) are arranged in a square lattice of 8 rows and 8 columns as shown in FIG. 2, and are supported at several locations in the middle by spacers 6. and is housed in the channel box 7. The fuel assembly is then loaded into the reactor core along the control rod 8, which has a cross-shaped cross section, as shown in FIG.

前期ウオータロツド5はジルカロイ製の管で、
冷却材が下方から上方に向けて流通するように形
成されている。
The early Waterrod 5 was a Zircaloy tube.
It is formed so that the coolant flows from the bottom to the top.

また、燃料棒3は、ジルカロイ製の燃料被覆管
3a内に、ウラン235を濃縮した二酸化ウラン
(UO2)を焼き固めてペレツト状にした二酸化ウ
ランペレツト(図示せず)を軸方向に複数個装填
して形成されている。そして、各燃料棒3の軸方
向の二酸化ウランの濃縮度は一定に形成されてい
る。
In addition, the fuel rod 3 has a Zircaloy fuel cladding tube 3a loaded with a plurality of uranium dioxide pellets (not shown) in which uranium dioxide (UO 2 ) enriched with uranium 235 is sintered into pellets (not shown). It is formed by The enrichment degree of uranium dioxide in the axial direction of each fuel rod 3 is formed to be constant.

また、可燃性毒物入燃料棒4は、ジルカロイ製
の燃料被覆管内に、二酸化ウランにガドリニア
(Gd2O3)等の可燃性毒物を数重量%の濃度で混
入して焼き固めてペレツト状にしたガドリニア混
入ペレツトを軸方向に複数個装填して形成されて
いる。そして、各可燃性毒物入燃料棒4の軸方向
の二酸化ウランの濃縮度およびガドリニア混入量
は一定に形成されている。
In addition, the burnable poison-containing fuel rod 4 is made by mixing uranium dioxide with a burnable poison such as gadolinia (Gd 2 O 3 ) at a concentration of several percent by weight in a Zircaloy fuel cladding tube, and baking the mixture into a pellet shape. It is formed by loading a plurality of gadolinia-mixed pellets in the axial direction. The enrichment degree of uranium dioxide and the amount of gadolinia mixed in the axial direction of each burnable poison-containing fuel rod 4 are set constant.

〔背景技術の問題点〕[Problems with background technology]

燃料集合体中の核燃料は燃焼が進むにつれて、
内部のウラン235の濃度が減少し、燃料集合体
の無限増倍率が低下し、反応度が低下してゆく。
As the nuclear fuel in the fuel assembly progresses,
The concentration of uranium-235 inside decreases, the infinite multiplication factor of the fuel assembly decreases, and the reactivity decreases.

そこで高い反応度のもとで原子炉運転を行なう
ため、一定期間毎に原子炉を停止し、炉心に装荷
された全燃料集合体のうちの1/4〜1/3を新燃料集
合体と交換している。
Therefore, in order to operate the reactor under high reactivity, the reactor is shut down at regular intervals and 1/4 to 1/3 of the total fuel assemblies loaded in the core are replaced with new fuel assemblies. are being exchanged.

ところが、この燃料交換によつて原子炉が長期
間に亘つて停止し、稼働率が低下するので、燃料
交換の間隔はできるだけ長くすることが望まれて
いる。
However, this fuel exchange causes the reactor to stop for a long period of time, reducing the operating rate, so it is desired that the interval between fuel exchanges be as long as possible.

このため、従来は各燃料棒のウラン235濃縮
度を大きくし、長期間に亘つて燃料集合体の無限
増倍率を運転に必要な値以上に維持できるように
形成している。更に、ウラン235の濃縮度が大
きくなることによつて生じる燃焼運転期間の初期
の余剰の無限増倍率を、前記したように複数の可
燃性毒物入燃料棒4,4によつて抑制している。
For this reason, conventionally, the uranium-235 enrichment of each fuel rod is increased so that the infinite multiplication factor of the fuel assembly can be maintained over a long period of time at a value greater than that required for operation. Furthermore, the surplus infinite multiplication factor at the beginning of the combustion operation period, which occurs due to the increase in the enrichment of uranium-235, is suppressed by the plurality of burnable poison-filled fuel rods 4, 4, as described above. .

しかし、各燃料棒3,3のウラン235の濃縮
度を大きくすると燃料製造のコストが高くなり、
また可燃性毒物棒による燃料集合体の無限増倍率
抑制の能力にも限界があるため、ウラン濃縮度を
あまり大きくすることはできず、燃料交換間隔の
長期化にも限界があつた。
However, increasing the enrichment of uranium-235 in each fuel rod 3 increases the cost of fuel production.
Furthermore, there was a limit to the ability of burnable poison rods to suppress the infinite multiplication factor of fuel assemblies, so the uranium enrichment could not be increased too much, and there was also a limit to the lengthening of fuel replacement intervals.

また、核燃料の燃焼効率を向上させることも要
求されているが、従来の燃料集合体においてはそ
の燃焼効率の向上にも限界があつた。
There is also a need to improve the combustion efficiency of nuclear fuel, but there is a limit to the improvement in combustion efficiency in conventional fuel assemblies.

〔発明の目的〕[Purpose of the invention]

本発明はこれらの点に鑑みてなされたものであ
り、長期間に亘つて反応度を所定値以上に維持す
ることができ、燃料交換の間隔を長期化すること
ができ、原子炉の長期間の連続運転を可能として
原子炉の稼働率を向上させ、また燃料の燃焼効率
を向上させることができる燃料集合体を提供する
ことを目的とする。
The present invention has been made in view of these points, and it is possible to maintain the reactivity at a predetermined value or higher for a long period of time, and it is possible to extend the interval between fuel exchanges, so that the reactor can be used for a long period of time. The purpose of the present invention is to provide a fuel assembly that enables continuous operation of the nuclear reactor, improves the operating rate of the reactor, and improves the combustion efficiency of the fuel.

〔発明の概要〕 本発明は、複数本の燃料棒とN2本の少なくと
も下半部に可燃性毒物が混入された可燃性毒物入
燃料棒とを配列して形成されている燃料集合体に
おいて、下半部に可燃性毒物が混入された可燃性
毒物入燃料棒のN2本の内、上半部に可燃性毒物
を混入した可燃性毒物入燃料棒をN1本とし、少
なくとも下半部に可燃性毒物が混入された(N2
−N1+1)本以上の可燃性毒物入燃料棒の下半
部の可燃性毒物濃度を、上半部に可燃性毒物が混
入された可燃性毒物入燃料棒の上半部の可燃性毒
物濃度より小さく形成したことを特徴とする。
[Summary of the Invention] The present invention provides a fuel assembly formed by arranging a plurality of fuel rods and two burnable poison-containing fuel rods in which at least the lower half of the fuel rods are mixed with a burnable poison. , out of N 2 fuel rods with burnable poison mixed in the lower half, N 1 fuel rod with burnable poison mixed in the upper half, and at least the lower half A burnable poison was mixed into the unit ( N2
-N 1 +1) Burnable poison concentration in the lower half of more than one fuel rod containing burnable poison is calculated as the burnable poison concentration in the upper half of the fuel rod containing burnable poison in the upper half of the fuel rod. It is characterized by being formed smaller than the concentration.

〔発明の実施例〕[Embodiments of the invention]

以下、本発明を第3図から第11図に示す実施
例について説明する。
The present invention will be described below with reference to embodiments shown in FIGS. 3 to 11.

第3図から第8図は本発明の一実施例を示す。 3 to 8 show one embodiment of the present invention.

第3図において従来と同一部分には同一符号を
付してある。
In FIG. 3, the same parts as in the prior art are given the same reference numerals.

本発明は、第3図および第4図に示すように8
本の可燃性毒物入燃料棒(以下、Gdロツドとい
う。)のうち、符号G1の2本をその上部には二酸
化ウランにガドリニアを5重量%程度混入し焼き
固めペレツト状にしたものを装填し、その下部に
は二酸化ウランにガドリニアを1重量%程度混入
し焼き固めペレツト状にしたものを装填して形成
している。また、他の符号G2の6本には二酸化
ウランにガドリニアを5重量%程度混入し焼固め
ペレツト状にしたものをその長さ方向全体に装填
している。
As shown in FIG. 3 and FIG.
Two of the burnable poison-containing fuel rods (hereinafter referred to as Gd rods) with the code G1 were loaded with uranium dioxide mixed with about 5% by weight of gadolinia and baked into pellets. The lower part is filled with uranium dioxide mixed with about 1% by weight of gadolinia, which is baked and hardened into pellets. In addition, the other six tubes with reference numeral G2 are loaded with uranium dioxide mixed with about 5% by weight of gadolinia in the form of sintered pellets throughout their length.

すなわち、燃料運転期間(サイクル)の初期す
なわち燃焼度が0〜2GWD/Tの場合には、第
5A図に示すように、Gdロツドの上半部と下半
部との本数は共に8本と同数であるが、2本の
GdロツドG1の下部のガドリニア濃度が上部より
低く、全体としてGdロツドG1、G2の上半部のガ
ドリニア濃度が下半部より多くしてあり、第6図
に示すように燃料集合体全体の下半部の無限増倍
率Bより、上半部の無限増倍率Aが同程度か若干
低くなるようにしてある。
That is, at the beginning of the fuel operation period (cycle), that is, when the burnup is between 0 and 2 GWD/T, the number of Gd rods in the upper and lower halves is both eight, as shown in Figure 5A. The same number, but two
The gadolinia concentration in the lower part of Gd rod G 1 is lower than the upper part, and the gadolinia concentration in the upper half of Gd rods G 1 and G 2 as a whole is higher than that in the lower half. The infinite multiplication factor A in the upper half is set to be about the same level or slightly lower than the infinite multiplication factor B in the lower half of the whole.

そして、濃度の低い2本のGdロツドG1の下部
のガドリウム(Gd155とGd157)が燃焼し尽くし
てしまつたサイクル中期すなわち燃焼度が2〜
9GWD/Tの場合には、第5B図に示すように、
上半部のGdロツドが8本となり、下半部の6本
より多くなり、第6図に示すように、燃料集合体
全体の下半部の無限増倍率Bより、上半部の無限
増倍率Aが約3%程度低くなるようにしてある。
Then, in the middle of the cycle, when the gadolinium (Gd155 and Gd157) at the bottom of the two low-concentration Gd rods G1 has been completely burned out, that is, the burnup is between 2 and 2.
In the case of 9GWD/T, as shown in Figure 5B,
The number of Gd rods in the upper half is 8, which is more than the 6 in the lower half, and as shown in Figure 6, the infinite multiplication factor B in the lower half of the entire fuel assembly is greater than the infinite multiplication factor B in the lower half. The magnification A is set to be about 3% lower.

そして、このような燃焼の結果、サイクル末期
すなわち燃焼度9〜11GWD/Tにおいては、燃
料集合体の上半部のウラン235の残存量が下半
部に比較して相対的に多くなり、上半部の無限増
倍率がAが下半部の無限増倍率Bに次第に近づく
ようにしてある。
As a result of such combustion, at the end of the cycle, that is, at a burnup of 9 to 11 GWD/T, the remaining amount of uranium-235 in the upper half of the fuel assembly becomes relatively larger than that in the lower half. The infinite multiplication factor A in the half section is made to gradually approach the infinite multiplication factor B in the lower half section.

しかして、このような燃料集合体の装填によつ
てその燃焼運転期間中、原子炉はそのサイクル初
期から中期にかけては、第7図実線に示すように
炉心の軸方向の出力分布が下部ピークとなり、サ
イクル末期においては、第8図実線に示すように
軸方向の出力分布は上部ピークとなる。
However, due to the loading of such fuel assemblies, during the combustion operation period of the reactor, the power distribution in the axial direction of the reactor core reaches a lower peak from the beginning to the middle of the cycle, as shown by the solid line in Figure 7. At the end of the cycle, the output distribution in the axial direction reaches an upper peak as shown by the solid line in FIG.

また、炉心内のボイド率についてみると、サイ
クルの初期および中期からなる大部分において、
蒸気が炉心の下部から発生し、第7図破線で示す
炉心内の平均ボイド率は従来の沸騰水型原子炉に
比較して約5〜10%高くなる。このボイド率が高
いと、中性子の減速作用が抑制され熱中性子より
高いエネルギの共鳴領域のエネルギを保有する中
性子が増加する。そして、これに伴つてウラン2
38の共鳴吸収が増加し、プルトニウムへの転換
量が増加する。これによつて燃料の燃焼効率が向
上し、ひいては燃料経済性が向上することとな
る。
In addition, when looking at the void rate in the core, in most of the early and middle stages of the cycle,
Steam is generated from the lower part of the core, and the average void fraction in the core, indicated by the broken line in Figure 7, is about 5 to 10% higher than in conventional boiling water reactors. When this void fraction is high, the moderation effect of neutrons is suppressed, and the number of neutrons having energy in a resonance region higher than that of thermal neutrons increases. Along with this, uranium 2
The resonance absorption of 38 increases, and the amount of conversion to plutonium increases. This improves fuel combustion efficiency and, in turn, improves fuel economy.

そして、サイクル末期へ移行するにつれて蒸気
の発生域は、軸方向上方に移動する。これによつ
て第8図破線で示す平均ボイド率は従来に比較し
て約5〜10%低くなる。そして、中性子の減速作
用が促進され、炉心反応度が増加される。これに
より、炉心の反応度を長期に亘つて必要な値以上
に維持し、原子炉の長期間の運転が可能となる。
As the cycle progresses toward the end, the steam generation region moves upward in the axial direction. As a result, the average void ratio shown by the broken line in FIG. 8 is lowered by about 5 to 10% compared to the conventional method. Then, the moderation effect of neutrons is promoted, and the core reactivity is increased. As a result, the reactivity of the reactor core can be maintained at a required value or higher for a long period of time, and the reactor can be operated for a long period of time.

このように燃料集合体の下部のガドリニア混入
量を上部のそれより少なくし、上半部の無限増倍
率が下半部の無限増倍率より小さくなるようにし
たことにより、炉心出力分布をサイクルの大部分
において下部ピークとし、サイクル末期において
上部ピークとすることができる。更に、プルトニ
ウム転換量が増加し、燃料を経済的に燃焼させる
ことができ、燃料経済性を向上させることができ
る。
In this way, by making the amount of gadolinia mixed in the lower part of the fuel assembly smaller than that in the upper part, and by making the infinite multiplication factor in the upper half smaller than the infinite multiplication factor in the lower half, the core power distribution was changed over the cycle. It can be a lower peak for the most part and an upper peak at the end of the cycle. Furthermore, the amount of plutonium conversion is increased, and the fuel can be burnt economically, improving fuel economy.

本実施例は上半部と下半部とにおけるGdロツ
ドの本数が等しい場合に、少なくとも1本の下半
部のガドリニア濃度をガドリニアが混入した上半
部のガドリニア濃度より小さく形成したものであ
る。
In this example, when the number of Gd rods in the upper half and lower half is equal, the gadolinia concentration of at least one of the lower half is made lower than the gadolinia concentration of the upper half mixed with gadolinia. .

また、サイクル初期、特に取替サイクルにおい
て、前サイクルの燃焼履歴に応じて、炉心の軸方
向出力分布を調整するために、Gdロツドの上半
部と下半部とのガドリウム量の分布を次のように
変えるとよい。
In addition, at the beginning of the cycle, especially in the replacement cycle, in order to adjust the axial power distribution of the core according to the combustion history of the previous cycle, the distribution of the amount of gadolinium in the upper and lower halves of the Gd rod was determined as follows. It would be better to change it like this.

例えば、前サイクルで下半部のウラン235の
燃焼が余り進まず、多量のウラン235が残存し
ている場合には、下半部の燃焼速度を上半部より
若干早い速度にさせて炉心の熱的健全性を保持す
る必要がある。
For example, if the combustion of uranium-235 in the lower half did not progress much in the previous cycle and a large amount of uranium-235 remains, the combustion rate in the lower half is set to be slightly faster than in the upper half. Thermal integrity must be maintained.

この時には、第9図から第11図に示すよう
に、少なくとも下半部にガドリニアを混入させた
Gdロツドの本数N2を上半部にガドリニアを混入
させたGdロツドの本数N1より多くし、下半部に
ガドリニアが混入された(N2−N1+1)本以上
のGdロツドの下半部のガドリニアの濃度を、上
半部にガドリニアが混入されたGdロツドの上半
部のガドリニアの濃度より小さく形成するとよ
い。すなわち、第9図から第11図に示す実施例
は、上半部のガドリニア濃度が5重量%で下半部
が1重量%のGdロツドG1が3本、上半部および
下半部をも5重量%のGdロツドG2が4本、上半
部が0重量%で下半部が5重量%のGdロツドG3
が2本とされている。
At this time, as shown in Figures 9 to 11, gadolinia was mixed into at least the lower half.
The number of Gd rods N 2 is greater than the number N 1 of Gd rods with gadolinia mixed in the upper half, and the number of Gd rods with Gd rods mixed with gadolinia in the lower half (N 2 - N 1 + 1) is lower. It is preferable that the concentration of gadolinia in the half part is lower than the concentration of gadolinia in the upper half of the Gd rod in which gadolinia is mixed in the upper half. That is, in the example shown in FIGS. 9 to 11, three Gd rods G1 with a gadolinia concentration of 5% by weight in the upper half and 1% by weight in the lower half are used. 4 pieces of Gd rod G 2 with 5% weight, the upper half is 0% by weight and the lower half is 5% by weight Gd rod G 3
There are said to be two.

この場合、下半部のガドリニア濃度の小さい
GdロツドG1の本数が下半部のガドリニア濃度の
大きいGdロツドG3の本数より1本多いので、燃
料集合体全体としては下部ピークとして燃焼する
が、そのピークの度合は低く抑えられる。そし
て、サイクル初期から中期に入ると、Gdロツド
G1の下半部のガドリウムが燃焼し尽すので、上
半部のGdロツドの本数が下部よりも1本多くな
り、以後は前記と同様にして下部ピークとなる燃
焼が行なわれる。また、この場合サイクル初期に
おいて更に下部ピークの度合を低く抑えるには、
GdロツドG2およびG3のガドリニア濃度を6重量
%とすればよい。
In this case, the gadolinia concentration in the lower half is small.
Since the number of Gd rods G 1 is one more than the number of Gd rods G 3 in the lower half where the gadolinia concentration is high, the fuel assembly as a whole burns as a lower peak, but the degree of the peak is suppressed to a low level. Then, in the early to middle cycle, Gd rods
Since the gadolinium in the lower half of G1 is completely burnt out, the number of Gd rods in the upper half becomes one more than in the lower part, and from then on, combustion with the lower peak occurs in the same manner as described above. In this case, in order to further reduce the degree of the lower peak at the beginning of the cycle,
The gadolinia concentration of Gd rods G2 and G3 may be 6% by weight.

〔発明の効果〕〔Effect of the invention〕

このように本発明の燃料集合体は構成され、作
用するものであるから、長期間に亘つて反応度を
所定値以上に維持することができ、燃料交換の間
隔を長期化することができ、原子炉の長期間の連
続運転を可能とし、原子炉の稼働率を向上させ、
更に燃料の燃焼効率を向上させる等の効果を奏す
る。
Since the fuel assembly of the present invention is constructed and operates in this manner, it is possible to maintain the reactivity above a predetermined value over a long period of time, and the interval between fuel exchanges can be extended. Enables long-term continuous operation of nuclear reactors, improves reactor availability,
Furthermore, it has effects such as improving fuel combustion efficiency.

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

第1図は従来の燃料集合体を示す一部切断斜視
図、第2図は第1図の−線に沿つた拡大断面
図、第3図から第11図は本発明の燃料集合体の
実施例を示し、第3図から第8図は本発明の一実
施例を示し、第3図は第2図同様の図、第4図は
Gdロツドの種類とその炉心軸方向のガドリニア
濃度を示す説明図、第5A図はサイクル初期にお
けるGdロツドの軸方向本数を示す線図、第5B
図はサイクル中期および末期のGdロツドの軸方
向本数を示す線図、第6図は燃焼度(GWD/
T)に対する無限増倍率(K∞)の変化を示す特
性図、第7図はサイクル初期および中期における
炉心軸方向の炉心出力分布およびボイド発生分布
を示す特性図、第8図はサイクル末期における第
7図同様の図、第9図および第10図はそれぞれ
本発明の他の実施例を示す第3図同様の図、第1
1図は第9図および第10図におけるGdロツド
を示す第4図同様の図である。 3……燃料棒、G1,G2,G3……Gdロツド(可
燃性毒物入燃料棒)。
FIG. 1 is a partially cutaway perspective view showing a conventional fuel assembly, FIG. 2 is an enlarged sectional view taken along the line - in FIG. 1, and FIGS. 3 to 11 are implementations of the fuel assembly of the present invention. For example, Figures 3 to 8 show an embodiment of the present invention, Figure 3 is similar to Figure 2, and Figure 4 is a diagram similar to Figure 2.
An explanatory diagram showing the types of Gd rods and their gadolinia concentrations in the axial direction of the core, Figure 5A is a diagram showing the number of Gd rods in the axial direction at the beginning of the cycle, and Figure 5B
The figure shows the number of Gd rods in the axial direction in the middle and end of the cycle, and Figure 6 shows the burnup (GWD/
Figure 7 is a characteristic diagram showing the change in the infinite multiplication factor (K∞) with respect to T). Figure 7 is a characteristic diagram showing the core power distribution and void generation distribution in the core axis direction at the early and middle stages of the cycle. FIG. 7 is a similar view, FIG. 9 and FIG. 10 are similar views to FIG. 3, and FIG.
FIG. 1 is a diagram similar to FIG. 4 showing the Gd rod in FIGS. 9 and 10. 3...Fuel rods, G1 , G2 , G3 ...Gd rods (fuel rods containing burnable poison).

Claims (1)

【特許請求の範囲】[Claims] 1 複数本の燃料棒とN2本の少なくとも下半部
に可燃性毒物が混入された可燃性毒物入燃料棒と
を配列して形成されている燃料集合体において、
下半部に可燃性毒物が混入された可燃性毒物入燃
料棒のN2本の内、上半部に可燃性毒物を混入し
た可燃性毒物入燃料棒をN1本とし、少なくとも
下半部に可燃性毒物が混入された(N2−N1
1)本以上の可燃性毒物入燃料棒の下半部の可燃
性毒物濃度を、上半部に可燃性毒物が混入された
可燃性毒物入燃料棒の上半部の可燃性毒物濃度よ
り小さく形成したことを特徴とする燃料集合体。
1. In a fuel assembly formed by arranging a plurality of fuel rods and two fuel rods containing burnable poison, at least the lower half of which is mixed with burnable poison,
Of N 2 fuel rods with burnable poison mixed with burnable poison in the lower half, N 1 fuel rod with burnable poison mixed in the upper half, at least in the lower half. burnable poison was mixed into (N 2 −N 1 +
1) The burnable poison concentration in the lower half of one or more fuel rods containing burnable poison is lower than the burnable poison concentration in the upper half of the fuel rod containing burnable poison in the upper half. A fuel assembly characterized in that it has been formed.
JP58095547A 1983-05-30 1983-05-30 Fuel assembly Granted JPS59220674A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP58095547A JPS59220674A (en) 1983-05-30 1983-05-30 Fuel assembly

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP58095547A JPS59220674A (en) 1983-05-30 1983-05-30 Fuel assembly

Publications (2)

Publication Number Publication Date
JPS59220674A JPS59220674A (en) 1984-12-12
JPH0555836B2 true JPH0555836B2 (en) 1993-08-18

Family

ID=14140594

Family Applications (1)

Application Number Title Priority Date Filing Date
JP58095547A Granted JPS59220674A (en) 1983-05-30 1983-05-30 Fuel assembly

Country Status (1)

Country Link
JP (1) JPS59220674A (en)

Families Citing this family (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS62276494A (en) * 1986-05-24 1987-12-01 株式会社日立製作所 Fuel assembly for boiling water reactors
JP2563287B2 (en) * 1986-12-15 1996-12-11 株式会社東芝 Fuel assembly for nuclear reactor
JPH07109435B2 (en) * 1989-03-20 1995-11-22 株式会社日立製作所 Fuel assembly
CN105843178B (en) * 2015-01-13 2019-10-01 国核(北京)科学技术研究院有限公司 Automatic material-changing method and system for circulating fuel management

Also Published As

Publication number Publication date
JPS59220674A (en) 1984-12-12

Similar Documents

Publication Publication Date Title
JP3531011B2 (en) Fuel assemblies and reactors
US5781604A (en) Initial core and fuel assembly
JPH07101237B2 (en) Fuel assembly and nuclear reactor
JPH0536757B2 (en)
JPH0555836B2 (en)
JPH0915361A (en) Initially loaded core
US5422922A (en) Fuel assembly and reactor core
JPH0439919B2 (en)
JPH022977A (en) Boiling water reactor fuel assembly
JP3237922B2 (en) Fuel assemblies and cores for boiling water reactors
JP2966877B2 (en) Fuel assembly
US4871508A (en) Method for operation of a light water boiling reactor
JPS59147295A (en) Fuel assembly
JP2610254B2 (en) Boiling water reactor
JPS63293489A (en) Fuel assembly
JP3075749B2 (en) Boiling water reactor
JPH0342436B2 (en)
JPH0827370B2 (en) Boiling water reactor
JP2852101B2 (en) Reactor core and fuel loading method
JP2739515B2 (en) Boiling water reactor
JP4044993B2 (en) Reactor fuel loading method
JP3435874B2 (en) Fuel assemblies and reactor cores
JPH07109435B2 (en) Fuel assembly
JPH058398B2 (en)
JPS6361991A (en) Fuel aggregate