JPH07159570A - Fuel assembly - Google Patents

Fuel assembly

Info

Publication number
JPH07159570A
JPH07159570A JP5304967A JP30496793A JPH07159570A JP H07159570 A JPH07159570 A JP H07159570A JP 5304967 A JP5304967 A JP 5304967A JP 30496793 A JP30496793 A JP 30496793A JP H07159570 A JPH07159570 A JP H07159570A
Authority
JP
Japan
Prior art keywords
fuel assembly
temperature
coolant
mixed
low
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
JP5304967A
Other languages
Japanese (ja)
Inventor
Hideaki Abe
英昭 安部
Megumi Kato
恵 加藤
Norikatsu Yokota
憲克 横田
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 JP5304967A priority Critical patent/JPH07159570A/en
Publication of JPH07159570A publication Critical patent/JPH07159570A/en
Pending 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

  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

PURPOSE:To expand the mixed region of high-temperature and low-temperature coolants downward and mitigate a thermal shock by providing a conical center rod increasing the cross sectional area toward the upper face from the lower face at the upper section of a handling head and at its center. CONSTITUTION:A coolant flows into a fuel assembly 1 from the coolant inflow port 2 of an inlet nozzle 3, it passes through passages among fuel rods 5, reaches a handing head 4, and flows out to the upper section of the fuel assembly 1. The high-temperature coolant flowing out from the fuel assembly 1 and the low-temperature coolant flowing out from adjacent control rods are mixed at the upper section of a core. Part of the coolant flows out along a conical center rod 14 provided at the upper end section of the handling head 4 of the fuel assembly 1, the mixed region of the high/ low temperature coolants is expanded to directly above the fuel assembly 1, and they are thoroughly mixed. The thermal shock is mitigated near the surface of the connection section of the guide pipes and lattice plates for a control rod driving mechanism. The thermal shock of the fuel assembly 1 at an optional portion of the upper structure of the core can be also mitigated.

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、高速増殖炉の燃料集合
体に関する。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a fuel assembly for a fast breeder reactor.

【0002】[0002]

【従来の技術】従来の高速増殖炉の燃料集合体1を図5
をもとに説明する。燃料集合体1の下端には複数個の冷
却材流入口2を有した入口ノズル3が装着され、上端に
はハンドリングヘッド4が装着されている。燃料集合体
1内には燃料棒5が、螺旋状に巻きつけられたワイヤ6
を介し、燃料集合体1内の下部に水平に装着された支持
板7により配置されている。
2. Description of the Related Art A conventional fuel assembly 1 for a fast breeder reactor is shown in FIG.
I will explain based on. An inlet nozzle 3 having a plurality of coolant inlets 2 is attached to the lower end of the fuel assembly 1, and a handling head 4 is attached to the upper end. In the fuel assembly 1, a fuel rod 5 and a wire 6 spirally wound.
The support plate 7 is horizontally mounted on the lower part of the fuel assembly 1 through the.

【0003】冷却材は入口ノズル3の冷却材流入口2よ
り流入し、燃料棒5の間の流路8を除熱しながら通って
ハンドリングヘッド4に到り、燃料集合体1の上部へと
流出する。燃料集合体1から流出する冷却材は、燃料棒
5の発熱量が大きいために高温になっている。これに対
し、例えば、制御棒集合体15又はブランケット燃料集
合体のような発熱量が比較的小さい集合体から流出する
冷却材は、燃料集合体1から流出する冷却材に比べて低
温となる。ブランケット燃料集合体は核分裂性のウラン
235が0.3% 以下の減損ウランを使用しているた
め、プルトニウムの生成が少ない使用の初期には入口ノ
ズル3からハンドリングヘッド4にいたる間の温度上昇
は小さく、入口ノズル3における温度と近い温度でハン
ドリングヘッド4からブランケット燃料集合体の上方へ
流出する。この低温度の冷却材はブランケット燃料集合
体が装荷された原子炉の冷却材の出口温度を低下させ
る。
The coolant flows from the coolant inlet port 2 of the inlet nozzle 3, passes through the passage 8 between the fuel rods 5 while removing heat, reaches the handling head 4, and flows out to the upper part of the fuel assembly 1. To do. The coolant flowing out of the fuel assembly 1 has a high temperature because the calorific value of the fuel rods 5 is large. On the other hand, for example, the coolant flowing out of the control rod assembly 15 or the assembly having a relatively small heat generation amount such as the blanket fuel assembly has a lower temperature than the coolant flowing out of the fuel assembly 1. Since the blanket fuel assembly uses depleted uranium whose fissionable uranium 235 is 0.3% or less, the temperature rise from the inlet nozzle 3 to the handling head 4 is small in the early stage of use when the production of plutonium is small. It is small and flows out of the handling head 4 above the blanket fuel assembly at a temperature close to that at the inlet nozzle 3. This low temperature coolant reduces the exit temperature of the coolant in the reactor loaded with blanket fuel assemblies.

【0004】炉心上部ではこれらの高温と低温の冷却材
が混合しながら上部構造物9の方へ上昇していく。上部
構造物9は炉心監視のための各種計装機構の支持機能、
および冷却材の整流機能等を有している。整流装置は制
御棒用案内管11と、その周りに格子上に配置された格
子板13に支持される整流筒12等からなるが、このよ
うな上部構造物9の高温と低温の冷却材にさらされる表
面付近では熱衝撃を受けることになる。特に制御棒用案
内管11と格子板13の結合部は熱衝撃が大きくなる。
このため耐熱合金で上部構造物9表面を覆う方法もある
が原子炉内での使用実績がなく、製作・加工も難かしい
ためコストも高くなる。
At the upper part of the core, these high-temperature and low-temperature coolants are mixed and rise toward the upper structure 9. The upper structure 9 is a supporting function of various instrumentation mechanisms for core monitoring,
It also has the function of rectifying the coolant. The rectifying device includes a control rod guide tube 11 and a rectifying cylinder 12 supported by a lattice plate 13 arranged on the lattice around the control rod guide tube 11, and the like. It will be subject to thermal shock near the exposed surface. In particular, the thermal shock increases at the joint between the control rod guide tube 11 and the lattice plate 13.
For this reason, there is a method of covering the surface of the upper structure 9 with a heat-resistant alloy, but there is no record of use in the nuclear reactor, and manufacturing and processing are difficult, so the cost is high.

【0005】この問題点を解決するために、特願昭63−
109392号明細書に記載の燃料集合体1のラッパ管10に
周方向に分布して孔を設けた構造のものが知られてお
り、孔付近で高温と低温の冷却材の混合が開始される。
In order to solve this problem, Japanese Patent Application No. 63-
A fuel assembly 1 described in the specification of No. 109392 has a structure in which holes are provided in the trumpet tube 10 distributed in the circumferential direction, and mixing of high-temperature and low-temperature coolant is started near the holes. .

【0006】[0006]

【発明が解決しようとする課題】上記従来技術におい
て、燃料集合体と制御棒集合体の流れが主流路から分岐
して途中で混合する状態となり大流量を有する燃料集合
体の流体の一部が、小流量の制御棒集合体等に流れ込む
可能性があり、好ましくない。
In the above-mentioned prior art, the flow of the fuel assembly and the control rod assembly is branched from the main flow path and mixed in the middle, so that a part of the fluid of the fuel assembly having a large flow rate is discharged. However, it may flow into the control rod assembly having a small flow rate, which is not preferable.

【0007】本発明の目的は、高温と低温の冷却材の混
合領域を下方に拡大して熱衝撃を緩和する燃料集合体を
提供することにある。
An object of the present invention is to provide a fuel assembly which expands a mixed region of high-temperature and low-temperature coolant downwards to mitigate thermal shock.

【0008】[0008]

【課題を解決するための手段】本発明の燃料集合体は液
体金属を冷却材とする高速増殖炉の炉心を構成するもの
であり、ハンドリングヘッドの上部で、ハンドリングヘ
ッドの中心に、下面から上面にかけて横断面積が増加す
る円錐状の中心棒を設けたものである。
The fuel assembly of the present invention constitutes the core of a fast breeder reactor using liquid metal as a coolant, and is located above the handling head, at the center of the handling head, and from the bottom surface to the top surface. It is provided with a conical center rod whose cross-sectional area increases over time.

【0009】[0009]

【作用】上記構成の本発明の燃料集合体を使用した炉心
上部の特定部位では、隣接して流出する低温の冷却材と
の混合領域が下方に拡大し、炉心上部の冷却材の温度ゆ
らぎが抑制される。そのため炉心の上部構造物に対する
疲労損傷が緩和されることになる。
In the specific portion of the core upper portion using the fuel assembly of the present invention having the above-described structure, the mixing region with the low temperature coolant flowing out adjacently expands downward, and the temperature fluctuation of the coolant in the core upper portion Suppressed. Therefore, the fatigue damage to the upper structure of the core is alleviated.

【0010】[0010]

【実施例】図1は本発明により構成した燃料集合体1の
縦断面図であり、図2は本発明により構成した燃料集合
体1のハンドリングヘッド4における横断面図である。
ここでハンドリングヘッド4の上部において、ハンドリ
ングヘッドの中心に、下面から上面にかけて横断面積が
増加する円錐状の中心棒14を設けている。燃料集合体
1には入口ノズル3の冷却材流入口2より冷却材が流入
し、燃料棒5の間の流路8を通ってハンドリングヘッド
4に到り燃料集合体1の上部へ流出する。燃料集合体1
から流出する冷却材は、燃料棒5の発熱量が大きいため
に高温になっている。これに対し、例えば、制御棒集合
体15やブランケット燃料集合体のような発熱量が小さ
い集合体から流出する冷却材は、燃料集合体1から流出
する冷却材に比べて低温となる。炉心上部ではこれらの
高温と低温の冷却材が混合しながら上部構造物9の方へ
上昇していく。図3は従来から用いられている燃料集合
体1から流出する高温の冷却材と隣接する集合体から流
出する低温の冷却材が炉心上部で混合する状態の説明図
であり、図4は本発明による燃料集合体1から流出する
高温と低温の冷却材が混合する状態を示した図である。
両図中で左下に向かう斜線を施した区域Aは高温の冷却
材が流出する領域を示し、右下に向かう斜線を施した区
域Bは低温の冷却材が流出する領域を示し、点の区域C
は高温と低温の冷却材が混合している領域を示す。区域
C内の下の部分では高温と低温の冷却材どうしが乱流状
態で揺らいでいるが、上に流れるにつれて温度が均一化
して来る。図3に示すように従来から用いられている燃
料集合体1では高温と低温の冷却材が充分に混合されて
なく、上部構造物9の冷却材にさらされる表面付近では
厳しい熱衝撃を受けることになる。本発明による燃料集
合体1を用いると、ハンドリングヘッド4の上端部に設
けられた中心棒14に沿って冷却材の一部が流出するた
め、図4に示すように区域Cの領域が集合体の直上まで
拡大して混合が充分に行われ、制御棒駆動機構用案内管
11と格子板13の結合部の表面付近では熱衝撃が緩和
されることになる。
1 is a vertical sectional view of a fuel assembly 1 constructed according to the present invention, and FIG. 2 is a transverse sectional view of a handling head 4 of the fuel assembly 1 constructed according to the present invention.
Here, in the upper part of the handling head 4, a conical center bar 14 whose cross-sectional area increases from the lower surface to the upper surface is provided at the center of the handling head. The coolant flows into the fuel assembly 1 from the coolant inlet port 2 of the inlet nozzle 3, passes through the flow path 8 between the fuel rods 5, reaches the handling head 4, and flows out to the upper part of the fuel assembly 1. Fuel assembly 1
The coolant flowing out from the fuel rod 5 has a high temperature because the calorific value of the fuel rod 5 is large. On the other hand, for example, the coolant flowing out from the control rod assembly 15 or the blanket fuel assembly that generates a small amount of heat has a lower temperature than the coolant flowing out of the fuel assembly 1. In the upper part of the core, the high temperature and low temperature coolants are mixed and rise toward the upper structure 9. FIG. 3 is an explanatory view of a state in which a high temperature coolant flowing out from a fuel assembly 1 that has been conventionally used and a low temperature coolant flowing out from an adjacent assembly are mixed in the upper part of the core, and FIG. FIG. 6 is a diagram showing a state in which high-temperature and low-temperature coolants flowing out from the fuel assembly 1 according to the above are mixed.
In both figures, a shaded area A to the lower left shows an area where high-temperature coolant flows out, and a shaded area B to the lower right shows an area where low-temperature coolant flows out. C
Indicates a region where the hot and cold coolants are mixed. In the lower part of the area C, the high-temperature and low-temperature coolants fluctuate in a turbulent state, but the temperature becomes uniform as they flow upward. As shown in FIG. 3, in the conventionally used fuel assembly 1, the high-temperature and low-temperature coolants are not sufficiently mixed, and severe thermal shock occurs near the surface of the upper structure 9 exposed to the coolant. become. When the fuel assembly 1 according to the present invention is used, a part of the coolant flows out along the center rod 14 provided at the upper end portion of the handling head 4, so that the region of the area C is the assembly as shown in FIG. As a result, the heat shock is reduced near the surface of the joint between the control rod drive mechanism guide tube 11 and the lattice plate 13 by expanding to just above.

【0011】本発明による燃料集合体1では、制御棒駆
動機構用案内管11と格子板13の結合部のみならず、
炉心の上部構造物9の任意の部位における熱衝撃が緩和
できる。
In the fuel assembly 1 according to the present invention, not only the connecting portion between the control rod drive mechanism guide tube 11 and the lattice plate 13,
The thermal shock at any part of the core upper structure 9 can be relaxed.

【0012】また、本発明による燃料集合体1はラッパ
管10の側面に孔を空けないため各集合体間で冷却材そ
のものの相互干渉が小さく、より高精度の設計ができ
る。またハンドリングヘッド4の製作・加工も従来技術
により可能である。
Further, since the fuel assembly 1 according to the present invention has no holes on the side surface of the trumpet tube 10, mutual interference of the coolant itself between the assemblies is small, and a more accurate design can be performed. Further, the manufacturing and processing of the handling head 4 can be performed by the conventional technique.

【0013】[0013]

【発明の効果】本発明の燃料集合体によれば、高温の冷
却材を流出する燃料集合体と、隣接する低温の冷却材を
流出する集合体の冷却材の混合領域が拡大するため、炉
心上部の冷却材の温度揺らぎを抑制でき熱衝撃が緩和さ
れることになるので、上部機構に対する疲労を緩和でき
る。
According to the fuel assembly of the present invention, the mixed region of the fuel assembly that flows out the high-temperature coolant and the coolant of the adjacent assembly that flows out the low-temperature coolant is expanded, so that the reactor core is expanded. Since the temperature fluctuation of the upper coolant can be suppressed and the thermal shock can be mitigated, fatigue to the upper mechanism can be mitigated.

【0014】また、上部構造物の破損を防止することに
より、燃料集合体内への構造物落下による冷却材の流路
閉塞事故を防ぐことができる。
Further, by preventing the upper structure from being damaged, it is possible to prevent the flow passage of the coolant from being blocked due to the structure falling into the fuel assembly.

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

【図1】本発明の一実施例の燃料集合体の縦断面図。FIG. 1 is a vertical cross-sectional view of a fuel assembly according to an embodiment of the present invention.

【図2】本発明の一実施例の燃料集合体の横断面図。FIG. 2 is a cross-sectional view of a fuel assembly according to an embodiment of the present invention.

【図3】従来から用いられている燃料集合体から流出す
る高温の冷却材と隣接する制御棒集合体から流出する低
温の冷却材が炉心上部で混合する状態の説明図。
FIG. 3 is an explanatory view showing a state in which a high temperature coolant flowing out from a fuel assembly which has been conventionally used and a low temperature coolant flowing out from an adjacent control rod assembly are mixed in the upper part of the core.

【図4】本発明による燃料集合体から流出する高温の冷
却材と隣接する制御棒集合体から流出する低温の冷却材
が炉心上部で混合する状態の説明図。
FIG. 4 is an explanatory view showing a state in which a high temperature coolant flowing out from a fuel assembly according to the present invention and a low temperature coolant flowing out from an adjacent control rod assembly are mixed in an upper portion of the core.

【図5】従来の燃料集合体の縦断面図。FIG. 5 is a vertical sectional view of a conventional fuel assembly.

【符号の説明】[Explanation of symbols]

1…燃料集合体、2…冷却材流入口、3…入口ノズル、
4…ハンドリングヘッド、11…制御棒用案内管。
1 ... Fuel assembly, 2 ... Coolant inlet, 3 ... Inlet nozzle,
4 ... Handling head, 11 ... Control rod guide tube.

Claims (1)

【特許請求の範囲】[Claims] 【請求項1】冷却材が内部を下方から上方へと流れる燃
料集合体のハンドリングヘッドの上部において、ハンド
リングヘッドの中心に、下面から上面にかけて横断面積
が増加する円錐状の部材を有することを特徴とする燃料
集合体。
1. A conical member having a cross-sectional area increasing from the lower surface to the upper surface at the center of the handling head in the upper portion of the handling head of the fuel assembly in which the coolant flows from the lower side to the upper side. And the fuel assembly.
JP5304967A 1993-12-06 1993-12-06 Fuel assembly Pending JPH07159570A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP5304967A JPH07159570A (en) 1993-12-06 1993-12-06 Fuel assembly

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP5304967A JPH07159570A (en) 1993-12-06 1993-12-06 Fuel assembly

Publications (1)

Publication Number Publication Date
JPH07159570A true JPH07159570A (en) 1995-06-23

Family

ID=17939473

Family Applications (1)

Application Number Title Priority Date Filing Date
JP5304967A Pending JPH07159570A (en) 1993-12-06 1993-12-06 Fuel assembly

Country Status (1)

Country Link
JP (1) JPH07159570A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2015517664A (en) * 2012-05-15 2015-06-22 ジーイー−ヒタチ・ニュークリア・エナジー・アメリカズ・エルエルシーGe−Hitachi Nuclear Energy Americas, Llc Fuel bundles for liquid metal cooled reactors.

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2015517664A (en) * 2012-05-15 2015-06-22 ジーイー−ヒタチ・ニュークリア・エナジー・アメリカズ・エルエルシーGe−Hitachi Nuclear Energy Americas, Llc Fuel bundles for liquid metal cooled reactors.

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