JPS59229475A - Fuel channel box - Google Patents
Fuel channel boxInfo
- Publication number
- JPS59229475A JPS59229475A JP58102649A JP10264983A JPS59229475A JP S59229475 A JPS59229475 A JP S59229475A JP 58102649 A JP58102649 A JP 58102649A JP 10264983 A JP10264983 A JP 10264983A JP S59229475 A JPS59229475 A JP S59229475A
- Authority
- JP
- Japan
- Prior art keywords
- channel box
- fuel channel
- fuel
- longitudinal direction
- alloy
- 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
Links
Classifications
-
- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22F—CHANGING THE PHYSICAL STRUCTURE OF NON-FERROUS METALS AND NON-FERROUS ALLOYS
- C22F1/00—Changing the physical structure of non-ferrous metals or alloys by heat treatment or by hot or cold working
- C22F1/16—Changing the physical structure of non-ferrous metals or alloys by heat treatment or by hot or cold working of other metals or alloys based thereon
- C22F1/18—High-melting or refractory metals or alloys based thereon
- C22F1/186—High-melting or refractory metals or alloys based thereon of zirconium or alloys based thereon
Landscapes
- Chemical & Material Sciences (AREA)
- Physics & Mathematics (AREA)
- Thermal Sciences (AREA)
- Crystallography & Structural Chemistry (AREA)
- Engineering & Computer Science (AREA)
- Materials Engineering (AREA)
- Mechanical Engineering (AREA)
- Metallurgy (AREA)
- Organic Chemistry (AREA)
- Heat Treatment Of Nonferrous Metals Or Alloys (AREA)
Abstract
Description
【発明の詳細な説明】
〔発明の利用分野〕
本発明は沸騰水型原子炉用燃料集合体を構成する燃料チ
ャンネルボックスに係シ、特に照射による曲シ変形の少
ない特性を有する制御棒案内面として好適な燃料チャン
ネルボックスに関する。[Detailed Description of the Invention] [Field of Application of the Invention] The present invention relates to a fuel channel box constituting a fuel assembly for a boiling water nuclear reactor, and in particular to a control rod guide surface having a characteristic of less bending deformation due to irradiation. The present invention relates to a fuel channel box suitable as a fuel channel box.
沸騰水型原子炉の燃料集合体は第１図に示すように、複
数体の核燃料要素２、核燃料要素２の水平方向間隔を一
定値以上に保持するための数個の支持格子３並びに核燃
料要素２を支持しかつその間隔を一定に保持する上部タ
イプレート４及び下部タイプレート５が燃料チャンネル
ボックス６内に収納されている構造を有している。As shown in FIG. 1, the fuel assembly of a boiling water reactor includes a plurality of nuclear fuel elements 2, several support grids 3 for maintaining the horizontal spacing of the nuclear fuel elements 2 at a certain value or more, and the nuclear fuel elements. The fuel channel box 6 has a structure in which an upper tie plate 4 and a lower tie plate 5, which support the fuel cell 2 and maintain a constant interval between them, are housed in a fuel channel box 6.
燃料集合体における燃料チャンネルボックス６の主な機
能は核燃料要素２を冷却するに十分な冷却材の確保とそ
の流路の形成、制御棒案内面の形成及び燃料集合体の剛
性の確保でおる。The main functions of the fuel channel box 6 in the fuel assembly are to secure enough coolant to cool the nuclear fuel element 2, to form a flow path for the coolant, to form a control rod guide surface, and to ensure the rigidity of the fuel assembly.
燃料チャ／ネルボックス６を構成するジルコニウム合金
は、原子炉の運転に伴う高速中性子の照射によって特定
方向に伸びる所開照射成長伸びを生じる特性があり、前
記照射成長伸びは燃料チャンネルボックス６において特
に長手方向が太きい。The zirconium alloy constituting the fuel channel box 6 has a characteristic of causing open irradiation growth elongation that extends in a specific direction by irradiation with fast neutrons during nuclear reactor operation. It is thicker in the longitudinal direction.
ところが、例えば原子炉の炉心周辺領域のように高速中
性子束の炉心径方向分布に勾配がある領域では、燃料チ
ャンネルボックスの各側面で高速中性子束（φ）が異な
るため、燃料チャンネルボックスの各側面長手方向の照
射成長伸びた差が生じる。However, in a region where the distribution of fast neutron flux in the core radial direction has a gradient, such as the region around the core of a nuclear reactor, the fast neutron flux (φ) differs on each side of the fuel channel box. Longitudinal irradiation growth causes elongated differences.
このように燃料チャンネルボックスの各側面長手方向に
照射成長伸び差を生じると、第２図に示すように高速中
性子束が大なる方が凸となる湾曲を生じ、特に炉心最外
周部では制御棒側に凸となる曲シが発生するので、制御
棒挿入通路の間隙が減少する可能性がある。When the difference in irradiation growth and elongation occurs in the longitudinal direction of each side of the fuel channel box, as shown in Figure 2, a curve is created in which the faster the fast neutron flux is larger, the more convex the control rod becomes. Since a convex bend occurs on the side, the gap in the control rod insertion passage may be reduced.
そこで、従来は炉心最周部に装荷される燃料については
、燃料チャンネルボックスの曲シという観点から炉心最
外周部の装荷期間、最外周燃料セル内の制御棒をはさん
で対峙する燃料の組合せ並びに燃料シャラフリング等を
考える際、燃料チャンネルボックスの曲シによる影響を
少なくする方法を採っていた。Therefore, conventionally, regarding the fuel loaded in the outermost part of the core, from the viewpoint of the curve of the fuel channel box, the loading period of the outermost part of the reactor core, the combination of fuels facing each other across the control rods in the outermost fuel cell, Also, when considering fuel shuffling, etc., a method was adopted to reduce the influence of the bending of the fuel channel box.
しかしながら、前記炉心最外周部燃料に関する考慮は燃
料シャラフリング計画を複雑にする要因となっていた。However, consideration regarding the fuel at the outermost periphery of the core has become a factor that complicates the fuel shoring plan.
本発明の目的は、沸騰水型原子炉用燃料集合体を構成す
る燃料チャンネルボックスにおいて、照射面シ変形が少
なく制御棒案内面形成機能上すぐれた特性を有する燃料
チャンネルボックスを提供することにある。An object of the present invention is to provide a fuel channel box constituting a fuel assembly for a boiling water reactor, which has less deformation of the irradiated surface and has excellent characteristics in terms of control rod guide surface formation function. .
高速中性子束の炉心径方向勾配が燃料チャンネルボック
スの照射面シ変形の原因のひとつであることは既に述べ
たが、本質的には燃料チャンネルボックスが長手方向に
照射成長伸びを生じることに起因している。It has already been mentioned that the gradient of fast neutron flux in the core radial direction is one of the causes of deformation of the irradiated surface of the fuel channel box, but essentially it is caused by the irradiation growth and elongation of the fuel channel box in the longitudinal direction. ing.
そこで、本発明は、長手方向の照射成長伸びが少ない特
性を有するジルコニウム合金製板材で構成された燃料チ
ャンネルボックスであれば、仮に高速中性子束の炉心径
方向勾配がある炉心位置に装荷されても照射による曲り
変形が発生しにくいということに着目したものである。Therefore, the present invention provides a fuel channel box made of a zirconium alloy plate material that has a characteristic of little irradiation growth and elongation in the longitudinal direction, even if it is loaded at a core position where there is a core radial gradient of fast neutron flux. The focus was on the fact that bending and deformation due to irradiation is less likely to occur.
以下本発明の一実施例について説明する。 An embodiment of the present invention will be described below.
燃料チャンネルボックスを構成しているジルコニウム合
金は特定の結晶方向が、板材の特定方向にかたよった配
列をなす所謂集合組織を形成しており、板材の方向によ
って機械的性質が異なるなどの異方性を有している。こ
のため、照射成長伸び特性も板材の各方向によって異な
っておシ、ジルコニウム合金製板材の板材各方向の照射
伸び特性の差異は前述の集合組織に依存している。The zirconium alloy that makes up the fuel channel box forms a so-called texture in which specific crystal orientations are arranged in a specific direction of the plate material, and is anisotropic, with mechanical properties differing depending on the direction of the plate material. have. For this reason, the irradiation growth and elongation characteristics differ depending on each direction of the sheet material, and the difference in the irradiation growth and elongation characteristics in each direction of the sheet material of a zirconium alloy sheet material depends on the above-mentioned texture.
そこで、本発明は燃料チャンネルボックスの長手方向の
照射伸びをジルコニウム合金製板材の集合組織の詞整に
よって低く抑え、照射量）変形を少なくすることをねら
った。Therefore, the present invention aims to suppress the irradiation elongation in the longitudinal direction of the fuel channel box by adjusting the texture of the zirconium alloy plate material, thereby reducing the deformation (irradiation dose).
以上、本実施例について、その効果を含め具体的に説明
する。・
ジルコニウム及びその合金の照射伸びは、照射温度（Ｔ
）集合組織、高速中性子照射量（φｔ）工
並びに冷間カーに依存する。すなわち次式で表せる。The present embodiment will be specifically described above, including its effects. - The irradiation elongation of zirconium and its alloys is determined by the irradiation temperature (T
) depends on texture, fast neutron dose (φt) and cold car. In other words, it can be expressed by the following equation.
す・−Ａ （Ｔ）・Ｂ（ｆ）・Ｃ（φｔ）・Ｄ（ｗ）
（１）ζこで、ａ ｇｒ’ ：ジルコニウムない
しその合金の照射成長歪
Ａ（Ｔ）：照射温度（Ｔ）の関数
Ｂ（ｆ）：ジルコニウムないしその合金の集合組織に依
存する関数
Ｃ（φｔ）：高速中性子照射量（φｔ）の関数Ｈ（Ｗ）
：冷間加工率（−）の関数
（５）
なお、燃料チャンネルボックスは再結晶化焼鈍を行うの
で式（１）中のＨ（Ｗ）は１となる。また、集合組織に
依存する関数Ｂ（ｆ）は、板材の任意方向においての金
属結晶面（０００２）のＸ線回折強度から算出されるｆ
値（Ｂａ５ａｌ ｐｏｌｅ ｔｅｘｔｕｒｅｆＢｃｔｏ
ｒ）で表され、近似的に次式となる。S・-A (T)・B(f)・C(φt)・D(w)
(1) ζwhere, a gr': Irradiation growth strain A(T) of zirconium or its alloy: Function B(f) of irradiation temperature (T): Function C(φt) that depends on the texture of zirconium or its alloy. ): Function H(W) of fast neutron irradiation amount (φt)
:Function of cold working rate (-) (5) Note that since the fuel channel box undergoes recrystallization annealing, H(W) in equation (1) is 1. In addition, the function B(f) that depends on the texture is f calculated from the X-ray diffraction intensity of the metal crystal plane (0002) in an arbitrary direction of the plate material.
Value (Ba5al pole texturefBcto
r), which is approximated by the following equation.
Ｂ （ｆ ） ＝ １−３ ｆ Ｉ（２）ここで、ｆ！
：板材の任意方向ｉ（圧延方向、圧延直角方向、肉厚
方向）のｆ値
したがって式（１） 、 （２）よシ
ｇ、 、 ｏｃ １−３ ｆ、 （
３）式（３）よシ、燃料チャンネルボックスの長手方向
（圧延方向）のｆ値がｆｔ中０．３３３であればε５．
＝０となシ、長手方向に照射成長伸びを生じないことに
なる。すなわち、このようなジルコニウム合金製板材で
燃料チャンネルボックスを構成すれば、照射面シ変形を
生じにくい燃料チャンネルボックスが得られることにな
る。B (f) = 1-3 f I (2) where f!
: f value in any direction i (rolling direction, rolling direction, wall thickness direction) of the plate material. Therefore, formulas (1), (2), , oc 1-3 f, (
3) According to equation (3), if the f value in the longitudinal direction (rolling direction) of the fuel channel box is 0.333 in ft, then ε5.
= 0, no irradiation growth elongation occurs in the longitudinal direction. That is, if a fuel channel box is constructed from such a zirconium alloy plate material, a fuel channel box that is less likely to cause deformation of the irradiated surface can be obtained.
したがって、燃料チャンネルボックス長手方向（６）
のｆ値が０．１５〜０．５の範囲でめれば照射成長伸び
の抑制に有効であるが、好ましくは０．３３３に近い０
．２５〜０．４０の範囲が最も効果があシ、この場合的
シ変形は十分小さく抑えられ、第３図に示すように解析
上は従来の曲り変形の半分以下となる。Therefore, if the f value in the longitudinal direction (6) of the fuel channel box is within the range of 0.15 to 0.5, it is effective in suppressing irradiation growth and elongation, but it is preferable to have an f value close to 0.333.
．． The range of 25 to 0.40 is most effective; in this case, the occasional bending deformation can be kept sufficiently small, and as shown in FIG. 3, it is analytically less than half of the conventional bending deformation.
本発明によって照射面シ変形が従来と比べ半分以下の燃
料チャンネルボックスが得られるので、従来、炉心最外
周部燃料に適用していた考慮事項の撤廃かいし緩和が可
能となシ、燃料シャラフリンク計画の自由度が増す。The present invention makes it possible to obtain a fuel channel box with less than half the deformation of the irradiated surface compared to the conventional one, making it possible to eliminate or alleviate the considerations that were conventionally applied to the fuel at the outermost periphery of the core. Increased flexibility in planning.
第１図は沸騰水型原子炉用燃料集合体の構造図、第２図
は燃料チャンネルボックスの照射向シ概念図、第３図は
本発明の効果を示す線図である。
１・・・燃料集合体、２・・・核燃料要素、３・・・支
持格子、４・・・上記タイプレート、５・・・下部タイ
プレート、６・・・燃料チャンネルボックス。
代理人 弁理士 高橋明夫
＄ １ ｍFIG. 1 is a structural diagram of a fuel assembly for a boiling water reactor, FIG. 2 is a conceptual diagram of the irradiation direction of a fuel channel box, and FIG. 3 is a diagram showing the effects of the present invention. DESCRIPTION OF SYMBOLS 1... Fuel assembly, 2... Nuclear fuel element, 3... Support grid, 4... Above tie plate, 5... Lower tie plate, 6... Fuel channel box. Agent Patent Attorney Akio Takahashi $1m
Claims (1)
ンネルボックスにおいて、結晶面（０００２）のＸ線回
折強度から算出される板材長手方向のｆ値すなわちｆ、
が０．１５〜０．５の範囲を有する板材で構成すること
を特徴とする燃料チャンネルボックス。1. In a fuel channel box made of a plate made of zirconium alloy, the f value in the longitudinal direction of the plate calculated from the X-ray diffraction intensity of the crystal plane (0002), that is, f,
A fuel channel box characterized in that it is constructed of a plate material having a range of 0.15 to 0.5.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58102649A JPS59229475A (en) | 1983-06-10 | 1983-06-10 | Fuel channel box |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58102649A JPS59229475A (en) | 1983-06-10 | 1983-06-10 | Fuel channel box |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS59229475A true JPS59229475A (en) | 1984-12-22 |
Family
ID=14333087
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP58102649A Pending JPS59229475A (en) | 1983-06-10 | 1983-06-10 | Fuel channel box |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS59229475A (en) |
Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS61179859A (en) * | 1985-01-08 | 1986-08-12 | Sumitomo Metal Ind Ltd | Manufacture of nuclear fuel cladding tube made of zr base alloy |
| JPH0517837A (en) * | 1990-11-28 | 1993-01-26 | Hitachi Ltd | Zirconium-base alloy plate reduced in irradiation growth, its production, and its use |
| US5297177A (en) * | 1991-09-20 | 1994-03-22 | Hitachi, Ltd. | Fuel assembly, components thereof and method of manufacture |
| EP0795618A1 (en) * | 1996-03-13 | 1997-09-17 | Hitachi, Ltd. | Zirconium based alloy of low irradiation growth, method of producing the same, and use of the same |
| WO1998010427A1 (en) * | 1996-09-04 | 1998-03-12 | Siemens Aktiengesellschaft | Guide tube for pressurized water reactor fuel element and corresponding production process |
| US6704386B2 (en) | 2000-01-21 | 2004-03-09 | Hitachi, Ltd. | Fuel channel box and a method of manufacturing the same |
-
1983
- 1983-06-10 JP JP58102649A patent/JPS59229475A/en active Pending
Cited By (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS61179859A (en) * | 1985-01-08 | 1986-08-12 | Sumitomo Metal Ind Ltd | Manufacture of nuclear fuel cladding tube made of zr base alloy |
| JPH0517837A (en) * | 1990-11-28 | 1993-01-26 | Hitachi Ltd | Zirconium-base alloy plate reduced in irradiation growth, its production, and its use |
| US5223211A (en) * | 1990-11-28 | 1993-06-29 | Hitachi, Ltd. | Zirconium based alloy plate of low irradiation growth, method of manufacturing the same, and use of the same |
| EP0689209A1 (en) | 1990-11-28 | 1995-12-27 | Hitachi, Ltd. | Method of operating a nuclear reactor containing a plurality of nuclear fuel channel boxes and manufacturing said boxes |
| EP0488027B2 (en) † | 1990-11-28 | 2008-12-31 | Hitachi Ltd. | Method of manufacturing a zirconium based alloy fuel channel box |
| US5297177A (en) * | 1991-09-20 | 1994-03-22 | Hitachi, Ltd. | Fuel assembly, components thereof and method of manufacture |
| EP0795618A1 (en) * | 1996-03-13 | 1997-09-17 | Hitachi, Ltd. | Zirconium based alloy of low irradiation growth, method of producing the same, and use of the same |
| US5862194A (en) * | 1996-03-13 | 1999-01-19 | Hitachi, Ltd. | Zirconium based alloy of low irradiation growth, method of producing the same, and use of the same |
| WO1998010427A1 (en) * | 1996-09-04 | 1998-03-12 | Siemens Aktiengesellschaft | Guide tube for pressurized water reactor fuel element and corresponding production process |
| US6704386B2 (en) | 2000-01-21 | 2004-03-09 | Hitachi, Ltd. | Fuel channel box and a method of manufacturing the same |
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