JPS62165181A - Grid spacer for nuclear fuel aggregate - Google Patents

Grid spacer for nuclear fuel aggregate

Info

Publication number
JPS62165181A
JPS62165181A JP61006213A JP621386A JPS62165181A JP S62165181 A JPS62165181 A JP S62165181A JP 61006213 A JP61006213 A JP 61006213A JP 621386 A JP621386 A JP 621386A JP S62165181 A JPS62165181 A JP S62165181A
Authority
JP
Japan
Prior art keywords
spacer
fuel
nuclear fuel
grid spacer
grid
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
JP61006213A
Other languages
Japanese (ja)
Inventor
彰 桑子
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
Toshiba Corp
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 Toshiba Corp filed Critical Toshiba Corp
Priority to JP61006213A priority Critical patent/JPS62165181A/en
Publication of JPS62165181A publication Critical patent/JPS62165181A/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

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  • Prostheses (AREA)

Abstract

(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。
(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.

Description

【発明の詳細な説明】 [発明の技術分野1 本発明は、核燃料集合体のグリッドスペーサに係り、特
に軽水炉に用いられる核燃料集合体のグリッドスペーサ
に関する。
DETAILED DESCRIPTION OF THE INVENTION [Technical Field of the Invention 1] The present invention relates to a grid spacer for a nuclear fuel assembly, and particularly to a grid spacer for a nuclear fuel assembly used in a light water reactor.

[発明の技術的背景とその問題点] 現在たとえば、軽水炉で使用されている核燃料集合体お
よび使用が検討されている核燃料集合体は、チャンネル
ボックスに多数燃料ビンを収容し、これらの燃料ピンを
グリッドスペーサで保持した構造とされている。
[Technical background of the invention and its problems] For example, nuclear fuel assemblies currently used in light water reactors and nuclear fuel assemblies whose use is being considered house a large number of fuel bins in a channel box and connect these fuel pins. The structure is held in place by grid spacers.

第6図に示すように、このグリッドスペーサ1は、燃料
ピン2を収容する中空六角柱形状のスペーサ素子1Aを
多数組み付けてハニカム形状のスペーサ素子組立体を構
成し、このスペーサ素子組立体の周囲を薄板からなる中
空六角柱形状のスペーサ枠1Bにて補強したものである
。そして、このスペーサ枠1Bがチャンネルボックス3
の内壁に固定される。
As shown in FIG. 6, this grid spacer 1 constitutes a honeycomb-shaped spacer element assembly by assembling a large number of hollow hexagonal columnar spacer elements 1A that accommodate fuel pins 2. is reinforced with a hollow hexagonal columnar spacer frame 1B made of a thin plate. And this spacer frame 1B is the channel box 3
fixed to the inner wall of the

以上のごとき従来の核燃料集合体のグリッドスペーサに
あっては、第7図にも示すごとく燃料ピン2の支持間隔
を保つため、スペーサ素子1Aの内側に3個の凸部IC
が設けられ、これによって燃料ピンの外周を支持するよ
うにしている。
In the grid spacer of the conventional nuclear fuel assembly as described above, in order to maintain the supporting interval of the fuel pins 2, three convex portions IC are provided inside the spacer element 1A, as shown in FIG.
is provided to support the outer periphery of the fuel pin.

ところで、軽水炉においては燃料棒表面の熱流束が大き
く、燃料棒表面では核沸騰から膜沸1農への遷移が生じ
やすく、特に、スペーサ部のような冷却材流路の狭い領
域でその傾向が大きい。この沸Il!遷移が生じると燃
料温度は急上昇し、燃料の破損が生じるおそれがある。
By the way, in light water reactors, the heat flux on the surface of the fuel rods is large, and a transition from nucleate boiling to film boiling tends to occur on the surface of the fuel rods, especially in narrow areas of the coolant flow path such as the spacer section. big. This boiling point! If a transition occurs, the fuel temperature will rise rapidly and fuel failure may occur.

[発明の目的] 本発明は、上述のごとき従来の問題点を解決すべく成さ
れたものであり、その目的とするところは燃料温度が高
温時には冷却材流路を広げて圧損を低減し、かつ通常運
転中の低温時には燃料ピン間の間隔を確実に保持しさら
に燃料ピンが振動しないようにした核燃料集合体のグリ
ッドスペーサを提供するにある。
[Object of the Invention] The present invention has been made to solve the conventional problems as described above, and its purpose is to widen the coolant flow path when the fuel temperature is high to reduce pressure loss, Another object of the present invention is to provide a grid spacer for a nuclear fuel assembly that reliably maintains the spacing between fuel pins and prevents the fuel pins from vibrating during low temperatures during normal operation.

[発明の概要] しかる目的を達成すべく本発明は核燃料集合体を構成す
るグリッドスペーサのスペーサ素子の少なくとも一部に
運転中の低温時すなわち通常運転時には燃料ピンを押圧
し、高温時すなわち沸m遷移が生じた場合には冷却材流
路を広げ圧損を低減する形状となる記憶合金を設けたこ
とをその特徴としている。
[Summary of the Invention] In order to achieve the above object, the present invention presses a fuel pin against at least a part of the spacer elements of a grid spacer constituting a nuclear fuel assembly when the temperature is low during operation, that is, during normal operation, and when the temperature is high, that is, during boiling. It is characterized by the provision of a memory alloy that assumes a shape that widens the coolant flow path and reduces pressure loss when a transition occurs.

[発明の実施例] 以下に本発明の実施例を添付図面に基づいて詳細に説明
する。
[Embodiments of the Invention] Examples of the present invention will be described in detail below with reference to the accompanying drawings.

一般に原子炉内においてはM2図に示すごとく核燃料集
合体が支持部材に挿着された状態で支持されている。
Generally, in a nuclear reactor, a nuclear fuel assembly is supported by being inserted into a support member as shown in Fig. M2.

核燃料集合体4は、チャンネルボックス3とこのチャン
ネルボックス3の上下にそれぞれ設けられたタイブレー
ト5.6、エントランスノズル7とグリッドスペーサ1
を介してチャンネルボックス3内に収容された燃料ピン
2とから成る。グリッドスペーサ1は核燃料集合体4の
長手方向に適宜間隔で複数個チャンネルボックス3の内
壁に固定される。
The nuclear fuel assembly 4 includes a channel box 3, tie plates 5.6 provided above and below the channel box 3, an entrance nozzle 7, and a grid spacer 1.
The fuel pin 2 is housed in the channel box 3 via the fuel pin 2. A plurality of grid spacers 1 are fixed to the inner wall of the channel box 3 at appropriate intervals in the longitudinal direction of the nuclear fuel assembly 4.

また、この核燃料集合体は炉心支持板10により支持さ
れている。
Further, this nuclear fuel assembly is supported by a core support plate 10.

第1図(a)および(b)は本発明にかかるグリッドス
ペーサの第1実施例を示すものであり、スペーサ素子2
0は記憶合金からなり、通常運転中の低温時には第1図
(a)に示すごとく、スペーサ素子20の各側面が外側
および内側に交互に突出している。
FIGS. 1(a) and 1(b) show a first embodiment of the grid spacer according to the present invention, in which the spacer element 2
0 is made of a memory alloy, and at low temperatures during normal operation, each side surface of the spacer element 20 alternately protrudes outward and inward as shown in FIG. 1(a).

一方、高温時、すなわちスペーサ近傍で沸騰遷移が生じ
た場合には第1図(b)に示すごとく、スペーサ素子2
0の各側面に突出していた部分がまっずぐになり、スペ
ーサ素子20は中空六角柱形状となり、燃料ピン2との
間に隙間が生じるように設定されている。ずなわちスペ
ーサ素子20はある温度に達すると記憶していた形状と
なるようにされている。
On the other hand, at high temperatures, that is, when a boiling transition occurs near the spacer, the spacer element 2
The portions that were protruding from each side of the spacer element 20 become straight, and the spacer element 20 has a hollow hexagonal column shape, and is set so that a gap is created between it and the fuel pin 2. That is, the spacer element 20 assumes its memorized shape when it reaches a certain temperature.

また第3図は本発明の第2実施例を示すものであり、ス
ペーサ素子21の一部が記憶合金からなる舌状片22(
押え片)で形成されている。この舌状片22は低温時に
は、第3図(a)、(b)に示すように各舌状片22が
内側に膨出し、燃料ピン2を三方から押圧固定するよう
に設定されている。また、高温時には第3図(C)、(
d)に示すように、舌状片22はスペーサ素子21の側
面と同一面となるように設定されている。
Further, FIG. 3 shows a second embodiment of the present invention, in which a part of the spacer element 21 is a tongue-like piece 22 (
It is formed by a presser piece). The tongue-like pieces 22 are set so that when the temperature is low, each tongue-like piece 22 bulges inward as shown in FIGS. 3(a) and 3(b), and the fuel pin 2 is pressed and fixed from three sides. Also, at high temperatures, Fig. 3 (C), (
As shown in d), the tongue-shaped piece 22 is set to be flush with the side surface of the spacer element 21.

第4図は本発明の第3実施例を示し、スペーサ素子23
の一部をなり記憶合金からなる舌状片24く押え片)は
前記第2実施例と異なり縦方向に設けられており、この
実施例にあっても前記同様に、低温時には第4図(a>
、(b)、(C)に示すごとく、各舌状片24は内側に
膨出し、燃料ピン2を押圧して固定する。一方高温時に
は第4図(d)、(lに示すごとく、舌状片24はスペ
ーサ素子23の側面と同一面となるように設定されてい
る。
FIG. 4 shows a third embodiment of the invention, in which the spacer element 23
Unlike the second embodiment, the tongue-shaped piece 24 (holding piece) made of a memory alloy is provided in the vertical direction, and in this embodiment as well, as in the case of the above-mentioned case, at low temperatures, the a>
, (b) and (C), each tongue-like piece 24 bulges inward and presses the fuel pin 2 to fix it. On the other hand, at high temperatures, the tongue-shaped piece 24 is set to be flush with the side surface of the spacer element 23, as shown in FIGS. 4(d) and 4(l).

第5図は本発明の第4実施例を示すものであり、中空六
角柱形状をなすスペーサ素子25の側面のうち1つおき
の各側面に両端を接続した記憶合金からなる凸状片26
(押え片)を設けている。この凸状片26も前記同様原
子炉運転中の低温時には、第5図(a)、(b)に示す
ごとく、内側に突出し、燃料ピン2を三方から押圧し固
定する。
FIG. 5 shows a fourth embodiment of the present invention, in which a convex piece 26 made of a memory alloy is connected at both ends to every other side surface of a spacer element 25 having a hollow hexagonal column shape.
(holding piece) is provided. Similarly to the above, when the reactor is operating at low temperatures, this convex piece 26 also protrudes inward, as shown in FIGS. 5(a) and 5(b), and presses and fixes the fuel pin 2 from three sides.

また高温時には第5図(C)、(d)に示すように、各
凸状片26は突出部が後退して平坦になり、燃料ピン2
との間には一定隙間が形成されて、流路面積が大きくと
れるようになっている。
Furthermore, at high temperatures, as shown in FIGS. 5(C) and 5(d), the protrusions of each convex piece 26 recede and become flat, causing the fuel pin 2
A certain gap is formed between the two and the flow path area can be increased.

[発明の効果] 以上の説明で明らかなごとく本発明は、燃料ピンを保持
するグリッドスペーサのスペーサ素子の少なくとも一部
に、高温時には燃料ピンとの間に隙間を形成し、低温時
には燃料ピンを押圧する形状となる記憶合金を設けたの
で、運転中の低温時には、燃料ピン同士の隙間を確実に
保ち、燃料ピンの振動を防止して、振動により生じる被
覆管の損(具等から燃料ピンを保護することができる一
方、沸111i!遷移発生時の高温時には冷却材を流れ
やすくしてこの沸llff1遷移を解消して、燃料温度
を低下させることができ、従って、原子炉の安全性を向
上せしめ得る等の効果を有する。
[Effects of the Invention] As is clear from the above description, the present invention forms a gap between at least a part of the spacer element of the grid spacer that holds the fuel pin when the temperature is high, and presses the fuel pin when the temperature is low. Since we have provided a memory alloy with a shape that allows the fuel pins to maintain a certain gap during low temperatures during operation, it prevents vibration of the fuel pins and prevents damage to the cladding tube caused by vibration (fuel pins may be removed from fittings, etc.). On the other hand, at high temperatures when the boiling 111i! transition occurs, it is possible to make the coolant flow more easily to eliminate the boiling llff1 transition and lower the fuel temperature, thus improving the safety of the reactor. It has the effect of encouraging

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

第1図(a)は本発明の第1実施例のグリッドスペーサ
の低温時の平面図、第1図(b)は同実施例の高温時の
平面図、第2図は核燃料集合体とその周辺の一部を示す
部分断面図、第3図(a)は本発明の第2実施例の低温
時の平面図、第3図(b)は同側面図、第3図(C)は
同実施例の高温時の平面図、第3図(d)は同高温時の
側面図、第4図(a)は本発明の第3実施例の低温時の
平面図、第4図(b)は同低温時の側面図、第4図(C
)は第4図(b)の8−8線における断面図、第4図(
d)は同実施例の高温時の平面図、第4図(e)は同高
温時の側面図、第5図(a>は本発明の第4実施例の低
温時の平面図、第5図(b)は第5図(a)のC−C線
における断面図、第5図(C)は同実施例の高温時の平
面図、第5図(d)は第5図(C)のD−[)線におけ
る断面図、第6図<a)は従来のグリッドスペーサの平
面図、第6図(b)は同グリッドスペーサのIII!1
面図、第7図(a)は同グリッドスペーサの一部拡大平
面図、第7図(b)は第7図(a)のA−A線における
断面図である。 1・・・・・・・・・グリッドスペーサ2・・・・・・
・・・燃料ピン 3・・・・・・・・・チャンネルボックス4・・・・・
・・・・核燃料集合体 10・・・・・・・・・炉心支持体 1A、20,21.23.25 ・・・・・・・・・スペーサ素子 22.24.26・・・・・・記憶合金からなる押え片
代理人 弁理士  則 近 憲 缶 周        三  俣  弘  文第1 口 ((3+            (C)(e) (cll             (C)(j))(
d)。 +6)
FIG. 1(a) is a plan view of a grid spacer according to a first embodiment of the present invention at a low temperature, FIG. 1(b) is a plan view of the same embodiment at a high temperature, and FIG. 2 shows a nuclear fuel assembly and its 3(a) is a plan view of the second embodiment of the present invention at low temperature, FIG. 3(b) is a side view of the same, and FIG. 3(C) is a partial sectional view showing a part of the surrounding area. FIG. 3(d) is a plan view of the embodiment at high temperature; FIG. 4(a) is a plan view of the third embodiment of the present invention at low temperature; FIG. 4(b) is a side view of the embodiment at high temperature. is a side view at the same low temperature, Figure 4 (C
) is a cross-sectional view taken along line 8-8 in Fig. 4(b), and Fig. 4(
d) is a plan view of the same embodiment at high temperature, FIG. 4(e) is a side view at high temperature, and FIG. Figure 5(b) is a sectional view taken along line C-C in Figure 5(a), Figure 5(C) is a plan view of the same example at high temperature, and Figure 5(d) is Figure 5(C). FIG. 6<a) is a plan view of the conventional grid spacer, and FIG. 6(b) is the III! 1
FIG. 7(a) is a partially enlarged plan view of the grid spacer, and FIG. 7(b) is a sectional view taken along line A--A in FIG. 7(a). 1...Grid spacer 2...
...Fuel pin 3...Channel box 4...
......Nuclear fuel assembly 10...Core support 1A, 20, 21.23.25......Spacer element 22.24.26...・Representative for holding piece made of memory alloy Patent attorney Nori Chika Hirofumi Mitsumata 1st mouth ((3+ (C) (e) (cll (C) (j)) (
d). +6)

Claims (1)

【特許請求の範囲】[Claims] (1)チャンネルボックス内の複数本の燃料ピンをそれ
ぞれ把持する複数のスペーサ素子から成るグリッドスペ
ーサにおいて、前記各スペーサ素子が、原子炉通常運転
時の温度以下の温度では燃料ピンを押圧し、高温時には
冷却材流路を広げて圧損を低減する形状に成形された記
憶合金で少なくともその一部が構成されて成ることを特
徴とする核燃料集合体のグリッドスペーサ。
(1) In a grid spacer consisting of a plurality of spacer elements each gripping a plurality of fuel pins in a channel box, each spacer element presses the fuel pin at a temperature below the normal operating temperature of the reactor, and A grid spacer for a nuclear fuel assembly, characterized in that the grid spacer is at least partially composed of a memory alloy formed into a shape that sometimes widens the coolant flow path and reduces pressure loss.
JP61006213A 1986-01-17 1986-01-17 Grid spacer for nuclear fuel aggregate Pending JPS62165181A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP61006213A JPS62165181A (en) 1986-01-17 1986-01-17 Grid spacer for nuclear fuel aggregate

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP61006213A JPS62165181A (en) 1986-01-17 1986-01-17 Grid spacer for nuclear fuel aggregate

Publications (1)

Publication Number Publication Date
JPS62165181A true JPS62165181A (en) 1987-07-21

Family

ID=11632245

Family Applications (1)

Application Number Title Priority Date Filing Date
JP61006213A Pending JPS62165181A (en) 1986-01-17 1986-01-17 Grid spacer for nuclear fuel aggregate

Country Status (1)

Country Link
JP (1) JPS62165181A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH0471010A (en) * 1990-07-12 1992-03-05 Nec Corp Air-conditioner control system

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH0471010A (en) * 1990-07-12 1992-03-05 Nec Corp Air-conditioner control system

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