JPS6322277B2 - - Google Patents
Info
- Publication number
- JPS6322277B2 JPS6322277B2 JP56059846A JP5984681A JPS6322277B2 JP S6322277 B2 JPS6322277 B2 JP S6322277B2 JP 56059846 A JP56059846 A JP 56059846A JP 5984681 A JP5984681 A JP 5984681A JP S6322277 B2 JPS6322277 B2 JP S6322277B2
- Authority
- JP
- Japan
- Prior art keywords
- tube
- nuclear fuel
- baffle
- fuel assembly
- rod
- 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
Links
- 239000003758 nuclear fuel Substances 0.000 claims description 19
- 239000000446 fuel Substances 0.000 claims description 16
- 230000002093 peripheral effect Effects 0.000 description 10
- 239000002826 coolant Substances 0.000 description 7
- 238000005253 cladding Methods 0.000 description 5
- 238000004519 manufacturing process Methods 0.000 description 5
- 238000000034 method Methods 0.000 description 5
- 239000012530 fluid Substances 0.000 description 4
- 238000003466 welding Methods 0.000 description 3
- 230000000712 assembly Effects 0.000 description 2
- 238000000429 assembly Methods 0.000 description 2
- 230000001629 suppression Effects 0.000 description 2
- 238000000576 coating method Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000005553 drilling Methods 0.000 description 1
- 238000003825 pressing Methods 0.000 description 1
Classifications
-
- Y—GENERAL 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
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Monitoring And Testing Of Nuclear Reactors (AREA)
Description
【発明の詳細な説明】
本発明は高速増殖炉用核燃料集合体に係り、特
に周辺部サブチヤンネルの流量抑制機構に関す
る。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a nuclear fuel assembly for a fast breeder reactor, and more particularly to a flow rate suppression mechanism for a peripheral subchannel.
第1図に従来の核燃料集合体の横断面図を示
す。高速増殖炉用核燃料集合体は、正三角形格子
状に配列された多数の燃料要素1をラツパ管2で
覆つたものでラツパ管2で囲まれた燃料要素の間
隙を冷却材が流れるようになつている。 FIG. 1 shows a cross-sectional view of a conventional nuclear fuel assembly. A nuclear fuel assembly for a fast breeder reactor consists of a large number of fuel elements 1 arranged in an equilateral triangular lattice and covered with wrapper tubes 2, so that coolant flows through the gaps between the fuel elements surrounded by the wrapper tubes 2. ing.
この冷却材の流路は燃料要素やラツパ管によつ
て囲まれる仮想的な流路であるサブチヤンネルと
呼ばれる概念で分割して考えることができ、核燃
料集合体の周辺部のサブチヤンネル3は内側のサ
ブチヤンネル4に比べて流路面積が広く冷却材が
流れ易いために、周辺部の方が内側に比べて過冷
却される傾向がある。そのため周辺部のサブチヤ
ンネル3を流れる冷却材の流量を抑制して、内側
のサブチヤンネル4に流れる流量を増し、除熱能
力を均一化することが要求されていた。 This coolant flow path can be divided into subchannels, which are virtual flow paths surrounded by fuel elements and wrapper tubes, and subchannel 3 at the periphery of the nuclear fuel assembly is inside. Since the flow path area is wider than that of the subchannel 4, and the coolant flows easily, the peripheral portion tends to be supercooled compared to the inside. Therefore, it has been required to suppress the flow rate of the coolant flowing through the peripheral subchannel 3 and increase the flow rate flowing through the inner subchannel 4, thereby making the heat removal ability uniform.
この問題を解決するため、従来は最外周燃料要
素に細径のワイヤを一重又は二重に巻いたりして
周辺部サブチヤンネルの流量を制限していた。し
かしこの抑制方法は燃料集合体の組立に係る工程
の増加や製品管理の複雑化が生じ、更には組立時
における放射線被曝量が増加するなどの欠点があ
つた。又他の方法として、第2図に示すように、
周辺部サブチヤンネルに邪魔棒5と呼ばれる棒を
差し込んで流量を制限する方法もあつたが、この
場合には挿入された棒の流力振動による燃料被覆
管の摩耗や損傷などが生ずるという欠点であつ
た。 In order to solve this problem, the flow rate of the peripheral subchannel has conventionally been restricted by wrapping a thin wire around the outermost fuel element in one or two layers. However, this method of suppression has disadvantages such as an increase in the number of steps involved in assembling the fuel assembly, complication of product management, and an increase in the amount of radiation exposure during assembly. As another method, as shown in Figure 2,
There was also a method of restricting the flow rate by inserting a rod called a baffle rod 5 into the peripheral subchannel, but this method had the disadvantage that the flow vibration of the inserted rod would cause wear and damage to the fuel cladding tube. It was hot.
本発明の目的は、除熱能力の均一化を図り燃料
被覆管の損傷を防止できると共に製造の容易な核
燃料集合体を提供することにある。 SUMMARY OF THE INVENTION An object of the present invention is to provide a nuclear fuel assembly that can uniformize heat removal capacity, prevent damage to fuel cladding tubes, and is easy to manufacture.
本発明の特徴は、邪魔棒は複数本の短尺棒を軸
方向に嵌合して構成され、分割された各々の短尺
棒をラツパ管に固定する手段を有することにあ
る。 A feature of the present invention is that the baffle rod is constructed by fitting a plurality of short rods in the axial direction, and has means for fixing each of the divided short rods to the wrapper tube.
本発明の好適な一実施例である核燃料集合体を
以下に第3図、第4図及び第5図により説明す
る。 A nuclear fuel assembly which is a preferred embodiment of the present invention will be explained below with reference to FIGS. 3, 4 and 5.
第2図に示す従来例では周辺部サブチヤンネル
に邪魔棒を挿入して邪魔棒を上下端部のみでラツ
パ管に溶接にて固定されていた。しかしながら、
本実施例では、横断面が三角形をしている複数の
短尺棒5Aを軸方向に嵌合させることによつて一
本の邪魔棒5を構成している。各短尺棒5Aは、
上端部に孔部13を下端部に突起部9を有してい
る。短尺棒5Aの一面に一つの突起6が設けられ
ており、この突起6はラツパ管2の側壁に設けら
れた穴7内に差し込まれる。穴7内に差し込まれ
た突起6は溶接8にてラツパ管2に固定される。
このため短尺棒5Aの流力振動が防止でき、短尺
棒5Aに隣接している燃料要素1の燃料被覆間の
摩耗及び損傷を防止できる。短尺棒5Aには突起
6を一つ設けているが、これは突起6を複数設け
た場合にはラツパ管2への穴明け加工精度の誤差
によつて突起6と穴7との寸法不整合の発生を防
止するためである。 In the conventional example shown in FIG. 2, a baffle rod is inserted into the peripheral subchannel, and the baffle rod is fixed to the lapper tube only at the upper and lower ends by welding. however,
In this embodiment, one baffle bar 5 is constructed by fitting a plurality of short bars 5A each having a triangular cross section in the axial direction. Each short rod 5A is
It has a hole 13 at the upper end and a protrusion 9 at the lower end. One protrusion 6 is provided on one surface of the short rod 5A, and this protrusion 6 is inserted into a hole 7 provided in the side wall of the wrapper tube 2. The protrusion 6 inserted into the hole 7 is fixed to the wrapper tube 2 by welding 8.
Therefore, fluid vibration of the short rod 5A can be prevented, and wear and damage between the fuel coatings of the fuel element 1 adjacent to the short rod 5A can be prevented. One protrusion 6 is provided on the short rod 5A, but this is because when multiple protrusions 6 are provided, there may be a dimensional mismatch between the protrusion 6 and the hole 7 due to errors in the accuracy of drilling into the tube 2. This is to prevent the occurrence of
また、短尺棒5Aの孔部13内に軸方向に隣接
して配置された他の短尺棒5Aの突起部9を嵌合
することによつて一本の邪魔棒5が構成される。
このように複数の短尺棒5Aを嵌合することによ
つて、この嵌合部にて軸方向における突起6間と
穴7間との寸法誤差を吸収することができて突起
6と穴7との嵌合が容易にできしかも各短尺棒5
Aのねじれを等の変形を防止することができる。
第2図の従来例のような一本の邪魔棒に複数の突
起を設けてこの突起をラツパ管に設けた穴にそれ
ぞれ嵌合させる場合には、予め突起間及び穴間の
各間隔を極めて高い精度で加工する必要があり、
製造的に困難である。本実施例の場合には、この
ような問題が生じない。第5図は、短尺棒5Aか
らなる邪魔棒5をラツパ管2の側壁に取付けた状
態を示している。 Moreover, one baffle rod 5 is constructed by fitting the protrusion 9 of another short rod 5A arranged adjacently in the axial direction into the hole 13 of the short rod 5A.
By fitting the plurality of short rods 5A in this way, it is possible to absorb the dimensional error between the protrusions 6 and the holes 7 in the axial direction at this fitting part. can be easily fitted, and each short rod 5
Deformation such as twisting of A can be prevented.
When a single baffle bar is provided with a plurality of protrusions as in the conventional example shown in Fig. 2, and these protrusions are fitted into holes provided in the wrapper tube, the spacing between the protrusions and the holes must be carefully adjusted in advance. It is necessary to process with high precision,
It is difficult to manufacture. In the case of this embodiment, such a problem does not occur. FIG. 5 shows a state in which a baffle bar 5 consisting of a short bar 5A is attached to the side wall of the tuppan tube 2.
本実施例は、邪魔棒5の流力振動の防止によつ
て燃料被覆管の損傷を防止することができ、周辺
部サブチヤンネルの流量抑制による核燃料集合体
内の冷却材流量の均一化を図ることができ、しか
も邪魔棒5のラツパ管2への取り付けが容易であ
り核燃料集合体の製造を容易にすることができ
る。 In this embodiment, damage to the fuel cladding tube can be prevented by preventing fluid vibration of the baffle rod 5, and the flow rate of coolant in the nuclear fuel assembly can be made uniform by suppressing the flow rate of the peripheral subchannel. Moreover, the baffle rod 5 can be easily attached to the wrapper tube 2, and the manufacturing of the nuclear fuel assembly can be facilitated.
本発明の他の実施例である核燃料集合体を第6
図及び第7図に基づいて説明する。本実施例の邪
魔棒5も、前述の実施例と同様に複数の短尺棒が
嵌合されて構成されている。これらの短尺棒には
突起6が設けられていない。本実施例において
は、邪魔棒5、すなわち各短尺棒が第7図に示す
ように押え板10によつてラツパ管2に固定され
ている。押え板10は、ビス11をラツパ管2に
設けられた穴7内に挿入することにより固定され
る。押え板10は、三角形状の山形に成形した突
起部12を有している。ラツパ間2の内面に並行
に配置された複数の各短尺棒は、突起部12の三
角形の穴に挿入されている。押え板10の突起部
12は、第8図に示すように曲げ板構造によつて
も作ることができる。 A sixth nuclear fuel assembly which is another embodiment of the present invention
This will be explained based on the diagram and FIG. 7. The baffle bar 5 of this embodiment is also constructed by fitting a plurality of short bars in the same way as in the previous embodiment. These short bars are not provided with protrusions 6. In this embodiment, the baffle rods 5, that is, each short rod, are fixed to the wrapper tube 2 by a holding plate 10, as shown in FIG. The holding plate 10 is fixed by inserting screws 11 into holes 7 provided in the wrapper tube 2. The holding plate 10 has a protrusion 12 formed into a triangular mountain shape. A plurality of short rods arranged in parallel on the inner surface of the gap 2 are inserted into triangular holes of the protrusion 12. The protrusion 12 of the presser plate 10 can also be made of a bent plate structure as shown in FIG.
押え板10にて邪魔棒を固定する場合、邪魔棒
を分割せず第2図の従来例のようにラツパ管の軸
方向の長さにほぼ等しくすると、細長く長尺な複
数の邪魔棒を並列に配置することが極めて困難で
ありこれらの邪魔棒を押え板にてラツパ管に固定
することが著しく難しい。しかしながら、本実施
例のように複数の短尺棒の嵌合により邪魔棒を構
成することによつて、押え板10による邪魔棒5
の固定が著しく容易になり核燃料集合体の製造が
容易になる。邪魔棒5の流力振動の防止によつて
燃料被覆管の損傷を防止することができ、周辺部
サブチヤンネルの流量抑制による核燃料集合体内
の冷却材流量の均一化を図ることができること
は、前述の実施例と同様である。 When fixing the baffle rods with the presser plate 10, if the baffle rods are not divided and made to be approximately equal in length to the axial direction of the tube as in the conventional example shown in Fig. 2, multiple long and thin baffle rods can be arranged in parallel. It is extremely difficult to arrange these baffle rods on the rack tube with a presser plate. However, by configuring the baffle bar by fitting a plurality of short bars as in this embodiment, the baffle bar 5 is
This makes it extremely easy to fix and manufacture nuclear fuel assemblies. As mentioned above, damage to the fuel cladding tube can be prevented by preventing fluid vibration of the baffle rods 5, and the flow rate of coolant in the nuclear fuel assembly can be made uniform by suppressing the flow rate of the peripheral subchannel. This is similar to the embodiment.
本発明によれば、邪魔棒の流力振動の防止によ
つて燃料被覆管の損傷を防止することができ、周
辺部サブチヤンネルの流量抑制による核燃料集合
体内の冷却材流量の均一化を図ることができ、し
かも邪魔棒のラツパ管への取り付けが容易であり
核燃料集合体の製造を容易にすることができる。 According to the present invention, it is possible to prevent damage to the fuel cladding tube by preventing fluid vibration of the baffle rod, and to equalize the flow rate of coolant in the nuclear fuel assembly by suppressing the flow rate of the peripheral subchannel. Furthermore, the baffle rods can be easily attached to the lapper tube, making it easier to manufacture nuclear fuel assemblies.
第1図は従来の核燃料集合体の横断面図、第2
図は邪魔棒を有する従来の核燃料集合体の要部拡
大横断面図、第3図は本発明の実施例を示す一部
破断面の要部斜視図、第4図は第3図に示す本発
明の実施例の組立状態の要部縦断面図、第5図は
本発明に係る実施例の要部拡大横断面図である。
第6図乃至第8図は本発明の他の実施例で第6図
はラツパ管を押え板の斜視図、第7図は邪魔棒の
組立状態を示す斜視図、第8図は押え板の他の実
施例を示す斜視図である。
1…燃料要素、2…ラツパ管、3…周辺部サブ
チヤンネル、5…邪魔棒、6…突起、7…穴、8
…溶接、10…押え板。
Figure 1 is a cross-sectional view of a conventional nuclear fuel assembly;
The figure is an enlarged cross-sectional view of the main part of a conventional nuclear fuel assembly having baffle rods, FIG. 3 is a partially broken perspective view of the main part showing an embodiment of the present invention, and FIG. FIG. 5 is a longitudinal sectional view of the main part of the embodiment of the invention in an assembled state, and FIG. 5 is an enlarged cross-sectional view of the main part of the embodiment of the invention.
Figures 6 to 8 are other embodiments of the present invention, in which Figure 6 is a perspective view of the holding plate holding the wrapper tube, Figure 7 is a perspective view showing the assembled state of the baffle bar, and Figure 8 is a perspective view of the holding plate. FIG. 7 is a perspective view showing another embodiment. DESCRIPTION OF SYMBOLS 1... Fuel element, 2... Rapper tube, 3... Peripheral subchannel, 5... Baffle bar, 6... Projection, 7... Hole, 8
...welding, 10...pressing plate.
Claims (1)
外側を取り囲むラツパ管と、最外周に配置された
前記燃料要素間に位置して前記ラツパ管の内壁に
取付けられている邪魔棒とを備えてなる核燃料集
合体において、前記邪魔棒は複数本の短尺棒を軸
方向に嵌合して構成され、分割された各々の前記
短尺棒を前記ラツパ管に固定する手段を有するこ
とを特徴とする核燃料集合体。 2 前記固定手段が前記短尺棒に設けられて前記
ラツパ管側壁の貫通孔に挿入されしかも前記ラツ
パ管に溶接された突起部である特許請求の範囲第
1項記載の核燃料集合体。 3 前記固定手段が前記ラツパ管に取付けられる
押さえ手段である特許請求の範囲第1項記載の核
燃料集合体。[Claims] 1. A plurality of fuel elements, a wrapper tube surrounding the outside of a bundle of these fuel elements, and a wrapper tube located between the fuel elements disposed at the outermost periphery and attached to the inner wall of the wrapper tube. A nuclear fuel assembly comprising a baffle rod, wherein the baffle rod is configured by fitting a plurality of short rods in the axial direction, and a means for fixing each of the divided short rods to the rapture tube. A nuclear fuel assembly comprising: 2. The nuclear fuel assembly according to claim 1, wherein the fixing means is a protrusion provided on the short rod, inserted into a through hole in the side wall of the wrapper tube, and welded to the wrapper tube. 3. The nuclear fuel assembly according to claim 1, wherein the fixing means is a holding means attached to the wrapper tube.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP56059846A JPS57175287A (en) | 1981-04-22 | 1981-04-22 | Nuclear fuel assembly |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP56059846A JPS57175287A (en) | 1981-04-22 | 1981-04-22 | Nuclear fuel assembly |
Publications (2)
Publication Number | Publication Date |
---|---|
JPS57175287A JPS57175287A (en) | 1982-10-28 |
JPS6322277B2 true JPS6322277B2 (en) | 1988-05-11 |
Family
ID=13124974
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP56059846A Granted JPS57175287A (en) | 1981-04-22 | 1981-04-22 | Nuclear fuel assembly |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPS57175287A (en) |
Families Citing this family (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP4630811B2 (en) * | 2005-12-27 | 2011-02-09 | 財団法人電力中央研究所 | Nuclear fuel assembly |
JP4559965B2 (en) * | 2005-12-27 | 2010-10-13 | 株式会社東芝 | Nuclear fuel assembly |
-
1981
- 1981-04-22 JP JP56059846A patent/JPS57175287A/en active Granted
Also Published As
Publication number | Publication date |
---|---|
JPS57175287A (en) | 1982-10-28 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
US4056441A (en) | Bracing device for a bundle of parallel pins in a nuclear reactor assembly | |
JP3605171B2 (en) | Reactor fuel assembly | |
US4252613A (en) | Nuclear fuel assembly guide tube with integral intermittent projections | |
US4235669A (en) | Nuclear reactor composite fuel assembly | |
JPS637353B2 (en) | ||
US3687805A (en) | Pressure tube reactor fuel bundle | |
US4557892A (en) | Nuclear fuel element | |
US3239426A (en) | Bow restraint means for rod cluster nuclear fuel assembly | |
US6385271B2 (en) | Nuclear fuel assembly | |
US3746617A (en) | Nuclear reactor fuel element spacer assembly | |
EP0545587A1 (en) | Fuel bundle and spacer utilizing tapered fuel rods | |
GB2163888A (en) | Fission gas plenum chamber for nuclear fuel element sub-assembly | |
JPS6322277B2 (en) | ||
US4134791A (en) | Plate-type fuel assembly for a nuclear reactor | |
US5859888A (en) | Part length fuel rod extension | |
US3719559A (en) | Fuel pin spacer structure | |
US4914679A (en) | Fuel assembly | |
US5164155A (en) | Fuel bundle with short and intermediate part length rods minimized for flow induced vibration risk and rod bow | |
US6151376A (en) | Nuclear fuel assembly | |
JPS6055289A (en) | Spacer grating inserting body | |
US5186890A (en) | Reactor core of fast breeder reactor, components of same, and regulating method of coolant distribution of same | |
JPS5837036Y2 (en) | nuclear fuel assembly | |
JPH0421835B2 (en) | ||
JP3190095B2 (en) | Fuel assembly | |
JP3029903B2 (en) | Fuel assembly |