JP2525827B2 - Fuel assembly - Google Patents
Fuel assemblyInfo
- Publication number
- JP2525827B2 JP2525827B2 JP62221889A JP22188987A JP2525827B2 JP 2525827 B2 JP2525827 B2 JP 2525827B2 JP 62221889 A JP62221889 A JP 62221889A JP 22188987 A JP22188987 A JP 22188987A JP 2525827 B2 JP2525827 B2 JP 2525827B2
- Authority
- JP
- Japan
- Prior art keywords
- fuel assembly
- fuel
- coolant
- tube
- reactor
- 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
Links
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
- Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Description
【発明の詳細な説明】 ［発明の目的］ （産業上の利用分野） 本発明は燃料交換時の保守性を改良した原子炉用燃料
集合体に関する。DETAILED DESCRIPTION OF THE INVENTION [Object of the Invention] (Field of Industrial Application) The present invention relates to a fuel assembly for a nuclear reactor with improved maintainability during refueling.
（従来の技術） 原子炉の炉心は、複数本の燃料集合体を植設して構成
されており、燃料集合体はたとえば第３図に示すような
構成を有している。すなわち、第３図は炉心に設置され
た高速増殖炉用燃料集合体数本の縦断面図である。図に
おいて燃料集合体１は、保護管２内に、複数本の燃料棒
３と、燃料棒相互間および燃料棒３と保護管２の内面と
の間の間隔を保持する複数段のスペーサ４と、各燃料棒
３の上端および下端をそれぞれ支持する上部タイプレー
ト５および下部タイプレート６とを設置して構成され、
上記保護管２は、断面が例えば六角形の枠状に形成され
たラッパ管11と、ラッパ管内へ冷却材を導くためにこの
ラッパ管11の一端側に取り付けられたエントランスノズ
ル12と、ラッパ管11の他端側（上部）に取り付けられた
ハンドリングヘッド13とで構成されている。また保護管
２の外側面には、燃料集合体同士の間隔を一定に保つた
めと間隔部を流れる冷却材の流力振動を抑えるために、
スペーサパッド14が設置されている。(Prior Art) A core of a nuclear reactor is configured by implanting a plurality of fuel assemblies, and the fuel assembly has a configuration as shown in FIG. 3, for example. That is, FIG. 3 is a longitudinal sectional view of several fuel assemblies for a fast breeder reactor installed in the core. In the figure, a fuel assembly 1 includes a plurality of fuel rods 3 in a protection tube 2, and a plurality of stages of spacers 4 for maintaining a space between the fuel rods and between the fuel rods 3 and an inner surface of the protection tube 2. , An upper tie plate 5 and a lower tie plate 6 supporting the upper and lower ends of each fuel rod 3, respectively,
The protection tube 2 includes a trumpet tube 11 having a hexagonal frame shape in cross section, an entrance nozzle 12 attached to one end of the trumpet tube 11 for guiding a coolant into the trumpet tube, and a trumpet tube. It is composed of a handling head 13 attached to the other end side (upper part) of 11. Further, on the outer surface of the protective tube 2, in order to keep the distance between the fuel assemblies constant and to suppress the hydrodynamic vibration of the coolant flowing in the distance portion,
Spacer pads 14 are installed.
このように構成された燃料集合体において、冷却材は
ラッパ管11のエントランスノズル12より入り、保護管２
内を燃料棒３に平行して流れる。In the fuel assembly configured as described above, the coolant enters from the entrance nozzle 12 of the trumpet tube 11 and the protective tube 2
It flows in parallel with the fuel rods 3.
また、燃料集合体１に装荷された燃料棒３は、長さが
約3mあり、その内部構造は燃料集合体に装荷した位置に
おいて示すと第４図のようになっている。すなわち、第
４図は燃料集合体内における燃料棒の内部構造を示す概
略図であり、燃料棒３は下から軸方向下部ブランケット
15,炉心燃料16,軸方向上部ブランケット17およびガスプ
レナム18で構成されている。The fuel rod 3 loaded in the fuel assembly 1 has a length of about 3 m, and its internal structure is as shown in FIG. 4 when shown in the position loaded in the fuel assembly. That is, FIG. 4 is a schematic view showing the internal structure of the fuel rods in the fuel assembly, and the fuel rods 3 are from the bottom to the axial lower blanket.
It consists of 15, core fuel 16, axial upper blanket 17 and gas plenum 18.
燃料集合体は、一定期間炉心で使用されると、原子炉
停止時に燃料交換される。この燃料交換の際、燃料集合
体の崩壊熱が発生するので、これを除去するために一般
的には自然循環冷却機能が活用される。When the fuel assembly is used in the core for a certain period of time, it is refueled when the reactor is shut down. At the time of this refueling, decay heat of the fuel assembly is generated, and therefore the natural circulation cooling function is generally utilized to remove it.
すなわちこの方法は、第５図に示すように使用済燃料
集合体１を炉心部20から冷却材21中に引き上げ、冷却材
21を自然対流によりエントランスノズルの流入口から燃
料集合体内を保護管上部へと抜けさせることによって冷
却し、発生熱を除去するものである。That is, as shown in FIG. 5, this method pulls up the spent fuel assembly 1 from the core 20 into the coolant 21,
21 is cooled by removing natural heat from the inlet of the entrance nozzle through the fuel assembly to the upper part of the protective tube by natural convection.
（発明が解決しようとする問題点） しかしながら、上記のように構成された燃料集合体に
は、次のような問題点があった。(Problems to be Solved by the Invention) However, the fuel assembly configured as described above has the following problems.
すなわち、燃料棒が長尺であり、しかもこれが保護管
内に複数本密集して装荷されているので、流動抵抗が大
きくなり冷却材の自然環境流が充分に得られない。That is, since the fuel rods are long and a plurality of the fuel rods are densely loaded in the protective tube, the flow resistance increases and the natural environment flow of the coolant cannot be sufficiently obtained.
また、自然循環流路を得るには炉心から引き上げた燃
料集合体ハンドリングヘッド13より上部に冷却材液面22
がなければならないので、燃料集合体が長尺であると冷
却材液面はそれだけ高くする必要があり、そのために炉
容器が長尺化する。Further, in order to obtain the natural circulation flow path, the coolant level 22 is provided above the fuel assembly handling head 13 pulled up from the core.
Therefore, if the fuel assembly is long, the coolant level needs to be increased accordingly, which lengthens the reactor vessel.
本発明は、このような事情な鑑みてなされたもので、
その目的とするところは、使用済燃料集合体交換時に発
生する崩壊熱を除去するに際し、冷却材の自然循環流を
円滑にすることであり、さらに上記冷却材のための炉容
器が長尺化する点を改良することである。The present invention has been made in view of such circumstances,
Its purpose is to smooth the natural circulation flow of the coolant when removing the decay heat generated when the spent fuel assembly is replaced, and further to elongate the reactor vessel for the coolant. The point is to improve.
［発明の構成］ （問題点を解決するための手段） すなわち、本発明は保護管内に複数の燃料棒を収納し
てなる原子炉用燃料集合体において、燃料交換時に冷却
材が流出するための流出孔を前記保護管側面の上部位置
に設け、かつ炉稼働時には隣接する燃料集合体の保護管
の流出孔をすべて塞ぐことのできるパッドを前記各流出
孔の近くに設けたことを特徴とする原子炉用燃料集合体
に関する。[Configuration of the Invention] (Means for Solving the Problems) That is, the present invention provides a fuel assembly for a nuclear reactor in which a plurality of fuel rods are housed in a protective pipe, which is designed to prevent a coolant from flowing out during refueling. Outflow holes are provided in the upper position of the side surface of the protection pipe, and a pad that can close all the outflow holes of the protection pipe of the adjacent fuel assembly when the furnace is operating is provided near each of the outflow holes. The present invention relates to a fuel assembly for a nuclear reactor.
（作 用） 本発明の燃料集合体は、保護管側面に冷却材を流出さ
せるための流出孔を設けたので、燃料交換の際に発生す
る崩壊熱を除去するに当たって、冷却材の自然循環流を
円滑にすることができ、冷却効果を向上させることがで
きる。また、上記流出孔より冷却材を流出させるので冷
却材液面レベルを従来より下げることができ、それによ
って炉容器の長さを従来より短くすることができる。(Operation) Since the fuel assembly of the present invention is provided with the outflow hole for allowing the coolant to flow out on the side surface of the protective pipe, in removing the decay heat generated during the fuel exchange, the natural circulation flow of the coolant is used. Can be smoothed and the cooling effect can be improved. Further, since the coolant flows out through the outflow holes, the liquid level of the coolant can be lowered as compared with the conventional case, whereby the length of the furnace vessel can be shortened as compared with the conventional case.
なお、炉稼動時には、隣接する保護管のパッドがすべ
ての流出孔を塞ぎかつ燃料集合体相互の間隔を保持する
ので、本発明の燃料集合体は従来と同様に稼動時の冷却
材流れを維持し、流力振動を防止することができる。When the furnace is in operation, the pads of the adjacent protection tubes block all the outflow holes and maintain the intervals between the fuel assemblies, so that the fuel assembly of the present invention maintains the coolant flow during operation as in the conventional case. However, it is possible to prevent hydrodynamic vibration.
（実施例） 本発明の実施例を図面を参照して説明する。(Example) The Example of this invention is described with reference to drawings.
第１図（Ａ）は本発明の一実施例を説明する燃料集合
体の保護管外側面の斜視図であり、第１図（Ｂ）は隣接
する保護管同士が接触している状態を示す図である。図
中、２は保護管であり、30は保護管に穿った流出孔,31
は隣接する保護管の流出孔30を塞ぐことのできるパッド
である。流出孔30およびパッド31は、燃料集合体に収納
した燃料棒３の軸方向上部ブランケット17（第４図参
照）の高さ位置にあることが好ましい。第１図（Ｂ）に
示すように、原子炉稼動時には多数の保護管が隣接して
配置されているので、パッド31は隣接する保護管の流出
孔30を塞ぐことになる。またパッド31は燃料集合体同士
の間隔を一定に保持する機能を有する。したがってパッ
ド31は流出孔30の孔径を塞ぐに充分な大きさでなければ
ならず、また隣接の燃料集合体の保護管に接する厚さが
必要であり、さらに隣接パッドとぶつからない寸法でな
ければならない。FIG. 1 (A) is a perspective view of an outer surface of a protective tube of a fuel assembly for explaining an embodiment of the present invention, and FIG. 1 (B) shows a state where adjacent protective tubes are in contact with each other. It is a figure. In the figure, 2 is a protective tube, 30 is an outflow hole formed in the protective tube, 31
Is a pad capable of closing the outflow hole 30 of the adjacent protection tube. The outflow hole 30 and the pad 31 are preferably located at the height of the axially upper blanket 17 (see FIG. 4) of the fuel rod 3 housed in the fuel assembly. As shown in FIG. 1 (B), since a large number of protection tubes are arranged adjacent to each other when the reactor is in operation, the pad 31 closes the outflow hole 30 of the adjacent protection tube. Further, the pad 31 has a function of keeping the interval between the fuel assemblies constant. Therefore, the pad 31 must be large enough to close the hole diameter of the outflow hole 30, must have a thickness that contacts the protective tube of the adjacent fuel assembly, and must have a size that does not collide with the adjacent pad. I won't.
第２図は上記燃料集合体の燃料交換時の崩壊熱除去操
作の状態を示す図である。図面に示すように、燃料集合
体１は炉心部20から冷却材21中へ引き上げられると、冷
却材はエントランスノズル12の流入口から入って燃料棒
の間を通り、保護管２の流出孔30へ抜ける。したがって
冷却材液面は従来のレベル22（高さh1）から22′（高さ
h2）まで下げることができる。FIG. 2 is a diagram showing a state of decay heat removal operation at the time of refueling of the fuel assembly. As shown in the drawing, when the fuel assembly 1 is pulled up from the core portion 20 into the coolant 21, the coolant enters from the inlet of the entrance nozzle 12 and passes between the fuel rods, and the outflow hole 30 of the protection tube 2 is introduced. Exit to. Therefore, the coolant level changes from the conventional level 22 (height h 1 ) to 22 ′ (height
h 2 ) can be lowered.
原子炉稼動時は燃料集合体各側面にあるパッド31が隣
接する保護管の流出孔30を塞ぐので、稼動時の冷却材の
流れが不均一になることはなく、またパッド31が燃料集
合体同士を保持する機能を有するので、燃料集合体間の
流力振動を抑えることができる。When the reactor is in operation, the pads 31 on each side of the fuel assembly block the outflow holes 30 of the adjacent protection tubes, so that the flow of the coolant during operation does not become non-uniform, and the pad 31 is the fuel assembly. Since they have a function of holding each other, it is possible to suppress the hydrodynamic vibration between the fuel assemblies.
なお、流出孔の形状は上記に示したもの以外の型でも
よく、例えば楕円形状でも円形でもよい。The shape of the outflow hole may be a shape other than those shown above, and may be, for example, an elliptical shape or a circular shape.
［発明の効果］ 以上説明したように、本発明によれば、燃料交換時の
崩壊熱除去の際の冷却材の流れを改善して信頼性を向上
することができ、また炉容器の長さも短縮化できる。[Effects of the Invention] As described above, according to the present invention, it is possible to improve the flow rate of the coolant at the time of removing decay heat at the time of refueling and improve reliability, and also to increase the length of the furnace vessel. Can be shortened.
第１図（Ａ）は本発明の一実施例を説明する燃料集合体
の保護管外側面の一部斜視図、第１図（Ｂ）は本発明の
一実施例の保護管の炉心内装荷の様子を説明する一部斜
視図、第２図は本発明の燃料集合体の燃料交換時の崩壊
熱除去操作の状態を示す図、第３図は従来の高速増殖炉
用燃料集合体が炉心に設置されているときの縦断面図、
第４図は従来の燃料集合体における燃料棒の内部構造を
示す概略図、第５図は従来の使用済燃料集合体交換時の
崩壊熱除去操作の状態を示す図である。 １……燃料集合体,2……保護管 ３……燃料棒,20……炉心 21……冷却材,22……従来の冷却材液面 22′……本発明による冷却材液面 30……流出孔,31……パッドFIG. 1 (A) is a partial perspective view of the outer surface of a protective tube of a fuel assembly for explaining an embodiment of the present invention, and FIG. 1 (B) is a core internal load of the protective tube of the embodiment of the present invention. Fig. 2 is a partial perspective view for explaining the state of Fig. 2, Fig. 2 is a view showing a state of decay heat removal operation at the time of refueling the fuel assembly of the present invention, and Fig. 3 is a core of the conventional fuel assembly for a fast breeder reactor. Vertical section when installed in
FIG. 4 is a schematic diagram showing the internal structure of a fuel rod in a conventional fuel assembly, and FIG. 5 is a diagram showing a state of decay heat removal operation when replacing a conventional spent fuel assembly. 1 ... Fuel assembly, 2 ... Protection tube 3 ... Fuel rod, 20 ... Core 21 ... Coolant, 22 ... Conventional coolant level 22 '... Coolant level 30 according to the present invention ... … Outflow hole, 31 …… Pad
Claims (2)
子炉用燃料集合体において、燃料交換時に冷却材が流出
するための流出孔を前記保護管側面の上部位置に設け、
かつ炉稼働時には隣接する燃料集合体の保護管の流出孔
をすべて塞ぐことのできるパッドを前記各流出孔の近く
に設けたことを特徴とする原子炉用燃料集合体。1. A fuel assembly for a nuclear reactor comprising a plurality of fuel rods housed in a protection tube, wherein an outflow hole for a coolant to flow out during refueling is provided at an upper position of a side surface of the protection tube.
Further, a fuel assembly for a nuclear reactor, characterized in that a pad capable of closing all the outflow holes of the protection pipe of the adjacent fuel assembly during operation of the reactor is provided near each of the outflow holes.
ケット位置に相当する位置にある特許請求の範囲第１項
記載の原子炉用燃料集合体。2. The fuel assembly for a nuclear reactor according to claim 1, wherein the outflow holes and the pads are located at positions corresponding to the positions of the upper blankets of the fuel rods.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62221889A JP2525827B2 (en) | 1987-09-07 | 1987-09-07 | Fuel assembly |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62221889A JP2525827B2 (en) | 1987-09-07 | 1987-09-07 | Fuel assembly |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS6465490A JPS6465490A (en) | 1989-03-10 |
| JP2525827B2 true JP2525827B2 (en) | 1996-08-21 |
Family
ID=16773763
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP62221889A Expired - Lifetime JP2525827B2 (en) | 1987-09-07 | 1987-09-07 | Fuel assembly |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JP2525827B2 (en) |
Families Citing this family (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2010236642A (en) | 2009-03-31 | 2010-10-21 | Denso Corp | Connector |
| CN102280155A (en) * | 2011-06-24 | 2011-12-14 | 华北电力大学 | Non-passive water level control and residual heat removal device of spent fuel storage pool |
| JP6219752B2 (en) * | 2014-03-04 | 2017-10-25 | 日立Ｇｅニュークリア・エナジー株式会社 | Fast reactor core |
Family Cites Families (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS6055288A (en) * | 1983-09-07 | 1985-03-30 | 株式会社日立製作所 | Fast breeder reactor |
-
1987
- 1987-09-07 JP JP62221889A patent/JP2525827B2/en not_active Expired - Lifetime
Also Published As
| Publication number | Publication date |
|---|---|
| JPS6465490A (en) | 1989-03-10 |
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