JPS646423B2 - - Google Patents
Info
- Publication number
- JPS646423B2 JPS646423B2 JP59017914A JP1791484A JPS646423B2 JP S646423 B2 JPS646423 B2 JP S646423B2 JP 59017914 A JP59017914 A JP 59017914A JP 1791484 A JP1791484 A JP 1791484A JP S646423 B2 JPS646423 B2 JP S646423B2
- Authority
- JP
- Japan
- Prior art keywords
- fuel
- screen
- nozzle
- lower nozzle
- foreign matter
- 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
- 239000000446 fuel Substances 0.000 claims description 48
- 239000008188 pellet Substances 0.000 claims description 5
- 239000000498 cooling water Substances 0.000 description 13
- 238000005253 cladding Methods 0.000 description 8
- 230000037431 insertion Effects 0.000 description 3
- 238000003780 insertion Methods 0.000 description 3
- 239000002184 metal Substances 0.000 description 3
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 3
- 230000000712 assembly Effects 0.000 description 2
- 238000000429 assembly Methods 0.000 description 2
- 239000000428 dust Substances 0.000 description 2
- 230000002093 peripheral effect Effects 0.000 description 2
- 238000010248 power generation Methods 0.000 description 2
- 230000000630 rising effect Effects 0.000 description 2
- 229910001220 stainless steel Inorganic materials 0.000 description 2
- 229910001093 Zr alloy Inorganic materials 0.000 description 1
- 239000012141 concentrate Substances 0.000 description 1
- 238000001816 cooling Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 239000012857 radioactive material Substances 0.000 description 1
- 230000003014 reinforcing effect Effects 0.000 description 1
- 239000010935 stainless steel Substances 0.000 description 1
- 238000003466 welding 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)
- Inert Electrodes (AREA)
Description
【発明の詳細な説明】
〔産業上の利用分野〕
この発明は加圧水型軽水炉等の原子炉において
使用される燃料集合体に関する。DETAILED DESCRIPTION OF THE INVENTION [Field of Industrial Application] This invention relates to a fuel assembly used in a nuclear reactor such as a pressurized water type light water reactor.
従来、この種の燃料集合体としては、第１図な
いし第３図に示すものがある。これらの図におい
て、符号１，２は上下に対向配置された上部ノズ
ル、下部ノズルである。これら上部ノズル１と下
部ノズル２との間には、上端部と下端部とがそれ
ぞれ上部ノズル１と下部ノズル２とに支持された
複数の制御棒案内管３が設けられている。この制
御棒案内管３には、支持格子４が固定されてい
る。この支持格子４は、第３図に示すように、剛
性支持部５および弾性支持部６を多数組有するも
のであり、これら剛性支持部５および弾性支持部
６によつて多数の燃料棒７がその軸線を上下に向
けた状態で挟持固定されている。この燃料棒７
は、多数の燃料ペレツト８を収納するジルカロイ
製の被覆管９と、この被覆管９の上下の開口部を
それぞれ密封する端栓１０とからなるものであ
る。
Conventionally, fuel assemblies of this type include those shown in FIGS. 1 to 3. In these figures, reference numerals 1 and 2 indicate an upper nozzle and a lower nozzle that are vertically opposed to each other. A plurality of control rod guide tubes 3 are provided between the upper nozzle 1 and the lower nozzle 2, the upper end and the lower end of which are supported by the upper nozzle 1 and the lower nozzle 2, respectively. A support grid 4 is fixed to the control rod guide tube 3 . As shown in FIG. 3, this support grid 4 has many sets of rigid support parts 5 and elastic support parts 6, and a large number of fuel rods 7 are supported by these rigid support parts 5 and elastic support parts 6. It is clamped and fixed with its axis facing up and down. This fuel rod 7
The cladding tube 9 consists of a Zircaloy cladding tube 9 that accommodates a large number of fuel pellets 8, and end plugs 10 that seal the upper and lower openings of the cladding tube 9, respectively.
このように構成された燃料集合体Ａは、第４図
に示すように、原子炉容器１１内の炉心１２に垂
直状態で多数挿入され、上部炉心板１３および下
部炉心板１４に挟持固定される。そして、原子炉
容器１１の流入口１５から流入し、下部プレナム
部１６で反転して上向きに流れる冷却水を、それ
が下部ノズル２のノズル孔２ａを通つて燃料棒
７，７間を通過する際に加熱するものである。な
お、加熱された冷却水は流出口１７から熱交換器
（図示せず）へ送られ、発電に供される。 As shown in FIG. 4, a large number of fuel assemblies A configured in this manner are vertically inserted into the reactor core 12 in the reactor vessel 11, and are clamped and fixed between the upper core plate 13 and the lower core plate 14. . Cooling water flows in from the inlet 15 of the reactor vessel 11, turns around in the lower plenum part 16, and flows upward, passing through the nozzle hole 2a of the lower nozzle 2 and between the fuel rods 7. It is heated at the same time. Note that the heated cooling water is sent from the outlet 17 to a heat exchanger (not shown) and is used for power generation.
ところで、上記の燃料集合体Ａは、原子力発電
に用いられるものであるから、トラブルの発生を
極力防止し得るものであることが必要である。特
に、燃料棒７の被覆管９についてはそれが燃料ペ
レツト８を収納するものであることから、その点
が強く要望される。 Incidentally, since the fuel assembly A described above is used for nuclear power generation, it is necessary that it be able to prevent troubles as much as possible. In particular, since the cladding tube 9 of the fuel rod 7 accommodates the fuel pellets 8, this point is strongly desired.
ところが、上記従来の燃料集合体Ａにおいて
は、被覆管９の下端部が損傷するおそれがあるこ
とが判明した。すなわち、下部ノズル２のノズル
孔２ａから燃料集合体Ａ内に流入した冷却水は、
燃料棒７の下端部においては流れが激しく乱れて
いる。このため、冷却水中に何らかの原因によつ
て、ごみ、金属くず等の異物が混入すると、その
異物が被覆管９の下端部に激しく衝突し、この結
果被覆管９の下端部が損傷を受けるおそれがある
のである。 However, it has been found that in the conventional fuel assembly A described above, there is a risk that the lower end portion of the cladding tube 9 may be damaged. That is, the cooling water flowing into the fuel assembly A from the nozzle hole 2a of the lower nozzle 2 is
At the lower end of the fuel rod 7, the flow is severely turbulent. Therefore, if foreign matter such as dust or metal scraps gets mixed into the cooling water for some reason, the foreign matter will violently collide with the lower end of the cladding tube 9, and as a result, the lower end of the cladding tube 9 may be damaged. There is.
この発明は、上記事情に鑑みてなされたもの
で、冷却水中に異物が混入したとしても燃料棒の
下端部が損傷されるおそれのない燃料集合体を提
供することを目的とする。
The present invention has been made in view of the above circumstances, and an object of the present invention is to provide a fuel assembly in which the lower ends of the fuel rods are not damaged even if foreign matter gets mixed into the cooling water.
この発明は、上記の目的を達成するために、燃
料棒の下端部と下部ノズルの上面との中間部分に
スクリーンを配設したことを構成上の特徴とする
ものである。
In order to achieve the above object, the present invention is characterized in that a screen is disposed at an intermediate portion between the lower end of the fuel rod and the upper surface of the lower nozzle.
以下、この発明の一実施例について、第５図お
よび第６図を参照して説明する。なお、これらの
図において上記従来例と同様な部分には同一符号
を付してその説明を省略する。
An embodiment of the present invention will be described below with reference to FIGS. 5 and 6. In these figures, parts similar to those in the conventional example described above are denoted by the same reference numerals, and explanations thereof will be omitted.
第５図はこの発明に係る燃料集合体A′の上端
部を省略して示す正面図である。この図に示す燃
料集合体A′においては、燃料棒７の下端部と下
部ノズル２の上面との中間部分に、冷却水中の異
物を捕捉除去するスクリーン１８が水平な状態で
配設されている。このスクリーン１８は、ステン
レス製の金網１８ａ等により形成されたもので、
下部ノズル２の上面と略同形の四角形状をなすと
ともに、その所定位置には複数の挿入孔１８ｂ
が、その孔径と位置を制御棒案内管３や計装管１
９に合わせて穿設されており、また、その周縁部
と上記挿入孔１８ｂの縁部等は補強部材１８ｃに
よつて適宜に補強されている。そして、スクリー
ン１８は、上記複数の挿入孔１８ｂに制御棒案内
管３や計装管１９を挿通することにより燃料棒７
の下端部と下部ノズル２の上面との中間部分の所
定位置に位置せしめられ、溶接等の固定手段によ
り制御棒案内管３に固定されている。 FIG. 5 is a front view showing the fuel assembly A' according to the present invention, with the upper end portion omitted. In the fuel assembly A' shown in this figure, a screen 18 for capturing and removing foreign matter in the cooling water is horizontally disposed at an intermediate portion between the lower end of the fuel rod 7 and the upper surface of the lower nozzle 2. . This screen 18 is formed of a stainless steel wire mesh 18a or the like.
It has a rectangular shape that is approximately the same shape as the upper surface of the lower nozzle 2, and has a plurality of insertion holes 18b at predetermined positions.
However, the hole diameter and position are determined by the control rod guide tube 3 and instrumentation tube 1.
9, and its peripheral edge and the edge of the insertion hole 18b are appropriately reinforced by a reinforcing member 18c. The screen 18 allows the fuel rods to be inserted into the fuel rods by inserting the control rod guide tubes 3 and the instrumentation tubes 19 into the plurality of insertion holes 18b.
It is located at a predetermined position midway between the lower end of the lower nozzle 2 and the upper surface of the lower nozzle 2, and is fixed to the control rod guide tube 3 by fixing means such as welding.
なお、上記スクリーン１８の金網１８ａとして
は、例えば線材径が0.3〜1.0mmφ、網目が0.5〜
2.0mm□の32〜７メツシユのものを使用すること
ができる。また、スクリーン１８は、燃料棒７の
熱による伸長を考慮に入れた高さに設けられる必
要がある。 The wire mesh 18a of the screen 18 may have a wire diameter of 0.3 to 1.0 mmφ and a mesh size of 0.5 to 1.0 mm, for example.
A 2.0mm square 32 to 7 mesh can be used. Further, the screen 18 needs to be provided at a height that takes into consideration the expansion of the fuel rods 7 due to heat.
しかして、上記構成の燃料集合体A′において
は、燃料棒７の下端部と下部ノズル２の上面との
中間部分にスクリーン１８が配設されているか
ら、ごみ、金属くず等の異物を含んだ冷却水が下
部ノズル２のノズル孔２ａから流入してきたとし
ても、その異物はスクリーン１８によつて捕捉除
去される。加えて、スクリーン１８を燃料棒７の
下端部と下部ノズル２の上面との中間部分に設け
ているので、隣接する下部ノズル２，２間の僅か
な間隙を通つて燃料棒７下部に流れ込んでくる冷
却水中の異物も捕捉除去することができる。した
がつて、燃料棒７の被覆管９の下端部が異物によ
り損傷を受けるおそれはなく、燃料集合体A′の
健全性は向上する。 In the fuel assembly A' having the above configuration, the screen 18 is disposed at the intermediate portion between the lower end of the fuel rod 7 and the upper surface of the lower nozzle 2, so that foreign matter such as dust and metal chips is not contained. Even if the cooling water flows in from the nozzle hole 2a of the lower nozzle 2, the foreign matter is captured and removed by the screen 18. In addition, since the screen 18 is provided at the intermediate portion between the lower end of the fuel rod 7 and the upper surface of the lower nozzle 2, the fuel flows into the lower part of the fuel rod 7 through the slight gap between the adjacent lower nozzles 2. It is also possible to capture and remove foreign objects in the cooling water. Therefore, there is no risk that the lower end of the cladding tube 9 of the fuel rod 7 will be damaged by foreign matter, and the integrity of the fuel assembly A' is improved.
また、異物が燃料棒７の外面等の各所に付着す
ると、その異物は燃料ペレツト８からの放射能に
より汚染されて放射性物質となるが、上記燃料集
合体A′では、異物は、燃料ペレツト８から離れ
たスクリーン１８に集中的に付着するので、その
除去が容易である。 Further, when foreign matter adheres to various parts such as the outer surface of the fuel rods 7, the foreign matter becomes contaminated with radioactivity from the fuel pellets 8 and becomes radioactive material. Since it concentrates on the screen 18 that is far from the screen 18, it is easy to remove it.
さらに、冷却水は、下部ノズル２のノズル孔２
ａから乱流として流入してスクリーン１８を通過
するが、その際スクリーン１８が下部ノズル２の
上面から離間しているので、このスクリーン１８
により一層激しい乱流となる。したがつて、冷却
水と燃料棒７との間の熱交換効率が一段と高ま
る。 Furthermore, the cooling water is supplied to the nozzle hole 2 of the lower nozzle 2.
turbulent flow from a and passes through the screen 18, but since the screen 18 is separated from the upper surface of the lower nozzle 2, this screen 18
This results in even more intense turbulence. Therefore, the heat exchange efficiency between the cooling water and the fuel rods 7 is further increased.
一方、第７図はこの発明の他の実施例を示すも
ので、金網１８ａにより形成された所定高さの垂
直な立上り部２０ａを周縁部に有するスクリーン
２０を、燃料棒７の下端部と、下部ノズル２の上
面との中間部分に配設したものである。この場
合、下部ノズル２のノズル孔２ａを通つて流入し
てきた冷却水中の異物は、スクリーン２０の水平
部２０ｂによつて捕捉除去される。また、スクリ
ーン２０には立上り部２０ａが設けられているの
で、下部ノズル２と該下部ノズル２に隣り合う下
部ノズル２′との間のわずかな間隙（約１mm）を
通つて流入してくる冷却水中の異物が、スクリー
ン２０の周縁部の側傍を通つて燃料棒７の下端部
に流入するのを一層確実に防ぐことができる。 On the other hand, FIG. 7 shows another embodiment of the present invention, in which a screen 20 having a vertical rising part 20a of a predetermined height formed by a wire mesh 18a on the periphery is connected to the lower end of the fuel rod 7. It is disposed at an intermediate portion between the upper surface of the lower nozzle 2 and the upper surface of the lower nozzle 2. In this case, foreign matter in the cooling water that has flowed in through the nozzle hole 2a of the lower nozzle 2 is captured and removed by the horizontal portion 20b of the screen 20. In addition, since the screen 20 is provided with a rising portion 20a, the cooling that flows in through a small gap (about 1 mm) between the lower nozzle 2 and the lower nozzle 2' adjacent to the lower nozzle 2. Foreign matter in the water can be more reliably prevented from flowing into the lower end of the fuel rod 7 through the side of the peripheral edge of the screen 20.
また、上記において、スクリーン１８，２０
は、所定メツシユの金網１８ａを用いて形成した
が、下部ノズル２のノズル孔２ａを垂直に投影し
た位置とその周辺部分にのみこの金網１８ａを設
け、他の部分は金属板により形成してもよい。さ
らに、所定径の多数の透孔を全面に備えたステン
レス製の多孔板を用いてスクリーン１８，２０を
構成してもよいし、第８図に示すように、下部ノ
ズル２のノズル孔２ａを垂直に投影した位置とそ
の周辺部分にのみ透孔２１ａを設けた多孔板２１
を用いてもよい。またさらに、スクリーン１８，
２０は上下方向に複層に設けても構わない。加え
て、スクリーン１８，２０にミキシングベーンを
付けると、さらに冷却水の乱流の促進がなされる
ので熱交換効率が高まる。 In addition, in the above, the screens 18, 20
is formed using a wire mesh 18a of a predetermined mesh, but it is also possible to provide the wire mesh 18a only in the vertically projected position of the nozzle hole 2a of the lower nozzle 2 and the surrounding area, and to form the other parts with a metal plate. good. Furthermore, the screens 18 and 20 may be constructed using stainless steel perforated plates that are provided with a large number of through holes of a predetermined diameter on the entire surface, and as shown in FIG. A perforated plate 21 with through holes 21a provided only in the vertically projected position and its surrounding area.
may also be used. Furthermore, the screen 18,
20 may be provided in multiple layers in the vertical direction. In addition, adding mixing vanes to the screens 18, 20 further promotes turbulent flow of cooling water, thereby increasing heat exchange efficiency.
以上説明したように、この発明の燃料集合体に
あつては、燃料棒の下端部と下部ノズルの上面と
の中間部分にスクリーンを配設しているから、た
とえ冷却水中に異物が混入したとしても、この異
物は上記スクリーンにより確実に捕捉除去され
る。したがつて、燃料棒の下端部が損傷されるお
それは全くなくなり、燃料集合体の健全性が格段
と高まる。
As explained above, in the fuel assembly of the present invention, since the screen is disposed in the middle part between the lower end of the fuel rod and the upper surface of the lower nozzle, even if foreign matter gets into the cooling water, However, this foreign matter is reliably captured and removed by the screen. Therefore, there is no possibility that the lower ends of the fuel rods will be damaged, and the integrity of the fuel assembly is greatly improved.
第１図ないし第３図は従来の燃料集合体の一例
を示すもので、第１図は一部切り欠き正面図、第
２図は下端部の拡大正面図、第３図は第２図の
円部の拡大図である。また、第４図はこの種の燃
料集合体が用いられる原子炉容器の内部構造の一
例を示す縦断面図、第５図および第６図はこの発
明の一実施例を示すもので、第５図は下端部の拡
大正面図、第６図はスクリーンの一部分の平面図
である。さらに、第７図および第８図はそれぞれ
この発明の他の実施例を示し、第７図は下端部の
拡大正面図、第８図はスクリーンの一部分の平面
図である。
２……下部ノズル、７……燃料棒、８……燃料
ペレツト、１８……スクリーン、A′……燃料集
合体。
Figures 1 to 3 show an example of a conventional fuel assembly. Figure 1 is a partially cutaway front view, Figure 2 is an enlarged front view of the lower end, and Figure 3 is the same as Figure 2. It is an enlarged view of a circular part. Further, FIG. 4 is a longitudinal sectional view showing an example of the internal structure of a reactor vessel in which this type of fuel assembly is used, and FIGS. 5 and 6 show an embodiment of the present invention. The figure is an enlarged front view of the lower end, and FIG. 6 is a plan view of a portion of the screen. Furthermore, FIGS. 7 and 8 respectively show other embodiments of the present invention, with FIG. 7 being an enlarged front view of the lower end, and FIG. 8 being a plan view of a portion of the screen. 2... lower nozzle, 7... fuel rod, 8... fuel pellet, 18... screen, A'... fuel assembly.
Claims (1)
ルとの間に、燃料ペレツトを収納する複数の燃料
棒が、その軸線を上下に向けて並設されてなる燃
料集合体において、上記燃料棒の下端部と下部ノ
ズルの上面との中間部分にスクリーンが配設され
てなることを特徴とする燃料集合体。1. In a fuel assembly in which a plurality of fuel rods storing fuel pellets are arranged in parallel with their axes facing upward and downward between an upper nozzle and a lower nozzle that are arranged vertically opposite to each other, the lower end of the fuel rod is A fuel assembly characterized in that a screen is disposed at an intermediate portion between the lower nozzle and the upper surface of the lower nozzle.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP59017914A JPS60162985A (en) | 1984-02-03 | 1984-02-03 | Fuel aggregate |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP59017914A JPS60162985A (en) | 1984-02-03 | 1984-02-03 | Fuel aggregate |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS60162985A JPS60162985A (en) | 1985-08-24 |
| JPS646423B2 true JPS646423B2 (en) | 1989-02-03 |
Family
ID=11957019
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP59017914A Granted JPS60162985A (en) | 1984-02-03 | 1984-02-03 | Fuel aggregate |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS60162985A (en) |
Families Citing this family (16)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4980121A (en) * | 1989-07-28 | 1990-12-25 | Westinghouse Electric Corp. | Protective device for lower end portion of a nuclear fuel rod cladding |
| US5094802A (en) * | 1989-10-13 | 1992-03-10 | B&W Fuel Company | Nuclear fuel assembly debris filter |
| US5037605A (en) * | 1989-10-13 | 1991-08-06 | B&W Fuel Company | Nuclear fuel assembly debris filter |
| SE9202828L (en) * | 1992-09-30 | 1994-03-31 | Asea Atom Ab | Fuel elements for a light water nuclear reactor |
| DE4240537A1 (en) * | 1992-12-02 | 1994-06-09 | Siemens Ag | Method for producing a screen plate for a fuel assembly base and corresponding fuel assembly |
| US5483564A (en) * | 1993-04-12 | 1996-01-09 | General Electric Company | Lower tie plate strainers including double corrugated strainers for boiling water reactors |
| US5390220A (en) * | 1993-11-29 | 1995-02-14 | General Electric Company | Lower tie plate strainers including helical spring strainers for boiling water reactors |
| US5345483A (en) * | 1993-12-02 | 1994-09-06 | General Electric Company | Lower tie plate strainers having double plate with offset holes for boiling water reactors |
| US5488634A (en) * | 1994-02-10 | 1996-01-30 | General Electric Company | Lower tie plate debris catcher for a nuclear reactor |
| US5473650A (en) * | 1994-04-15 | 1995-12-05 | General Electric Company | Lower tie plate debris catcher for a nuclear reactor |
| US5481578A (en) * | 1994-06-24 | 1996-01-02 | General Electric Company | Perforated tube debris catcher for a nuclear reactor |
| US5539793A (en) * | 1994-10-27 | 1996-07-23 | General Electric Company | Lower tie plate debris catcher for a nuclear reactor |
| US5519745A (en) * | 1994-11-03 | 1996-05-21 | General Electric Company | Lower tie plate debris catcher for a nuclear reactor |
| US5528640A (en) * | 1994-11-07 | 1996-06-18 | General Electric Company | Low pressure double offset plate catcher for a nuclear reactor |
| US5748694A (en) * | 1996-03-26 | 1998-05-05 | General Electric Company | Fuel bundle filter for a nuclear reactor fuel bundle assembly |
| CN105938074B (en) * | 2016-05-17 | 2018-07-03 | 西安交通大学 | Fuel assembly for nuclear reactor bottom nozzle waterpower scour simulation system and its test method |
Family Cites Families (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS60147684A (en) * | 1984-01-13 | 1985-08-03 | 三菱原子力工業株式会社 | Nuclear fuel aggregate |
-
1984
- 1984-02-03 JP JP59017914A patent/JPS60162985A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS60162985A (en) | 1985-08-24 |
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