JPS63157093A - Nuclear fuel aggregate - Google Patents
Nuclear fuel aggregateInfo
- Publication number
- JPS63157093A JPS63157093A JP61305988A JP30598886A JPS63157093A JP S63157093 A JPS63157093 A JP S63157093A JP 61305988 A JP61305988 A JP 61305988A JP 30598886 A JP30598886 A JP 30598886A JP S63157093 A JPS63157093 A JP S63157093A
- Authority
- JP
- Japan
- Prior art keywords
- nuclear fuel
- fuel assembly
- straps
- cooling water
- support
- 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
- 239000003758 nuclear fuel Substances 0.000 title claims description 30
- 230000037431 insertion Effects 0.000 claims 1
- 238000003780 insertion Methods 0.000 claims 1
- 239000000498 cooling water Substances 0.000 description 14
- 230000000712 assembly Effects 0.000 description 7
- 238000000429 assembly Methods 0.000 description 7
- 238000005253 cladding Methods 0.000 description 7
- 239000000446 fuel Substances 0.000 description 5
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 3
- 230000000694 effects Effects 0.000 description 2
- 238000004519 manufacturing process Methods 0.000 description 2
- 238000003466 welding Methods 0.000 description 2
- 238000005452 bending Methods 0.000 description 1
- 230000015572 biosynthetic process Effects 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 239000000428 dust Substances 0.000 description 1
- 239000003292 glue Substances 0.000 description 1
- 229910001026 inconel Inorganic materials 0.000 description 1
- 239000002184 metal Substances 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 239000008188 pellet Substances 0.000 description 1
- 238000003825 pressing Methods 0.000 description 1
- 239000002915 spent fuel radioactive waste Substances 0.000 description 1
- 229910001220 stainless steel Inorganic materials 0.000 description 1
- 239000000126 substance Substances 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
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】
「産業上の利用分野」
本発明は、加圧水型軽水炉等の原子炉において使用され
る核燃料集合体に係わり、特に、冷却水中の異物を除去
することができるものに関する。DETAILED DESCRIPTION OF THE INVENTION "Field of Industrial Application" The present invention relates to nuclear fuel assemblies used in nuclear reactors such as pressurized water type light water reactors, and particularly to nuclear fuel assemblies that can remove foreign substances in cooling water.
「従来の技術」
第５図は、この種の一般的な核燃料集合体を示す正面図
である。"Prior Art" FIG. 5 is a front view showing this type of general nuclear fuel assembly.
図中符号ｌおよび２は、上下に対向配置された上部ノズ
ルおよび下部ノズルであり、これら上部ノズルｌと下部
ノズル２の間には、複数の制御棒案内管３・・・が掛は
渡されて固定されている。そして、これら案内管３・・
・の中途部には、複数の支持格子４・・・が取り付けら
れており、各支持格子４・・・の格子内に、ペレットが
封入された多数の燃料棒５・・・が頁通支持されている
。Symbols l and 2 in the figure are an upper nozzle and a lower nozzle arranged vertically opposite each other, and a plurality of control rod guide tubes 3 are connected between the upper nozzle l and the lower nozzle 2. Fixed. And these guide tubes 3...
- A plurality of support grids 4... are attached to the middle part, and a large number of fuel rods 5... with pellets sealed are supported in each support grid 4... has been done.
このような核燃料集合体は、原子炉容器の炉心に垂直状
態で多数装入され、上部炉心板および下部炉心板の間に
はさまれて支持される。そして、原子炉の稼動時には、
下方から上方へ向けて炉心内部に勢いよく冷却水が循環
されるようになっていて、この冷却水が、下部ノズル２
に形成されたノズル孔（図示せず）を通り、燃料棒５・
・・の間を通り抜け、上部ノズルｌに形成されているノ
ズル孔（図示せず）から排出されるまでの間に、加熱さ
れるようになっている。A large number of such nuclear fuel assemblies are vertically charged into the core of a nuclear reactor vessel, and are supported by being sandwiched between an upper core plate and a lower core plate. And when the reactor is in operation,
Cooling water is circulated vigorously inside the core from the bottom to the top, and this cooling water flows through the lower nozzle 2.
The fuel rods 5 and 5 pass through nozzle holes (not shown) formed in the
... and is heated before being discharged from a nozzle hole (not shown) formed in the upper nozzle l.
ところで、このような核燃料集合体においては、従来よ
り燃料棒５・・の下端部が損傷するおそれがあることが
指摘されている。すなわち、なんらかの原因で冷却水中
にゴミ、金属屑等の異物が混入すると、これら異物が冷
却水とともに下部ノズル２のノズル孔を通過し、冷却水
の流れが激しく乱れている燃料棒５・・・の下端部近傍
において被覆管に衝突して、被覆管の下端部を傷つける
可能性が全くないとはいえないのである。By the way, in such a nuclear fuel assembly, it has been pointed out that there is a risk of damage to the lower end portions of the fuel rods 5. That is, if foreign matter such as dust or metal chips gets mixed into the cooling water for some reason, these foreign matter will pass through the nozzle holes of the lower nozzle 2 together with the cooling water, and the flow of the cooling water will be severely disturbed in the fuel rods 5... It cannot be said that there is no possibility that it will collide with the cladding tube near the lower end and damage the lower end of the cladding tube.
そこで、本出願人等は、特願昭５９−１７９１４号にお
いて、このような被覆管損傷を防ぐことのできる核燃料
集合体を提案しｊコ。Therefore, in Japanese Patent Application No. 59-17914, the present applicant proposed a nuclear fuel assembly that can prevent such damage to the cladding tube.
第６図は、その核燃料集合体の要部を示す正面図である
。この核燃料集合体は、燃料棒５・・・と、ノズル孔２
Ａを有する下部ノズル２との間に、冷却水中の異物を捕
捉するためのスクリーンｌＯを水平に配設したことを特
徴としている。FIG. 6 is a front view showing the main parts of the nuclear fuel assembly. This nuclear fuel assembly includes fuel rods 5... and nozzle holes 2.
A feature is that a screen 10 for trapping foreign matter in the cooling water is horizontally disposed between the lower nozzle 2 and the lower nozzle 2 having A.
このスクリーン１０は、ステンレス製の金網であって、
第７図に示すように下部ノズル２の上面と略同形状をな
すとともに、制御棒案内管３・・・および計装管６を挿
入固定するための孔１１・・・が形成されている。そし
て、このスクリーンｌＯは、前記孔１１・・・内に案内
管３・・・および計装管６が挿通された後、案内管３・
・・に対し溶接固定されている。This screen 10 is a stainless steel wire mesh,
As shown in FIG. 7, holes 11 are formed which have approximately the same shape as the upper surface of the lower nozzle 2, and into which the control rod guide tubes 3 and the instrumentation tubes 6 are inserted and fixed. Then, after the guide tube 3... and the instrumentation tube 6 are inserted into the hole 11...
It is welded and fixed to...
「発明が解決しようとする問題点」
ところで、前記の核燃料集合体にあっては、スクリーン
ｌＯを装着するに際し、■スクリーンＩＯの孔１１・・
・に制御棒案内管３・・・および計装管６を挿通する、
■スクリーンｌＯを下部ノズル２の上面と平行に位置決
めする、■スクリーンｌＯの孔１１・・・の周縁と案内
管３・・・とを溶接してスクリーン１０を固定する、と
いった一連の作業が必要で、核燃料集合体の組み立てに
手間がかかるという欠点があった。"Problems to be Solved by the Invention" By the way, in the above-mentioned nuclear fuel assembly, when installing the screen IO, the hole 11 of the screen IO...
・Insert the control rod guide tube 3... and the instrumentation tube 6 into the
A series of operations are required: ■Positioning the screen 10 parallel to the upper surface of the lower nozzle 2, ■Welding the periphery of the hole 11 of the screen 10 and the guide tube 3 to fix the screen 10. However, the drawback was that it took time and effort to assemble the nuclear fuel assembly.
また、この核燃料集合体では、原子炉稼動時にスクリー
ン１０に対し大きな流水圧がかかるうえ、スクリーンＩ
Ｏを案内管３・・・に対して溶接固定しているだけなの
で、取付強度の点で信頼性が十分であるとは言い難かっ
た。In addition, in this nuclear fuel assembly, large flowing water pressure is applied to the screen 10 during reactor operation, and the screen I
Since O is simply fixed to the guide tube 3 by welding, it is difficult to say that the reliability is sufficient in terms of mounting strength.
「発明の目的」
本発明は、前記事情に鑑みてなされたもので、冷却水中
の異物を捕捉して被覆管損傷を防ぐことができ、しかも
スクリーンを取り付ける従来の方法に比べて核燃料集合
体の組み立てが容易で、異物捕捉部の強度が高い核燃料
集合体を提供することを目的とする。``Object of the Invention'' The present invention was made in view of the above-mentioned circumstances, and is capable of trapping foreign objects in cooling water to prevent damage to the cladding tube. It is an object of the present invention to provide a nuclear fuel assembly that is easy to assemble and has a foreign object trapping part with high strength.
「問題点を解決するための手段」
本発明の核燃料集合体は、最下方に位置する支持格子を
構成する各ストラップに、これらのストラップが画成す
る各格子空間の下方四隅部分に張り出す凸部を形成した
ことを特徴とし、これらの凸部により冷却水中の異物を
捕捉する。"Means for Solving the Problems" The nuclear fuel assembly of the present invention has protrusions on each of the straps constituting the support lattice located at the lowest position, projecting from the lower four corners of each lattice space defined by these straps. These protrusions trap foreign matter in the cooling water.
「実施例」 以下、図面を用いて本発明の実施例を詳細に説明する。"Example" Embodiments of the present invention will be described in detail below with reference to the drawings.
第１図および第２図は、本発明に係わる核燃料集合体を
構成する支持格子のうち、最下方に位置するしのを示す
平面図およびロー■線視断面図である。FIGS. 1 and 2 are a plan view and a sectional view taken along the line 2, respectively, showing the lowermost support grid of the support grid constituting the nuclear fuel assembly according to the present invention.
この支持格子は、正方形状の外枠を構成する外ストラツ
プ２０・・・と、この外ストラツプ２０・・・内で互い
に交差して固定された内ストラツプ２１・・・とからな
る。そして、これらストラップ２０・・・。This support lattice consists of outer straps 20 constituting a square outer frame, and inner straps 21 fixed so as to cross each other within the outer straps 20. And these straps 20...
２１・・・により、多数、の格子空間２２・・・が画成
されている。A large number of lattice spaces 22... are defined by 21....
前記ストラップ２０．２１はいずれも、インコネル製ま
たはノルカロイ製の薄板により成形されたしのである。Each of the straps 20, 21 is formed from a thin sheet of Inconel or Norcaloy.
また各ストラップ２０．２１には、各格子空間２２内に
突出するスプリング２３・・・およびディンプル２４・
・・が形成されており、これらスプリング２３とディン
プル２４によって各格子空間２２に挿通される核燃料棒
２５を支持するようになっている。In addition, each strap 20.21 has a spring 23 projecting into each grid space 22, and a dimple 24.
... are formed, and the nuclear fuel rods 25 inserted into each lattice space 22 are supported by these springs 23 and dimples 24.
ここまでの構成は従来の核燃料集合体と同様であり、以
下が本実施例の要点である。The configuration up to this point is the same as that of a conventional nuclear fuel assembly, and the main points of this embodiment are as follows.
各ストラップ２０．２１には、これらが画成ず−る格子
空間２２内の下方四隅部分に張り出したリブ（凸部）２
６・・・が形成されている。これらリブ２６は、各交差
点において交差する一方のストラッブ２０（２１）の下
端部に、鉤状に切れ込みを入れて長方形の舌部を形成し
、この舌部を４５°折り曲げて、その遊端部を他方のス
トラップ２１（２０）にロウ付けしてなるものである。Each strap 20, 21 has ribs (convex portions) 2 projecting from the lower four corners of the lattice space 22 defined by these straps.
6... is formed. These ribs 26 are formed by making a hook-shaped cut in the lower end of one of the strubs 20 (21) that intersects at each intersection to form a rectangular tongue, and bending this tongue by 45 degrees to form a free end. is brazed to the other strap 21 (20).
そして、このリブ２６は、各ストラップ２０．２１の交
差点と、格子空間２２に挿通される核燃料棒２５の周面
とを結ぶ線分の中点付近を通るようにされている。The rib 26 is configured to pass near the midpoint of a line segment connecting the intersection of each strap 20.21 and the circumferential surface of the nuclear fuel rod 25 inserted into the lattice space 22.
なお、リブ２６の幅は、前記スプリング２３およびディ
ンプル２４の形成に支障がない範囲とされる。The width of the rib 26 is set within a range that does not interfere with the formation of the spring 23 and dimple 24.
このような支持格子を備えた核燃料集合体によれば、原
子炉内を流れる冷却水中に万一異物が混入した場合にも
、冷却水が前記支持格子の格子空間２２内の四隅部分を
流れる際に、前記リブ２６・・・により核燃料棒２５の
被覆管を傷付けるおそれのある大きさ以上の異物の通過
を阻止し、被覆管損傷を防ぐことができる。According to a nuclear fuel assembly equipped with such a support grid, even if foreign matter should get mixed into the cooling water flowing inside the reactor, when the cooling water flows through the four corners of the grid space 22 of the support grid, In addition, the ribs 26 prevent foreign matter larger than the size that may damage the cladding tube of the nuclear fuel rod 25 from passing through, thereby preventing damage to the cladding tube.
また、前記リブ２６・・・はストラップ２０（２１）と
一体に形成されれているうえ、遊端部は強固にロウ付け
されているので、異物との衝突に対する強度が高く、前
記従来の異物捕捉用のスクリーンを設けた核燃料集合体
に比して信頼性が高い。しかし、リブ２６の肉厚は薄い
ため、スクリーンに比べて冷却水の流水抵抗に及ぼす影
響が少ない。In addition, the ribs 26 are integrally formed with the strap 20 (21), and the free ends are firmly brazed, so they have high strength against collisions with foreign objects, and are more durable than the conventional foreign objects. It is more reliable than nuclear fuel assemblies equipped with capture screens. However, since the ribs 26 are thin, they have less influence on the flow resistance of cooling water than the screen.
また、この支持格子では、従来の支持格子と全く同様に
核燃料集合体の組み立てができるので、スクリーンを取
り付ける方法に比べて組み立てに手間がかからない点で
有利である。In addition, this support grid allows the nuclear fuel assembly to be assembled in exactly the same way as with conventional support grids, so it is advantageous in that it requires less time and effort to assemble compared to the method of attaching screens.
またさらζこ、前δ己すブ２６・・・はストラップ２０
゜２１の交差点を補強しているため、支持格子の組み立
て強度が高いという利点も有する。Again, ζ, front δ self-bu 26...is strap 20
Since the intersections at angles of 21° are reinforced, there is also the advantage that the assembly strength of the support grid is high.
なお、このようなリブ２６を形成する代わりに、第３図
および第４図のようにディンプルを形成した構成として
もよい。Incidentally, instead of forming such ribs 26, dimples may be formed as shown in FIGS. 3 and 4.
この実施例では、第４図に示すように格子空間２２の下
方四隅部分にあたる各ストラップ２０゜２１の下端部に
、水平な２本の切り込み３０，３Ｉを形成し、これによ
ってできる帯状の部分をストラップ２０．２１と垂直な
方向に互いに反対方向に突出させることにより、格子空
間２２内の下方四隅部分に張り出す半円状のディンプル
（凸部）３０Ａ、３１Ａが形成されている。In this embodiment, as shown in FIG. 4, two horizontal cuts 30 and 3I are formed at the lower end of each strap 20 and 21, which correspond to the four lower corners of the grid space 22. Semicircular dimples (protrusions) 30A, 31A projecting from the four lower corners of the lattice space 22 are formed by projecting in opposite directions in a direction perpendicular to the straps 20, 21.
このような支持格子では、スプリング２３やディンプル
２４と同様にプレス加工によってディンプル３０Ａ、３
１Ａを形成することができるので、前述のり１２６のよ
うにａつ付けの必要がない分、製造か容易でコスト低下
が図れるといった利点がある。In such a support grid, the dimples 30A and 3 are formed by pressing, similar to the springs 23 and dimples 24.
1A, there is no need to attach A as in the case of the above-mentioned glue 126, and there is an advantage that manufacturing is easy and costs can be reduced.
なお、以上説明したリブ２６、ディンプル３０Ａ、３１
Ａの形状は図に示すものに限らず、例えばそれぞれを円
弧状または多角形状としてもよい。Note that the ribs 26, dimples 30A, 31 explained above
The shape of A is not limited to that shown in the figure, and each may be arcuate or polygonal, for example.
「発明の効果」
本発明の下部ノズルによれば以下のような優れた効果が
得られる。"Effects of the Invention" According to the lower nozzle of the present invention, the following excellent effects can be obtained.
■原子炉内を流れる冷却水中に万一異物が混入した場合
にも、冷却水が最下方の支持格子の格子空間内の四隅部
分を流れる際に、この部分に張り出した凸部により異物
の通過を阻止し、被覆管損傷を防ぐことができる。■Even in the unlikely event that a foreign object gets mixed into the cooling water flowing inside the reactor, when the cooling water flows through the four corners of the lattice space of the lowest support grid, the foreign object will pass through the convex parts that protrude into this part. This can prevent damage to the cladding.
■前記凸部はストラップと一体に形成することができる
ので、異物との衝突に対する強度が高く、従来の異物捕
捉用のスクリーンを設けた核燃料集合体に比して信頼性
が高い。(2) Since the convex portion can be formed integrally with the strap, it has high strength against collisions with foreign objects, and is more reliable than conventional nuclear fuel assemblies provided with screens for trapping foreign objects.
■通常使用されている核燃料集合体と全く同様に組み立
てることができるので、スクリーンを取り付けた核燃料
集合体に比べて製造が容易である。■Since it can be assembled in exactly the same way as normally used nuclear fuel assemblies, it is easier to manufacture than nuclear fuel assemblies with screens attached.
第１図および第２図は本発明゛の核燃料集合体を構成す
る支持格子の要部を示す平面図およびＵ−■線視断面図
、第３図および第４図は本発明の他の実施例の第１図お
よび第２図と同様の図である。
また、第５図は一般的な核燃料集合体の正面図、第６図
および第７図は本出願人が先に出願した核燃料集合体の
要部の正面図および平面図である。1 and 2 are a plan view and a sectional view taken along the line U-■ showing the main parts of a support grid constituting a nuclear fuel assembly according to the present invention, and FIGS. 3 and 4 are views showing other embodiments of the present invention. FIG. 2 is a diagram similar to FIGS. 1 and 2 in the example; Further, FIG. 5 is a front view of a general nuclear fuel assembly, and FIGS. 6 and 7 are a front view and a plan view of essential parts of a nuclear fuel assembly previously filed by the present applicant.
Claims (1)
差させて組み立てられた支持格子を、複数個離間して配
置し、これら支持格子の前記格子空間に多数の核燃料棒
を挿通支持してなる核燃料集合体において、 前記支持格子のうち最下方の支持格子を構成する各スト
ラップに、これらのストラップが画成する各格子空間内
の下方四隅部分に張り出す凸部を形成したことを特徴と
する核燃料集合体。[Claims] A plurality of support grids assembled with straps crossing each other so as to define a large number of grid spaces are arranged at intervals, and a large number of nuclear fuel rods are placed in the grid spaces of these support grids. In a nuclear fuel assembly formed by insertion and support, each of the straps constituting the lowermost support grid among the support grids is formed with a convex portion projecting from the lower four corners of each grid space defined by these straps. A nuclear fuel assembly characterized by:
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP61305988A JPS63157093A (en) | 1986-12-22 | 1986-12-22 | Nuclear fuel aggregate |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP61305988A JPS63157093A (en) | 1986-12-22 | 1986-12-22 | Nuclear fuel aggregate |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS63157093A true JPS63157093A (en) | 1988-06-30 |
Family
ID=17951718
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP61305988A Pending JPS63157093A (en) | 1986-12-22 | 1986-12-22 | Nuclear fuel aggregate |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS63157093A (en) |
Cited By (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| 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 |
| US5390220A (en) * | 1993-11-29 | 1995-02-14 | General Electric Company | Lower tie plate strainers including helical spring strainers for boiling water reactors |
| US5390221A (en) * | 1993-08-23 | 1995-02-14 | General Electric Company | Debris filters with flow bypass for boiling water reactors |
| US5473650A (en) * | 1994-04-15 | 1995-12-05 | General Electric Company | Lower tie plate debris catcher for a nuclear reactor |
| US5483564A (en) * | 1993-04-12 | 1996-01-09 | General Electric Company | Lower tie plate strainers including double corrugated strainers for boiling water reactors |
| US5488634A (en) * | 1994-02-10 | 1996-01-30 | 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 |
| US5539793A (en) * | 1994-10-27 | 1996-07-23 | General Electric Company | Lower tie plate debris 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 |
-
1986
- 1986-12-22 JP JP61305988A patent/JPS63157093A/en active Pending
Cited By (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5483564A (en) * | 1993-04-12 | 1996-01-09 | General Electric Company | Lower tie plate strainers including double corrugated strainers for boiling water reactors |
| US5390221A (en) * | 1993-08-23 | 1995-02-14 | General Electric Company | Debris filters with flow bypass 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 |
| 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 |
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