JPS60162985A - Fuel aggregate - Google Patents
Fuel aggregateInfo
- Publication number
- JPS60162985A JPS60162985A JP59017914A JP1791484A JPS60162985A JP S60162985 A JPS60162985 A JP S60162985A JP 59017914 A JP59017914 A JP 59017914A JP 1791484 A JP1791484 A JP 1791484A JP S60162985 A JPS60162985 A JP S60162985A
- Authority
- JP
- Japan
- Prior art keywords
- fuel
- screen
- nozzle
- lower nozzle
- fuel assembly
- 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.)
- Granted
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
- Inert Electrodes (AREA)
- Monitoring And Testing Of Nuclear Reactors (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】
〔産業上の利用分野〕
この発明は加圧木型軒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 [Industrial Field of Application] This invention relates to a fuel assembly used in a nuclear reactor such as a pressurized wooden eaves water reactor.
従来、この種の燃１１集合体どしては、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下部ノズル、下部ノズルであ
る。これら上部ノズル１ど下部ノズル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。Conventionally, there are fuel 11 assemblies of this type as shown in FIGS. 1 to 3. In these figures, reference numeral 1.
Reference numeral 2 denotes a lower nozzle, which is arranged vertically to face each other. Between these upper nozzle 1 and lower nozzle 2, the upper end and the lower end are connected to the upper nozzle 1 and the lower nozzle 2, respectively.
A plurality of control rod guide tubes 3 supported by the control rod guide tubes 3 are provided. A support grid 4 is fixed to the control rod guide tube 3 .
この支持格子４は、第３図に示すＪ：うに、割竹支持部
５および弾性支持部６を多数粗石するものであり、これ
ら割竹支持部５おにび弾性支持部６によって多数の燃料
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、多数の燃料ペレット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どからなるものである
。This support grid 4 has a large number of split bamboo support parts 5 and elastic support parts 6 as shown in FIG. The fuel rods 7 are clamped and fixed with their axes facing upward and downward. The fuel rod 7 consists of a cladding tube 9 made of Zircaloy 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.
このように椙成された燃料集合体Ａは、第１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、−Ｌ部炉心板１３おにび下部炉心板１／Ｉ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を通っ
て燃料棒７゜７間を通過Ｊる際に加熱り−る１〕のであ
る。なＪ３、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. 1, the fuel assemblies A prepared in this way are inserted into the reactor core 12 in the reactor vessel 11 in a vertical state in large numbers, and are inserted into the -L section core plate 13 and the lower core plate 1. /I is clamped and fixed. Cooling water flows in from the inlet 15 of the reactor vessel 11, reverses in the lower plenum part 16, and flows upward through the nozzle hole 2a of the lower nozzle 2, and passes between the fuel rods 7. It is heated during cooking 1]. J3, the heated cooling water is sent from the outlet 17 to a heat exchanger (not shown) and used for power generation.
ところで、−に配の燃料集合体△は、原子力発電に用い
られるものであるから、１−ラブルの発生を極力防止し
冑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ット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。By the way, since the fuel assembly Δ arranged in the negative direction is used for nuclear power generation, it is necessary to prevent and eliminate the occurrence of 1-rubble 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Δ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の下端部においでは流
れが激しく乱れている。However, it has been found that in the conventional fuel assembly Δ, the lower end of the cladding tube 9 may be damaged. That is, from the nozzle hole 2a of the lower nozzle 2, the fuel assembly A
The flow of the cooling water flowing into the fuel rod 7 is severely turbulent at the lower end of the fuel rod 7.
このため、冷却水中に何らかの原因によって、ごみ、金
属くず等の貸物が混入すると、その安物が被覆管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。Therefore, if for some reason dirt, metal scraps, or other rental items get mixed into the cooling water, the cheap items will violently collide with the lower end of the cladding tube 9, and as a result, there is a risk that the lower end of the cladding tube 9 will 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どしても燃料棒の下９＆ｉ：部が損
傷されるおそれのない燃１Ｎ集合体を提供づることを目
的とづる。The present invention has been made in view of the above circumstances, and an object of the present invention is to provide a fuel 1N assembly in which there is no risk of damage to the lower portions of the fuel rods even if foreign matter gets mixed into the cooling water.
（発明の構成〕
この発明は、上記の目的を達成Ｊるために、燃料棒と下
部ノズルとの間にスクリーンを配置Ｑ ｌノたことを構
成上の特徴と覆るしのである。(Structure of the Invention) In order to achieve the above object, the present invention has a structural feature in that a screen is disposed between the fuel rod and 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
従来例と同様り部分には同一符号を付してその説明を省
略づる。Hereinafter, one embodiment of the present invention will be explained as shown in FIGS. 5 and 6.
This will be explained with reference to the figures. In these figures, the same parts as in the conventional example described above are designated by the same reference numerals, and the explanation thereof will be omitted.
第５図はこの発明に係る燃料集合体Δ′の」二端部を省
略して示す正面図である。この図に示ず燃料集合体へ−
においては、燃料棒７と下部ノズル２どの間に、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１８８等により形成されたｂ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１８１）が、その孔径と位置を制御
棒案内管３３やｈ１装管１９に合わせて穿設されており
、また、イの周縁部と上記挿入孔１８ｂの縁部等は補強
部ＩＪ１８ＣにＪ：って適宜に補強されている。イして
、スクリーン１８は、上記複数の挿入孔１８ｂに制御棒
案内管３や訓装管１９を挿通することにより燃料棒７と
下部ノズル２との間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 of the fuel assembly Δ' according to the present invention, with the two ends thereof omitted. To the fuel assembly (not shown in this figure)
In this case, a screen 18 for capturing and removing foreign matter in the cooling water is disposed horizontally between the fuel rod 7 and the lower nozzle 2. This screen 18 is formed of a stainless steel wire mesh 188 or the like, so that the lower nozzle 2
It has a rectangular shape that is approximately the same shape as the upper surface, and a plurality of insertion holes 181) are bored at predetermined positions with the hole diameter and position matching the control rod guide tube 33 and the H1 tube 19. , A and the edge of the insertion hole 18b are appropriately reinforced by a reinforcing portion IJ18C. Then, the screen 18 is positioned at a predetermined position between the fuel rod 7 and the lower nozzle 2 by inserting the control rod guide tube 3 and the training tube 19 into the plurality of insertion holes 18b, and welding, etc. It is fixed to the control rod guide tube 3 by means of fixing means.
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０．３〜１．０祁φ、網目が０．５〜２．０
ｍｍ口の３２〜７メツシユのものを使用することかでき
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 mm and a mesh size of 0.5 to 2.0 mm, for example.
It is possible to use one with a 32 to 7 mesh opening. 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へ−においては、燃料
棒７と下部ノズル２との間にスクリーン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から流入してぎたとしても
、その異物はスクリ５−
一ン１８によって捕捉除去される。したがって、燃料棒
７の被覆管９の下０ｉ１部が安物により損傷を受けるお
それはなく、燃料集合体へ−の健全性は向上する。However, in the fuel assembly having the above configuration, since the screen 18 is disposed between the fuel rods 7 and the lower nozzle 2, the cooling water containing foreign matter such as dust and metal scraps flows into the lower nozzle. Even if the foreign matter flows in from the nozzle hole 2a of No. 2, the foreign matter is captured and removed by the screen 5-1. Therefore, there is no risk that the lower Oi1 portion of the cladding tube 9 of the fuel rod 7 will be damaged by cheap materials, and the integrity of the fuel assembly 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１へ８からの放射能により汚染され
て放射性物質となるが、上記燃料集合体へ−では、異物
は、燃料ペレット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 rod 7, the foreign matter becomes contaminated with radioactivity from the fuel pellets 1 and 8 and becomes a radioactive substance. Since it concentrates on the screen 18 away from the pellets 8, it is easy to remove it.
さらに、冷ノオ水は、下部ノズル２のノズル孔２ａから
乱流として流入してスクリーン１８を通過するが、イの
際スクリーン１８にＪ：ってより激しい乱流となる。し
たがって、冷７Ｊｌ水と燃料棒７どの間の熱交換効率が
一段ど高まる。Furthermore, the cold spray water flows in as a turbulent flow from the nozzle hole 2a of the lower nozzle 2 and passes through the screen 18, but at the time of A, the cold water flows into the screen 18 and becomes a more intense turbulent flow. Therefore, the heat exchange efficiency between the cold 7Jl 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Ｊ：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
と下部ノズル２との間に配設したものである。この場合
、下部ノズル２のノズル６一
孔２ａを通って流入してぎた冷７ＪＩ水中の異物は、ス
クリーン２０の水平部２０１）によって捕捉除去される
。また、スクリーン２０には立上り部２０ａ ／Ｊ＜設
（）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１胴
）を通っ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って燃料棒７の下端部に流入す
ることはない。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 on a wire mesh 18a at the periphery is attached to a fuel rod 7.
and the lower nozzle 2. In this case, foreign matter in the cold 7JI water that has flowed through the nozzle 6 and hole 2a of the lower nozzle 2 is captured and removed by the horizontal portion 201) of the screen 20. In addition, since the screen 20 is provided with a rising portion 20a/J<(), it is possible to pass through a small gap (approximately one cylinder) between the lower nozzle 2 and the lower nozzle 2' adjacent to the lower nozzle 2. Foreign matter in the inflowing cooling water does not flow into the lower end of the fuel rod 7 through the side of the peripheral edge of the screen 20.
また、」二層において、スクリーン１８．２０は、所定
メッシコの金網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Ｊ：いし、第８図に示づように、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【プた多孔板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
に複層に設りても構わない。加えて、スクリーン１８．
２０にミキシングベーンを付【プるど、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 two-layer case, the screen 18.20 was formed using a wire mesh 18a of a predetermined mesh size, but this wire mesh 18a was provided only at the position where the nozzle hole 2a of the lower nozzle 2 is vertically projected and the surrounding area, Other parts may be formed from metal plates. Furthermore, a screen 18.
20, as shown in FIG. May be used. Furthermore, the screens 18 and 20 may be provided in multiple layers in the vertical direction. In addition, screen 18.
Adding a mixing vane to 20 further promotes turbulent flow of cooling water, increasing heat exchange efficiency.
（発明の効果）
双子説明した」、うに、この発明の燃料集合体にあって
は、燃料棒と下部ノズルとの間にスクリーンを配設して
いるから、たとえ冷却水中に貢物が混入したどしても、
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
。したがって、燃料棒の下端部が損傷されるおぞれは全
くなくなり、燃料集合体の健全性が格段ど高まる。(Effects of the invention) In the fuel assembly of this invention, a screen is provided between the fuel rods and the lower nozzle, so even if tribute gets mixed into the cooling water, Even if
This foreign matter is reliably captured and removed by the screen. Therefore, there is no risk of damage to the lower ends of the fuel rods, 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ずち
ので、第１図は一部切り欠ぎ正面図、第２図は下端部の
拡大正面図、第３図は第２図の■内部の拡大図である。
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ｍ造の一例を示す縦断面図、第５図４５よび
第６図はこの発明の一実施例を示寸ムので、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。ざらに、第７図および第８図はぞれぞれこの
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
・・・・・・燃料ペレッ１〜、′１８・・・・・・スク
リーン、Ａ′・・・・・・燃料集合体。
出願人 三菱原子燃判株式会ネ１
９−
第１図
第７図Figures 1 to 3 show an example of a conventional fuel assembly, so Figure 1 is a partially cutaway front view, Figure 2 is an enlarged front view of the lower end, and Figure 3 is a front view of the lower end. This is an enlarged view of the inside of the figure. Furthermore, FIG. 4 is a vertical sectional view showing an example of the internal structure of a reactor vessel in which this type of fuel assembly is used, and FIGS. , FIG. 5 is an enlarged front view of the lower end, and FIG. 6 is a plan view of a portion of the screen. Briefly, FIGS. 7 and 8 each 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 pellets 1-,'18...Screen, A'...Fuel assembly. Applicant Mitsubishi Nuclear Fuel Co., Ltd. Ne1 9- Figure 1 Figure 7
Claims (1)
、燃料ペレットを収納する複数の燃料棒が、その軸線を
上下に自Ｃノで並設されてなる燃料集合体において、上
記燃料棒と下部ノズルとの間にスクリーンが配設されて
なることを特徴どする燃料集合体。In a fuel assembly in which a plurality of fuel rods storing fuel pellets are arranged in parallel with each other vertically with respect to their axes between an upper nozzle and a lower nozzle that are arranged vertically opposite to each other, the above-mentioned fuel rods and A fuel assembly characterized in that a screen is disposed between the lower nozzle and 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 true JPS60162985A (en) | 1985-08-24 |
| JPS646423B2 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) |
Cited By (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 |
| US5037605A (en) * | 1989-10-13 | 1991-08-06 | B&W Fuel Company | Nuclear fuel assembly debris filter |
| US5094802A (en) * | 1989-10-13 | 1992-03-10 | B&W Fuel Company | Nuclear fuel assembly debris filter |
| 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 |
| US5471514A (en) * | 1992-09-30 | 1995-11-28 | Abb Atom Ab | Fuel element for a light-water 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 |
| 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 |
| US5867550A (en) * | 1992-12-02 | 1999-02-02 | Siemens Aktiengesellschaft | Process for the production of a screen plate for a fuel assembly foot and corresponding fuel assembly |
| CN105938074A (en) * | 2016-05-17 | 2016-09-14 | 西安交通大学 | Nuclear reactor fuel assembly bottom nozzle hydraulic scouring test system and test method thereof |
Citations (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
Patent Citations (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 |
Cited By (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 |
| US5037605A (en) * | 1989-10-13 | 1991-08-06 | B&W Fuel Company | Nuclear fuel assembly debris filter |
| US5094802A (en) * | 1989-10-13 | 1992-03-10 | B&W Fuel Company | Nuclear fuel assembly debris filter |
| US5471514A (en) * | 1992-09-30 | 1995-11-28 | Abb Atom Ab | Fuel element for a light-water nuclear reactor |
| US5867550A (en) * | 1992-12-02 | 1999-02-02 | Siemens Aktiengesellschaft | Process for the production of a screen plate for a fuel assembly foot 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 |
| CN105938074A (en) * | 2016-05-17 | 2016-09-14 | 西安交通大学 | Nuclear reactor fuel assembly bottom nozzle hydraulic scouring test system and test method thereof |
Also Published As
| Publication number | Publication date |
|---|---|
| JPS646423B2 (en) | 1989-02-03 |
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