JPH0980188A - Pressurized water reactor and its non-nuclear fuel core structure - Google Patents
Pressurized water reactor and its non-nuclear fuel core structureInfo
- Publication number
- JPH0980188A JPH0980188A JP7238634A JP23863495A JPH0980188A JP H0980188 A JPH0980188 A JP H0980188A JP 7238634 A JP7238634 A JP 7238634A JP 23863495 A JP23863495 A JP 23863495A JP H0980188 A JPH0980188 A JP H0980188A
- Authority
- JP
- Japan
- Prior art keywords
- reactor
- fuel
- nuclear
- core
- nuclear fuel
- 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.)
- Withdrawn
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
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
Description
【０００１】[0001]
【発明の属する技術分野】本発明は、加圧水型原子炉に
関し、特にその原子炉容器内の構造に関する。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a pressurized water reactor, and more particularly to the structure inside the reactor vessel.
【０００２】[0002]
【従来の技術】現在、広く使用されている発電用原子炉
の一に加圧水型原子炉があるが、これは軽水を冷却材兼
減速材に使用するものである。その代表的炉内構造を図
３を参照して説明すると、原子炉容器本体１は、図示し
ない制御棒駆動装置を備えた上蓋３により上部が閉じら
れていて、内部に炉心を形成する多数の燃料集合体５が
装荷される。原子炉は、炉心内で生ずる核反応熱を冷却
材により取り出すものであるが、その核反応を適切に制
御するため、炉心内の中性子束を適宜計測する必要があ
り、そのために底壁に貫設した管台７に耐圧案内管９を
接続し、中性子束検出器の挿入案内通路としている。そ
して、原子炉容器１の内部には、図４に示すように燃料
集合体５の計装案内管１１に整列して案内筒１３が設け
られていて、中性子検出器のシンブルチューブ１５を案
内する。このように中性子検出器を原子炉容器１の底か
ら挿入する設計を採用した理由の一つは、前述したよう
に制御棒駆動装置を上蓋３に設け、制御棒を上方から駆
動することにある。2. Description of the Related Art At present, one of the widely used power generation reactors is a pressurized water reactor, which uses light water as a coolant and moderator. A typical internal structure of the reactor will be described with reference to FIG. 3. The reactor vessel body 1 is closed at its upper part by an upper lid 3 provided with a control rod driving device (not shown), and has a large number of cores formed therein. The fuel assembly 5 is loaded. The nuclear reactor takes out the heat of nuclear reaction generated in the core by a coolant, but in order to properly control the nuclear reaction, it is necessary to measure the neutron flux in the core as appropriate, and therefore the bottom wall is penetrated. A pressure resistant guide tube 9 is connected to the stub 7 provided to serve as an insertion guide passage for the neutron flux detector. As shown in FIG. 4, a guide cylinder 13 is provided inside the reactor vessel 1 so as to be aligned with the instrumentation guide tube 11 of the fuel assembly 5, and guides the thimble tube 15 of the neutron detector. . One of the reasons for adopting the design in which the neutron detector is inserted from the bottom of the reactor vessel 1 is that the control rod driving device is provided on the upper lid 3 and the control rod is driven from above as described above. .
【０００３】尤も、炉心の燃料集合体５の全てに制御棒
が挿入されているのではなく、原子炉運転に必要なその
他の炉心構成体、例えば可燃性毒物棒組立体、中性子源
棒、シンブルプラグ組立体等が所定の位置の燃料集合体
５に挿入されている。その状態が図５に示されている。
前述のような炉心構成体は、核燃料を含まないことから
一般に非核燃料炉心構成体と呼ばれているが、図５に示
すように非核燃料棒１７，中空のハブ２１，コイルスプ
リング２３、リテーナ２５及びボルト２７等から構成さ
れ、燃料集合体５に挿入されて燃料集合体５と上部炉心
板２９との間に固定されている。又、上部炉心板２９に
連結された上部炉心支持柱３１のノズルには、熱電対３
３が設けられ、冷却材の炉心出口温度を計測するように
なっている。However, the control rods are not inserted in all of the fuel assemblies 5 in the core, but other core components necessary for the operation of the reactor, such as a burnable poison rod assembly, a neutron source rod, and a thimble, are required. A plug assembly or the like is inserted in the fuel assembly 5 at a predetermined position. This state is shown in FIG.
The core structure as described above is generally called a non-nuclear fuel core structure because it does not contain nuclear fuel, but as shown in FIG. 5, the non-nuclear fuel rod 17, the hollow hub 21, the coil spring 23, and the retainer 25 are used. And a bolt 27 and the like, and is inserted into the fuel assembly 5 and fixed between the fuel assembly 5 and the upper core plate 29. Further, the thermocouple 3 is attached to the nozzle of the upper core supporting column 31 connected to the upper core plate 29.
3 is provided to measure the core outlet temperature of the coolant.
【０００４】[0004]
【発明が解決しようとする課題】しかしながら、以上の
ような構成では次のような問題がある。即ち、計測機器
を案内する管台が原子炉容器の底壁を貫通しているの
で、その貫通部に亀裂等の損傷が発生するとそこから原
子炉容器内の冷却材が流出する虞れがある。又、原子炉
容器内の冷却材は、底部で反転して上向きに炉心内に流
入するが、燃料集合体と案内筒との間で、検出器のシン
ブルチューブがその冷却材流に晒され、流体励起振動を
発生して損傷を受ける虞れがある。従って、本発明の課
題は、亀裂等が発生しても冷却材の流出がなく、更に計
装機器が流体励起振動を受けないような炉内核計装を実
現できる原子炉構造を提供し、且つそれを可能とする非
核燃料構成体を提供することにある。However, the above structure has the following problems. That is, since the nozzle that guides the measuring device penetrates the bottom wall of the reactor vessel, if the penetration portion is damaged, such as cracks, the coolant in the reactor vessel may flow out. . Further, the coolant in the reactor vessel is inverted at the bottom and flows upward into the core, but the thimble tube of the detector is exposed to the coolant flow between the fuel assembly and the guide tube. There is a risk of fluid-induced vibrations and damage. Therefore, an object of the present invention is to provide a reactor structure capable of realizing nuclear reactor internal instrumentation in which coolant does not flow out even if cracks or the like occur, and instrumentation equipment is not subjected to fluid-excited vibration, and It is to provide a non-nuclear fuel structure that enables this.
【０００５】[0005]
【課題を解決するための手段】かかる課題を解決するた
め、本発明によれば、原子炉容器内に装荷された複数の
燃料集合体が炉心を形成し、前記燃料集合体を上方から
押さえて支持する上部炉心板を含む炉内上部構造物が前
記原子炉容器内の上部に設けられた加圧水型原子炉にお
いて、前記炉内上部構造物内に前記原子炉容器の外側か
ら前記燃料集合体に至る炉内核計装機器の案内通路を形
成している。そして、前述の炉内上部構造物の案内通路
から計装機器を燃料集合体の計装案内管の中に導く非核
燃料炉心構成体を、燃料集合体の中空案内管に挿入され
る非核燃料棒と、同非核燃料棒の先端が連結される放射
状ベーン部材及び中空ハブを有するスパイダ本体と、前
記中空ハブ内に同軸状に設けられた円筒スリーブと、前
記中空ハブ内に前記円筒スリーブを囲んで設けられたコ
イルスプリングと、同コイルスプリングを変形自在に保
持するリテーナとから構成し、前記円筒スリーブ内に計
装機器を通すようにしている。In order to solve the above problems, according to the present invention, a plurality of fuel assemblies loaded in a reactor vessel form a core, and the fuel assemblies are pressed from above. In a pressurized water reactor in which an in-reactor superstructure including an upper core plate that supports is provided in an upper portion of the reactor vessel, the fuel assembly is provided in the in-reactor upper structure from the outside of the reactor vessel. It forms a guide passage for all nuclear instrumentation equipment in the reactor. Then, a non-nuclear fuel core structure for guiding instrumentation equipment into the instrumentation guide tube of the fuel assembly from the guide passage of the above-mentioned reactor upper structure is inserted into the hollow guide tube of the fuel assembly. A spider body having a radial vane member and a hollow hub to which the tips of the non-nuclear fuel rods are connected; a cylindrical sleeve coaxially provided in the hollow hub; and surrounding the cylindrical sleeve in the hollow hub. The coil spring is provided and a retainer for deformably holding the coil spring is provided, and the instrumentation device is passed through the cylindrical sleeve.
【０００６】[0006]
【発明の実施の形態】以下添付の図面を参照して本発明
の実施形態を説明する。なお、全図にわたり、従来構造
を含む同一部分には、同一の符号を付し、理解の便を図
っている。図１において、上部ノズル５ａ及び計装案内
管１１のみが示された燃料集合体５に、非核燃料炉心構
成体４０が挿入されて示されている。非核燃料炉心構成
体４０の詳細は、後述するように図２に示されている
が、燃料集合体５の上部には上部炉心支持柱３５に支持
された上部炉心板２９が配置され、炉心全体の燃料集合
体５を上方から押さえている。上部炉心支持柱３５は、
内部に連通孔３７を有し、その下端部にノズル３９が取
り付けられている。そのノズル３９には更にエクステン
ション３９ａが突出形成されて、非核燃料炉心構成体４
０の中空ハブ４１の中に先端が入っている。Embodiments of the present invention will be described below with reference to the accompanying drawings. In all the drawings, the same parts including the conventional structure are designated by the same reference numerals to facilitate understanding. In FIG. 1, the non-nuclear fuel core structure 40 is shown inserted into the fuel assembly 5 in which only the upper nozzle 5a and the instrumentation guide tube 11 are shown. The details of the non-nuclear fuel core structure 40 are shown in FIG. 2 as described later, but the upper core plate 29 supported by the upper core support columns 35 is disposed above the fuel assembly 5, and the entire core is The fuel assembly 5 is pressed from above. The upper core support column 35 is
It has a communication hole 37 inside and a nozzle 39 is attached to the lower end thereof. An extension 39a is further formed on the nozzle 39 so as to project, and the non-nuclear fuel core structure 4 is formed.
A hollow hub 41 of 0 has a tip.
【０００７】図２を参照するに、非核燃料炉心構成体４
０の中空ハブ４１の内部上方は、従来からある取扱工具
のグリッパ等が挿入係合できるような形状に形成されて
いるが、本発明には直接の関係が無いので詳細な説明は
割愛する。中空ハブ４１の下方外面からは、複数のベー
ン４３が放射状に延出しており、更にベーン４３の下部
に複数の非核燃料棒４５が個別に連結され、垂下して房
状になっている。非核燃料棒としては、中性子を吸収す
る可燃性毒物棒、中性子を放出する中性子源棒、制御棒
の使用されない燃料集合体の中空案内管を塞ぐシンブル
プラグ等があるが、本発明はどの場合でも適用できるの
で単に非核燃料棒としている。このような非核燃料棒４
５は、燃料集合体５の制御棒案内用中空管に挿入され
る。中空ハブ４１の中心部には、同軸的に円筒スリーブ
４７が配置され、上端が溶接４９によりハブ４１に固着
されている。円筒スリーブ４７には、軸対称位置に軸方
向スロット４７ａが形成されていて後述するリテーナ５
１のピン５３が挿通される。リテーナ５１は、円筒スリ
ーブ４７に遊嵌された肩段付き環状部材で、円筒スリー
ブ４７を囲んで設けられたコイルスプリング５３を伸長
短縮自在に保持している。スロット４７ａは、その伸長
短縮に応じたリテーナ５１の変位を許容するためのもの
であるから、図示のように円筒スリーブ４７の上端まで
延びている必要はなく、ピン５３の所定のストロークが
確保される長さでよい。非核燃料炉心構成体４０は、こ
のように構成されていて、図１に示すように炉心内に取
り付けられ、コイルスプリング５３の弾性力によりリテ
ーナ５１の下面を燃料集合体５の上部ノズルの上面に押
し付け、流体励起振動から非核燃料炉心構成体４０を保
護する。Referring to FIG. 2, a non-nuclear fuel core structure 4
The inside of the hollow hub 41 of No. 0 is formed in a shape such that a gripper or the like of a conventional handling tool can be inserted and engaged, but since it is not directly related to the present invention, detailed description thereof will be omitted. A plurality of vanes 43 extend radially from the lower outer surface of the hollow hub 41. Further, a plurality of non-nuclear fuel rods 45 are individually connected to the lower portion of the vane 43 and hang down to form a tuft. Non-nuclear fuel rods include burnable poison rods that absorb neutrons, neutron source rods that emit neutrons, thimble plugs that block the hollow guide tubes of fuel assemblies in which control rods are not used, but the present invention is in any case Since it is applicable, it is simply a non-nuclear fuel rod. Such non-nuclear fuel rods 4
5 is inserted into the control rod guide hollow tube of the fuel assembly 5. A cylindrical sleeve 47 is coaxially arranged at the center of the hollow hub 41, and the upper end thereof is fixed to the hub 41 by welding 49. An axial slot 47a is formed in the cylindrical sleeve 47 at an axially symmetrical position, and a retainer 5 to be described later is provided.
One pin 53 is inserted. The retainer 51 is an annular member with a shoulder that is loosely fitted in the cylindrical sleeve 47, and holds a coil spring 53 that surrounds the cylindrical sleeve 47 so as to extend and shorten. Since the slot 47a is for allowing the retainer 51 to be displaced in accordance with the expansion and contraction thereof, it is not necessary to extend to the upper end of the cylindrical sleeve 47 as shown in the drawing, and a predetermined stroke of the pin 53 is secured. The length is enough. The non-nuclear fuel core structure 40 is configured in this way, is installed in the core as shown in FIG. 1, and the lower surface of the retainer 51 is brought to the upper surface of the upper nozzle of the fuel assembly 5 by the elastic force of the coil spring 53. Pressing and protecting the non-nuclear fuel core structure 40 from fluid induced vibrations.
【０００８】再び図１を参照するに、上部炉心支持柱３
１の中空連通孔３７及びノズル３９の中に案内管６１が
延び、案内管６１に整列したエクステンション３９ａの
孔は、非核燃料炉心構成体４０の円筒スリーブ４７の上
端開口に整列している。案内管６１の図示しない部分
は、図示しない上部炉心支持板等を通り、図３に示すよ
うな原子炉容器の上蓋を貫通して外部に延出している。
このような案内管６１に可動中性子検出器の案内導管６
３を押し込み、挿入すれば図示のように燃料集合体５の
計装案内管１１内に入り込み、中性子検出器の炉心内挿
入が可能となる。そして、図示しない中性子検出器を炉
心内に位置決めして炉内中性子束を検出する。Referring again to FIG. 1, the upper core support column 3
A guide tube 61 extends into the hollow communication hole 37 and the nozzle 39 of No. 1, and the hole of the extension 39 a aligned with the guide tube 61 is aligned with the upper end opening of the cylindrical sleeve 47 of the non-nuclear fuel core structure 40. A portion (not shown) of the guide pipe 61 passes through an upper core support plate (not shown) and the like, penetrates the upper lid of the reactor vessel as shown in FIG. 3, and extends to the outside.
The guide pipe 6 of the movable neutron detector is attached to such a guide pipe 61.
When 3 is pushed in and inserted, it enters the instrumentation guide tube 11 of the fuel assembly 5 as shown in the figure, and the neutron detector can be inserted into the core. Then, a neutron detector (not shown) is positioned in the core to detect the neutron flux in the reactor.
【０００９】[0009]
【発明の効果】以上説明したように、本発明によれば、
原子炉炉心内に固定して使用される非核燃料炉心構成体
に炉内核計装機器を通す通路を形成し、さらに炉内上部
構造物に前記通路に整列した炉内核計装機器の案内通路
を形成したので、原子炉容器の底部に通路を設けること
なく炉心内の中性子束密度を計測できる上に、通路の破
損に伴う冷却材の流出を完全に防止でき、原子炉を安全
に運転することができる。As described above, according to the present invention,
A passage for passing nuclear reactor instrumentation equipment is formed in the non-nuclear fuel core structure that is fixedly used in the reactor core, and a guide passage for the nuclear reactor instrumentation equipment aligned with the passage is formed in the reactor upper structure. Since it was formed, it is possible to measure the neutron flux density in the core without providing a passage at the bottom of the reactor vessel, and to completely prevent the coolant from flowing out due to the breakage of the passage, and operate the reactor safely. You can
【図１】本発明の実施形態を示す部分断面図である。FIG. 1 is a partial sectional view showing an embodiment of the present invention.
【図２】前記実施形態の要部を取り出して示す一部切欠
き部分立面図である。FIG. 2 is a partially cutaway partial elevational view showing a main part of the embodiment.
【図３】従来の構造を示す全体構成図である。FIG. 3 is an overall configuration diagram showing a conventional structure.
【図４】図３の一部を拡大して示す部分概念図である。FIG. 4 is a partial conceptual diagram showing a part of FIG. 3 in an enlarged manner.
【図５】従来の構造を拡大して示す部分断面図である。FIG. 5 is an enlarged partial cross-sectional view of a conventional structure.
１ 原子炉容器本体 ５ 燃料集合体 ２９ 上部炉心支持板 ４０ 非核燃料炉心構成体 ４１ 中空ハブ ４３ ベーン ４５ 非核燃料棒 ４７ 円筒スリーブ ５１ リテーナ ５３ コイルスプリング ６１ 案内管 1 Reactor Vessel Main Body 5 Fuel Assembly 29 Upper Core Support Plate 40 Non-nuclear Fuel Core Construct 41 Hollow Hub 43 Vane 45 Non-nuclear Fuel Rod 47 Cylindrical Sleeve 51 Retainer 53 Coil Spring 61 Guide Tube
Claims (2)
合体が炉心を形成し、前記燃料集合体を上方から支持す
る上部炉心板を含む炉内上部構造物が前記原子炉容器内
の上部に設けられた加圧水型原子炉において、前記炉内
上部構造物内に前記原子炉容器の外側から前記燃料集合
体に至る炉内核計装機器の通路を形成したことを特徴と
する加圧水型原子炉。1. A plurality of fuel assemblies loaded in a reactor vessel form a core, and an in-reactor upper structure including an upper core plate for supporting the fuel assemblies from above is provided in the reactor vessel. In a pressurized water nuclear reactor provided in the upper part, a pressurized water atomic reactor characterized in that a passage of in-reactor nuclear instrumentation equipment from the outside of the reactor vessel to the fuel assembly is formed in the reactor upper structure. Furnace.
る非核燃料棒と、同非核燃料棒の先端が連結される放射
状ベーン部材及び中空ハブを有するスパイダ本体と、前
記中空ハブ内に同軸状に設けられた円筒スリーブと、前
記中空ハブ内に前記円筒スリーブを囲んで設けられたコ
イルスプリングと、同コイルスプリングを変形自在に保
持するリテーナとを有することを特徴とする加圧水型原
子炉の非核燃料炉心構成体。2. A non-nuclear fuel rod to be inserted into a hollow guide tube of a fuel assembly, a spider body having a radial vane member and a hollow hub to which tips of the non-nuclear fuel rod are connected, and a hollow hub inside the hollow hub. A pressurized water nuclear reactor comprising: a cylindrical sleeve provided coaxially, a coil spring provided inside the hollow hub so as to surround the cylindrical sleeve, and a retainer for deformably holding the coil spring. Non-nuclear fuel core structure.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP7238634A JPH0980188A (en) | 1995-09-18 | 1995-09-18 | Pressurized water reactor and its non-nuclear fuel core structure |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP7238634A JPH0980188A (en) | 1995-09-18 | 1995-09-18 | Pressurized water reactor and its non-nuclear fuel core structure |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH0980188A true JPH0980188A (en) | 1997-03-28 |
Family
ID=17033064
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP7238634A Withdrawn JPH0980188A (en) | 1995-09-18 | 1995-09-18 | Pressurized water reactor and its non-nuclear fuel core structure |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0980188A (en) |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2008108187A1 (en) | 2007-02-28 | 2008-09-12 | Mitsubishi Heavy Industries, Ltd. | Structure for suppressing flow vibration of instrumentation guide tube |
| JP2012532315A (en) * | 2009-07-01 | 2012-12-13 | ウエスチングハウス・エレクトリック・カンパニー・エルエルシー | Core performance verification method using in-core instrument |
| WO2016093488A1 (en) * | 2014-12-11 | 2016-06-16 | 한전원자력연료 주식회사 | Nuclear fuel top nozzle having in-core instrument insertion structure using upper core plate guide pin |
-
1995
- 1995-09-18 JP JP7238634A patent/JPH0980188A/en not_active Withdrawn
Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2008108187A1 (en) | 2007-02-28 | 2008-09-12 | Mitsubishi Heavy Industries, Ltd. | Structure for suppressing flow vibration of instrumentation guide tube |
| US8903032B2 (en) | 2007-02-28 | 2014-12-02 | Mitsubishi Heavy Industries, Ltd. | Structure for suppressing flow vibration of instrumentation guide tube |
| JP2012532315A (en) * | 2009-07-01 | 2012-12-13 | ウエスチングハウス・エレクトリック・カンパニー・エルエルシー | Core performance verification method using in-core instrument |
| WO2016093488A1 (en) * | 2014-12-11 | 2016-06-16 | 한전원자력연료 주식회사 | Nuclear fuel top nozzle having in-core instrument insertion structure using upper core plate guide pin |
| KR20160071551A (en) * | 2014-12-11 | 2016-06-22 | 한전원자력연료 주식회사 | Nuclear fuel assembly top nozzle having a structure of inserting an ICI utilizing an upper core plate pin |
| US10692613B2 (en) | 2014-12-11 | 2020-06-23 | Kepco Nuclear Fuel Co., Ltd. | Nuclear fuel assembly top nozzle having in-core instrument insertion structure using an upper core plate hollow guide pin |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| US7995701B2 (en) | Nuclear core component hold-down assembly | |
| US20080137799A1 (en) | Nuclear fuel assembly | |
| US4990304A (en) | Instrumentation tube features for reduction of coolant flow-induced vibration of flux thimble tube | |
| US3595748A (en) | Nuclear reactor control device | |
| KR100423739B1 (en) | Instrumented Capsule for Materials Irradiation Tests in Research Reactor | |
| KR100613581B1 (en) | Instrumented capsule for nuclear fuel irradiation test in research reactor | |
| US4778647A (en) | Vibration-damping extender for a thimble guide | |
| KR100435226B1 (en) | Non-instrumented capsule for nuclear fuel irradiation test in research reactor | |
| KR100892638B1 (en) | Top nozzle assembly having on-off holddown spring in nuclear fuel assembly | |
| KR100275299B1 (en) | Spectral shift-producing subassembly for use in a nuclaer fuel assembly | |
| US3929570A (en) | Failed fuel detection for PWR | |
| JPH0980188A (en) | Pressurized water reactor and its non-nuclear fuel core structure | |
| KR100844470B1 (en) | Top nozzle assembly having volute spring in nuclear fuel assembly | |
| KR101071416B1 (en) | Capsule for high-temperature irradiation | |
| US5100608A (en) | In-core nuclear instrumentation for fast breeder reactors | |
| US20140241486A1 (en) | Fuel assembly | |
| JPS63253292A (en) | Fixture for upper nozzle and control-rod guide thimble | |
| KR20010028839A (en) | Integral Reactor with Hollow-Cylinder Type Self-Pressurizer | |
| KR100592559B1 (en) | Remote instrumented rig device for irradiation test of nuclear fuel | |
| KR20130080349A (en) | Nuclear reactor core upper component hold-down assembly | |
| JPH0821889A (en) | Fuel assembly for fast breeder reactor | |
| JP2006126147A (en) | Core fuel assembly for liquid metal cooling fast reactor | |
| JP2022076608A (en) | Core of high speed reactor | |
| JPH05333183A (en) | Boiling water reactor | |
| SE458322B (en) | MEASURING HEAD WITH MEASURING INSTRUMENTS TO MEET THE PRESSURE OF CLIP GAS RELEASED IN A NUCLEAR BURNING ROD |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| A300 | Withdrawal of application because of no request for examination |
Free format text: JAPANESE INTERMEDIATE CODE: A300 Effective date: 20021203 |