JPH0296687A - Fast breeder reactor nuclear fuel assembly - Google Patents
Fast breeder reactor nuclear fuel assemblyInfo
- Publication number
- JPH0296687A JPH0296687A JP63247381A JP24738188A JPH0296687A JP H0296687 A JPH0296687 A JP H0296687A JP 63247381 A JP63247381 A JP 63247381A JP 24738188 A JP24738188 A JP 24738188A JP H0296687 A JPH0296687 A JP H0296687A
- Authority
- JP
- Japan
- Prior art keywords
- fuel
- particle trap
- nuclear fuel
- fuel assembly
- coolant
- 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
- 239000003758 nuclear fuel Substances 0.000 title claims description 26
- 239000000446 fuel Substances 0.000 claims abstract description 47
- 239000002245 particle Substances 0.000 claims abstract description 40
- 239000002826 coolant Substances 0.000 claims abstract description 16
- 238000003860 storage Methods 0.000 claims description 10
- 238000004904 shortening Methods 0.000 claims description 2
- 229910001220 stainless steel Inorganic materials 0.000 claims description 2
- 239000010935 stainless steel Substances 0.000 claims description 2
- 238000001514 detection method Methods 0.000 description 24
- 230000000712 assembly Effects 0.000 description 9
- 238000000429 assembly Methods 0.000 description 9
- 239000000463 material Substances 0.000 description 6
- 239000000126 substance Substances 0.000 description 5
- 239000008358 core component Substances 0.000 description 3
- 238000005192 partition Methods 0.000 description 3
- 238000005253 cladding Methods 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 2
- 206010062717 Increased upper airway secretion Diseases 0.000 description 1
- 230000005856 abnormality Effects 0.000 description 1
- 239000003795 chemical substances by application Substances 0.000 description 1
- 238000002485 combustion reaction Methods 0.000 description 1
- 238000001816 cooling Methods 0.000 description 1
- 230000003111 delayed effect Effects 0.000 description 1
- 238000011161 development Methods 0.000 description 1
- 239000012535 impurity Substances 0.000 description 1
- 229910001338 liquidmetal Inorganic materials 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 239000008188 pellet Substances 0.000 description 1
- 239000012466 permeate Substances 0.000 description 1
- 208000026435 phlegm Diseases 0.000 description 1
- 238000012827 research and development Methods 0.000 description 1
- 230000035945 sensitivity Effects 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)
Abstract
Description
【発明の詳細な説明】
[産業上の利用分野]
この発明は、液体金属冷却材を用いる高速炉用の核燃料
集合体に関するものである。DETAILED DESCRIPTION OF THE INVENTION [Industrial Application Field] This invention relates to a nuclear fuel assembly for a fast reactor using a liquid metal coolant.
[従来の技術]
高速炉は軽水炉に比べて炉心単位体積当りの出力が高い
ため2冷却材による除M能力の確保は燃料集合体の健全
性を含め、炉心安全上および運転管理上きわめて重要で
ある。[Conventional technology] Since fast reactors have higher output per core unit volume than light water reactors, securing M removal capacity with two coolants is extremely important for core safety and operational management, including the integrity of fuel assemblies. be.
特に、炉心の大型化に伴い炉心の局所的な除熱異常を高
い信頼性をもって高感度かつ早期に検出できるような破
損燃料検出システムの開発が必須となる。In particular, as the size of the reactor core increases, it is essential to develop a damaged fuel detection system that can detect local heat removal abnormalities in the core with high reliability, high sensitivity, and early on.
これらの検出システムに供するための核燃料集合体の開
発実績については経験が浅い状況下にある。従来の核燃
料集合体の例を第1図、第2図に示すが、ハンドリング
ヘッドlとエントランスノズル3の間に設けられたラッ
パ管(六角管)2内に燃料要素4を燃ネ4要素支持機構
5を介してエントランスノズル3上に正列配置して多数
本が装荷立脚される構造である。There is little experience in developing nuclear fuel assemblies for use with these detection systems. Examples of conventional nuclear fuel assemblies are shown in FIGS. 1 and 2, in which a fuel element 4 is supported in a trumpet tube (hexagonal tube) 2 provided between a handling head l and an entrance nozzle 3. It has a structure in which a large number of nozzles are loaded and placed in a regular row on the entrance nozzle 3 via a mechanism 5.
第2図で、燃料要素4はF部端栓9と下部端栓10との
間に被覆管7を接続し外殻部を形成して内部に燃料ベレ
ット8等を装荷し形成する。In FIG. 2, the fuel element 4 is formed by connecting a cladding tube 7 between an F end plug 9 and a lower end plug 10 to form an outer shell, and loading a fuel pellet 8 and the like therein.
また、各燃料要素4にはラッピングワイヤ6を施し、集
合体内でピンハンドル構成時に各燃料要素4間に均一な
る間隙を保つとともに冷却材流路を確保するべく各要素
毎に巻き付けられている。Further, each fuel element 4 is provided with a wrapping wire 6, which is wrapped around each element in order to maintain a uniform gap between each fuel element 4 and to secure a coolant flow path when forming a pin handle in the assembly.
一方、破損燃料検出装置は第3図のごとく、原子炉容器
内装荷型の構造システムが安全、検出精度および製作コ
ス)・等に関して有効であり採用段階に至っている。On the other hand, as shown in Fig. 3, the damaged fuel detection device is equipped with a structural system mounted inside the reactor vessel, which is effective in terms of safety, detection accuracy, manufacturing cost, etc., and has reached the adoption stage.
このような破損燃料検出装aは、システム本体20が細
円筒(くφ200□)形状を呈して内部にディボジッシ
ョンリング11、流量計12、遅発中性子検出器13等
の検出機構を配備するとともに、各種機能を装備して炉
上部機構上面上14に据付けられる。In such a damaged fuel detection device a, the system main body 20 has a slender cylindrical shape (φ200□), and a detection mechanism such as a diversion ring 11, a flow meter 12, a delayed neutron detector 13, etc. is provided inside. At the same time, it is equipped with various functions and installed on the top surface 14 of the furnace upper mechanism.
また、主要検出機構部である燃料破損物質捕獲用の粒子
トラップ16はその交換性、取扱性等の観点から燃料1
5(IIに配備されている。In addition, the particle trap 16 for capturing fuel-damaged substances, which is the main detection mechanism, is designed for fuel 1 from the viewpoint of replaceability and handling.
5 (deployed in II.
しかし21要検出機構部である粒子トラップ16を核燃
料集合体に組み込んだ燃料集合体の研究開発および採用
実績等については従来技術に先行例かなく、今後の開発
か急務となっている。However, there is no prior precedent in the prior art regarding the research and development and employment results of fuel assemblies in which the particle trap 16, which is the detection mechanism part 21, is incorporated into the nuclear fuel assembly, and future development is urgently needed.
[発明が解決しようとする課題]
従来の核燃料集合体は固有(独自)に燃料破損物質を捕
獲する機部を有さない構造であったか、本発明は核燃料
集合体に粒子トラップを組み込んだ破損燃料検出システ
ムを構成して検出部を除く破損燃料検出システム本体等
のflT利用利用図り、主要検出部である粒子トラップ
の交換法のfm素化および燃交設備の流用化、さらに、
固イ1に燃料破損物質を捕獲する粒子トラップ組込型核
燃料集合体を構築することを目的としている。[Problems to be Solved by the Invention] Conventional nuclear fuel assemblies have a structure that does not have an inherent (original) mechanism for capturing fuel damaged substances. Utilization of the damaged fuel detection system main body, etc. that constitutes the detection system excluding the detection part, FM standardization of the replacement method of the particle trap, which is the main detection part, and reuse of the combustion equipment,
The purpose of this study is to construct a nuclear fuel assembly with a built-in particle trap that captures fuel-damaged substances.
し課題を解決するためのf段]
核燃料集合体内の燃料要素ピンバンドル上端(冷却材流
下流側)に必要となるNa透過表面積を有した粒子トラ
ップを配備して粒子トラップ部はその取扱、交換性を踏
え外殻部を形成する収納筒内に装備するとともに、燃料
要素の短尺化を避けるため1粒子トラップな細径ピンバ
ンドル構成にて形成する。[F stage to solve the problem] A particle trap with the necessary Na permeation surface area is installed at the upper end of the fuel element pin bundle (downstream side of the coolant flow) in the nuclear fuel assembly, and the particle trap section is handled and replaced. Considering the nature of the fuel element, it is installed in the storage cylinder that forms the outer shell, and in order to avoid shortening the fuel element, it is formed with a small diameter pin bundle configuration that is a single particle trap.
また、粒子トラップ収納筒は核燃料集合体頂部のハンド
リングヘッドにボルトまたは固定ピン等にて着脱容易に
取付けられる構造とし、併せて燃料要素ピンの核熱特性
および粒子トラップ閉塞(目詰まり)事象を踏えて冷却
材バイパス流路孔な収納筒上端近傍に周方向複数配備す
る構成とする。In addition, the particle trap storage cylinder has a structure that allows it to be easily attached to and removed from the handling head at the top of the nuclear fuel assembly using bolts or fixing pins. In addition, a plurality of coolant bypass passage holes are arranged in the circumferential direction near the upper end of the storage cylinder.
[作用1
従来の核燃料集合体は固有(独自)に燃料破損物質を捕
獲する機ス七を有さない構造であったが。[Effect 1 Conventional nuclear fuel assemblies have a structure that does not have an inherent (original) mechanism to capture fuel-damaged substances.
L記の構成により粒子トラップ(中空円筒形状のSUS
焼結体)を配備することにより、燃料要素破損時におけ
る破損物質を独自に捕獲する機能を有することができる
。併せてこれらは、原子炉容器内への破相物賀の放出を
防止・抑ル1することかできる。The particle trap (hollow cylindrical SUS
By deploying a sintered body (sintered body), it is possible to have the function of uniquely capturing damaged materials when a fuel element breaks. Together, these can prevent and suppress the release of phlegm into the reactor vessel.
燃料側粒子トラップ組込型破損燃料検出システムにおい
て、その主要検出部の粒子トラップが燃料側に配備可能
となることにより、検出システムの成立性が得られると
ともに、検出部を除く破損燃料検出システム本体等の再
利用を図ることかできる。In a damaged fuel detection system with a built-in particle trap on the fuel side, the particle trap, which is the main detection part, can be installed on the fuel side, which makes the detection system viable, and the main part of the damaged fuel detection system excluding the detection part can be installed on the fuel side. It is possible to reuse such items.
さらに、核燃料集合体側に主要な検出部の粒子トラップ
を装備したため、粒子トラップの交換法はきわめて簡便
となり、通常の炉心構成要素の燃料交換ルートにて対応
可能となり、サイト内取扱設備をそのまま流用すること
かできるとともに3破損燃料検出波行と独立に取り扱え
るのて破損燃料検出装置は炉」一部機構上面上に据付け
たままで粒子トラップの交換が行える。Furthermore, since the particle trap for the main detection part is installed on the nuclear fuel assembly side, particle trap replacement is extremely simple and can be done through the normal fuel exchange route for core components, allowing on-site handling equipment to be used as is. In addition to being able to handle the three damaged fuel detection waves independently, the particle trap can be replaced while the damaged fuel detection device is installed on top of the furnace mechanism.
[実施例]
第4図はこの発明の粒子トラップを内蔵した核燃料集合
体を示すもので粒子トラップ16(例えば中空円筒形状
のSUS焼結体)を、別途実施した水流動試験の結果を
反映して多柱状配列、この例では7本ピンバンドル構成
とし、その外側に一括収納を図るとともに核燃料集合体
内に取付・離脱が容易に図れる収納筒17を外殻部にし
て一体的に形成されている。[Example] Fig. 4 shows a nuclear fuel assembly incorporating a particle trap of the present invention, in which the particle trap 16 (for example, a hollow cylindrical SUS sintered body) was prepared based on the results of a water flow test conducted separately. The pins are arranged in a multi-column arrangement, in this example a 7-pin bundle configuration, and are integrally formed with a storage cylinder 17 as an outer shell that can be stored all at once on the outside and can be easily installed and removed from the nuclear fuel assembly. .
これらの粒子トラップ16は核燃料集合体の外殻部を形
成するハンドリングヘッド1、ラッパ管(六角管)2.
エントランスノズル3内に収納された燃料要素4上に配
備され4上端部を形成するハンドリングへ・ンド1の内
面下端に固定ピン21にて着脱容易に取付けられ一体化
されている。These particle traps 16 include a handling head 1, a wrapper tube (hexagonal tube) 2.
The fuel element 4 is disposed on the fuel element 4 housed in the entrance nozzle 3, and is easily attached to and integrated with the lower end of the inner surface of the handling end 1 forming the upper end of the fuel element 4 with a fixing pin 21.
また、冷却材18の流路としては1粒子トラップ下端内
面な開孔状態にし、上端に盲栓を施して下方内面より流
入した冷却材18が外面に透過するIN→OUT方向の
流路を形成しており、これらは引抜交換時におけるN、
lりの防止構造対応となっている。併せて収納筒17の
上端部には燃料要素4の健全性(除熱)を図るためにバ
イパス流路孔22.この例ては6か所を第5図のごとく
、円周上に配備するとともに下端部にはN、トレン孔2
3を周方向に数か所配備した構造となっている。In addition, the flow path for the coolant 18 is made open on the inner surface of the lower end of the single particle trap, and a blind plug is provided at the upper end to form a flow path in the IN→OUT direction through which the coolant 18 flowing from the lower inner surface permeates to the outer surface. These are N at the time of withdrawal and replacement,
It has a structure that prevents leakage. In addition, a bypass passage hole 22 is provided at the upper end of the storage cylinder 17 to ensure the integrity (heat removal) of the fuel element 4. In this example, as shown in Figure 5, six locations are arranged on the circumference, and the bottom end is N and two train holes are arranged.
3 are arranged in several places in the circumferential direction.
第5図は第4図のA−A部の断面を示し、粒子トラップ
16の収納筒17上端近傍の冷却材流路孔の配置状況を
示すものである。FIG. 5 shows a cross section taken along the line AA in FIG. 4, and shows the arrangement of the coolant passage holes near the upper end of the storage tube 17 of the particle trap 16.
第6図は第4図のB−B部の断面を示し、粒子トラップ
16、収納筒17.ラッパ管2および冷却材流路18等
の配置状況を示すものである。FIG. 6 shows a cross section taken along the line B-B in FIG. 4, showing the particle trap 16, storage tube 17. It shows the arrangement of the wrapper tube 2, the coolant flow path 18, and the like.
第7図〜第10図は粒子トラップ16の異なる構造例を
示し、第7図は流路分岐型、第8図は二重円筒型、第9
図は仕切板19装備型の例1.第1O図は仕切板19装
置il型の例2を示す装荷構造の部分Jl断面図である
。7 to 10 show different structural examples of the particle trap 16, in which FIG. 7 is a branched flow path type, FIG. 8 is a double cylindrical type, and FIG.
The figure shows example 1 of the type equipped with a partition plate 19. FIG. 1O is a sectional view of part Jl of the loading structure showing Example 2 of the partition plate 19 device il type.
このように構成された核燃料集合体は第3図に示す原子
炉容器内装荷型破損燃料検出装置のシステム構成を満足
させることができるとともに燃料要素破損時における破
損物質を独自に捕獲する機teを有し、併せて原子炉容
器内への破損物質の放出を防止・抑制することが可能と
なる。The nuclear fuel assembly configured in this manner can satisfy the system configuration of the damaged fuel detection device loaded inside the reactor vessel shown in Fig. 3, and also has the ability to independently capture damaged materials when a fuel element breaks. At the same time, it is possible to prevent and suppress the release of damaged materials into the reactor vessel.
また1粒子トラップの交換に際しては、破損燃料検出装
置本体に関係なく1通常の炉心構成要素の燃料交換ルー
トにて対応可能となり、その取扱はきわめて簡便となる
とともにサイト内取扱設備をそのまま流用することがで
きる。これはサイト内ハンドリング操作を含む燃料取扱
設備の繁雑・増大化を防ぐことかできるとともにプラン
ト稼動率の向上を併せて図ることができる。In addition, when replacing a single particle trap, it is possible to replace the fuel by using the normal core component fuel exchange route regardless of the damaged fuel detection device itself, making the handling extremely simple and allowing the on-site handling equipment to be used as is. Can be done. This can prevent the complexity and increase of fuel handling equipment, including on-site handling operations, and can also improve plant operating efficiency.
なお2粒子トラップ16は燃料要素頂部側に配備するだ
けでなく、下部(下端)側にも併設、すなわち、エント
ランスノズル3上端に装荷して炉内および核燃料集合体
内に流入する冷却材不純物を捕獲する構造とすることも
できる。The two-particle trap 16 is not only installed on the top side of the fuel element, but also on the bottom (lower end) side, that is, it is loaded on the top end of the entrance nozzle 3 to capture coolant impurities flowing into the reactor and nuclear fuel assembly. It is also possible to have a structure where
上述するような粒子トラップ16を内蔵した核燃料集合
体の他に別案として、燃料要素の被覆管部に粒子トラッ
プとして中空円筒形状を呈したステンレス鋼焼結体を直
接用いるJll造とすることもできる。In addition to the above-mentioned nuclear fuel assembly incorporating the particle trap 16, as an alternative, a Jll structure may be used in which a stainless steel sintered body having a hollow cylindrical shape is directly used as a particle trap in the cladding section of the fuel element. can.
[発明の効果]
以上説明したとおり、従来の核燃料集合体は独自(固有
)に燃料破損物質を捕獲する機部を有さない構造であっ
たが、本発明は粒子トラップを配備することにより、燃
料要素破損時における破損物質を独自に捕獲する機能を
有することができる。[Effects of the Invention] As explained above, conventional nuclear fuel assemblies do not have a structure that uniquely (inherently) captures fuel-damaged substances, but the present invention provides particle traps to It can have the ability to uniquely capture damaged materials in the event of fuel element failure.
また、これらは、a子炉容器内への破損物質の放出を防
止・抑制して原子炉の安全性の向上に有効であり、さら
に粒子トラップおよび核燃料集合体の交換に際しては、
破損燃料検出装置本体に関係なく、通常の炉心構成要素
の燃料交換ルートにて対応回部となり、その取扱法はき
わめて簡便となるとともにサイト内取扱設備をそのまま
流用することができる。これらはサイト内ハンドリング
操作における建家を含む燃料取扱設備の繁雑・増大化を
防ぐことができる。In addition, these are effective in preventing and suppressing the release of damaged materials into the A reactor vessel and improving the safety of the reactor.Furthermore, when replacing particle traps and nuclear fuel assemblies,
Regardless of the main body of the damaged fuel detection system, it can be handled through the normal refueling route for core components, making its handling extremely simple and allowing on-site handling equipment to be used as is. These can prevent the complexity and expansion of fuel handling equipment, including buildings, during on-site handling operations.
第1図は従来の核燃料集合体の一例を示す斜視図、第2
図は第F図における燃料要素部分の詳細を示す斜視図、
第3図は原子炉容器内装荷型破損燃料検出!It22の
具体的構造の一例を示す縦断面図、第4図はこの発明の
粒子トラップを組込んだ核燃料集合体の縦断面図、第5
図は第4図のA−A部断面であり粒子トラップ収納筒上
端近傍の冷却材流路孔の配置状況を示す図、i6図は第
4図のB−B部断面であり粒子トラップおよび冷却材流
路等の配置状況を示す図、第7図、第8図、第9図、第
1O図はこの発明の核燃料集合体であって第4図に示す
粒子トラップ構造とは異なる構造を示す部分縦断面図で
ある。
図中。
l:ハンドリングヘッド
2ニラツバ管
3:エントランスノズル
4:燃料要素
16:粒子トラップ
17:収納筒
18:冷却材
19:仕切板
代理人 弁理士 1)北 嵩 晴
第
図
第
図
第
図
竿
閏
第
図Figure 1 is a perspective view showing an example of a conventional nuclear fuel assembly;
The figure is a perspective view showing details of the fuel element portion in Figure F;
Figure 3 shows the detection of damaged fuel loaded inside the reactor vessel! FIG. 4 is a vertical cross-sectional view showing an example of the specific structure of It22, FIG. 4 is a vertical cross-sectional view of a nuclear fuel assembly incorporating the particle trap of the present invention, and FIG.
The figure is a cross section taken along line A-A in Figure 4, and shows the layout of the coolant passage holes near the upper end of the particle trap storage cylinder. Figure i6 is a cross section taken along line B-B in Figure 4, showing the particle trap and cooling. Figures 7, 8, 9, and 10 showing the arrangement of material flow paths, etc. are nuclear fuel assemblies of the present invention, and show structures different from the particle trap structure shown in Figure 4. It is a partial vertical cross-sectional view. In the figure. l: Handling head 2 Niratsuba tube 3: Entrance nozzle 4: Fuel element 16: Particle trap 17: Storage tube 18: Coolant 19: Partition plate agent Patent attorney 1) Haru Kitatake
Claims (3)
状を呈したステンレス鋼焼結体の粒子トラップを複数本
多柱状に正列配置してピンバンドル構成とした粒子トラ
ップを核燃料集合体内の燃料要素上方およびハンドリン
グヘッド下方に介在装備したことを特徴とする核燃料集
合体。(1) In order to avoid shortening of fuel element pins, particle traps made of hollow cylindrical stainless steel sintered bodies are arranged in regular rows in a multi-column configuration to form a pin bundle structure. A nuclear fuel assembly characterized by intervening equipment above a fuel element and below a handling head.
子トラップをエントランスノズル上端に併設装備した高
速炉用核燃料集合体。(2) A nuclear fuel assembly for a fast reactor according to claim (1), which is equipped with a particle trap at the upper end of the entrance nozzle.
子トラップの外周部にそれを一括収納する収納筒を配備
形成するとともに、その上下端部には冷却材の流路確保
およびN_a溜りを考慮した冷却材流路孔を複数円周上
に設けたことを特徴とする高速炉用核燃料集合体。(3) In the nuclear fuel assembly according to claim (1), a storage cylinder for collectively storing the particle trap is provided on the outer periphery of the particle trap, and a flow path for the coolant is secured and an N_a reservoir is provided at the upper and lower ends of the particle trap. A nuclear fuel assembly for a fast reactor, characterized in that a plurality of coolant flow passage holes are provided on the circumference in consideration of the above.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP63247381A JPH0769445B2 (en) | 1988-10-03 | 1988-10-03 | Nuclear fuel assembly for fast reactor |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP63247381A JPH0769445B2 (en) | 1988-10-03 | 1988-10-03 | Nuclear fuel assembly for fast reactor |
Publications (2)
Publication Number | Publication Date |
---|---|
JPH0296687A true JPH0296687A (en) | 1990-04-09 |
JPH0769445B2 JPH0769445B2 (en) | 1995-07-31 |
Family
ID=17162584
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP63247381A Expired - Fee Related JPH0769445B2 (en) | 1988-10-03 | 1988-10-03 | Nuclear fuel assembly for fast reactor |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPH0769445B2 (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2013507631A (en) * | 2009-10-16 | 2013-03-04 | コミッサリア ア レネルジー アトミーク エ オ ゼネルジ ザルタナテイヴ | Nuclear fuel assemblies and nuclear reactors comprising such assemblies |
-
1988
- 1988-10-03 JP JP63247381A patent/JPH0769445B2/en not_active Expired - Fee Related
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2013507631A (en) * | 2009-10-16 | 2013-03-04 | コミッサリア ア レネルジー アトミーク エ オ ゼネルジ ザルタナテイヴ | Nuclear fuel assemblies and nuclear reactors comprising such assemblies |
Also Published As
Publication number | Publication date |
---|---|
JPH0769445B2 (en) | 1995-07-31 |
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