JPS6125109B2 - - Google Patents
Info
- Publication number
- JPS6125109B2 JPS6125109B2 JP53107183A JP10718378A JPS6125109B2 JP S6125109 B2 JPS6125109 B2 JP S6125109B2 JP 53107183 A JP53107183 A JP 53107183A JP 10718378 A JP10718378 A JP 10718378A JP S6125109 B2 JPS6125109 B2 JP S6125109B2
- Authority
- JP
- Japan
- Prior art keywords
- core
- fuel assembly
- rectifying
- tube
- grid
- 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 30
- 239000002826 coolant Substances 0.000 claims description 16
- 229910001338 liquidmetal Inorganic materials 0.000 claims description 9
- 230000000712 assembly Effects 0.000 claims description 5
- 238000000429 assembly Methods 0.000 claims description 5
- 239000007788 liquid Substances 0.000 claims description 4
- 239000003758 nuclear fuel Substances 0.000 claims 1
- 238000000926 separation method Methods 0.000 description 3
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 description 2
- 230000005856 abnormality Effects 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 238000004519 manufacturing process Methods 0.000 description 2
- 229910052708 sodium Inorganic materials 0.000 description 2
- 239000011734 sodium Substances 0.000 description 2
- 238000003466 welding Methods 0.000 description 2
- 238000005452 bending Methods 0.000 description 1
- 238000005259 measurement Methods 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 238000012544 monitoring process Methods 0.000 description 1
- 238000005070 sampling Methods 0.000 description 1
- 230000007847 structural defect Effects 0.000 description 1
- 230000008961 swelling 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)
Description
【発明の詳細な説明】
本発明は液体金属冷却高速炉炉心上部機構に関
する。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a liquid metal cooled fast reactor core upper structure.
液体金属冷却高速炉の炉容器内部の構造の概略
は第1図に示す通りである。同図において、炉容
器1には下部に液体金属入口ノズル2、中央部に
出口ノズル3が設けられている。炉容器1の下部
には炉心燃料集合体4と、それをとり巻くブラン
ケツト集合体5、反射体6および制御棒7等が配
列されている。これらの集合体等は炉構造物8に
よつて支持されており、炉心構造物8には冷却材
である液体金属の通路が形成されている。 The structure inside the reactor vessel of a liquid metal cooled fast reactor is schematically shown in FIG. In the figure, a furnace vessel 1 is provided with a liquid metal inlet nozzle 2 at the bottom and an outlet nozzle 3 at the center. In the lower part of the reactor vessel 1, a core fuel assembly 4, a blanket assembly 5 surrounding it, a reflector 6, a control rod 7, etc. are arranged. These assemblies and the like are supported by a reactor structure 8, and a passage for liquid metal, which is a coolant, is formed in the reactor core structure 8.
炉容器1の上部には炉心上部機構9が回転プラ
グ10を介して取付けられている。炉心上部機構
9の下部は第2図にその構造の概略が示されてい
る。すなわち同図において、炉心上部機構9の下
部は整流格子17、制御棒案内管16熱遮へい板
14、炉内計装用ウエル15等から構成されてい
る。炉容器1は炉心構造物8および燃料集合体4
によつて上部プレナム12と下部プレナム13と
に分れ、液体金属の液面近くにはデイツププレー
ト11が配置されている(第1図参照)。 A core upper mechanism 9 is attached to the upper part of the reactor vessel 1 via a rotating plug 10 . The structure of the lower part of the core upper mechanism 9 is schematically shown in FIG. That is, in the figure, the lower part of the upper core mechanism 9 is composed of a rectifying grid 17, a control rod guide tube 16, a heat shield plate 14, an in-core instrumentation well 15, and the like. The reactor vessel 1 includes a core structure 8 and a fuel assembly 4
The plenum is divided into an upper plenum 12 and a lower plenum 13, and a dip plate 11 is disposed near the liquid metal surface (see FIG. 1).
冷却材としては通常液体ナトリウムが用いられ
る。冷却材は炉容器1の入口ノズル2から下部プ
レナム13に流入し、炉心構造物8に設けられた
通路によつて各燃料集合体4に流量配分され、各
燃料集合体4において発生した熱を吸収する。熱
を吸収して高温となつた液体ナトリウムは燃料集
合体4の上部から流出し、整流格子17を通過
し、炉心上部機構9のその他の下部構成物を横切
つて上部プレナム12に放射状に流出し、さらに
上部プレナム12から出口ノズル3を経て炉容器
1に取出される。 Liquid sodium is usually used as a coolant. The coolant flows into the lower plenum 13 from the inlet nozzle 2 of the reactor vessel 1, and is distributed in flow to each fuel assembly 4 by passages provided in the core structure 8, dissipating the heat generated in each fuel assembly 4. Absorb. The liquid sodium, which has become high temperature by absorbing heat, flows out from the upper part of the fuel assembly 4, passes through the straightening grid 17, crosses other lower components of the upper core mechanism 9, and flows out radially into the upper plenum 12. It is then taken out from the upper plenum 12 through the outlet nozzle 3 into the furnace vessel 1 .
炉心上部機構9の下部に各燃料集合体4に対応
して配置される炉内計装機器は、高速炉の運転中
における各炉心燃料集合体4における冷却材の流
動状態、燃料ピンの異状および破損の測定、検出
を目的としている。 The in-core instrumentation equipment arranged in the lower part of the upper core mechanism 9 corresponding to each fuel assembly 4 monitors the flow state of the coolant in each core fuel assembly 4, abnormalities in fuel pins, and the like during operation of the fast reactor. The purpose is to measure and detect damage.
炉内計装機器の先端部は、温度計、流量計のセ
ンサ、FDD(燃料破損検出器)のサンプリング
ノズル等が一体となつて構成され、センサ等が挿
入されている部分が炉内計装ウエル15となつて
整流格子17の筒部分の中央に来るように配置さ
れている(第2図参照)。 The tip of the in-core instrumentation equipment is composed of a thermometer, flowmeter sensor, FDD (fuel failure detector) sampling nozzle, etc., and the part where the sensors are inserted is the in-core instrumentation. The well 15 is arranged at the center of the cylindrical portion of the rectifying grid 17 (see FIG. 2).
高速炉を安全に効率よく運転するためには、炉
心の各燃料集合体4に対応して配置する炉内計装
機器によつて、燃料集合体4の個個の運転状況、
異常等の情報を正確に得る必要がある。 In order to operate a fast reactor safely and efficiently, in-core instrumentation equipment placed corresponding to each fuel assembly 4 in the reactor core is used to monitor the operating status of each fuel assembly 4,
It is necessary to obtain accurate information on abnormalities, etc.
炉心上部機構9の下部に配置される整流格子1
7は、炉内計装機器の上記した必要な機能を維持
するため、燃料集合体4から流出した冷却材を整
流する機能と(整流機能)、隣接する燃料集合体
4の相互間の冷却材の混合等による相互干渉を防
止する機能(分離機能)とを併せ有しなければな
らない。 Rectifier grid 1 placed at the bottom of core upper mechanism 9
7 has a function of rectifying the coolant flowing out from the fuel assembly 4 (straightening function) and a function of rectifying the coolant between adjacent fuel assemblies 4 in order to maintain the above-mentioned necessary functions of the in-core instrumentation equipment. It must also have a function (separation function) to prevent mutual interference due to mixing, etc.
整流格子17はその分離機能上は、その下端を
なるべく燃料集合体4に近接させることが望まし
いが、スエリング、熱膨脹等のため燃料集合体4
の高さが不ぞろいとなるため、50mm程度は間隔を
あける必要がある。 It is desirable for the lower end of the rectifying grid 17 to be as close to the fuel assembly 4 as possible in terms of its separation function; however, due to swelling, thermal expansion, etc.
Since the heights of the two will be uneven, it is necessary to leave an interval of about 50 mm.
第3図は従来の炉心上部機構9における整流格
子17の代表的な例を示したものであり、aは平
面図、bは断面図である。同図において、燃料集
合体4の出口孔より小さい孔径の円管状の整流筒
19の上端および下端には、各6ケ所宛のスリツ
ト19Aが設けられており、該スリツト19Aに
保持板18を挿入して多数の整流筒19の相互同
志を結合した後、要部を溶接して整流格子17を
構成している。 FIG. 3 shows a typical example of the rectifying grid 17 in the conventional upper core mechanism 9, in which a is a plan view and b is a cross-sectional view. In the figure, slits 19A are provided at six locations at each of the upper and lower ends of a cylindrical straightening tube 19 with a hole diameter smaller than the outlet hole of the fuel assembly 4, and the holding plate 18 is inserted into the slits 19A. After a large number of rectifier cylinders 19 are connected to each other, the main parts are welded to form a rectifier grid 17.
整流筒19の径は炉心上部の冷却材の流動状況
から、前記した整流機能、分離機能を考慮して定
められるが、図示(第3図)したように多数の整
流筒19を多数の保持板18によつて結合してあ
るので構造が複雑であり、溶接に際しての熱歪に
よる変形、構成上の不具合等の理由によつて、多
くの数の燃料集合体4に対して対応する整流筒1
9を同軸となるように位置の精度を維持して操作
することは至難の業であり、整流格子17は分離
機能に欠ける憾みがあつた。 The diameter of the straightening tubes 19 is determined from the flow condition of the coolant in the upper part of the core, taking into account the above-mentioned straightening function and separation function. 18, the structure is complicated, and due to reasons such as deformation due to thermal strain during welding and structural defects, the rectifier cylinder 1 corresponding to a large number of fuel assemblies 4 has a complicated structure.
It is extremely difficult to operate the rectifying grid 9 coaxially while maintaining positional accuracy, and the rectifying grid 17 lacks a separating function.
本発明は従来の整流格子の以上述べた欠点を解
消し、高速炉運転中の炉心における燃料集合体の
個々の動作状況を炉内計測機器で正確に測定監視
するため、各燃料集合体の出口における冷却材に
対し、整流機能および分離機能を維持し、しかも
製作が容易で対応する燃料集合体と一対した軸心
を有する整流格子を備えた炉心上部機構を提供す
ることを目的としている。 The present invention solves the above-mentioned drawbacks of the conventional rectifying grid, and enables accurate measurement and monitoring of the operating status of each fuel assembly in the reactor core during fast reactor operation using in-core measuring equipment. It is an object of the present invention to provide an upper core mechanism that maintains a rectifying function and a separating function for coolant in a reactor, is easy to manufacture, and is equipped with a rectifying grid having axes aligned with the corresponding fuel assemblies.
以下図面に基いて本発明の実施例について説明
する。第4図a〜fは本発明に係る整流格子の一
例を示したものであり、aおよびbはその組立方
法を示した図、cは組立後の構成を示した平面
図、dは断面図、eは一部を拡大した平面図、f
は同じく拡大した断面図である。 Embodiments of the present invention will be described below based on the drawings. Figures 4a to 4f show an example of a rectifying grid according to the present invention, where a and b are views showing the method of assembling the same, c is a plan view showing the configuration after assembly, and d is a sectional view. , e is a partially enlarged plan view, f
is a similarly enlarged cross-sectional view.
同図において、整流格子17は複数個の円管状
の整流筒19と、整流筒19の外円周に外接する
複数個の中空六角柱状の整流筒支持具20とから
ハニカム状に構成されている。整流筒支持具20
はa図に示すように、中空六角柱を別個に作つて
それらを集め、要部を溶接して構成するか、また
はb図に示すように、薄板を梯形の連続した形に
折り曲げ加工した後、中空六角柱状になるように
寄せ集めて要部を溶接して構成する。いずれの場
合においてもハニカムを構成する各六角柱の大き
さを、燃料集合体4の大きさの半分としているの
でc図に示すように、ハニカムの各中空六角柱の
1つおきに整流筒19を挿入すれば、前記したよ
うに整流筒19の外円周が中空六角柱に内接して
いるため、整流筒19は整流筒支持具20によつ
て支持され、またそのピツチは燃料集合体4のピ
ツチと一致し、両者の芯合わせはきわめて容易に
行なうことができる。 In the figure, the rectifying grid 17 is configured in a honeycomb shape from a plurality of cylindrical rectifying cylinders 19 and a plurality of hollow hexagonal columnar rectifying cylinder supports 20 circumscribing the outer circumference of the rectifying cylinders 19. . Rectifier cylinder support 20
As shown in figure a, hollow hexagonal columns are made separately, assembled and the main parts are welded together, or as shown in figure b, after bending a thin plate into a continuous trapezoid shape. It is constructed by assembling it into a hollow hexagonal column shape and welding the main parts. In either case, the size of each hexagonal column constituting the honeycomb is half the size of the fuel assembly 4, so as shown in Figure c, every other hollow hexagonal column of the honeycomb has a rectifying tube 19. As described above, since the outer circumference of the straightening tube 19 is inscribed in the hollow hexagonal column, the straightening tube 19 is supported by the straightening tube support 20, and its pitch is aligned with the fuel assembly 4. The pitch of the two matches, and alignment of the two can be done extremely easily.
各整流筒19の上部からは炉内計装ウエル15
が挿入されているが、燃料集合体4ね軸心と整流
筒19の軸心とが一致しているので、各燃料集合
体4中を流れる冷却材の主流が対応する整流筒1
9内に流れ込み、隣接する燃料集合体4中を流れ
る冷却材の主流が対応する整流筒19内に流れ込
み、隣接する燃料集合体4からの冷却材が混入す
るおそれがないため、炉内計装ウエル15に設け
られた各計装機器の先端センサは確実に対応する
燃料集合体4の運転状況等の情報を捕えることが
できる。 The in-furnace instrumentation well 15 is connected from the top of each straightening tube 19.
are inserted, but since the axis of the fuel assembly 4 and the axis of the straightening tube 19 are aligned, the main flow of the coolant flowing through each fuel assembly 4 is directed to the corresponding straightening tube 1.
The main flow of the coolant flowing into the fuel assembly 9 and the adjacent fuel assembly 4 flows into the corresponding straightening tube 19, and there is no risk of the coolant from the adjacent fuel assembly 4 getting mixed in, so the in-core instrumentation The tip sensors of each instrumentation device provided in the well 15 can reliably capture information such as the operating status of the corresponding fuel assembly 4.
第5図は本発明の第2の実施例を示したもので
aは拡大平面図、bはその断面図である。前記実
施例にあつては、1個の整流筒支持具20が整流
筒19の中央部で整流筒19を支持していたが、
本実施例であつては、2個の整流筒支持具20
が、整流筒19の上端部と下端部において支持し
ており、前記例にくらべて、一層確実で正確に支
持することが可能である。 FIG. 5 shows a second embodiment of the present invention, in which a is an enlarged plan view and b is a sectional view thereof. In the embodiment described above, one straightening tube support 20 supported the straightening tube 19 at the center of the straightening tube 19.
In this embodiment, two rectifier tube supports 20
is supported at the upper end and lower end of the rectifying tube 19, and it is possible to support it more reliably and accurately than in the above example.
第6図は本発明の第3の実施例を示したもので
aは断面を含む平面図、bは断面を含む平面図で
ある。前記2つの実施例では、計装ウエル15の
下端は整流筒19内に挿入されているが、整流筒
19によつて支持されていない自由端となつてい
た。整流格子17内を流れる冷却材の流れは、炉
心上部機構9の影響によつて対称的な流れでな
く、非対称的な流れとなつているが、このため、
各燃料集合体4内の冷却材の流動状態を正確に知
るためには、計装ウエル15が整流筒19と同軸
に配置されていることが肝要である。このため本
実施例にあつては、整流筒19の内周に計装ウエ
ル保持具22が設けられ、計装ウエル15を整流
筒19の中心で正確にかつ確実に保持している。
したがつて本実施例では整流筒19と計装ウエル
15とが軸心が正確に一致し、計装精度が向上す
る。 FIG. 6 shows a third embodiment of the present invention, in which a is a plan view including a cross section, and b is a plan view including a cross section. In the two embodiments described above, the lower end of the instrumentation well 15 was inserted into the rectifier tube 19, but was a free end not supported by the rectifier tube 19. The flow of coolant flowing within the straightening grid 17 is not a symmetrical flow but an asymmetrical flow due to the influence of the upper core mechanism 9.
In order to accurately know the flow state of the coolant in each fuel assembly 4, it is important that the instrumentation well 15 is arranged coaxially with the rectifier tube 19. For this reason, in this embodiment, an instrumentation well holder 22 is provided on the inner periphery of the rectifying tube 19 to accurately and reliably hold the instrumentation well 15 at the center of the rectifying tube 19.
Therefore, in this embodiment, the axes of the rectifier tube 19 and the instrumentation well 15 are precisely aligned, improving instrumentation accuracy.
また計装ウエル15は炉心上部機構9に設けら
れた支持板21にその上端を固定されているが、
固定部分から下端までは通常1m以上もあり、一
方冷却材が整流格子17を通過した後は、熱遮へ
い板14に沿つて計装ウエル15を横切つて流れ
るため、場合によつては計装ウエル15は冷却材
の流動によつて振動を起こすおそれがあり、それ
によつて計装ウエル15が疲労破壊を招く懸念が
あるが、本例にあつては計装ウエル15の下端が
整流筒19に確実に保持されているためその懸念
を無くすことができる。 Furthermore, the upper end of the instrumentation well 15 is fixed to a support plate 21 provided in the upper core mechanism 9.
The distance from the fixed part to the lower end is usually 1 m or more, and on the other hand, after the coolant passes through the rectifier grid 17, it flows along the heat shield plate 14 and across the instrumentation well 15, so in some cases, the instrumentation There is a risk that the well 15 may vibrate due to the flow of coolant, which may cause fatigue failure of the instrumentation well 15, but in this example, the lower end of the instrumentation well 15 is connected to the rectifier tube 19. This concern can be eliminated because it is reliably maintained.
本発明は以上述べたように確実な整流機能と分
離機能を有する整流格子を具えた液体金属冷却高
速炉炉心上部機構を提供し、炉内計装機器によ
り、精度よく確実に各燃料集合体における運転状
況等の把握を可能とすると共に、炉心上部機構の
製作が比較的容易であり、液体金属冷却高速炉の
安全確保、性能向上、原価低減に資することは極
めて大である。 As described above, the present invention provides a liquid metal cooled fast reactor upper core mechanism equipped with a rectifying grid having a reliable rectifying function and a separating function. In addition to making it possible to understand the operating status, etc., the fabrication of the upper core mechanism is relatively easy, and it greatly contributes to ensuring the safety, improving performance, and reducing costs of liquid metal cooled fast reactors.
第1図は液体金属冷却高速炉の炉容器内部の概
略の構造を示す図、第2図炉心上部機構下部の構
造の概略を示す図、第3図は従来の炉心上部機構
における整流格子の代表例を示した図、第4図a
〜fは本発明に係る整流格子の第1の実施例を示
す図、第5図、第6図はそれぞれ本発明に係る整
流格子の第2および第3の実施例を示す図であ
る。
1……炉容器、4……燃料集合体、8……炉心
構造物、9……炉心上部構造、15……炉内計装
ウエル、17……整流格子、19……整流筒、2
0……整流筒支持具、21……支持板、22……
ウエル保持具。
Figure 1 shows the general structure inside the reactor vessel of a liquid metal cooled fast reactor, Figure 2 shows the outline of the structure of the lower part of the upper core mechanism, and Figure 3 is a representative of the rectifying grid in the conventional upper core mechanism. Illustration showing an example, Figure 4a
-f are diagrams showing a first embodiment of the rectifying grating according to the present invention, and FIGS. 5 and 6 are diagrams showing second and third embodiments of the rectifying grating according to the present invention, respectively. DESCRIPTION OF SYMBOLS 1... Reactor vessel, 4... Fuel assembly, 8... Core structure, 9... Core upper structure, 15... In-core instrumentation well, 17... Rectifier grid, 19... Rectifier tube, 2
0... Rectifier tube supporter, 21... Support plate, 22...
Well holder.
Claims (1)
され、複数個の円管状の整流筒とこの整流筒の外
円周に外接する複数個の中空六角柱状の整流筒支
持具とより成りこの中空六角柱の外径が前記燃料
集合体の外径の2分の1であるハニカム状の整流
格子を有する液体金属冷却高速炉炉心上部機構。 2 前記ハニカム状の整流格子が、その一の整流
筒には対応する一の燃料集合体から流出した冷却
材が選択的に流れるように配設されている特許請
求の範囲第1項記載の液体金属冷却高速炉炉心上
部機構。 3 前記ハニカム状整流格子の整流筒内周に、整
流筒内に挿入された計装ウエルの先端を保持する
計装ウエル保持具を設けた特許請求の範囲第1項
または第2項記載の液体金属冷却高速炉炉心上部
機構。[Scope of Claims] 1. A plurality of cylindrical rectifier tubes and a plurality of hollow hexagonal columnar rectifier tube supports circumscribing the outer circumference of the rectifier tubes, which are installed on the upper part of nuclear fuel assemblies arranged in the reactor core. A liquid metal cooled fast reactor upper core mechanism having a honeycomb-shaped rectifying grid consisting of a hollow hexagonal column having an outer diameter that is one-half of the outer diameter of the fuel assembly. 2. The liquid according to claim 1, wherein the honeycomb-shaped rectifying grid is arranged so that the coolant flowing out from the corresponding one fuel assembly selectively flows into one of the rectifying tubes. Metal-cooled fast reactor core upper mechanism. 3. The liquid according to claim 1 or 2, wherein an instrumentation well holder for holding a tip of an instrumentation well inserted into the rectification tube is provided on the inner periphery of the rectification tube of the honeycomb-shaped rectification grid. Metal-cooled fast reactor core upper mechanism.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP10718378A JPS5533661A (en) | 1978-08-31 | 1978-08-31 | Upper portion mechanism of lmfbr reactor core |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP10718378A JPS5533661A (en) | 1978-08-31 | 1978-08-31 | Upper portion mechanism of lmfbr reactor core |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS5533661A JPS5533661A (en) | 1980-03-08 |
| JPS6125109B2 true JPS6125109B2 (en) | 1986-06-13 |
Family
ID=14452563
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP10718378A Granted JPS5533661A (en) | 1978-08-31 | 1978-08-31 | Upper portion mechanism of lmfbr reactor core |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS5533661A (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2649625B2 (en) * | 1991-12-10 | 1997-09-03 | 株式会社 ケミカル山本 | Electrolyte for electrolytic polishing of chromium-containing alloy steel |
-
1978
- 1978-08-31 JP JP10718378A patent/JPS5533661A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS5533661A (en) | 1980-03-08 |
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