JPS63117293A - Nuclear reactor - Google Patents
Nuclear reactorInfo
- Publication number
- JPS63117293A JPS63117293A JP61261798A JP26179886A JPS63117293A JP S63117293 A JPS63117293 A JP S63117293A JP 61261798 A JP61261798 A JP 61261798A JP 26179886 A JP26179886 A JP 26179886A JP S63117293 A JPS63117293 A JP S63117293A
- Authority
- JP
- Japan
- Prior art keywords
- shield
- control rod
- nuclear reactor
- cooling
- drive device
- 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
- 238000001816 cooling Methods 0.000 claims description 26
- 239000002184 metal Substances 0.000 claims description 9
- 229910052751 metal Inorganic materials 0.000 claims description 9
- 239000000835 fiber Substances 0.000 claims description 8
- 230000005855 radiation Effects 0.000 claims description 4
- 230000000694 effects Effects 0.000 description 9
- 238000009413 insulation Methods 0.000 description 7
- 238000003780 insertion Methods 0.000 description 5
- 230000037431 insertion Effects 0.000 description 5
- RYGMFSIKBFXOCR-UHFFFAOYSA-N Copper Chemical compound [Cu] RYGMFSIKBFXOCR-UHFFFAOYSA-N 0.000 description 2
- 239000002826 coolant Substances 0.000 description 2
- 229910052802 copper Inorganic materials 0.000 description 2
- 239000010949 copper Substances 0.000 description 2
- 230000004992 fission Effects 0.000 description 2
- 239000007789 gas Substances 0.000 description 2
- 239000011810 insulating material Substances 0.000 description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 2
- 210000002268 wool Anatomy 0.000 description 2
- 244000171726 Scotch broom Species 0.000 description 1
- 229910000831 Steel Inorganic materials 0.000 description 1
- 239000011358 absorbing material Substances 0.000 description 1
- 230000004323 axial length Effects 0.000 description 1
- 230000015556 catabolic process Effects 0.000 description 1
- 239000003795 chemical substances by application Substances 0.000 description 1
- 238000010411 cooking Methods 0.000 description 1
- 239000000112 cooling gas Substances 0.000 description 1
- 238000001514 detection method Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000020169 heat generation Effects 0.000 description 1
- 230000002452 interceptive effect Effects 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 230000000630 rising effect Effects 0.000 description 1
- 229910001220 stainless steel Inorganic materials 0.000 description 1
- 239000010935 stainless steel Substances 0.000 description 1
- 239000010959 steel Substances 0.000 description 1
- 238000004804 winding Methods 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
- Analysing Materials By The Use Of Radiation (AREA)
- Treatment Of Water By Oxidation Or Reduction (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) [Abstract] This bulletin contains application data before electronic filing, so abstract data is not recorded.
Description
【発明の詳細な説明】
［発明の目的］
（産業上の利用分野）
本発明は原子炉、例えばガス冷却型原子炉のような原子
炉上部のスタンドパイプ内で、その下方に遮蔽体を設け
た制御棒駆動装置等の駆動機構部を備えた原子炉に関す
る。[Detailed Description of the Invention] [Object of the Invention] (Industrial Application Field) The present invention provides a method for providing a shield below a stand pipe in the upper part of a nuclear reactor, such as a gas-cooled nuclear reactor. The present invention relates to a nuclear reactor equipped with a drive mechanism such as a control rod drive device.
（従来の技術）
一般に、ガス冷却型原子炉においては、中性子吸収材を
充填した制御棒を制御棒駆動装置により炉心部に挿入し
たり、あるいは引火いたりして炉心の核分裂反応を制御
している。かかる制御俸駆′１１Ｊ装置としては、例え
ばワイヤロープで制御棒を吊持し、そのワイヤロープの
巻取りと繰出しによって制御棒を昇降させるものが知ら
れている。(Prior art) Generally, in gas-cooled nuclear reactors, the nuclear fission reaction in the reactor core is controlled by inserting control rods filled with neutron absorbing material into the reactor core using a control rod drive device, or by igniting them. . As such a control rod drive device 11J, one is known in which, for example, a control rod is suspended by a wire rope and the control rod is raised and lowered by winding and letting out the wire rope.
従来のガス冷却型原子炉を第２図を参照して説明する。A conventional gas-cooled nuclear reactor will be explained with reference to FIG.
同図において、炉床部１上に支持された炉心２内には複
数の制御棒挿入孔３（図では１個のみ図示）が形成され
、各制御棒挿入孔３の上方部には案内管支持部材４から
懸垂した制御棒案内管５が、制御棒挿入孔３の軸線と同
一軸線上にそれぞれ配設されている。また、炉心２の各
制御棒挿入孔３内に挿入される制御棒６は、連結金具７
を介してワイヤロー１８に連結され、このワイヤロープ
８は軸受９に回転自在に軸支されたドラム１２に巻回さ
れている。このドラム１２は駆動モータ１０により歯車
前溝１１を介して駆動され、歯車機構１１には制御棒６
の位置をドラム１２の回転角度によって検出する位置検
出機構１３が連結されている。In the figure, a plurality of control rod insertion holes 3 (only one is shown in the figure) are formed in a reactor core 2 supported on a hearth part 1, and guide tubes are formed in the upper part of each control rod insertion hole 3. Control rod guide tubes 5 suspended from the support member 4 are arranged on the same axis as the axis of the control rod insertion hole 3, respectively. In addition, the control rods 6 inserted into each control rod insertion hole 3 of the reactor core 2 are connected to connecting fittings 7.
The wire rope 8 is connected to a wire rope 18 via a wire rope 8, and the wire rope 8 is wound around a drum 12 rotatably supported by a bearing 9. This drum 12 is driven by a drive motor 10 via a gear front groove 11, and a control rod 6 is connected to the gear mechanism 11.
A position detection mechanism 13 for detecting the position of the drum 12 based on the rotation angle of the drum 12 is connected thereto.
これらのワイＡ７０−プ８．駆動モータ１０．歯車機構
１１．ドラム１２等からなる制御棒駆動装置１４は原子
炉容器１５の上部開口より立上ったスタンドパイプ１６
内に図示しない他の駆動装置、例えば制御棒が不測の事
態で動作不能となった場合のバックアップとして設置さ
れる後備停止系の駆動装置部および炉心２への冷却ガス
流量を調整する流星調節装置の駆動装置部とともに収容
され、下部には前記案内管支持部材４と一体化された炉
心２からの核分裂反応に伴なう熱および放射線を許容値
以下に遮蔽するための遮蔽体１７を備えている。そして
、制御棒駆動装置１４等の駆動装置の上方、すなわちス
タンドパイプ１６の上端には、炉内の高圧力による飛び
出し防止および圧力バウンダリの役割を果たすクロージ
ャ１８が配設され、前記案内管支 □持部材４．制郊棒
駆動装置１４等の駆動装置部および遮蔽体１７はクロー
ジャ１８の下端より吊り下げられたかご形構造の支持部
材１９によって支持されている。These wipes A70-P8. Drive motor 10. Gear mechanism 11. A control rod drive device 14 consisting of a drum 12 and the like is connected to a stand pipe 16 rising from the upper opening of the reactor vessel 15.
Other drive devices (not shown), such as the drive device section of the standby shutdown system installed as a backup in case the control rod becomes inoperable due to an unexpected situation, and the meteor adjustment device that adjusts the flow rate of cooling gas to the reactor core 2. It is housed together with the drive unit of the guide tube supporting member 4, and is provided with a shielding body 17 at the lower part for shielding the heat and radiation accompanying the nuclear fission reaction from the reactor core 2, which is integrated with the guide tube support member 4, to below a permissible value. There is. A closure 18 is disposed above the drive devices such as the control rod drive device 14, that is, at the upper end of the stand pipe 16, and serves as a pressure boundary and to prevent ejection due to high pressure in the reactor. Holding member 4. The drive unit such as the bar drive unit 14 and the shield 17 are supported by a support member 19 having a cage-shaped structure suspended from the lower end of the closure 18.
（発明が解決しようとする問題点）
上述したように、遮蔽体１７を炉心２側に連結して設置
される制御棒駆動装置１４等の駆動装置部は、その駆動
源となる駆動モータや位置検出器等多くの電気部品を使
用しており、その機能を保護するため例えば約４００℃
にも達する遮蔽体１７の下端部温度を、遮蔽体１７の上
部の駆動装置収容部においては、その雰囲気温度として
例えば６５°Ｃ以下程度になるよう制限される。(Problems to be Solved by the Invention) As described above, the drive unit, such as the control rod drive unit 14, which is installed by connecting the shield 17 to the reactor core 2 side, is Many electrical parts such as detectors are used, and in order to protect their functions, the
The temperature at the lower end of the shield 17, which reaches the lower end of the shield 17, is limited to, for example, about 65° C. or less as the ambient temperature in the driving device accommodating portion above the shield 17.
しかして、炉心２側からの遮蔽体１７を通過しての入熱
およびワイヤロープ用の貫通孔８ａ等の遮蔽体貫通孔を
通っての入熱および駆動モータ等電気部品の発熱等によ
る温度上昇の要因となる熱量は、遮蔽体１７による断熱
効果およびスタンドパイプ外表面からの放熱等によって
除去されることになるが、遮蔽体１７の構成や軸方向長
さ寸法が放射線の低減には十分であっても、断熱効果が
前述した許容温度以下になるまでには寸法的に不十分で
あり、従来の構成で遮蔽体１７を延長することが原子炉
全体のスペースの制約から困難な場合、あるいは駆動モ
ータ等の電気部品からの発熱量の除去が、スタンドパイ
プ材質の熱伝導と外表面における自然対流による冷却で
不十分な場合等においては駆動装置収容部の雰囲気温度
が許容温度を越えてしまうことも考えられ、その場合に
は駆動モータ等の電気部品の絶縁破壊が発生し、制御棒
６の正常な駆動が不可能となる恐れがある。Therefore, the temperature rises due to heat input from the core 2 side through the shield 17, heat input through the shield through-holes such as the wire rope through-hole 8a, and heat generation from electric components such as the drive motor. The amount of heat that causes this will be removed by the insulation effect of the shield 17 and heat radiation from the outer surface of the standpipe, but the structure and axial length of the shield 17 are not sufficient to reduce radiation. Even if there is, the dimensions are insufficient for the insulation effect to drop below the above-mentioned allowable temperature, and it is difficult to extend the shield 17 with the conventional configuration due to the space constraints of the entire reactor, or In cases where heat conduction through the standpipe material and cooling by natural convection on the outer surface are insufficient to remove the heat generated from electrical components such as the drive motor, the ambient temperature in the drive unit housing area may exceed the allowable temperature. In that case, dielectric breakdown of electrical components such as the drive motor may occur, and normal driving of the control rod 6 may become impossible.
本発明は上記事情に基づいてなされたもので、その目的
は、制御棒駆動装置等の駆動装置電気部品の故障要因と
なる駆動装置収容部スタンドパイプ内雰囲気温度をその
許容値以下になるように炉心からの入熱を除去し、かつ
制御棒の炉心への挿入、引扱きを確実に行なうことがで
きる原子炉を提供することにある。The present invention has been made based on the above-mentioned circumstances, and its purpose is to reduce the atmospheric temperature in the standpipe of the drive unit housing part, which is a cause of failure of the drive unit electrical parts such as the control rod drive unit, to a permissible value or less. It is an object of the present invention to provide a nuclear reactor that can remove heat input from the reactor core and that can reliably insert and handle control rods into the reactor core.
［発明の構成コ
（問題点を解決するための手段）
本°発明は、上記目的を達成するために、遮蔽体下端に
その場所の形状に合せて容易に成型、充填可能な、大き
な断熱性能を有する金属繊維、例えばステンレスウール
を取り付け、さらに制御棒駆ｖＪ装置等駆動装置が収容
される部分′のスタンドパイプ外表面のほぼ全面に熱伝
導率がスタンドパイプ材質と比較して大きい、例えば銅
板に内部を冷却媒体、例えば水が循環する管を蛇管状に
溶着した冷却パネルを装着して、駆動装置収容部への入
熱量の減少および入熱量の除去をより効果的にしたこと
を特徴とするものでおる。[Structure of the Invention (Means for Solving Problems)] In order to achieve the above-mentioned object, the present invention provides a structure with high heat insulation performance that can be easily molded and filled according to the shape of the area at the lower end of the shield. A metal fiber having a high thermal conductivity, such as stainless steel wool, is attached to almost the entire outer surface of the standpipe in the part where the drive device such as the control rod drive VJ device is housed. A cooling panel in which a tube through which a cooling medium, such as water, circulates is welded in a serpentine shape is attached to the inside of the drive unit, thereby making it more effective to reduce the amount of heat input to the drive device housing part and remove the amount of heat input. I have something to do.
（作 用）
本発明によると、遮蔽体下端面を可能な限りほぼ仝而を
熱伝導率が非常に小さい金属繊維で所定厚さ覆っている
ので、遮蔽体の断熱性能を遮蔽体本体の寸法、構成を変
更せずに高めることができ、かつ、スタンドパイプ外表
面への冷却管を具備した冷却パネルの取り付けにより、
熱Ｍの除去能力を増すことができるので、スタンドパイ
プ内雰囲気温度を、確実に定められた許容値以下とする
ことができる。(Function) According to the present invention, the lower end surface of the shield is covered with metal fibers having extremely low thermal conductivity to a predetermined thickness, so that the insulation performance of the shield is determined by the dimensions of the shield body. , can be increased without changing the configuration, and by installing a cooling panel with cooling pipes on the outside surface of the standpipe.
Since the ability to remove heat M can be increased, the atmospheric temperature within the standpipe can be reliably kept below a predetermined allowable value.
（実施例） 本発明の一実施例を第１図を参照して説明する。(Example) An embodiment of the present invention will be described with reference to FIG.
既に説明した第２図と同一構成部品には同一符号を付し
てその詳細な説明は省略するものとする。Components that are the same as those in FIG. 2 that have already been described are given the same reference numerals, and detailed explanation thereof will be omitted.
第１図において、２１．２２は、遮蔽体１７の下端部に
設置される例えばステンレスウールと呼ばれる金属繊維
による綿状の断熱材であって、遮蔽体１７の下端の案内
管支持部材４に接続される。この金属繊維による綿状の
断熱材は制御棒６を炉心２の挿入孔３へ案内する制御棒
案内管５等の内側を含め、収納ケース２３．２４のほぼ
全面に必要厚さ充填され、支持金具２５と図示しないボ
ルトにより案内管５に固設される。また、２６は原子炉
容器１５上部の一次遮蔽体２０から突き出た制御棒駆動
装置１４等の駆動装置収容部に相当するスタンドパイプ
１６の外表面に装着した冷却パネルである。この冷却パ
ネル２６は周方向に、例えば少なくとも２分割されて図
示しないボルト等によりスタンドパイプ１６に装置され
ている。そして、この冷却パネル２６は熱伝導率の大き
い例えば銅板で作られており、その外表面に、内部を冷
却媒体例えば水が循環する鋼管等の冷却管２７を蛇管状
に溶着されている。In FIG. 1, reference numerals 21 and 22 are cotton-like heat insulating materials made of metal fibers called stainless wool, installed at the lower end of the shield 17, and connected to the guide tube support member 4 at the lower end of the shield 17. be done. This cotton-like heat insulating material made of metal fibers is filled to a required thickness over almost the entire surface of the storage case 23, 24, including the inside of the control rod guide tube 5 that guides the control rod 6 into the insertion hole 3 of the reactor core 2. It is fixed to the guide tube 5 with a metal fitting 25 and a bolt (not shown). Further, 26 is a cooling panel attached to the outer surface of the stand pipe 16 which corresponds to a drive device housing portion such as the control rod drive device 14 that protrudes from the primary shield 20 at the upper part of the reactor vessel 15. The cooling panel 26 is circumferentially divided into at least two parts, for example, and is attached to the stand pipe 16 with bolts (not shown) or the like. The cooling panel 26 is made of, for example, a copper plate having a high thermal conductivity, and a cooling pipe 27 such as a steel pipe through which a cooling medium, such as water, circulates inside is welded to the outer surface in the form of a serpentine tube.
次に、本実施例の作用について説明する。Next, the operation of this embodiment will be explained.
前述したように、原子炉運転中の遮蔽体１７の下面付近
の炉内ガス温度は約４００℃にも達するので、この温度
による入熱および駆動モータ等の駆動装置部の電気部品
の動作に伴う発熱間を、遮蔽体１７の断熱効果およびス
タンドパイプ１６の外表面における自然対流による冷却
効果によって、前述した制御棒駆動装置１４等が収容さ
れる遮蔽体１７の上部の収容部雰囲気温度を所定の許容
値以下に保つ必要がある。。As mentioned above, during reactor operation, the reactor gas temperature near the bottom surface of the shield 17 reaches approximately 400°C, so the heat input due to this temperature and the operation of electrical parts of the drive unit such as the drive motor The temperature of the atmosphere in the upper part of the housing part of the shield 17 where the control rod drive device 14 and the like described above are housed is maintained at a predetermined temperature by the heat insulation effect of the shield 17 and the cooling effect of natural convection on the outer surface of the stand pipe 16. Must be kept below the allowable value. .
本発明はこの遮蔽体１７の断熱性能およびスタンドパイ
プ１６の外表面からの冷却性能の向上に寄与するもので
ある。すなわち、遮蔽体１７の下部に制御棒案内管５の
取り付けあるいはワイヤロー１８の動作をさまたげずに
、任意の形状に成型可能で内部に多量の気体を包含する
ことにより非常に熱伝導率か小さくなる綿状の金属繊維
を必要厚さにして遮蔽体１７の下端部に設置することに
より、炉心側からの入熱の断熱効果を大きく向上させた
ものでおる。また、駆動装置収容部のスタンドパイプ１
６の外表面にはＨ肴のため分割したそれぞれの部分に冷
却管２７を具備した冷却パネル２６を、はぼ全周にわた
って取り付けているので、この冷却パネル２６は冷却水
の循環によってスタンドパイプ１６内雰囲気温度より常
に低い温度に維持される。さらに、スタンドパイプ１６
の外表面からの熱伝導による除熱作用で冷却能力を向上
させることが可能となる。The present invention contributes to improving the heat insulation performance of the shield 17 and the cooling performance from the outer surface of the standpipe 16. That is, it can be molded into any shape without interfering with the attachment of the control rod guide tube 5 or the operation of the wire row 18 at the bottom of the shield 17, and by containing a large amount of gas inside, the thermal conductivity is extremely low. By installing cotton-like metal fibers to the required thickness at the lower end of the shield 17, the heat insulating effect against heat input from the core side is greatly improved. In addition, the stand pipe 1 of the drive device housing section
A cooling panel 26 with a cooling pipe 27 in each divided part for H cooking is attached to the outer surface of the stand pipe 16 over almost the entire circumference. The temperature is always maintained lower than the internal ambient temperature. Furthermore, stand pipe 16
It becomes possible to improve the cooling capacity by the heat removal effect by heat conduction from the outer surface.
このように、本実施例では遮蔽体１７の下端部に断熱効
果の大きい金属繊維を必要厚さ設け、また、スタンドパ
イプ外表面への冷却パネルの取り付けにより、炉心から
の入熱および駆動モータ等電気部品による発熱を、その
断熱性能および冷却性能の向上により、電気部品の機能
喪失に至ることのない許容温度以下に保つことが容易に
可能となり、故障要因を排除して原子炉の正常な出力制
御を確実に行なうことができるものである。As described above, in this embodiment, a metal fiber with a large heat insulating effect is provided at the lower end of the shield 17 to a required thickness, and a cooling panel is attached to the outer surface of the stand pipe, thereby reducing heat input from the core and driving motors, etc. By improving the heat insulation and cooling performance of electrical components, it is now possible to easily keep the heat generated by electrical components below the allowable temperature without causing loss of function of the electrical components, eliminating the cause of failure and ensuring normal output of the reactor. This allows for reliable control.
なお、本発明の冷却パネルは上記実施例に限定されるも
のではなく、例えば、冷却管を具備した前記冷却パネル
の銅板部の外表面に多数の溝を設けた、いわゆるフィン
構造にして表面積を大きくすることにより自然対流によ
る除熱効果を高めることで更に冷却能力を向上させるこ
とができる。Note that the cooling panel of the present invention is not limited to the above-mentioned embodiments. For example, the cooling panel provided with cooling pipes may have a so-called fin structure in which a large number of grooves are provided on the outer surface of the copper plate portion of the cooling panel to increase the surface area. By increasing the size, the heat removal effect by natural convection can be enhanced, and the cooling capacity can be further improved.
［発明の効果］
以上説明したように、本発明によれば炉心からの入熱お
よび駆動モータ等の電気部品の発熱による駆動装置収容
部の温度上昇を、所定の許容温度以下に保つことが可能
になり、これにより制御棒駆動装置等の駆動装置の正常
な駆動が確保され、原子炉の稼動率の向上、信頼性およ
び安全性の向上を図ることができる。[Effects of the Invention] As explained above, according to the present invention, it is possible to keep the temperature rise in the drive device housing part due to heat input from the core and heat generated by electric components such as the drive motor below a predetermined allowable temperature. As a result, normal operation of drive devices such as control rod drive devices is ensured, and it is possible to improve the operating rate, reliability, and safety of the nuclear reactor.
第１図は本発明の一実施例の概略縦断面図、第２図は従
来のガス冷却型原子炉の概略縦断面図でおる。
２・・・炉心
６・・・制御棒
１４・・・制御棒駆動装置
１５・・・原子炉容器
１６・・・スタンドパイプ
２０・・・−次遮蔽体
２１、２２・・・金属繊維
２３、２４・・・収納ケース
２６・・・冷却パネル
２７・・・冷却管
（８７３３）代理人 弁理士 猪 股 祥 晃（ほか
１名）
箒 １ 図FIG. 1 is a schematic vertical cross-sectional view of an embodiment of the present invention, and FIG. 2 is a schematic vertical cross-sectional view of a conventional gas-cooled nuclear reactor. 2...Reactor core 6...Control rod 14...Control rod drive device 15...Reactor vessel 16...Stand pipe 20...Next shields 21, 22...Metal fiber 23, 24...Storage case 26...Cooling panel 27...Cooling pipe (8733) Agent Patent attorney Yoshiaki Inomata (and others)
1 person) Broom 1 diagram
Claims (3)
の熱および放射線を遮蔽する遮蔽体を設け、この遮蔽体
の上部に制御棒駆動装置等を設置する原子炉において、
前記遮蔽体下端に金属繊維による断熱層を設け、さらに
前記制御棒駆動装置の収容部に相当するスタンドパイプ
外表面部に冷却パネルを装着して、前記制御棒駆動装置
の収容部のスタンドパイプ内雰囲気温度を許容値以下に
低減するようにしたことを特徴とする原子炉。(1) In a nuclear reactor in which a shield is provided in the standpipe at the top of the reactor vessel to shield heat and radiation from the reactor core, and a control rod drive device, etc. is installed above this shield,
A heat insulating layer made of metal fibers is provided at the lower end of the shield, and a cooling panel is attached to the outer surface of the standpipe corresponding to the control rod drive device housing section, so that the interior of the standpipe in the control rod drive device housing section is provided. A nuclear reactor characterized by reducing the ambient temperature below a permissible value.
徴とする特許請求の範囲第１項記載の原子炉。(2) The nuclear reactor according to claim 1, characterized in that a cooling pipe is attached to the outer surface of the cooling panel.
とする特許請求の範囲第１項記載の原子炉。(3) The nuclear reactor according to claim 1, wherein fins are provided on the outer surface of the cooling panel.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP61261798A JPS63117293A (en) | 1986-11-05 | 1986-11-05 | Nuclear reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP61261798A JPS63117293A (en) | 1986-11-05 | 1986-11-05 | Nuclear reactor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS63117293A true JPS63117293A (en) | 1988-05-21 |
Family
ID=17366859
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP61261798A Pending JPS63117293A (en) | 1986-11-05 | 1986-11-05 | Nuclear reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS63117293A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| KR100333811B1 (en) * | 1998-06-08 | 2002-11-22 | 삼성전자 주식회사 | Rotary inverter with short-circuit commutator |
-
1986
- 1986-11-05 JP JP61261798A patent/JPS63117293A/en active Pending
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| KR100333811B1 (en) * | 1998-06-08 | 2002-11-22 | 삼성전자 주식회사 | Rotary inverter with short-circuit commutator |
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