JP2000098078A - Reactor safety installation - Google Patents
Reactor safety installationInfo
- Publication number
- JP2000098078A JP2000098078A JP10270931A JP27093198A JP2000098078A JP 2000098078 A JP2000098078 A JP 2000098078A JP 10270931 A JP10270931 A JP 10270931A JP 27093198 A JP27093198 A JP 27093198A JP 2000098078 A JP2000098078 A JP 2000098078A
- Authority
- JP
- Japan
- Prior art keywords
- reactor
- pressure vessel
- reactor pressure
- core
- cadmium
- 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
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
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
Description
【０００１】[0001]
【発明の属する技術分野】本発明は、原子力発電プラン
トに係り、特に原子炉事故時に再臨界を防止する原子炉
安全設備に関する。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a nuclear power plant, and more particularly to a reactor safety facility for preventing recriticality in a nuclear reactor accident.
【０００２】[0002]
【従来の技術】従来の原子力発電プラントに設置されて
いる再臨界防止の手段に関する原子炉安全設備の概要に
ついて図７により説明する。図７は従来の原子力発電プ
ラント（ＢＷＲ）の原子炉内構造物の概略を模式的に示
している。2. Description of the Related Art An outline of reactor safety equipment related to recriticality prevention means installed in a conventional nuclear power plant will be described with reference to FIG. FIG. 7 schematically shows an outline of a reactor internal structure of a conventional nuclear power plant (BWR).
【０００３】原子力発電プラント（ＢＷＲ）は、原子炉
圧力容器１及び原子炉格納容器１４で構成され、原子炉
圧力容器１には炉心５，セパレータ１６及びドライヤ１
７が設置され、更に貫通部３が接続されている。A nuclear power plant (BWR) includes a reactor pressure vessel 1 and a containment vessel 14, and the reactor pressure vessel 1 includes a core 5, a separator 16, and a dryer 1.
7 are provided, and the through portion 3 is further connected.
【０００４】原子力発電プラントにおいて、何らかの事
故時に炉心５の温度が上昇し、炉心５の燃料が溶融する
場合を想定すると、それが原子炉圧力容器１内の下方へ
落下し、そこで、再臨界するような場合の防止手段につ
いては、原子炉圧力容器１外に設置したホウ酸を注入す
る設備１５などが採用されている。[0004] In a nuclear power plant, assuming that the temperature of the core 5 rises in some accident and the fuel in the core 5 melts, it falls down into the reactor pressure vessel 1 and re-criticalizes there. As a preventive measure in such a case, a facility 15 for injecting boric acid installed outside the reactor pressure vessel 1 is employed.
【０００５】また、原子炉構造物を対象とした従来技術
としては、「特開平6−160572 号公報：原子炉内構造
物」及び「特開平6−265675 号公報：原子炉安全設備」
が見受けられる。[0005] Further, as a conventional technique for a nuclear reactor structure, Japanese Unexamined Patent Publication No. Hei 6-160572: Reactor internal structure and Japanese Unexamined Patent Publication No. Hei 6-265675: Reactor safety equipment
Can be seen.
【０００６】まず、従来技術として特開平6−160572 号
公報の例を図７を用いて紹介する。従来技術の原子炉内
構造物は、セパレータ１６またはドライヤ１７に熱中性
子吸収断面積の大きなホウ素もしくはカドミウムを含む
構造材料を用いる構成となっている。First, an example of the prior art disclosed in Japanese Patent Application Laid-Open No. 6-160572 will be introduced with reference to FIG. The prior art reactor internal structure has a configuration in which a separator 16 or a dryer 17 is made of a structural material containing boron or cadmium having a large thermal neutron absorption cross-sectional area.
【０００７】例えば、何らかの事故時に炉心５の温度が
上昇し、炉心溶融が起こり、溶融した炉心５が原子炉圧
力容器１内の下部に落下した場合、低融点物質で構成さ
れ熱中性子断面積の大きなホウ素もしくはカドミウムを
含むセパレータ１６、またはドライヤ１７は輻射熱で溶
融し、溶融物は原子炉圧力容器１の下方部へ落下すると
されている。そこで、落下した炉心の熱中性子を捕獲す
るため、再臨界を防止するとされている。[0007] For example, when the temperature of the core 5 rises in an accident and the core melts, and the melted core 5 falls to the lower part in the reactor pressure vessel 1, the thermal neutron cross section of the low-melting-point material is formed. The separator 16 containing a large amount of boron or cadmium, or the dryer 17 is melted by radiant heat, and the melt is said to fall to the lower part of the reactor pressure vessel 1. Therefore, it is said that re-criticality is prevented in order to capture the thermal neutrons of the dropped core.
【０００８】しかし、従来の技術の原子炉内構造物は、
セパレータ１６及びドライヤ１７を低融点物質で構成す
る必要があり、これは構造物の耐性を低下させることと
なり、通常運転中の冷却水中に不純物混入させるという
問題が生じていた。[0008] However, the prior art reactor internals are:
The separator 16 and the dryer 17 must be made of a low-melting substance, which lowers the durability of the structure, and causes a problem that impurities are mixed in the cooling water during normal operation.
【０００９】また、従来の技術の原子炉内構造物は、原
子炉圧力容器１に構造上必要とされるシュラウド１８及
びシュラウドヘッド１９が考慮されていないため、シュ
ラウドヘッド１９より上方に配置されるセパレータ１６
もしくはドライヤ１７が溶融し落下しても、原子炉圧力
容器１の下方に落下した炉心と混合しない可能性があ
り、再臨界を防止することができない可能性があった。Further, the reactor internal structure of the prior art is disposed above the shroud head 19 because the shroud 18 and the shroud head 19 required for the structure of the reactor pressure vessel 1 are not taken into consideration. Separator 16
Alternatively, even if the dryer 17 is melted and dropped, it may not mix with the core dropped below the reactor pressure vessel 1, and it may not be possible to prevent recriticality.
【００１０】次に、従来技術として特開平6−265675 号
公報の例を図７を用いて紹介する。従来技術の原子炉安
全設備は、原子炉格納容器１４内の原子炉圧力容器１の
下部に耐火性の材料もしくは耐火材の構造物２０を設置
し、更にその構造物２０に中性子吸収材を含有させるこ
とで、溶融炉心の再臨界を抑制するものである。Next, an example of the prior art disclosed in Japanese Patent Laid-Open No. 6-265675 will be introduced with reference to FIG. In the prior art reactor safety equipment, a structure 20 made of a refractory material or a refractory material is installed below the reactor pressure vessel 1 in a reactor containment vessel 14, and the structure 20 further contains a neutron absorbing material. By doing so, recriticality of the molten core is suppressed.
【００１１】しかし、従来の技術の原子炉安全設備は、
溶融炉心と接触しても破損しないことが要求されている
ため、耐火材で構成されており、含有した中性子吸収材
は溶融した炉心と混合しにくい構成であった。However, the conventional reactor safety equipment is
Since it is required not to be damaged even when it comes into contact with the molten core, it is made of a refractory material, and the neutron absorbing material contained is hardly mixed with the molten core.
【００１２】[0012]
【発明が解決しようとする課題】従来の事故時における
再臨界防止手段は、原子炉圧力容器の外部に設置したホ
ウ酸水を注入する設備の駆動用の電源が必要である。The conventional means for preventing recriticality in the event of an accident requires a power supply for driving equipment for injecting boric acid water installed outside the reactor pressure vessel.
【００１３】従って、事故時に万が一発電所の電源が確
保できないような場合を想定すると、システムが作動し
ない恐れがあり、再臨界防止ができないといった課題が
ある。Therefore, if it is assumed that the power supply of the power plant cannot be secured in the event of an accident, the system may not operate and there is a problem that recriticality cannot be prevented.
【００１４】また、原子炉構造物を対象とした再臨界防
止の従来技術である「特開平 6−160572 号公報：原子
炉内構造物」及び「特開平 6−265675 号公報：原子炉
安全設備」は、電源が確保できない場合にも、再臨界を
抑制することが図られているものの、炉心と十分混合し
ない可能性があり、再臨界を防止することができないと
いった課題がある。[0014] Also, the prior art of recriticality prevention for a nuclear reactor structure is disclosed in Japanese Unexamined Patent Publication No. 6-160572: Reactor Internal Structure and Japanese Unexamined Patent Publication No. 6-265675: Reactor Safety Equipment. "" Is intended to suppress re-criticality even when the power supply cannot be secured, but there is a possibility that re-criticality may not be prevented due to insufficient mixing with the core.
【００１５】本発明の目的は、上記課題を解決するため
になされたもので、何らかの事故時に原子力発電所の電
源が確保できないような場合にも、再臨界を防止する性
能の良い原子炉安全設備を提供するものである。SUMMARY OF THE INVENTION An object of the present invention is to solve the above-mentioned problems, and is a reactor safety equipment having a good performance for preventing re-criticality even when the power supply of a nuclear power plant cannot be secured in case of any accident. Is provided.
【００１６】[0016]
【課題を解決するための手段】上記目的を達成するため
に、本発明では、原子炉圧力容器内の下部及び原子炉圧
力容器外側の下部に熱中性子吸収断面積が大きい物質を
含む原子炉構造物を設置し、更に炉心と原子炉構造物の
混合性能を高める構成としたことを特徴とする。According to the present invention, there is provided a reactor structure including a substance having a large thermal neutron absorption cross-sectional area in a lower portion inside a reactor pressure vessel and a lower portion outside the reactor pressure vessel. In addition, a structure for improving the mixing performance of the reactor core and the reactor structure is provided.
【００１７】すなわち、本発明によれば、事故時に原子
力発電所の電源が確保できないような場合にも、原子力
発電プラントの原子炉圧力容器内下部に熱中性子吸収断
面積の大きなホウ素化合物，カドミウムもしくはハフニ
ウムを用いた原子炉安全設備を設置することにより、炉
心の再臨界を防止できる。更に、原子炉圧力容器の外部
にも熱中性子吸収断面積の大きなホウ素化合物，カドミ
ウムもしくはハフニウムを用いた原子炉安全設備を設置
することにより、原子炉圧力容器外での炉心の再臨界を
防止できる。That is, according to the present invention, even when the power supply of the nuclear power plant cannot be secured at the time of an accident, the boron compound, cadmium or cadmium having a large thermal neutron absorption cross section is provided in the lower part of the reactor pressure vessel of the nuclear power plant. By installing reactor safety equipment using hafnium, recriticality of the core can be prevented. Furthermore, by installing reactor safety equipment using a boron compound, cadmium, or hafnium with a large thermal neutron absorption cross section outside the reactor pressure vessel, recriticality of the core outside the reactor pressure vessel can be prevented. .
【００１８】[0018]
【発明の実施の形態】本発明の第一実施例について図
１，図２、及び図３を用いて説明する。DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS A first embodiment of the present invention will be described with reference to FIGS. 1, 2 and 3. FIG.
【００１９】原子炉圧力容器１の下部は、下部ヘッド壁
２，貫通部３で構成されており、通常運転中は冷却水４
で満たされている。更に下部ヘッド壁２の上部には炉心
５が設置されている。本発明の原子炉安全設備は、下部
ヘッド壁２の内側に、ホウ素化合物，カドミウムもしく
はハフニウムの粉末６をＳＵＳに封入した内張り７を設
置する構成としている。The lower part of the reactor pressure vessel 1 is composed of a lower head wall 2 and a penetrating part 3, and a cooling water 4 during normal operation.
Is filled with Further, a core 5 is provided above the lower head wall 2. The reactor safety equipment of the present invention is configured such that a lining 7 in which a powder 6 of a boron compound, cadmium or hafnium is sealed in SUS is installed inside the lower head wall 2.
【００２０】ここで、万一の事故時に炉心５が溶融し、
溶融した炉心５の燃料が原子炉圧力容器１内の下部に落
下した場合、燃料が再度臨界に達する可能性がある。し
かしながら、上記内張り７が溶融した炉心５の熱により
溶融し、内張り７に含まれるホウ素化合物やカドミウム
やハフニウムの粉末６が原子炉圧力容器１内に放出さ
れ、ホウ素化合物やカドミウムやハフニウムが熱中性子
を捕獲するため、再臨界を防止する。In the event of an accident, the core 5 melts,
If the melted fuel of the core 5 falls to the lower part in the reactor pressure vessel 1, the fuel may reach criticality again. However, the lining 7 is melted by the heat of the melted core 5, and the boron compound, cadmium and hafnium powder 6 contained in the lining 7 is released into the reactor pressure vessel 1, and the boron compound, cadmium and hafnium are converted into thermal neutrons. To prevent re-criticality.
【００２１】さらに、本発明の原子炉安全設備は、ＳＵ
Ｓ管材にホウ素化合物，カドミウムもしくはハフニウム
の粉末６を封入した構成としても良い。この場合は、原
子炉圧力容器１の内部を示す図２に示すように原子炉構
造材を矩形の構造物８とし、貫通部３の周囲に設置する
ことも可能である。また、図３に示すように前記構造物
８を適切な長さとし、ＳＵＳ等を構造材とした保持ネッ
ト９でカバーし、原子炉圧力容器１の下部に配置するこ
とも可能である。Further, the reactor safety equipment according to the present invention can
A configuration in which a powder 6 of a boron compound, cadmium or hafnium is sealed in the S pipe material may be used. In this case, as shown in FIG. 2 showing the inside of the reactor pressure vessel 1, the reactor structural material may be a rectangular structure 8 and may be installed around the penetration portion 3. Further, as shown in FIG. 3, the structure 8 may have an appropriate length, may be covered with a holding net 9 made of SUS or the like, and may be disposed below the reactor pressure vessel 1.
【００２２】本発明の第二実施例について図４及び図５
を用いて説明する。FIGS. 4 and 5 show a second embodiment of the present invention.
This will be described with reference to FIG.
【００２３】原子炉圧力容器１外部の下部には多数の貫
通部３が接続されている。本発明の原子炉安全設備は、
図４に示すように、貫通部３の周囲にポケット１０を設
置し、前記ポケット１０にホウ素化合物，カドミウムも
しくはハフニウムの粉末６を溜めておく構成としてい
る。A number of penetrations 3 are connected to a lower portion outside the reactor pressure vessel 1. The reactor safety equipment of the present invention
As shown in FIG. 4, a pocket 10 is provided around the through portion 3, and a powder 6 of a boron compound, cadmium, or hafnium is stored in the pocket 10.
【００２４】ここで万一の事故時に炉心５が溶融し、更
に溶融した炉心５の冷却ができず、炉心５が原子炉圧力
容器の外側へ放出することを想定する場合は、炉心５の
燃料が原子炉圧力容器１の下部の床に溜まり、燃料が臨
界に達する可能性もある。しかしながら、炉心５の燃料
が原子炉圧力容器１から放出される場合、貫通部３を伝
って下方へ落下するため、燃料は貫通部３を伝っている
最中に前記ポケット１０に捕獲され、ポケット１０に設
置されているホウ素化合物やカドミウムやハフニウムの
粉末６を吸収し、下方に落下する。これにより、ホウ素
化合物，カドミウムもしくはハフニウムが熱中性子を捕
獲するため、再臨界を防止する。Here, when it is assumed that the core 5 is melted in the event of an accident and the melted core 5 cannot be cooled and the core 5 is discharged to the outside of the reactor pressure vessel, the fuel in the core 5 is required. May accumulate on the lower floor of the reactor pressure vessel 1 and the fuel may reach a critical level. However, when the fuel in the reactor core 5 is discharged from the reactor pressure vessel 1, the fuel falls down along the penetration 3, so that the fuel is captured in the pocket 10 while traveling along the penetration 3, Absorbs the powder 6 of boron compound, cadmium, or hafnium provided in 10 and falls down. Thereby, the boron compound, cadmium or hafnium captures thermal neutrons, thereby preventing recriticality.
【００２５】更に、本発明の原子炉安全設備は、図５に
示すように原子炉圧力容器１下方の床１１に溝１２を形
成し、その溝にホウ素化合物，カドミウムもしくはハフ
ニウムの粉末６を設置する構成としても、燃料が原子炉
圧力容器下方の床１１に落下した場合に熱中性子を捕獲
するため、再臨界を防止する。Further, in the reactor safety equipment of the present invention, as shown in FIG. 5, a groove 12 is formed in a floor 11 below the reactor pressure vessel 1, and a boron compound, cadmium or hafnium powder 6 is placed in the groove. Even when the fuel is dropped on the floor 11 below the reactor pressure vessel, thermal neutrons are captured, thereby preventing recriticality.
【００２６】本発明の第三実施例を図６を用いて説明す
る。A third embodiment of the present invention will be described with reference to FIG.
【００２７】原子炉圧力容器外部の下部には保温材１３
が設置されている。本発明の原子炉安全設備は、図６に
示すように、原子炉圧力容器１の下方に設置された保温
材１３の内部にホウ素化合物，カドミウムもしくはハフ
ニウムの粉末６を封入する構成としている。A heat insulating material 13 is provided at a lower portion outside the reactor pressure vessel.
Is installed. As shown in FIG. 6, the reactor safety equipment of the present invention has a structure in which a boron compound, cadmium or hafnium powder 6 is sealed in a heat insulating material 13 installed below the reactor pressure vessel 1.
【００２８】ここで万一の事故時に炉心５が溶融し、更
に溶融した炉心５の冷却ができず、溶融した炉心５が原
子炉圧力容器の外側へ放出することを想定する場合は、
炉心５の燃料が原子炉圧力容器の下部の床１１に溜ま
り、燃料が臨界に達する可能性もある。Here, when it is assumed that the core 5 is melted in the event of an accident, the melted core 5 cannot be cooled, and the melted core 5 is discharged to the outside of the reactor pressure vessel.
Fuel in the reactor core 5 may accumulate on the floor 11 below the reactor pressure vessel, and the fuel may reach criticality.
【００２９】しかしながら、炉心５の燃料が原子炉圧力
容器１から放出される場合、保温材を貫通して下方へ落
下するため、保温材１３に封入されているホウ素化合物
やカドミウムやハフニウムの粉末６も噴出し、燃料が原
子炉圧力容器１の下方の床１１に落下するのと同時に落
下する。これにより、ホウ素化合物，カドミウムもしく
はハフニウムが熱中性子を捕獲するため、再臨界を防止
する。However, when the fuel in the reactor core 5 is discharged from the reactor pressure vessel 1, the fuel falls through the heat insulating material and falls downward, so that the boron compound, cadmium or hafnium powder 6 sealed in the heat insulating material 13 is discharged. Also spills out and drops at the same time as the fuel drops to the floor 11 below the reactor pressure vessel 1. Thereby, the boron compound, cadmium or hafnium captures thermal neutrons, thereby preventing recriticality.
【００３０】[0030]
【発明の効果】本発明によれば、事故時に原子力発電所
の電源が確保できないような場合にも、原子力発電プラ
ントの原子炉圧力容器内下部に熱中性子吸収断面積の大
きなホウ素化合物，カドミウムもしくはハフニウムを用
いた原子炉安全設備を設置することにより、炉心の再臨
界を防止できる。更に、原子炉圧力容器の外部にも熱中
性子吸収断面積の大きなホウ素化合物，カドミウムもし
くはハフニウムを用いた原子炉安全設備を設置すること
により、原子炉圧力容器外での炉心の再臨界を防止でき
る。According to the present invention, even when the power supply of a nuclear power plant cannot be secured at the time of an accident, a boron compound, cadmium or cadmium having a large thermal neutron absorption cross section is provided in the lower part of the reactor pressure vessel of a nuclear power plant. By installing reactor safety equipment using hafnium, recriticality of the core can be prevented. Furthermore, by installing reactor safety equipment using a boron compound, cadmium, or hafnium with a large thermal neutron absorption cross section outside the reactor pressure vessel, recriticality of the core outside the reactor pressure vessel can be prevented. .
【００３１】また、従来の原子炉構造物に対して、大き
な構造の変更を伴わず、本発明の原子炉安全設備を追加
するのみで、更なる安全性を向上させることができる。Further, the safety can be further improved only by adding the reactor safety equipment of the present invention without a major structural change to the conventional reactor structure.
【図１】本発明の第一実施例である原子炉圧力容器を示
す側断面図。FIG. 1 is a side sectional view showing a reactor pressure vessel according to a first embodiment of the present invention.
【図２】本発明の第一実施例である構造物の変形例を示
す斜視図。FIG. 2 is a perspective view showing a modification of the structure according to the first embodiment of the present invention.
【図３】本発明の第一実施例の変形例を示す側断面図。FIG. 3 is a side sectional view showing a modification of the first embodiment of the present invention.
【図４】本発明の第二実施例である原子炉圧力容器の一
部を示す部分断面図。FIG. 4 is a partial sectional view showing a part of a reactor pressure vessel according to a second embodiment of the present invention.
【図５】本発明の第二実施例である原子炉安全設備の変
形例を示す構成図。FIG. 5 is a configuration diagram showing a modification of the reactor safety equipment according to the second embodiment of the present invention.
【図６】本発明の第三実施例である原子炉圧力容器の一
部を示す部分図。FIG. 6 is a partial view showing a part of a reactor pressure vessel according to a third embodiment of the present invention.
【図７】従来技術の原子炉安全設備の例を示す構成図。FIG. 7 is a configuration diagram showing an example of a conventional reactor safety facility.
１…原子炉圧力容器、２…下部ヘッド壁、３…貫通部、
４…冷却水、５…炉心、６…ホウ素化合物，カドミウム
もしくはハフニウムの粉末、７…内張り、８…構造物、
９…保持ネット、１０…ポケット、１１…床、１２…
溝、１３…保温材、１４…原子炉格納容器、１５…ホウ
酸を注入する設備、１６…セパレータ、１７…ドライ
ヤ、１８…シュラウド、１９…シュラウドヘッド、２０
…構造物。1 ... reactor pressure vessel, 2 ... lower head wall, 3 ... penetration part,
4: cooling water, 5: core, 6: powder of boron compound, cadmium or hafnium, 7: lining, 8: structure,
9 ... holding net, 10 ... pocket, 11 ... floor, 12 ...
Groove, 13: heat insulating material, 14: reactor containment vessel, 15: equipment for injecting boric acid, 16: separator, 17: dryer, 18: shroud, 19: shroud head, 20
…Structure.
Claims (5)
構造物を、熱中性子吸収断面積が大きい物質を含む構造
材料で構成したことを特徴とする原子炉安全設備。1. A reactor safety facility wherein a reactor structure installed at a lower portion in a reactor pressure vessel is made of a structural material containing a substance having a large thermal neutron absorption cross-sectional area.
食性の高い構成材料で囲み、前記原子炉構造物を原子炉
圧力容器内面に固定することを特徴とする原子炉安全設
備。2. The reactor safety equipment according to claim 1, wherein the reactor structure is surrounded by a highly corrosion-resistant constituent material, and the reactor structure is fixed to the inner surface of the reactor pressure vessel. .
造物を、熱中性子吸収断面積が大きい物質を含む構造材
料で構成したことを特徴とする原子炉安全設備。3. A reactor safety facility wherein the reactor structure installed below the reactor pressure vessel is made of a structural material containing a substance having a large thermal neutron absorption cross-sectional area.
た構造物において、原子炉構造物を設置する箇所を設
け、熱中性子吸収断面積が大きい物質を含む構造材料で
構成した前記原子炉構造材を設置したことを特徴とする
請求項１から３のいずれか１項記載の原子炉安全設備。4. A structure installed on an outer wall of the reactor pressure vessel, wherein a place where the reactor structure is installed is provided, and the atom is made of a structural material containing a substance having a large thermal neutron absorption cross-sectional area. The reactor safety equipment according to any one of claims 1 to 3, wherein a reactor structural material is installed.
て、原子炉圧力容器の下部に設置する保温材内部に設置
したことを特徴とする原子炉安全設備。5. The reactor safety equipment according to claim 3, wherein the reactor safety equipment is installed inside a heat insulating material installed below the reactor pressure vessel.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP10270931A JP2000098078A (en) | 1998-09-25 | 1998-09-25 | Reactor safety installation |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP10270931A JP2000098078A (en) | 1998-09-25 | 1998-09-25 | Reactor safety installation |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JP2000098078A true JP2000098078A (en) | 2000-04-07 |
Family
ID=17493002
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP10270931A Pending JP2000098078A (en) | 1998-09-25 | 1998-09-25 | Reactor safety installation |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JP2000098078A (en) |
Cited By (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2012242375A (en) * | 2011-05-23 | 2012-12-10 | Motohiro Okada | Nuclear power plant system |
| CN102915774A (en) * | 2011-08-02 | 2013-02-06 | 李代甫 | Nuclear reactor and nuclear reactor shutdown method |
| JP2014048110A (en) * | 2012-08-30 | 2014-03-17 | Hitachi-Ge Nuclear Energy Ltd | Cooling facilities of reactor pressure vessel |
| JP2014527631A (en) * | 2011-08-12 | 2014-10-16 | アイエヌシーティー・カンパニー・リミテッド | Equipment for processing molten reactor fuel rods |
| KR101456575B1 (en) | 2013-03-05 | 2014-10-31 | 한국원자력연구원 | In vessel boron injection system |
| JP2015072149A (en) * | 2013-10-02 | 2015-04-16 | 株式会社東芝 | Nuclear reactor |
| JP2016048249A (en) * | 2013-05-01 | 2016-04-07 | 竹田 眞司 | Highly safe atomic power generation |
| JP2017040588A (en) * | 2015-08-20 | 2017-02-23 | 株式会社東芝 | Nuclear reactor facility |
-
1998
- 1998-09-25 JP JP10270931A patent/JP2000098078A/en active Pending
Cited By (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2012242375A (en) * | 2011-05-23 | 2012-12-10 | Motohiro Okada | Nuclear power plant system |
| CN102915774A (en) * | 2011-08-02 | 2013-02-06 | 李代甫 | Nuclear reactor and nuclear reactor shutdown method |
| JP2014527631A (en) * | 2011-08-12 | 2014-10-16 | アイエヌシーティー・カンパニー・リミテッド | Equipment for processing molten reactor fuel rods |
| JP2014048110A (en) * | 2012-08-30 | 2014-03-17 | Hitachi-Ge Nuclear Energy Ltd | Cooling facilities of reactor pressure vessel |
| KR101456575B1 (en) | 2013-03-05 | 2014-10-31 | 한국원자력연구원 | In vessel boron injection system |
| JP2016048249A (en) * | 2013-05-01 | 2016-04-07 | 竹田 眞司 | Highly safe atomic power generation |
| JP2015072149A (en) * | 2013-10-02 | 2015-04-16 | 株式会社東芝 | Nuclear reactor |
| JP2017040588A (en) * | 2015-08-20 | 2017-02-23 | 株式会社東芝 | Nuclear reactor facility |
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