JPH1194978A - Reactor equipment - Google Patents
Reactor equipmentInfo
- Publication number
- JPH1194978A JPH1194978A JP9256437A JP25643797A JPH1194978A JP H1194978 A JPH1194978 A JP H1194978A JP 9256437 A JP9256437 A JP 9256437A JP 25643797 A JP25643797 A JP 25643797A JP H1194978 A JPH1194978 A JP H1194978A
- Authority
- JP
- Japan
- Prior art keywords
- pressure vessel
- reactor
- bottom plate
- reactor pressure
- debris
- 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、原子炉などの発電
プラントに係わり、特に、炉心溶融事故発生時に溶融デ
ブリが原子炉圧力容器を破損して落下することを防止さ
せるのに好適な原子炉設備に関する。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a power plant such as a nuclear reactor, and more particularly, to a nuclear reactor suitable for preventing molten debris from falling down due to damage to a reactor pressure vessel when a core melting accident occurs. Equipment related.
【０００２】[0002]
【従来の技術】発電プラントにおける苛酷事故緩和設備
に関する公知技術例として、特開平6-130169号公報があ
る。本公知例では炉心溶融デブリは原子炉圧力容器を貫
通している場合が想定されている。2. Description of the Related Art Japanese Patent Application Laid-Open No. 6-130169 is an example of a known technique relating to a severe accident mitigation facility in a power plant. In this known example, it is assumed that the core molten debris penetrates the reactor pressure vessel.
【０００３】本公知技術例における、原子炉下部構造図
を図７に、原子炉構造図を図８に示す。[0003] Fig. 7 is a structural view of a lower part of a nuclear reactor and Fig. 8 is a structural view of a nuclear reactor in the prior art.
【０００４】図７は原子炉下部構造図を示すものであ
る。原子炉圧力容器底板２からＣＲＤハウジング６から
上方に制御棒案内管３，制御棒４と燃料集合体７が延び
ている。この型の原子炉では、苛酷事故を想定すると、
大破断ＬＯＣＡ後の注水失敗の場合、炉心溶融デブリに
より原子炉圧力容器が破損する可能性がある。FIG. 7 is a diagram showing a lower structure of a nuclear reactor. Control rod guide tubes 3, control rods 4, and fuel assemblies 7 extend from the reactor pressure vessel bottom plate 2 to above the CRD housing 6. In this type of reactor, assuming a severe accident,
In the case of failure of water injection after a large break LOCA, the reactor pressure vessel may be damaged by core melt debris.
【０００５】さらに、図８において、原子炉はシュラウ
ドのかわりに円筒のインターナルポンプ１を設けてい
る。また、原子炉圧力容器底板２から上方に制御棒案内
管３と制御棒４が延びている。この型の原子炉では、苛
酷事故を想定すると、炉心溶融時に炉心溶融デブリが原
子炉圧力容器壁５（図８中Ａ部分）を直接アタックする
可能性がある。Further, in FIG. 8, the nuclear reactor is provided with a cylindrical internal pump 1 instead of the shroud. A control rod guide tube 3 and a control rod 4 extend upward from the reactor pressure vessel bottom plate 2. In this type of reactor, assuming a severe accident, there is a possibility that core melt debris will directly attack the reactor pressure vessel wall 5 (portion A in FIG. 8) when the core melts.
【０００６】[0006]
【発明が解決しようとする課題】上記公知技術には以下
の課題が存在する。従来技術では、従来の原子炉圧力容
器底板２は、溶融デブリによるクリープ変形が進展し
て、はじめて、冷却材流路が形成されていた。さらに、
シュラウドのかわりに円筒を設けた原子炉では、苛酷事
故を想定すると、炉心溶融時に炉心溶融デブリが原子炉
圧力容器壁５（図８中Ａ部分）を直接アタックする可能
性がある。The above-mentioned known techniques have the following problems. In the prior art, the conventional coolant pressure vessel bottom plate 2 has a coolant flow path formed only when creep deformation due to molten debris progresses. further,
In a nuclear reactor provided with a cylinder instead of a shroud, assuming a severe accident, there is a possibility that core molten debris will directly attack the reactor pressure vessel wall 5 (portion A in FIG. 8) during core melting.
【０００７】本発明の目的は、従来の原子炉圧力容器底
板２において、溶融デブリによるクリープ変形の効果を
促進した構造の原子炉設備を提供することである。さら
に、シュラウドのかわりに円筒を設けた原子炉で、苛酷
事故時に、炉心溶融時に炉心溶融デブリが原子炉圧力容
器壁５（図８中Ａ部分）を直接アタックする可能性を防
止する原子炉設備を提供することである。An object of the present invention is to provide a reactor facility having a structure in which the effect of creep deformation due to molten debris is promoted in the conventional reactor pressure vessel bottom plate 2. Further, in a reactor provided with a cylinder instead of a shroud, a reactor facility for preventing the possibility that core molten debris directly attacks the reactor pressure vessel wall 5 (portion A in FIG. 8) at the time of core melting in a severe accident. It is to provide.
【０００８】[0008]
【課題を解決するための手段】上記の目的を達成するた
めに、本発明によれば、沸騰水型原子炉において、ＣＲ
Ｄハウジングと別のＣＲＤハウジングの間に、原子炉圧
力容器底板の表面に突出物を設けたことを特徴とする原
子炉設備が提供される。According to the present invention, there is provided a boiling water reactor having a CR.
A reactor facility is provided, wherein a protrusion is provided on a surface of a reactor pressure vessel bottom plate between a D housing and another CRD housing.
【０００９】さらに好ましくは、沸騰水型原子炉におい
て、ＣＲＤハウジングと別のＣＲＤハウジングの間に、
原子炉圧力容器底板の表面に管を設けたことを特徴とす
る原子炉設備が提供される。[0009] More preferably, in a boiling water reactor, between a CRD housing and another CRD housing.
A reactor facility is provided, wherein a pipe is provided on a surface of a reactor pressure vessel bottom plate.
【００１０】さらに好ましくは、沸騰水型原子炉におい
て、ＣＲＤハウジングと別のＣＲＤハウジングの間に、
原子炉圧力容器底板の表面に溝を設けたことを特徴とす
る原子炉設備が提供される。[0010] More preferably, in a boiling water reactor, between a CRD housing and another CRD housing.
A reactor facility is provided in which a groove is provided on a surface of a reactor pressure vessel bottom plate.
【００１１】さらに好ましくは、前記円筒と前記圧力容
器壁の間にそらせ板を設けたことを特徴とする原子炉設
備が提供される。[0011] More preferably, there is provided a nuclear reactor facility wherein a deflector is provided between the cylinder and the pressure vessel wall.
【００１２】さらに好ましくは、前記円筒と前記圧力容
器壁の間に断熱材を設けたことを特徴とする原子炉設備
が提供される。[0012] More preferably, there is provided a nuclear reactor facility wherein a heat insulating material is provided between the cylinder and the pressure vessel wall.
【００１３】即ち、従来の原子炉圧力容器底板２は、溶
融デブリによるクリープ変形の効果を促進した構造に関
して、考慮されてなかった。That is, the conventional reactor pressure vessel bottom plate 2 has not been considered with respect to a structure that promotes the effect of creep deformation due to molten debris.
【００１４】本発明においては、沸騰水型原子炉におい
て、ＣＲＤハウジングと別のＣＲＤハウジングの間に、
原子炉圧力容器底板の表面に突出物を設けるので、溶融
デブリが固化した固化デブリと原子炉圧力容器底板の間
のギャップ生成が促進され、このギャップに水が進入
し、圧力容器底板の冷却を促進するので、原子炉圧力容
器破損の確率を従来より低減できる。According to the present invention, in a boiling water reactor, between a CRD housing and another CRD housing,
Protrusions are provided on the surface of the reactor pressure vessel bottom plate, which promotes the creation of a gap between the solidified debris in which the molten debris has solidified and the reactor pressure vessel bottom plate, and water enters this gap to cool the pressure vessel bottom plate. Since it promotes, the probability of reactor pressure vessel breakage can be reduced as compared with the conventional case.
【００１５】本発明においては、沸騰水型原子炉におい
て、ＣＲＤハウジングと別のＣＲＤハウジングの間に、
原子炉圧力容器底板の表面に管を設けるので、溶融デブ
リが固化した固化デブリと原子炉圧力容器底板の間に管
が存在し、この管に水が進入し、圧力容器底板の冷却を
促進するので、原子炉圧力容器破損に至る時間を従来よ
り延長できる。According to the present invention, in a boiling water reactor, between a CRD housing and another CRD housing,
Since a tube is provided on the surface of the reactor pressure vessel bottom plate, there is a tube between the solidified debris in which the molten debris has solidified and the reactor pressure vessel bottom plate, and water enters this tube to promote cooling of the pressure vessel bottom plate. Therefore, the time required for damage to the reactor pressure vessel can be extended as compared with the conventional case.
【００１６】本発明においては、沸騰水型原子炉におい
て、ＣＲＤハウジングと別のＣＲＤハウジングの間に、
原子炉圧力容器底板の表面に溝を設けるので、溶融デブ
リが固化した固化デブリと原子炉圧力容器底板の間にギ
ャップが生成し、このギャップに水が進入し、圧力容器
底板の冷却を促進するので、原子炉圧力容器破損に至る
時間を従来より延長できる。According to the present invention, in a boiling water reactor, between a CRD housing and another CRD housing,
Since a groove is provided on the surface of the reactor pressure vessel bottom plate, a gap is generated between the solidified debris in which the molten debris has solidified and the reactor pressure vessel bottom plate, and water enters the gap to promote cooling of the pressure vessel bottom plate. Therefore, the time required for damage to the reactor pressure vessel can be extended as compared with the conventional case.
【００１７】シュラウドのかわりに円筒を設けた原子炉
では、苛酷事故を想定すると、炉心溶融時に炉心溶融デ
ブリが原子炉圧力容器壁５（図８中Ａ部分）を直接アタ
ックする可能性がある。In a reactor provided with a cylinder instead of a shroud, assuming a severe accident, there is a possibility that core melt debris will directly attack the reactor pressure vessel wall 5 (portion A in FIG. 8) when the core melts.
【００１８】本発明においては、この領域に前記円筒と
前記圧力容器壁の間にそらせ板を設けるので、そらせ板
により溶融デブリを圧力容器壁に触れることなく下方に
落下させることができ、原子炉圧力容器壁５（図８中Ａ
部分）を直接アタックすることを防止できる。In the present invention, since a deflector is provided between the cylinder and the pressure vessel wall in this region, the deflector allows molten debris to fall downward without touching the pressure vessel wall, and Pressure vessel wall 5 (A in FIG. 8)
Portion) can be prevented from being directly attacked.
【００１９】本発明においては、この領域に前記円筒と
前記圧力容器壁の間に断熱材を設けるので、断熱材によ
り溶融デブリを圧力容器壁を高温にさらすことなく下方
に落下させることができ、原子炉圧力容器壁５（図８中
Ａ部分）を直接アタックすることを防止できる。In the present invention, since a heat insulating material is provided between the cylinder and the pressure vessel wall in this region, the heat insulating material allows molten debris to fall downward without exposing the pressure vessel wall to high temperatures. Direct attack on the reactor pressure vessel wall 5 (portion A in FIG. 8) can be prevented.
【００２０】[0020]
【発明の実施の形態】以下、本発明の実施例を図１〜図
６により説明する。DESCRIPTION OF THE PREFERRED EMBODIMENTS An embodiment of the present invention will be described below with reference to FIGS.
【００２１】本発明の第１の実施例を図１により説明す
る。A first embodiment of the present invention will be described with reference to FIG.
【００２２】本実施例の原子炉設備を図１に示す。本発
明の第１の実施例を図１，図２により説明する。図１に
おいて原子炉圧力容器底板２からＣＲＤハウジング６か
ら上方に制御棒案内管３，制御棒４と燃料集合体７が延
びている。この型の原子炉では、苛酷事故を想定する
と、大破断ＬＯＣＡ後の注水失敗の場合、炉心溶融デブ
リにより原子炉圧力容器が破損する可能性があると予想
されている。従来の原子炉圧力容器底板２は、溶融デブ
リによるクリープ変形による冷却材流路形成の効果を促
進した構造に関して、考慮されてなかった。FIG. 1 shows the nuclear reactor equipment of this embodiment. A first embodiment of the present invention will be described with reference to FIGS. In FIG. 1, control rod guide tubes 3, control rods 4, and fuel assemblies 7 extend from the reactor pressure vessel bottom plate 2 to above the CRD housing 6. In this type of reactor, assuming a severe accident, it is expected that the reactor pressure vessel may be damaged by core melt debris if water injection fails after a large break LOCA. The conventional reactor pressure vessel bottom plate 2 has not been considered with respect to a structure that promotes the effect of forming a coolant passage by creep deformation due to molten debris.
【００２３】本発明によれば、沸騰水型原子炉におい
て、ＣＲＤハウジング６と別のＣＲＤハウジングの間
に、原子炉圧力容器底板の表面に突出物１０１を設ける
ので、溶融デブリが固化した固化デブリと原子炉圧力容
器底板の間のギャップ生成が促進され、このギャップに
水が進入し、圧力容器底板の冷却を促進するので、原子
炉圧力容器破損に至る時間を従来より延長できる効果が
ある。According to the present invention, in the boiling water reactor, since the protrusion 101 is provided on the surface of the bottom plate of the reactor pressure vessel between the CRD housing 6 and another CRD housing, the solidified debris in which the molten debris is solidified is provided. The formation of a gap between the reactor pressure vessel bottom plate and the reactor pressure vessel bottom plate is promoted, and water enters this gap to promote cooling of the pressure vessel bottom plate, so that the time required for reactor pressure vessel breakage can be extended as compared with the conventional case.
【００２４】図２において、固化デブリ１０２は圧力容
器底板２の突出物１０１により水１０３中に保持されて
おり、固化デブリ１０２と圧力容器底板２の間にはギャ
ップが生成している。In FIG. 2, the solidified debris 102 is held in water 103 by a projection 101 of the pressure vessel bottom plate 2, and a gap is formed between the solidified debris 102 and the pressure vessel bottom plate 2.
【００２５】本発明の第２の実施例を図３により説明す
る。図３において原子炉圧力容器底板２からＣＲＤハウ
ジング６から上方に制御棒案内管３，制御棒４と燃料集
合体７が延びている。この型の原子炉では、苛酷事故を
想定すると、大破断ＬＯＣＡ後の注水失敗の場合、炉心
溶融デブリにより４時間〜５時間で原子炉圧力容器が破
損すると予想されている。従来の原子炉圧力容器底板２
は、溶融デブリによるクリープ変形の効果を促進した構
造に関して、考慮されてなかった。A second embodiment of the present invention will be described with reference to FIG. In FIG. 3, control rod guide tubes 3, control rods 4, and fuel assemblies 7 extend from the reactor pressure vessel bottom plate 2 to above the CRD housing 6. In this type of reactor, assuming a severe accident, it is expected that, if water injection fails after a large break LOCA, the reactor pressure vessel will be damaged in 4 to 5 hours due to core melt debris. Conventional reactor pressure vessel bottom plate 2
No consideration was given to the structure that promoted the effect of creep deformation due to molten debris.
【００２６】本発明によれば、沸騰水型原子炉におい
て、ＣＲＤハウジング６と別のＣＲＤハウジングの間
に、原子炉圧力容器底板の表面に管１０４を設けるの
で、溶融デブリが固化した固化デブリと原子炉圧力容器
底板の間に管が存在し、この管に水が進入し、圧力容器
底板の冷却を促進するので、原子炉圧力容器破損に至る
時間を従来より延長できる効果がある。According to the present invention, in the boiling water reactor, the pipe 104 is provided on the surface of the bottom plate of the reactor pressure vessel between the CRD housing 6 and another CRD housing. There is a pipe between the reactor pressure vessel bottom plates, and water enters the pipe to promote cooling of the pressure vessel bottom plate, so that the time required for reactor pressure vessel breakage can be extended more than before.
【００２７】本発明の第３の実施例を図４により説明す
る。図４において原子炉圧力容器底板２からＣＲＤハウ
ジング６から上方に制御棒案内管３，制御棒４と燃料集
合体７が延びている。この型の原子炉では、苛酷事故を
想定すると、大破断ＬＯＣＡ後の注水失敗の場合、炉心
溶融デブリにより４時間〜５時間で原子炉圧力容器が破
損すると予想されている。従来の原子炉圧力容器底板２
は、溶融デブリによるクリープ変形の効果を促進した構
造に関して、考慮されてなかった。A third embodiment of the present invention will be described with reference to FIG. In FIG. 4, control rod guide tubes 3, control rods 4, and fuel assemblies 7 extend from the reactor pressure vessel bottom plate 2 to above the CRD housing 6. In this type of reactor, assuming a severe accident, it is expected that, if water injection fails after a large break LOCA, the reactor pressure vessel will be damaged in 4 to 5 hours due to core melt debris. Conventional reactor pressure vessel bottom plate 2
No consideration was given to the structure that promoted the effect of creep deformation due to molten debris.
【００２８】本発明によれば、沸騰水型原子炉におい
て、ＣＲＤハウジング６と別のＣＲＤハウジングの間
に、原子炉圧力容器底板の表面に溝１０５を設けるの
で、溶融デブリが固化した固化デブリと原子炉圧力容器
底板の間にギャップが生成し、このギャップに水が進入
し、圧力容器底板の冷却を促進するので、原子炉圧力容
器破損の確率を従来より低減できる効果がある。According to the present invention, in the boiling water reactor, the groove 105 is provided on the surface of the bottom plate of the reactor pressure vessel between the CRD housing 6 and another CRD housing, so that the molten debris becomes solidified debris. A gap is formed between the reactor pressure vessel bottom plates, and water enters the gap to promote cooling of the pressure vessel bottom plate, so that there is an effect that the probability of reactor pressure vessel breakage can be reduced as compared with the conventional case.
【００２９】本発明の第４の実施例を図５により説明す
る。図５において、原子炉はシュラウドのかわりに円筒
のインターナルポンプ１を設けている。また、原子炉圧
力容器底板２から上方に制御棒案内管３と制御棒４が延
びている。この型の原子炉では、苛酷事故を想定する
と、炉心溶融時に炉心溶融デブリが原子炉圧力容器壁５
（図５中Ａ部分）を直接アタックする可能性がある。A fourth embodiment of the present invention will be described with reference to FIG. In FIG. 5, the nuclear reactor is provided with a cylindrical internal pump 1 instead of the shroud. A control rod guide tube 3 and a control rod 4 extend upward from the reactor pressure vessel bottom plate 2. In a nuclear reactor of this type, assuming a severe accident, core melt debris is generated at the reactor pressure vessel wall 5 when the core melts.
(A portion in FIG. 5) may be directly attacked.
【００３０】本発明では円筒１と圧力容器壁５の間にそ
らせ板１１を周方向に設ける。従って、そらせ板１１に
より圧力容器壁に触れることなく溶融デブリを下方に落
下させることができ、原子炉圧力容器壁５（図５中Ａ部
分）を直接アタックすることを防止できる効果がある。In the present invention, a deflector 11 is provided between the cylinder 1 and the pressure vessel wall 5 in the circumferential direction. Therefore, the deflector plate 11 allows the molten debris to fall downward without touching the pressure vessel wall, and has the effect of preventing direct attack on the reactor pressure vessel wall 5 (portion A in FIG. 5).
【００３１】本発明の第５の実施例を図６により説明す
る。図６において、原子炉はシュラウドのかわりに円筒
のインターナルポンプ１を設けている。また、原子炉圧
力容器底板２から上方に制御棒案内管３と制御棒４が延
びている。この型の原子炉では、苛酷事故を想定する
と、炉心溶融時に炉心溶融デブリが原子炉圧力容器壁５
（図６中Ａ部分）を直接アタックする可能性がある。A fifth embodiment of the present invention will be described with reference to FIG. In FIG. 6, the nuclear reactor is provided with a cylindrical internal pump 1 instead of the shroud. A control rod guide tube 3 and a control rod 4 extend upward from the reactor pressure vessel bottom plate 2. In a nuclear reactor of this type, assuming a severe accident, core melt debris is generated at the reactor pressure vessel wall 5 when the core melts.
(A in FIG. 6) may be directly attacked.
【００３２】本発明では円筒１と圧力容器壁５の間に断
熱材１２を周方向に設ける。従って、断熱材１２により
圧力容器壁を高温にさらすことなく溶融デブリを下方に
落下させることができ、原子炉圧力容器壁５（図６中Ａ
部分）を直接アタックすることを防止できる効果があ
る。In the present invention, a heat insulating material 12 is provided between the cylinder 1 and the pressure vessel wall 5 in the circumferential direction. Therefore, the molten debris can be dropped downward without exposing the pressure vessel wall to high temperature by the heat insulating material 12, and the reactor pressure vessel wall 5 (A in FIG. 6)
(Part) can be prevented from being directly attacked.
【００３３】[0033]
【発明の効果】本発明の第１の実施例によれば、ＣＲＤ
ハウジング６と別のＣＲＤハウジングの間に、原子炉圧
力容器底板の表面に突出物１０１を設けるので、溶融デ
ブリが固化した固化デブリと原子炉圧力容器底板の間の
ギャップ生成が促進され、このギャップに水が進入し、
圧力容器底板の冷却を促進するので、原子炉圧力容器破
損の確率を従来より低減できる効果がある。According to the first embodiment of the present invention, CRD
Since the protrusion 101 is provided on the surface of the reactor pressure vessel bottom plate between the housing 6 and another CRD housing, the generation of a gap between the solidified debris in which the molten debris has solidified and the reactor pressure vessel bottom plate is promoted. Water enters,
Since the cooling of the bottom plate of the pressure vessel is promoted, there is an effect that the probability of damage to the reactor pressure vessel can be reduced as compared with the related art.
【００３４】本発明の第２の実施例によれば、ＣＲＤハ
ウジング６と別のＣＲＤハウジングの間に、原子炉圧力
容器底板の表面に管１０４を設けるので、溶融デブリが
固化した固化デブリと原子炉圧力容器底板の間に管が存
在し、この管に水が進入し、圧力容器底板の冷却を促進
するので、原子炉圧力容器破損の確率を従来より低減で
きる効果がある。According to the second embodiment of the present invention, since the tube 104 is provided on the surface of the bottom plate of the reactor pressure vessel between the CRD housing 6 and another CRD housing, the molten debris is solidified with the solidified debris. There is a pipe between the reactor pressure vessel bottom plates, and water enters the pipe to promote cooling of the pressure vessel bottom plate, so that there is an effect that the probability of reactor pressure vessel breakage can be reduced as compared with the conventional case.
【００３５】本発明の第３の実施例によれば、ＣＲＤハ
ウジング６と別のＣＲＤハウジングの間に、原子炉圧力
容器底板の表面に溝１０５を設けるので、溶融デブリが
固化した固化デブリと原子炉圧力容器底板の間にギャッ
プが生成し、このギャップに水が進入し、圧力容器底板
の冷却を促進するので、原子炉圧力容器破損の確率を従
来より低減できる効果がある。According to the third embodiment of the present invention, since the groove 105 is provided on the surface of the bottom plate of the reactor pressure vessel between the CRD housing 6 and another CRD housing, the molten debris is solidified with the solidified debris. A gap is formed between the reactor pressure vessel bottom plates, and water enters the gap to promote cooling of the pressure vessel bottom plate, so that there is an effect that the probability of reactor pressure vessel breakage can be reduced as compared with the conventional case.
【００３６】本発明の第４の実施例によれば、円筒１と
圧力容器壁５の間にそらせ板１１を周方向に設けるの
で、そらせ板１１により圧力容器壁に触れることなく溶
融デブリを下方に落下させることができ、原子炉圧力容
器壁５（図５中Ａ部分）を直接アタックすることを防止
できる効果がある。According to the fourth embodiment of the present invention, since the baffle 11 is provided in the circumferential direction between the cylinder 1 and the pressure vessel wall 5, the deflector 11 lowers the molten debris without touching the pressure vessel wall. This has the effect of preventing the reactor pressure vessel wall 5 (part A in FIG. 5) from directly attacking.
【００３７】本発明の第５の実施例によれば、円筒１と
圧力容器壁５の間に断熱材１２を周方向に設けるので、
断熱材１２により圧力容器壁を高温にさらすことなく溶
融デブリを下方に落下させることができ、原子炉圧力容
器壁５（図６中Ａ部分）を直接アタックすることを防止
できる効果がある。According to the fifth embodiment of the present invention, since the heat insulating material 12 is provided between the cylinder 1 and the pressure vessel wall 5 in the circumferential direction,
The heat insulating material 12 allows the molten debris to fall downward without exposing the pressure vessel wall to a high temperature, and has the effect of preventing direct attack on the reactor pressure vessel wall 5 (portion A in FIG. 6).
【図１】本発明の第１の実施例の原子炉下部構造を示す
図。FIG. 1 is a diagram showing a reactor lower structure according to a first embodiment of the present invention.
【図２】本発明の第２の実施例の原子炉下部構造を示す
図。FIG. 2 is a view showing a reactor lower structure according to a second embodiment of the present invention.
【図３】本発明の第３の実施例の原子炉下部構造を示す
図。FIG. 3 is a diagram showing a lower structure of a reactor according to a third embodiment of the present invention.
【図４】本発明の第３の実施例の原子炉下部構造を示す
図。FIG. 4 is a diagram showing a reactor lower structure according to a third embodiment of the present invention.
【図５】本発明の第４の実施例の原子炉構造を示す図。FIG. 5 is a diagram showing a reactor structure according to a fourth embodiment of the present invention.
【図６】本発明の第５の実施例の原子炉構造を示す図。FIG. 6 is a diagram showing a nuclear reactor structure according to a fifth embodiment of the present invention.
【図７】従来技術における原子炉下部構造を示す図。FIG. 7 is a diagram showing a lower structure of a reactor according to a conventional technique.
【図８】従来技術における原子炉構造を示す図。FIG. 8 is a diagram showing a reactor structure according to the related art.
１…インターナルポンプ、２…原子炉圧力容器底板、３
…制御棒案内管、４…制御棒、５…原子炉圧力容器壁、
６…ＣＲＤハウジング、７…燃料集合体、１１…そらせ
板、１２…断熱材、１０１…突出物、１０２…固化デブ
リ、１０３…水、１０４…管、１０５…溝。1. Internal pump, 2. Reactor pressure vessel bottom plate, 3.
... control rod guide tube, 4 ... control rod, 5 ... reactor pressure vessel wall,
Reference numeral 6: CRD housing, 7: fuel assembly, 11: deflector, 12: heat insulating material, 101: protrusion, 102: solidified debris, 103: water, 104: pipe, 105: groove.
Claims (5)
グと別のＣＲＤハウジングの間に、原子炉圧力容器底板
の表面に突出物を設けたことを特徴とする原子炉設備。In a boiling water reactor, a projection is provided on a surface of a bottom plate of a reactor pressure vessel between a CRD housing and another CRD housing.
グと別のＣＲＤハウジングの間に、原子炉圧力容器底板
の表面に管を設けたことを特徴とする原子炉設備。2. A boiling water reactor, wherein a pipe is provided on a surface of a bottom plate of a reactor pressure vessel between a CRD housing and another CRD housing.
グと別のＣＲＤハウジングの間に、原子炉圧力容器底板
の表面に溝を設けたことを特徴とする原子炉設備。3. A reactor facility in a boiling water reactor, wherein a groove is provided on a surface of a reactor pressure vessel bottom plate between a CRD housing and another CRD housing.
ポンプ）を設けた原子炉において、前記円筒と原子炉圧
力容器壁の間にそらせ板を周方向に設けたことを特徴と
する原子炉設備。4. A nuclear reactor having a cylinder (internal pump) provided in place of a shroud, wherein a deflector is provided between the cylinder and the reactor pressure vessel wall in a circumferential direction.
ポンプ）を設けた原子炉において、前記円筒と原子炉圧
力容器壁の間に断熱材を周方向に設けたことを特徴とす
る原子炉設備。5. A nuclear reactor having a cylinder (internal pump) instead of a shroud, wherein a heat insulating material is provided in a circumferential direction between the cylinder and a reactor pressure vessel wall.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP9256437A JPH1194978A (en) | 1997-09-22 | 1997-09-22 | Reactor equipment |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP9256437A JPH1194978A (en) | 1997-09-22 | 1997-09-22 | Reactor equipment |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH1194978A true JPH1194978A (en) | 1999-04-09 |
Family
ID=17292657
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP9256437A Pending JPH1194978A (en) | 1997-09-22 | 1997-09-22 | Reactor equipment |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH1194978A (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2015072149A (en) * | 2013-10-02 | 2015-04-16 | 株式会社東芝 | Nuclear reactor |
| JP2016003908A (en) * | 2014-06-16 | 2016-01-12 | 株式会社東芝 | Reactor bottom protection structure of nuclear reactor pressure vessel |
-
1997
- 1997-09-22 JP JP9256437A patent/JPH1194978A/en active Pending
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2015072149A (en) * | 2013-10-02 | 2015-04-16 | 株式会社東芝 | Nuclear reactor |
| JP2016003908A (en) * | 2014-06-16 | 2016-01-12 | 株式会社東芝 | Reactor bottom protection structure of nuclear reactor pressure vessel |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| JP3150451B2 (en) | Reactor equipment | |
| JP2013015375A (en) | Reactivity suppression method for nuclear fuel and reactivity suppression device therefor | |
| JPH1194978A (en) | Reactor equipment | |
| EP0632470A1 (en) | Corium shield | |
| GB1492420A (en) | System for the heat-insulation of horizontal closure surfaces in a nuclear reactor of the liquid-metal cooled type | |
| KR101967583B1 (en) | Cooling system comprising thermal insulating barrier for external cooling in nuclear reactor vessel | |
| KR100984017B1 (en) | Inner-wall structure for protecting a reactor vessel in the event of core melting accidecnt | |
| JPH0843575A (en) | Core catcher | |
| JP2003240887A (en) | Nuclear reactor pressure vessel | |
| WO2013150750A1 (en) | Structure for protecting penetrating part of reactor pressure vessel, and reactor | |
| Frano et al. | Innovative engineering safeguards to cope with corium relocation: identification of loads and failure modes | |
| JP2902142B2 (en) | Melting core cooling equipment | |
| WO2015089662A1 (en) | Nuclear reactor safety system | |
| JP5851357B2 (en) | Retainer for core melt | |
| JP3125596B2 (en) | Emergency core cooling equipment for nuclear reactors | |
| KR102483114B1 (en) | Core catcher with improved cooling performance and a manufacturing method thereof | |
| CN1150566C (en) | Gap structure for nuclear reactor pressure vessel | |
| JPS60238788A (en) | Liquid metal cooling type nuclear reactor | |
| JPS59133488A (en) | Incore structure for liquid metal cooled type fast breeder | |
| JP3774373B2 (en) | Molecular beam source cell | |
| JPH08189986A (en) | Structure for fixing pressure vessel housing | |
| JPH0821889A (en) | Fuel assembly for fast breeder reactor | |
| JP6101185B2 (en) | Reactor | |
| JPH1184051A (en) | Reactor container | |
| JPH055795A (en) | Nuclear reactor containment vessel |