JPH02136789A - Outflow preventive wall for reactor core melt - Google Patents
Outflow preventive wall for reactor core meltInfo
- Publication number
- JPH02136789A JPH02136789A JP63290016A JP29001688A JPH02136789A JP H02136789 A JPH02136789 A JP H02136789A JP 63290016 A JP63290016 A JP 63290016A JP 29001688 A JP29001688 A JP 29001688A JP H02136789 A JPH02136789 A JP H02136789A
- Authority
- JP
- Japan
- Prior art keywords
- reactor
- core melt
- reactor core
- preventive wall
- direct contact
- 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
- 230000003449 preventive effect Effects 0.000 title abstract 4
- 239000004567 concrete Substances 0.000 claims abstract description 3
- 230000001629 suppression Effects 0.000 claims description 3
- 239000002826 coolant Substances 0.000 claims 2
- 239000011150 reinforced concrete Substances 0.000 abstract description 10
- NJPPVKZQTLUDBO-UHFFFAOYSA-N novaluron Chemical compound C1=C(Cl)C(OC(F)(F)C(OC(F)(F)F)F)=CC=C1NC(=O)NC(=O)C1=C(F)C=CC=C1F NJPPVKZQTLUDBO-UHFFFAOYSA-N 0.000 abstract description 9
- 239000011449 brick Substances 0.000 abstract 1
- 239000011162 core material Substances 0.000 description 18
- 239000012768 molten material Substances 0.000 description 8
- 230000002265 prevention Effects 0.000 description 7
- 230000000694 effects Effects 0.000 description 2
- 238000005516 engineering process Methods 0.000 description 1
- 238000007689 inspection Methods 0.000 description 1
- 239000007788 liquid Substances 0.000 description 1
- 238000012423 maintenance Methods 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 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
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
Description
【発明の詳細な説明】
〔産業上の利用分野〕
本発明は、原子炉格納容器に係り、特に、炉心溶融を想
定した苛酷事故下における炉心溶融物の直接接触による
原子炉格納容器の破損を防止する構造に関する。[Detailed Description of the Invention] [Field of Industrial Application] The present invention relates to a nuclear reactor containment vessel, and in particular, to a method for preventing damage to the reactor containment vessel due to direct contact with molten material in a severe accident assuming a core meltdown. Regarding the structure to prevent.
この種の原子炉格納容器として、従来のマーク1原子炉
格納容器の縦断面を示したのが第3図で、1は原子炉圧
力容器、2は原子炉格納容器ドライウェルシェル、3は
サプレッションチェンバトーラスシェル、4はベント管
、5はプール水である。Figure 3 shows a vertical cross section of the conventional Mark 1 reactor containment vessel, which is used as this type of reactor containment vessel. 1 is the reactor pressure vessel, 2 is the reactor containment dry well shell, and 3 is the suppression vessel. Chamber torus shell, 4 is a vent pipe, and 5 is pool water.
原子炉格納容器ドライウェルシェル2の内部にはドライ
ウェル内底部鉄筋コンクリート部7が設けられ、これと
一体をなす原子炉圧力容器ペデスタル8によって原子炉
圧力容器1、および、原子炉遮蔽壁9が固定されている
。、6は、ドライウェル外側鉄筋コンクリート部、10
は、原子炉格納容器シールドウオールである。Inside the reactor containment vessel dry well shell 2, a dry well inner bottom reinforced concrete part 7 is provided, and the reactor pressure vessel 1 and the reactor shielding wall 9 are fixed by a reactor pressure vessel pedestal 8 that is integrated with this. has been done. , 6 is the outside reinforced concrete part of the dry well, 10
is the reactor containment vessel shield wall.
原子炉圧力容器ペデスタル8には、原子炉圧力容器1の
下部における保守2点検作業のため開[]11が設けら
れており、原子炉圧力容器ペデスタル8の内部、および
、外部空間をつなぐ役割りを果している。The reactor pressure vessel pedestal 8 is provided with an opening 11 for maintenance and inspection work at the lower part of the reactor pressure vessel 1, and serves to connect the inside of the reactor pressure vessel pedestal 8 with the outside space. is fulfilled.
第2図に示したようなマーク■原子炉格納容器では、炉
心溶融を想定した苛酷事故下に炉心m融物が原子炉圧力
容器ペデスタル8の内部空間に蓄積された後、開口11
を通ってドライウェル内底部鉄筋コンクリート部7へ流
出し、さらに、原子炉格納容器ドライウェルシェル2へ
到達することが考えられる。このように炉心溶融物が原
子炉格納容器ドライウェルシェル2へ到達した場合、原
子炉格納容器を破損させることが考えられる。Marks as shown in Figure 2 - In the reactor containment vessel, after core melt has accumulated in the internal space of the reactor pressure vessel pedestal 8 under a severe accident assuming a core meltdown, the opening 11
It is conceivable that the liquid may flow through the dry well to the inner bottom reinforced concrete part 7 and further reach the reactor containment vessel dry well shell 2. If the core molten material reaches the reactor containment vessel dry well shell 2 in this way, it is possible that the reactor containment vessel will be damaged.
本発明の目的は、炉心溶融を想定した苛酷事故下におけ
る炉心溶融物による原子炉格納容器への直接接触を避は
短時間での破損を防ぐ流出防止壁を堤供することにある
。An object of the present invention is to provide an outflow prevention wall that prevents direct contact with the reactor containment vessel by molten material in the event of a severe accident assuming a core meltdown, and prevents damage in a short period of time.
上記目的は、炉心溶融物流出防止壁を、ドライウェル内
底部鉄筋コンクリート−ヒに設け、原子炉格納容器へ炉
心溶融物が到達することを防ぐことによって達成される
。The above object is achieved by providing a core melt outflow prevention wall in the reinforced concrete at the bottom of the drywell to prevent core melt from reaching the reactor containment vessel.
炉心溶融物流出防止壁は、コンクリート、もしくは、耐
火煉瓦などにより作られ、下部はドライウェル内底部鉄
筋コンクリートに密着される。それによって炉心i8F
!A物は、原子炉圧力容器ペデスタルと炉心溶融物流出
防止壁間に蓄積され、炉心溶融物による原子炉格納容器
への直接接触を避は短時間での破損が防止される。The core melt outflow prevention wall is made of concrete or firebrick, and its lower part is tightly attached to the reinforced concrete at the bottom of the drywell. As a result, the core i8F
! Item A is accumulated between the reactor pressure vessel pedestal and the core molten material outflow prevention wall, and damage to the reactor containment vessel is prevented in a short period of time by avoiding direct contact with the reactor containment vessel by the core molten material.
以下、本発明の一実施例を第1図により説明する。第1
図は、原子炉格納容器の縦断面図である。An embodiment of the present invention will be described below with reference to FIG. 1st
The figure is a longitudinal cross-sectional view of the reactor containment vessel.
炉心溶融物流出防止壁12は、鉄筋コンクリートにより
形成され、原子炉圧力容器ペデスタル8の外側のドライ
ウェル内底部鉄筋コンクリート7トに、原子炉圧力容器
ペデスタル8を取り囲むようしこ設置されている。炉心
溶融物流出防止壁12は、その基部においてドライウェ
ル内底部鉄筋コンクリート7にアンカされており、炉心
溶融物を蓄積する強度をもち、原子炉格納容器の炉心溶
融物による直接接触を避け、短時間での破損を防止する
。The core melt outflow prevention wall 12 is formed of reinforced concrete, and is installed in the reinforced concrete bottom of the dry well outside the reactor pressure vessel pedestal 8 so as to surround the reactor pressure vessel pedestal 8. The core molten material outflow prevention wall 12 is anchored to the drywell inner bottom reinforced concrete 7 at its base, has the strength to accumulate core molten material, avoids direct contact with the core molten material in the reactor containment vessel, and can be used for a short period of time. to prevent damage.
本発明によれば、炉心溶融を想定した苛酷事故下におい
て、炉心溶融物による原子炉格納容器l・の直接接触を
避は短時間での破損を防止する。According to the present invention, in a severe accident assuming a core meltdown, direct contact with the reactor containment vessel l by molten core material is avoided, thereby preventing damage in a short period of time.
第1図は、本発明の一実施例の原子炉格納容器の縦断面
図、第2図は、従来のマークI原子炉格納容器の縦断面
図である。
8・・原子炉圧力容器ペデスタル、9・・・原子炉遮蔽
壁、10・・原子炉格納容器シールドウオール、11・
・・開口、12・炉心溶融物流出防止壁。
第10FIG. 1 is a longitudinal sectional view of a reactor containment vessel according to an embodiment of the present invention, and FIG. 2 is a longitudinal sectional view of a conventional Mark I reactor containment vessel. 8... Reactor pressure vessel pedestal, 9... Reactor shielding wall, 10... Reactor containment vessel shield wall, 11...
...Opening, 12. Core melt outflow prevention wall. 10th
Claims (1)
れた圧力抑制室と、一端が前記密封容器に連絡され、他
端が前記圧力抑制室内の前記冷却材に浸漬されるベント
管とを含む原子炉格納容器において、 ドライウェル内の底部コンクリートマット上に設けるこ
とを特徴とする炉心溶融物の流出防止壁。[Scope of Claims] 1. A sealed vessel containing a reactor vessel, a pressure suppression chamber filled with a coolant, one end of which is connected to the sealed vessel, and the other end of which is connected to the coolant in the pressure suppression chamber. A reactor containment vessel including a vent pipe to be immersed, the wall for preventing the outflow of reactor core melt, characterized by being provided on a bottom concrete mat in a dry well.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP63290016A JPH02136789A (en) | 1988-11-18 | 1988-11-18 | Outflow preventive wall for reactor core melt |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP63290016A JPH02136789A (en) | 1988-11-18 | 1988-11-18 | Outflow preventive wall for reactor core melt |
Publications (1)
Publication Number | Publication Date |
---|---|
JPH02136789A true JPH02136789A (en) | 1990-05-25 |
Family
ID=17750695
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP63290016A Pending JPH02136789A (en) | 1988-11-18 | 1988-11-18 | Outflow preventive wall for reactor core melt |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPH02136789A (en) |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
KR100465958B1 (en) * | 2000-11-09 | 2005-01-13 | 주식회사 포스코 | Apparatus for blocking outflow of melting steel in electric furnace |
US9025721B2 (en) | 2010-03-29 | 2015-05-05 | Kabushiki Kaisha Toshiba | Holding device |
-
1988
- 1988-11-18 JP JP63290016A patent/JPH02136789A/en active Pending
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
KR100465958B1 (en) * | 2000-11-09 | 2005-01-13 | 주식회사 포스코 | Apparatus for blocking outflow of melting steel in electric furnace |
US9025721B2 (en) | 2010-03-29 | 2015-05-05 | Kabushiki Kaisha Toshiba | Holding device |
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