JP2813360B2 - Containment vessel leak prevention equipment - Google Patents
Containment vessel leak prevention equipmentInfo
- Publication number
- JP2813360B2 JP2813360B2 JP1011588A JP1158889A JP2813360B2 JP 2813360 B2 JP2813360 B2 JP 2813360B2 JP 1011588 A JP1011588 A JP 1011588A JP 1158889 A JP1158889 A JP 1158889A JP 2813360 B2 JP2813360 B2 JP 2813360B2
- Authority
- JP
- Japan
- Prior art keywords
- containment vessel
- containment
- pressure
- equipment
- leak prevention
- 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 - Fee Related
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
-
- 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
- Installation Of Indoor Wiring (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Description
【発明の詳細な説明】 ［産業上の利用分野］ この発明は仮想事故対策としての原子炉格納容器漏洩
防止設備に関するものである。Description: TECHNICAL FIELD The present invention relates to a facility for preventing a containment vessel from leaking as a countermeasure against a virtual accident.
［従来の技術］ 第２図に従来の負圧方式アニュラス設備の系統図を示
す。[Prior Art] FIG. 2 shows a system diagram of a conventional negative pressure type annulus equipment.
原子力発電プラントは冷却材管破断等の事故を想定し
てもなお放射性物質が原子炉格納容器の外に漏れ出るこ
とがないように万全の対策を施すと共に、格納容器漏洩
検査を実施し、漏洩のないことを確認している。The nuclear power plant will take all possible measures to prevent radioactive materials from leaking out of the PCV even if an accident such as a break in the coolant tube is assumed. Make sure there is no.
しかし、第２図に示すように原子炉格納容器１には、
その格納容器壁を貫通する配線３や電線４の貫通部があ
り、この貫通部には例えば配管貫通部にあっては配管貫
通スリーブ３′、電線貫通部にあっては電線貫通スリー
ブ４′を用いて気密を保持している。これら貫通スリー
ブは構造が複雑であることから、格納容器の漏洩想定箇
所とされており、その対策も講じられている。However, as shown in FIG.
There is a penetrating portion of the wiring 3 and the electric wire 4 penetrating the containment container wall. For example, the penetrating portion includes a pipe penetrating sleeve 3 ′ in a pipe penetrating portion and a wire penetrating sleeve 4 ′ in a wire penetrating portion. It is used to maintain airtightness. Since these penetrating sleeves have a complicated structure, they are assumed to be leaking locations of the containment vessel, and measures have been taken against them.
その１つに負圧方式アニュラス設備があり、配線貫通
部や電線貫通部から漏洩が生じたとしても、アニュラス
ルーフ10′で区画されるアニュラス10の空気をアニュラ
ス空気浄化ファン12にてアニュラス空気浄化フィルタユ
ニット11を介して放射性物質を取り除いた後、排気筒13
から外部へ放出することで、環境を保護する。One of them is a negative pressure type annulus equipment. Even if leakage occurs from the wire penetration or wire penetration, the air in the annulus 10 partitioned by the annulus roof 10 ′ is purified by the annulus air purification fan 12. After removing radioactive materials through the filter unit 11, the stack 13
Protect the environment by releasing from the outside.
他の方式としては、格納容器内の圧力を外気圧より少
し低くして、容器の壁を通る漏洩が常に外側から内側に
向うようにすることによって格納容器から放射性物質が
漏れ出ないようにする技術が知られている。（株式会産
報発行「原子炉安全性ハンドブック」P38） ［発明が解決しようとする課題］ 前者の負圧方式アニュラス設備の場合、機能を維持す
るためには、アニュラス空気浄化ファンを事故後長期間
運転する必要があり、そのための電源設備、制御設備を
設置する必要がある。Another approach is to keep the pressure inside the containment vessel slightly below ambient pressure so that leakage through the vessel wall is always from outside to inside so that no radioactive material leaks out of the containment vessel. The technology is known. (Problems to be solved by the invention) In the case of the former negative pressure annulus equipment, in order to maintain the function, the annulus air purification fan must be extended after the accident. It is necessary to operate for a period, and it is necessary to install power supply equipment and control equipment for that.
また、これらの設備は想定事故時に環境への放射性物
質の放出を抑制する設備であることから安全系設備とし
ての要求事項が適用される。従って、動的機能維持のた
めに必要とする設備が多数必要になり、また、放射性物
質を除去する設備も必要であり、設備が複雑となる問題
がある。In addition, since these facilities are facilities that suppress the release of radioactive materials into the environment in the event of a possible accident, the requirements for safety-related facilities are applied. Therefore, a large number of facilities required for maintaining the dynamic function are required, and a facility for removing radioactive substances is also required, which causes a problem that the facility becomes complicated.
後者の格納容器内を若干負圧にする技術にあっては、
通常運転時はよいとしても、格納容器内の圧力が上昇す
るような冷却材管破断事故時には内外の圧力関係が逆と
なるため、格納容器からの放射性物質の漏洩を抑止でき
ない問題がある。In the latter technology, where the pressure inside the containment vessel is slightly negative,
Even if it is good at the time of normal operation, there is a problem that the leakage of radioactive material from the containment vessel cannot be suppressed because the relationship between the inside and outside pressures is reversed in the case of a coolant pipe rupture accident in which the pressure inside the containment vessel rises.
この発明は前述の如き事情に鑑みてなされたものであ
り、設備簡素化が図れ、フィルタ等の交換部品も必要と
せず、しかも、事故時格納容器内の圧力が上昇するよう
な場合にあっても十分機能しうる格納容器漏洩防止設備
を提供することを目的とするものである。The present invention has been made in view of the above-described circumstances, and can simplify equipment, does not require replacement parts such as a filter, and is more suitable for a case where the pressure in the containment vessel at the time of an accident increases. It is another object of the present invention to provide a containment container leakage prevention device that can function sufficiently.
［課題を解決するための手段］ この目的に対応して、この発明の原子炉格納容器漏洩
防止設備は、格納容器の貫通部位である漏洩想定箇所を
包み込むように前記格納容器と同じ材料で構成され前記
格納容器の壁に気密に取り付けられた加圧室と、一端が
前記加圧室に連通し他の一端が弁を介して加圧装置に連
通した加圧ガス供給管からなることを特徴としている。[Means for Solving the Problems] In response to this object, the containment vessel leak prevention equipment of the present invention is made of the same material as that of the containment vessel so as to wrap around the expected leak location, which is a penetration part of the containment vessel. A pressurized chamber airtightly attached to the wall of the storage container, and a pressurized gas supply pipe having one end connected to the pressurized chamber and the other end connected to a pressurizing device via a valve. And
［作用］ この発明の漏洩防止設備では格納容器内で事故が生じ
た場合に、格納容器壁に貫通部分を覆う加圧室を加圧す
ることにより、加圧室の圧力が格納容器の内圧よりも大
きくなり、従って格納容器からの放射性物質の漏洩は防
止される。[Operation] In the leak prevention equipment according to the present invention, when an accident occurs in the containment vessel, the pressure in the pressurization chamber that covers the penetrating portion on the containment vessel wall is increased, so that the pressure in the pressurization chamber becomes higher than the internal pressure of the containment vessel. The leaks of radioactive material from the containment are thus prevented.
［実施例］ 以下、この発明の詳細を一実施例を示す図面について
説明する。[Embodiment] Hereinafter, details of the present invention will be described with reference to the drawings showing one embodiment.
第１図において符号１は原子炉格納容器、符号２は外
部遮蔽である。原子炉格納容器１の容器壁には配管や電
線の貫通部があり、これら貫通部は従来技術と同様、配
管貫通部にあっては配管貫通スリーブ３′を介して配管
３が貫通しており、電線貫通部にあっては電線貫通スリ
ーブ４′を介して電線４が貫通している。これら貫通部
は前述の通り漏洩の想定箇所となっているので、これら
漏洩の想定される箇所を包み込むように加圧室５が設け
られている。この加圧室５は、例えば原子炉格納容器と
同材質の金属から成り、格納容器壁へは溶接により気密
に取り付けられる。一方、配管３や電線４の貫通部は図
示していないが格納容器壁の貫通部と同様の貫通スリー
ブを用いるか、他のシール部材を用いて気密に接合（必
要に応じ摺動可能に）されている。符号６は加圧ガス供
給管であり一端が前記加圧室５に連通し他の一端は圧力
を調節するための弁７を介して加圧装置８に連通してい
る。この加圧装置は格納容器設計圧力を2.5km/cm2と仮
定すると、例えば3km/cm2程度の加圧ガス（空気、また
は、窒素・炭酸ガス・アルゴン等の不活性ガス）を供給
または発生しうる装置で足り、図示のものはボンベであ
るが、コンプレッサであってもよい。In FIG. 1, reference numeral 1 denotes a containment vessel, and reference numeral 2 denotes an external shield. The vessel wall of the containment vessel 1 has penetrations for pipes and electric wires, and these penetrations are located in the penetrations of the pipes through the pipe penetration sleeves 3 'as in the prior art. The electric wire 4 penetrates through the electric wire penetration portion via the electric wire penetration sleeve 4 '. As described above, these penetrating portions are assumed locations of leakage, so the pressurized chamber 5 is provided so as to surround the locations where these leakages are expected. The pressurizing chamber 5 is made of, for example, a metal of the same material as that of the containment vessel, and is hermetically attached to the containment vessel wall by welding. On the other hand, the penetration part of the pipe 3 and the electric wire 4 is not shown, but a penetration sleeve similar to the penetration part of the containment vessel wall is used, or another sealing member is used to hermetically join (slidably if necessary). Have been. Reference numeral 6 denotes a pressurized gas supply pipe having one end connected to the pressurizing chamber 5 and the other end connected to a pressurizing device 8 via a valve 7 for adjusting pressure. Assuming that the design pressure of the containment vessel is 2.5 km / cm 2 , this pressurizing device supplies or generates a pressurized gas (air or an inert gas such as nitrogen, carbon dioxide, or argon) of, for example, about 3 km / cm 2. The device shown is a cylinder, but may be a compressor.
また、弁７は加圧室５内の圧力を一定の圧力に維持す
るための圧力調節弁であり、図示のものは人為的操作に
より弁の開度を調節するものであるが、例えばこの弁を
モータ駆動弁とし、図示していないが圧力センサを格納
容器内に設置して格納容器内の圧力が異常（事故時）と
なった場合、この圧力センサの信号により弁７を開とす
る構成とすることもできる。The valve 7 is a pressure control valve for maintaining the pressure in the pressurizing chamber 5 at a constant pressure, and the valve shown in the figure controls the opening degree of the valve by a manual operation. Is a motor-driven valve, and a pressure sensor (not shown) is installed in the containment vessel, and when the pressure in the containment vessel becomes abnormal (at the time of an accident), the valve 7 is opened by a signal from the pressure sensor. It can also be.
更に、前述のようなセンサの利用は加圧装置８がコン
プレッサの場合、駆動信号としても適用しうる。Further, the use of the sensor as described above can also be applied as a drive signal when the pressurizing device 8 is a compressor.
なお、加圧室５については図示のものは貫通部の各々
について設けているが、複数の貫通部を包含する如き態
様で設置しうることはもちろんである。更に、この加圧
室は格納容器壁の外側に設けた例を開示しているが、格
納容器壁の内側に設けることもできる。そして、このよ
うな態様も本技術に包含されるものである。The pressurizing chamber 5 is provided for each of the through-holes in the drawing, but it is needless to say that the pressurizing chamber 5 can be installed in such a manner as to include a plurality of through-holes. Further, although an example in which the pressurized chamber is provided outside the containment vessel wall is disclosed, it may be provided inside the containment vessel wall. And such an aspect is also included in the present technology.
このように構成された格納容器漏洩防止設備において
は、加圧室を格納容器事故時内圧より高い圧力に加圧す
ることによって、格納容器からの放射性物質等の漏出を
防止できる。In the containment container leakage prevention equipment configured as described above, the pressurizing chamber is pressurized to a pressure higher than the internal pressure at the time of the containment accident, so that leakage of radioactive substances and the like from the containment container can be prevented.
なお、通常運転時を含む常時加圧方式とすれば、運転
・制御を単純にできる。The operation and control can be simplified by adopting a constant pressurization method including a normal operation.
この加圧により、加圧室から格納容器内に漏洩が考え
られるが、現行のアニュラス設備設計基準の0.1パーセ
ント／日の漏洩量を想定したとしても、事故後30日で30
m3程度であり、格納容器の自由体積約50,000m3に対し、
無視できる量であり、格納容器の健全性が損われること
はない。Leakage from the pressurized room into the containment vessel due to this pressurization is conceivable, but even if the leak amount is assumed to be 0.1% / day of the current annulus equipment design standard, it will be 30 days after the accident.
a m 3 approximately, relative to the free volume of about 50,000 m 3 of the storage container,
It is negligible and does not compromise the integrity of the containment.
［発明の効果］ この発明によれば格納容器の配管貫通部や電線貫通部
等漏洩の想定される箇所を事故時の格納容器内圧より高
い圧力に保つ加圧機構（加圧室）が得られるので、格納
容器からの漏洩を確実に防止できる。[Effects of the Invention] According to the present invention, a pressurizing mechanism (pressurizing chamber) that keeps a location where leakage is expected, such as a pipe penetrating portion or an electric wire penetrating portion, of the containment vessel at a pressure higher than the containment vessel internal pressure at the time of the accident can be obtained. Therefore, leakage from the storage container can be reliably prevented.
更に、この発明の格納容器漏洩防止設備は従来の負圧
方式アニュラス設備に比べ、機能を維持するための付属
設備が少なくてすみ、設備の簡素化が図られ、しかも、
フィルタ等の交換部品を必要としないため、廃棄物の発
生を減少できる。また、アニュラスへの漏洩がなくな
り、想定事故時の放出放射能量及び被曝線量の低減が達
成される。Furthermore, the containment vessel leakage prevention equipment of the present invention requires less auxiliary equipment for maintaining its functions as compared with the conventional negative pressure type annulus equipment, and the equipment can be simplified.
Since no replacement parts such as filters are required, generation of waste can be reduced. In addition, there is no leakage to the annulus, and the amount of emitted radioactivity and radiation dose at the time of the assumed accident are reduced.
第１図はこの発明の一実施例に係わる原子炉格納容器漏
洩防止設備の系統図、第２図は従来の負圧方式アニュラ
ス設備の系統図である。 １……格納容器、２……外部遮蔽、 ３……配管、３′……配管貫通スリーブ、 ４……電線、４′……電線貫通スリーブ、 ５……加圧室、６……加圧ガス供給管、 ７……弁、８……加圧装置、 10……アニュラス、10′……アニュラスルーフFIG. 1 is a system diagram of a facility for preventing a containment vessel from leaking according to one embodiment of the present invention, and FIG. 2 is a system diagram of a conventional negative pressure type annulus system. DESCRIPTION OF SYMBOLS 1 ... Containment container, 2 ... External shielding, 3 ... Piping, 3 '... Piping penetration sleeve, 4 ... Electric wire, 4' ... Electric wire penetration sleeve, 5 ... Pressurizing chamber, 6 ... Pressurization Gas supply pipe, 7 Valve, 8 Pressurizing device, 10 Annulus, 10 'Annulus roof
───────────────────────────────────────────────────── フロントページの続き (56)参考文献 特開 昭63−43513（ＪＰ，Ａ) 実開 昭60−111299（ＪＰ，Ｕ) 実開 平２−67241（ＪＰ，Ｕ) 特公 昭57−14519（ＪＰ，Ｂ２) (58)調査した分野(Int.Cl.6，ＤＢ名) G21C 9/00 G21C 13/00 - 13/10 G21D 1/00 - 1/04──────────────────────────────────────────────────続 き Continuation of the front page (56) References JP-A-63-43513 (JP, A) JP-A-60-111299 (JP, U) JP-A-2-67241 (JP, U) 14519 (JP, B2) (58) Fields investigated (Int. Cl. 6 , DB name) G21C 9/00 G21C 13/00-13/10 G21D 1/00-1/04
Claims (1)
包み込むように前記格納容器と同じ材料で構成され前記
格納容器の壁に気密に取り付けられた加圧室と、一端が
前記加圧室に連通し他の一端が弁を介して加圧装置に連
通した加圧ガス供給管からなることを特徴とする原子炉
格納容器漏洩防止設備1. A pressurizing chamber made of the same material as the containment vessel and wrapped around the wall of the containment vessel so as to enclose a leakage expected portion which is a penetrating portion of the containment vessel, and one end of the pressurizing chamber. A reactor containment leak prevention device, characterized in that it comprises a pressurized gas supply pipe connected to the pressurizing device through a valve at the other end.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1011588A JP2813360B2 (en) | 1989-01-20 | 1989-01-20 | Containment vessel leak prevention equipment |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1011588A JP2813360B2 (en) | 1989-01-20 | 1989-01-20 | Containment vessel leak prevention equipment |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH02190799A JPH02190799A (en) | 1990-07-26 |
| JP2813360B2 true JP2813360B2 (en) | 1998-10-22 |
Family
ID=11782062
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP1011588A Expired - Fee Related JP2813360B2 (en) | 1989-01-20 | 1989-01-20 | Containment vessel leak prevention equipment |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JP2813360B2 (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106128523B (en) * | 2016-08-10 | 2018-06-26 | 长江勘测规划设计研究有限责任公司 | A kind of underground nuclear power station fluid-tight electrical penetration system |
Family Cites Families (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5714519A (en) * | 1980-06-30 | 1982-01-25 | Jiyon Sutefuenson Petsug Kiisu | Hair conditioning composition |
-
1989
- 1989-01-20 JP JP1011588A patent/JP2813360B2/en not_active Expired - Fee Related
Also Published As
| Publication number | Publication date |
|---|---|
| JPH02190799A (en) | 1990-07-26 |
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| LAPS | Cancellation because of no payment of annual fees |