JPS60202388A - Inhibitor for leakage of radioactive sodium aerosol - Google Patents
Inhibitor for leakage of radioactive sodium aerosolInfo
- Publication number
- JPS60202388A JPS60202388A JP59059099A JP5909984A JPS60202388A JP S60202388 A JPS60202388 A JP S60202388A JP 59059099 A JP59059099 A JP 59059099A JP 5909984 A JP5909984 A JP 5909984A JP S60202388 A JPS60202388 A JP S60202388A
- Authority
- JP
- Japan
- Prior art keywords
- sodium
- fire
- main cooling
- building
- aerosol
- 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
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) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.
Description
【発明の詳細な説明】
［発明の技術分野］
本発明は液体金属ナトリウム型高速ｍＷＪ炉の原子炉格
納施設内で発生するナトリウム火災時に放射性ナトリウ
ムエアロゾルの環境への漏洩を低減するｌｌ１Ｑ’ｌ性
ナトリウムエアロゾルの漏洩抑制装置に関する。Detailed Description of the Invention [Technical Field of the Invention] The present invention provides a method for reducing the leakage of radioactive sodium aerosol into the environment during a sodium fire that occurs in a reactor containment facility of a liquid metal sodium fast mWJ reactor. This invention relates to a sodium aerosol leakage suppression device.
［発明の技術的背景とその問題点］
一般に液体金属ナトリウム型高速増殖炉にＪ３いては、
−次冷却材として液体全屈ナトリウムが使用されている
。[Technical background of the invention and its problems] In general, liquid metal sodium fast breeder reactor J3 has
-Liquid total flex sodium is used as the secondary coolant.
第１図は液体金属ナトリウム形高速増殖炉の原子炉格納
施設を示すもので、図におい°Ｃ符号１は原子炉格納容
器外部遮蔽壁を示しており、この原子炉格納容器外部遮
蔽壁１内には原子炉格納容器２が収容されている。原子
炉格納容器２の下部中央部には原子炉容器室３が配設さ
れ、この原子炉容器室３内には炉心４を収容する原子炉
容器５が収容されている。Figure 1 shows a reactor containment facility for a liquid metal sodium fast breeder reactor. A reactor containment vessel 2 is housed in the reactor containment vessel 2. A reactor vessel chamber 3 is provided in the lower center of the reactor containment vessel 2, and a reactor vessel 5 that accommodates a reactor core 4 is housed within this reactor vessel chamber 3.
原子炉容器５内には液体金属ナトリウムが収容され、ま
た上端開口部は遮蔽プラグ６により閉塞され、遮蔽プラ
グ６に穿設された貫通孔には制御棒駆動機構７が配設さ
れＣいる。Liquid metal sodium is contained in the reactor vessel 5, and the upper end opening is closed by a shielding plug 6, and a control rod drive mechanism 7 is disposed in a through hole formed in the shielding plug 6.
原子炉容器室３に隣接して一次主冷却至８が配設されて
おり、この−法主冷却室８内には中間熱交換器９および
一次主冷却系循環ボンブ１０が配設されている。A primary main cooling chamber 8 is disposed adjacent to the reactor vessel chamber 3, and an intermediate heat exchanger 9 and a primary main cooling system circulation bomb 10 are disposed within this main cooling chamber 8. .
ずなわら、炉心４内でエネルギーを得た液体全屈ナトリ
ウムは、−法主冷却室８内に移送され、中間熱交換器９
により二次冷却材と熱交換した後、−次主冷Ｎ１系循環
ポンプ１０により再び原子炉容”器５内へ循環される。The liquid total flex sodium that has obtained energy in the reactor core 4 is then transferred to the primary cooling chamber 8 and transferred to the intermediate heat exchanger 9.
After exchanging heat with the secondary coolant, it is circulated again into the reactor vessel 5 by the secondary main cold N1 system circulation pump 10.
原子炉容器室３および一次主冷却室８の上部には仕切壁
１１が形成され、この仕切壁１１と原子炉格納容器２に
より床上建屋１２が形成されている。A partition wall 11 is formed above the reactor vessel chamber 3 and the primary main cooling chamber 8, and the partition wall 11 and the reactor containment vessel 2 form an above-floor building 12.
以上のＪ、うに構成された原子炉格納施設では、例えば
−法主冷却室８内で液体金属ナトリウムを循環Ｊる一次
主冷却系配管１３が破断した場合には、−法主冷却室８
内においてナトリウム火災が生ずる。In the reactor containment facility configured as described above, for example, if the primary main cooling system piping 13 that circulates liquid metal sodium in the main cooling room 8 breaks, - the main cooling room 8
A sodium fire occurs inside the building.
づなわち一般に、このような場合を考慮し、−次主冷Ｎ
１室８内は窒素雰囲気とされているが、実際には約３％
程度の酸素が存在しており、破断口から流出する液体全
屈ナトリウムはこの酸素と結合し、Ｎａ２ＯまたはＮａ
２Ｏ２からなるエーロゾルを生ずる。このエアロゾルは
数μｍから数十μｍの粒子Ｃあり、火災による一次主冷
却室８内の圧力上昇により一次主冷却室８から床上建屋
１２へ漏洩し、さらにこの床上建屋１２から原子炉格納
容器２外へ漏洩し、環境汚染を引き起こす（１３それが
ある。That is, in general, considering such a case, -th primary cold N
Room 18 is said to have a nitrogen atmosphere, but in reality it is about 3% nitrogen.
There is a certain amount of oxygen present, and the liquid total flex sodium flowing out from the fracture combines with this oxygen to form Na2O or Na
Produces an aerosol consisting of 2O2. This aerosol has particles C ranging from several μm to several tens of μm, and due to the pressure increase in the primary main cooling chamber 8 due to the fire, it leaks from the primary main cooling chamber 8 to the floor building 12, and then from this floor building 12 to the reactor containment vessel 2. It leaks outside and causes environmental pollution (13).
［発明の目的］
本発明はかかる従来の事情に対処してなされたもので、
液体金属ナトリウム型畠速増殖炉の原子炉格納施設内で
発生するナトリウム火災時に放射性ナトリウムエアロゾ
ルの環境への漏洩を低減り−ることのできる放射性ナト
リウムエアロゾルの漏洩抑制装置を提供しようとするも
のである。[Object of the invention] The present invention has been made in response to such conventional circumstances,
The purpose of the present invention is to provide a radioactive sodium aerosol leakage suppression device that can reduce the leakage of radioactive sodium aerosol into the environment in the event of a sodium fire occurring in the reactor containment facility of a liquid metal sodium type Hatsaya breeder reactor. be.
［発明の概要］
すなわら本発明は、原子炉容器内へ液体金属ナトリウム
を循環する配管を収容する建屋内でナトリウム火災時に
発生する酸化ナトリウムからなるエアロゾルの前記建屋
外への漏洩を防止する放射性ナトリウムエアロゾルの漏
洩抑制装置におい゛（、前記建屋内におけるナトリウム
火災を検出する火災検出器と、この火災検出器からの火
災信号を入力し前記ｊｌ屋内へ固体状の二酸化炭素を噴
出する二酸化炭素供給装置とを備えたことを特徴とする
放射性ナトリウムエアロゾルの漏洩抑制装置である。[Summary of the Invention] In other words, the present invention prevents the leakage of aerosols made of sodium oxide generated in the event of a sodium fire in a building housing piping for circulating liquid metal sodium into a nuclear reactor vessel to the outside of the building. The radioactive sodium aerosol leak suppression system includes a fire detector that detects a sodium fire in the building, and a carbon dioxide detector that receives a fire signal from the fire detector and spouts solid carbon dioxide into the building. This is a radioactive sodium aerosol leakage suppression device characterized by comprising a supply device.
［発明の実施例］
以上本発明の詳細を図面に示す一実施例について説明づ
゛る。[Embodiment of the Invention] Hereinafter, an embodiment of the present invention will be described in detail as shown in the drawings.
第２図は本発明の放射性ナトリウムエアＬ１ゾルの漏洩
抑制装置を一次主冷却室に適用した例を示りｂのぐ、図
において符号８は一次主冷却室を示しＣいる。この−法
主冷却室８内には原子炉容器５内の液体金属ナトリウム
を再循環する一次冷却系循環ポンプ１０が配設されＣお
り、また−法主冷却系配管１３内の液体金属ナトリウム
と二次冷却材とを熱交換する中間熱交換器９が配設され
ている。FIG. 2 shows an example in which the radioactive sodium air L1 sol leakage suppression device of the present invention is applied to a primary main cooling chamber. In the figure, reference numeral 8 indicates the primary main cooling chamber. A primary cooling system circulation pump 10 for recirculating the liquid metal sodium in the reactor vessel 5 is disposed within the main cooling chamber 8, and the liquid metal sodium in the main cooling system piping 13 is also recirculated. An intermediate heat exchanger 9 is provided to exchange heat with the secondary coolant.
図において符号１４は一次主冷却室８内に発生した火災
を検出する火災検ｌＪ１器を示している。この火災検出
器１４は一次主冷却室８内の放射能の変化または温度変
化により一次主冷却室８内のナトリウム火災を検出する
。−法主冷却室８の天井中央部には複数の細孔ノズルを
右する二酸化炭素噴出器１５が配設されでいる。この二
酸化炭素噴出器１５は加圧された二酸化炭素を収容し−
Ｃなるボンベ１６に配管１７を介しＣ接続されており、
この配管１７には開閉弁１８が介挿されている。In the figure, reference numeral 14 indicates a fire detector 1J1 for detecting a fire occurring within the primary main cooling chamber 8. This fire detector 14 detects a sodium fire in the primary main cooling chamber 8 based on a change in radioactivity or a change in temperature within the primary main cooling chamber 8. - A carbon dioxide ejector 15 having a plurality of small hole nozzles is disposed in the center of the ceiling of the main cooling room 8. This carbon dioxide ejector 15 contains pressurized carbon dioxide.
C is connected to a cylinder 16 called C via piping 17,
An on-off valve 18 is inserted into this pipe 17.
図において符号１９は火災検出器１４からの火災信−号
を入力し、前述した開閉弁１８を間とする制御装置を示
しでいる。In the figure, reference numeral 19 indicates a control device to which a fire signal from the fire detector 14 is input, and which has the above-mentioned on-off valve 18 in between.
すなわち、以上のような一次主冷却室８では、が生じた
時には放射能を帯びた液体金属ナトリウン−次主冷却配
管１３に亀裂が生じた時または破断ム２０が一次主冷却
室８内に漏洩し、ナトリウム火災が発生しナトリウムは
酸素ど結合しＮａ２ＯまたはＮａ２Ｏ２のエアロゾルが
発生する。That is, in the primary main cooling chamber 8 as described above, when a crack occurs in the radioactive liquid metal sodium-secondary main cooling pipe 13 or the broken dam 20 leaks into the primary main cooling chamber 8. However, a sodium fire occurs and sodium combines with oxygen, generating an aerosol of Na2O or Na2O2.
しかしながら、以上のように４を成された放射性ナトリ
ウムエアロゾルの漏洩抑制装置ひは、ナトリウム火災は
火災検出器１４により検出され制御装置１９へ出力され
、この制御装置１９により開閉弁１８が間とされる。こ
の結果、ボンベ１６内に圧縮状態で収容されている二酸
化炭素が配管１７を通り二酸化炭素噴出器１５の細孔ノ
ズルから一次主冷却室８内へ噴出する。このとぎ二酸化
炭素は雪状の固体状態となり、火災による圧力上昇にま
り上りへ移動してきたエアロゾル粒子と衝突し凝集を促
進させ、これによりエアロゾルは一次主冷却室ｊ室８か
ら漏洩することなく、−法主冷却室８の床」−に多量に
落下する。However, in the radioactive sodium aerosol leak suppression system constructed as described above, a sodium fire is detected by the fire detector 14 and output to the control device 19, and the control device 19 closes the on-off valve 18. Ru. As a result, the carbon dioxide contained in the cylinder 16 in a compressed state passes through the pipe 17 and is ejected from the small hole nozzle of the carbon dioxide ejector 15 into the primary main cooling chamber 8 . This shaved carbon dioxide becomes a snow-like solid state, collides with aerosol particles that have moved upward due to the increase in pressure caused by the fire, and promotes aggregation. As a result, the aerosol does not leak from the primary main cooling room J chamber 8. A large amount of water fell onto the floor of the master cooling room 8.
また、二酸化炭素の冷ＩＪＪ作用によりエアロゾルは壁
面に凝縮することとなる。さらに二酸化炭素はツートリ
ウム火災を抑制する効果をもつことが実験的に検証され
でおり、従つ【ナトリウム火災も同時に消火することか
できる。この結果、−法主冷却室８からの放射性液体全
屈ナトリウムエアロゾルの漏洩を従来より大幅に低減す
ることができる。Further, the aerosol will condense on the wall surface due to the cold IJJ action of carbon dioxide. Furthermore, it has been experimentally verified that carbon dioxide has the effect of suppressing tsutorium fires, and therefore [sodium fires can also be extinguished at the same time]. As a result, the leakage of the radioactive liquid total bending sodium aerosol from the main cooling chamber 8 can be significantly reduced compared to the conventional method.
なお以上述べた実施例では、−法主冷却室８内に火災検
出器１４および二酸化炭素噴出器１５を設けた例につい
て説明しＩＣが、本発明はかかる実施例に限定されるも
のでなく、床上建屋１２内に火災検出器を設け、さらに
この床上建屋１２の頂部に二酸化炭素噴出器を配設し、
床上建屋１２内で一次主冷却室８から漏洩し’Ｕ＜るナ
トリウムのエアロゾル粒子の凝集を促進さぜ′（もよい
ことは勿論Ｃ゛ある。In addition, in the embodiment described above, an example in which a fire detector 14 and a carbon dioxide ejector 15 are provided in the main cooling chamber 8 is explained, and the IC is not limited to this embodiment. A fire detector is provided in the floor building 12, and a carbon dioxide ejector is provided at the top of the floor building 12.
It is of course advantageous to promote agglomeration of sodium aerosol particles leaking from the primary main cooling chamber 8 in the above-floor building 12.
［発明の効果］
以上述べたように本発明の放射性す］〜リウム土アロゾ
ルの漏洩抑制装置によれば、原子炉格納施設内ぐ発生す
るナトリウム火災時にａ３ける放射性ナトリウムエアロ
ゾルの環境への漏洩を従来より大幅に低減することがで
きる。[Effects of the Invention] As described above, the radioactive sodium aerosol leakage suppression device of the present invention prevents the leakage of radioactive sodium aerosol into the environment during a sodium fire that occurs in a nuclear reactor containment facility. This can be significantly reduced compared to conventional methods.
第１図は原子炉格納施設を示す縦断面図、第２図は本発
明の放射性ナトリウム土アロゾルの漏洩抑制装置の一実
施例を一次主冷却室に適用した状態を示す一次主冷却室
の縦断面図である。
２・・・・・・・・・・・・原子炉格納容器５・・・・
・・・・・・・・原子炉容器８・・・・・・・・・・・
・−法主冷却室１２・・・・・・・・・・・・床上建屋
１４・・・・・・・・・・・・火災検出器１５・・・・
・・・・・・・・二酸化炭素噴出器代理人弁理士須山佐
−
第１図
第２図Fig. 1 is a vertical cross-sectional view showing the reactor containment facility, and Fig. 2 is a longitudinal cross-sectional view of the primary main cooling room, showing a state in which an embodiment of the radioactive sodium earth arosol leakage suppression device of the present invention is applied to the primary main cooling room. It is a front view. 2... Reactor containment vessel 5...
・・・・・・Reactor vessel 8・・・・・・・・・・・・
- Main cooling room 12... Floor building 14... Fire detector 15...
・・・・・・・・・Carbon dioxide ejector representative patent attorney Suyama Sa - Figure 1 Figure 2
Claims (1)
管を収容する建屋内でナトリウム火災時に発生づる酸化
ナトリウムからなるエアロゾルの前記建屋外への漏洩を
防止する放射性ナトリウムエアＵゾルの漏洩抑制装置に
おいて、前記建屋内にＪ５けるナトリウム火災を検出す
る火災検出器と、この火災検出器からの火災信号を入力
し前記建屋内へ固体状の二酸化炭素を噴出する二酸化炭
素供給装置とを備えたことを特徴とする放射性ナトリウ
ムエアロゾルの漏洩抑制装置。(1> Radioactive sodium aerosol leakage control device that prevents aerosols made of sodium oxide generated in the event of a sodium fire from leaking to the outside of the building in a building that houses piping that circulates liquid metal sodium into the reactor vessel. , comprising a fire detector for detecting a J5 sodium fire in the building, and a carbon dioxide supply device for inputting a fire signal from the fire detector and spouting solid carbon dioxide into the building. A radioactive sodium aerosol leakage suppression device characterized by:
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP59059099A JPS60202388A (en) | 1984-03-27 | 1984-03-27 | Inhibitor for leakage of radioactive sodium aerosol |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP59059099A JPS60202388A (en) | 1984-03-27 | 1984-03-27 | Inhibitor for leakage of radioactive sodium aerosol |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS60202388A true JPS60202388A (en) | 1985-10-12 |
Family
ID=13103544
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP59059099A Pending JPS60202388A (en) | 1984-03-27 | 1984-03-27 | Inhibitor for leakage of radioactive sodium aerosol |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS60202388A (en) |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2017066411A1 (en) * | 2015-10-16 | 2017-04-20 | Ge-Hitachi Nuclear Energy Americas Llc | Passive fire response system and method of manufacturing |
| JP2018503424A (en) * | 2014-12-22 | 2018-02-08 | ジーイー−ヒタチ・ニュークリア・エナジー・アメリカズ・エルエルシーＧｅ−Ｈｉｔａｃｈｉ Ｎｕｃｌｅａｒ Ｅｎｅｒｇｙ Ａｍｅｒｉｃａｓ， Ｌｌｃ | Method and system for suppressing pyrophoric metal fires |
| JP2019027955A (en) * | 2017-07-31 | 2019-02-21 | 三菱重工業株式会社 | Nuclear facility, dry ice supplying device, and method for suppressing radioactive material |
| CN111276269A (en) * | 2020-03-16 | 2020-06-12 | 上海交通大学 | Device and method for verifying aerosol retention efficiency of narrow slit of penetrating piece |
-
1984
- 1984-03-27 JP JP59059099A patent/JPS60202388A/en active Pending
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2018503424A (en) * | 2014-12-22 | 2018-02-08 | ジーイー−ヒタチ・ニュークリア・エナジー・アメリカズ・エルエルシーＧｅ−Ｈｉｔａｃｈｉ Ｎｕｃｌｅａｒ Ｅｎｅｒｇｙ Ａｍｅｒｉｃａｓ， Ｌｌｃ | Method and system for suppressing pyrophoric metal fires |
| WO2017066411A1 (en) * | 2015-10-16 | 2017-04-20 | Ge-Hitachi Nuclear Energy Americas Llc | Passive fire response system and method of manufacturing |
| US10004929B2 (en) | 2015-10-16 | 2018-06-26 | Ge-Hitachi Nuclear Energy Americas Llc | Passive fire response system and method of manufacturing |
| JP2019027955A (en) * | 2017-07-31 | 2019-02-21 | 三菱重工業株式会社 | Nuclear facility, dry ice supplying device, and method for suppressing radioactive material |
| CN111276269A (en) * | 2020-03-16 | 2020-06-12 | 上海交通大学 | Device and method for verifying aerosol retention efficiency of narrow slit of penetrating piece |
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