JPH0423235B2 - - Google Patents
Info
- Publication number
- JPH0423235B2 JPH0423235B2 JP58022443A JP2244383A JPH0423235B2 JP H0423235 B2 JPH0423235 B2 JP H0423235B2 JP 58022443 A JP58022443 A JP 58022443A JP 2244383 A JP2244383 A JP 2244383A JP H0423235 B2 JPH0423235 B2 JP H0423235B2
- Authority
- JP
- Japan
- Prior art keywords
- containment vessel
- reactor
- water
- concentration
- leakage
- 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 - Lifetime
Links
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 49
- 238000000034 method Methods 0.000 claims description 10
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 description 13
- 239000001257 hydrogen Substances 0.000 description 11
- 229910052739 hydrogen Inorganic materials 0.000 description 11
- 239000000498 cooling water Substances 0.000 description 6
- 238000009835 boiling Methods 0.000 description 5
- 239000002826 coolant Substances 0.000 description 5
- 230000005855 radiation Effects 0.000 description 4
- ZCYVEMRRCGMTRW-UHFFFAOYSA-N 7553-56-2 Chemical compound [I] ZCYVEMRRCGMTRW-UHFFFAOYSA-N 0.000 description 2
- 239000007789 gas Substances 0.000 description 2
- 239000011630 iodine Substances 0.000 description 2
- 229910052740 iodine Inorganic materials 0.000 description 2
- 238000005070 sampling Methods 0.000 description 2
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 238000012790 confirmation Methods 0.000 description 1
- 238000001816 cooling Methods 0.000 description 1
- 238000007791 dehumidification Methods 0.000 description 1
- 230000003111 delayed effect Effects 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 150000002431 hydrogen Chemical class 0.000 description 1
- 238000013508 migration Methods 0.000 description 1
- 230000005012 migration Effects 0.000 description 1
- 238000012544 monitoring process Methods 0.000 description 1
- 239000001301 oxygen Substances 0.000 description 1
- 229910052760 oxygen Inorganic materials 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 239000012857 radioactive material Substances 0.000 description 1
- 238000003608 radiolysis reaction Methods 0.000 description 1
- 239000008400 supply water Substances 0.000 description 1
- 238000012546 transfer Methods 0.000 description 1
- 239000012808 vapor phase Substances 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
- Monitoring And Testing Of Nuclear Reactors (AREA)
Description
【発明の詳細な説明】
［発明の技術分野］
本発明は沸騰水形原子力発電プラントの格納容
器内において漏洩事故が発生した場合に、漏洩源
が蒸気系であるか冷却水系であるかを適確に判断
し得る原子炉格納容器における漏洩源の判別方法
に関する。[Detailed Description of the Invention] [Technical Field of the Invention] The present invention provides a method for determining whether the leak source is a steam system or a cooling water system when a leakage accident occurs in the containment vessel of a boiling water nuclear power plant. This invention relates to a method for accurately determining a leak source in a reactor containment vessel.
［発明の技術的背景］
沸騰水形原子力発電プラントにおいて、収納容
器内で漏洩事故が発生した場合、漏洩量がい一定
値を越えた際には、プラントの安全を確保するた
め、プラントの運転を停止し、漏洩源の探索と必
要な対策を講ずる必要がある。[Technical Background of the Invention] In a boiling water nuclear power plant, if a leakage accident occurs in the storage container and the amount of leakage exceeds a certain value, plant operation must be stopped to ensure plant safety. It is necessary to stop the operation, search for the source of the leak, and take necessary measures.
原子炉格納容器内に一次系からの漏洩が発生し
た場合には、まず、格納容器内の湿度上昇による
露点の上昇、格納容器内除湿系等における凝縮水
ドレン流量の増加、あるいは格納容器内放射線モ
ニタ指示の変化により、一次系からの格納容器内
漏洩を検知することができる。 If a leak occurs from the primary system inside the reactor containment vessel, the first thing to do is to increase the dew point due to an increase in the humidity inside the containment vessel, increase the flow rate of condensed water drain in the dehumidification system inside the containment vessel, or increase the radiation inside the containment vessel. Leakage from the primary system into the containment vessel can be detected by changes in monitor instructions.
また、格納容器内の雰囲気ガスの放射能測定
や、格納容器除湿系凝縮水ドレンの流入するサン
プ水中の放射能測定により放射性核種が検出され
た場合には、原子炉水、および蒸気系からの漏洩
を知ることは可能である。 In addition, if radionuclides are detected by measuring the radioactivity of the atmospheric gas inside the containment vessel or the radioactivity of the sump water flowing into the containment vessel dehumidifying system condensate water drain, it is necessary to It is possible to know about the leak.
［開閉技術の問題点］
しかしながら、従来は、漏洩源が原子炉水であ
るか蒸気系であるかの選択決定や漏洩量評価を定
量的に行なつていなかつたため、格納容器内での
一次系漏洩発生によるプラント停止後の漏洩源調
査を困難なものとし、対策が遅延するという不都
合があつた。[Problems with opening/closing technology] However, in the past, it was not possible to select whether the leak source was reactor water or the steam system, or to quantitatively evaluate the amount of leakage. This had the disadvantage of making it difficult to investigate the leak source after the plant was shut down due to a leak, and countermeasures were delayed.
第１図は、原子炉格納容器内において、一次系
から漏洩が発生した場合の格納容器内水素濃度、
露点、放射線モニタ指示及び漏洩量の変化の様子
を示している。 Figure 1 shows the hydrogen concentration in the containment vessel when a leak occurs from the primary system in the reactor containment vessel.
It shows changes in dew point, radiation monitor instructions, and leakage amount.
同図において、Ｋ点で格納容器内における一次
系からの漏洩が発生した場合、漏洩量は時間と共
に曲線Ａに示す様に増加する。 In the figure, when leakage occurs from the primary system in the containment vessel at point K, the amount of leakage increases as shown by curve A with time.
また、格納容器内には一次系漏洩に伴ない放射
性物質が持ち込まれるため、格納容器放射線モニ
タの指示も曲線Ｂの様に上昇する。 Furthermore, since radioactive materials are brought into the containment vessel due to the primary system leakage, the indication of the containment vessel radiation monitor also increases as shown by curve B.
一方、格納容器内に漏洩した一次系の冷却材に
より格納容器内露点の指示は曲線Ｄの様に変化す
る。 On the other hand, the indication of the dew point inside the containment vessel changes as shown by curve D due to the primary coolant leaking into the containment vessel.
ところで、原子炉水においては、原子炉冷却材
である水が中性子による放射線分解を受けると、
2H2O→2H2＋O2
の様な反応で水素ガスを生成する。この発生水素
ガスの一部は主蒸気中に移行し、一部は原子炉水
に溶解することになる。 By the way, in nuclear reactor water, when water, which is a reactor coolant, undergoes radiolysis by neutrons, hydrogen gas is generated through a reaction such as 2H 2 O→2H 2 +O 2 . A portion of this generated hydrogen gas will migrate into the main steam, and a portion will be dissolved in the reactor water.
この場合、主蒸気及び原子炉水の水素濃度は、
０℃、１気圧の標準状態の体積換算で約30cm3／Kg
−蒸気、及び0.22cm3／Kg−原子炉水となる。 In this case, the hydrogen concentration in main steam and reactor water is
Approximately 30cm 3 /Kg in terms of volume under standard conditions of 0℃ and 1 atm.
- steam, and 0.22cm 3 /Kg - reactor water.
このことから、一次系の主蒸気や原子炉水が格
納容器内に漏洩した場合には、非凝縮性ガスであ
る水素濃度は、時間と共に上昇し、第１図の直線
C1、C2の様に変化する。従つて、原子炉水と主
蒸気の漏洩量が同じ場合には、蒸気漏洩による水
素濃度変化C1は原子炉水漏洩による水素濃度上
昇特性C2の約170倍になる。 From this, if main steam in the primary system or reactor water leaks into the containment vessel, the concentration of hydrogen, which is a non-condensable gas, will increase over time, and the concentration of hydrogen will increase as shown in Figure 1.
It changes like C 1 and C 2 . Therefore, when the leakage amounts of reactor water and main steam are the same, the hydrogen concentration change C 1 due to steam leakage is approximately 170 times the hydrogen concentration increase characteristic C 2 due to reactor water leakage.
また、原子炉水中に存在する放射性核種のうち
沃素核種であるＩ−131、Ｉ−135等は炉水濃度の
２×10-2程度が主蒸気中に移行し、Na−24、Mn
−56等の放射性核種は10-4程度が主蒸気に移行す
ることが経験的に知られている。 In addition, among the radionuclides present in the reactor water, iodine nuclides such as I-131 and I-135 are transferred into the main steam at a concentration of about 2 × 10 -2 , Na-24, Mn
It is empirically known that about 10 -4 of radionuclides such as -56 are transferred to the main steam.
従つて、例えば原子炉水中のＩ−131、Na−24
の放射能濃度をそれぞれAμc／ml、Bμc／mlとす
ると、主蒸気中のＩ−131濃度とNa−24濃度はそ
れぞれ２×10-2×Aμc／ml、10-4×Bμc／mlとな
る。 Therefore, for example, I-131, Na-24 in reactor water
If the radioactivity concentrations are Aμc/ml and Bμc/ml, respectively, the I-131 concentration and Na-24 concentration in the main steam are 2 × 10 -2 × Aμc/ml and 10 -4 × Bμc/ml, respectively. .
ここで、原子炉水または主蒸気中におけるＩ−
131とNa−24の濃度比をそれぞれRW、RSとする
と。 Here, I- in reactor water or main steam
Let the concentration ratios of 131 and Na−24 be R W and R S , respectively.
RW＝濃度（Ｉ−131）／濃度（Na−24） ＝Ａ／Ｂ ……(1) RS＝２×10-2×Ａ／（10-4×Ｂ） ＝200A／Ｂ ……(2) となる。 R W = Concentration (I-131) / Concentration (Na-24) = A/B ……(1) R S = 2×10 -2 × A/(10 -4 × B) = 200 A/B ……( 2) becomes.
これらの式から明らかなように、Ｉ−131とNa
−24の濃度比は主蒸気中の方が原子炉水中におけ
るよりも200倍も高くなる。 As is clear from these formulas, I-131 and Na
The concentration ratio of −24 in main steam is 200 times higher than in reactor water.
収納容器内において一次系からの漏洩が発生し
た場合には、前述したように格納容器内の水素ガ
ス濃度が上昇するとともに、漏洩した一次冷却水
中に含まれるＩ−131、Na−24等の放射性核種が
格納容器内で検出されることとなるので、上述の
放射濃度比の顕著な差異を利用すれば漏洩源が蒸
気系であるか、冷却系であるかを適確に判別する
ことができる。 If a leak occurs from the primary system within the storage vessel, the hydrogen gas concentration within the containment vessel will increase as described above, and the radioactivity of I-131, Na-24, etc. contained in the leaked primary cooling water will increase. Since the nuclide will be detected within the containment vessel, it is possible to accurately determine whether the leak source is from the steam system or the cooling system by using the above-mentioned significant difference in the radioactive concentration ratio. .
［発明の目的］
本発明は、上述の知見に基いてなされたもの
で、原子炉水と蒸気中で顕著な差のある放射性核
種間の放射能濃度比をもとにして、原子炉格納容
器内のサンプ水中の放射性核種組成、濃度の測定
によつて格納容器内への一次系からの漏洩源の判
別する方法を得ることを目的とするものである。[Objective of the Invention] The present invention was made based on the above-mentioned knowledge, and is based on the radioactivity concentration ratio between radionuclides that are significantly different in reactor water and steam. The purpose of this project is to obtain a method for determining the source of leakage from the primary system into the containment vessel by measuring the composition and concentration of radionuclides in the sump water inside the containment vessel.
［発明の概要］
本発明の原子炉格納容器における漏洩源の判別
方法は、原子炉水中に存在する放射性核種のう
ち、主蒸気中に移行する比率が事なる少なくとも
２種類の放射性核種について、原子炉格納容器内
のサンプ水中の放射能濃度を測定し、これらの放
射能濃度の比を原子炉水中の同濃度比と比較して
漏洩源が蒸気系であるか原子炉水素系であるかを
判別する方法である。[Summary of the Invention] The method of identifying a leak source in a reactor containment vessel according to the present invention is a method for identifying at least two types of radionuclides existing in reactor water that have different rates of migration into main steam. The radioactivity concentration in the sump water in the reactor containment vessel is measured, and the ratio of these radioactivity concentrations is compared with the same concentration ratio in the reactor water to determine whether the leak source is the steam system or the reactor hydrogen system. This is a method of determining.
［発明の実施例］
以下、本発明の詳細を第２図を参照して説明す
る。[Embodiments of the Invention] Details of the present invention will be described below with reference to FIG. 2.
第２図は本発明の方法を適用する原子炉格納容
器の系統配管を略図的に示すもので、格納容器１
内には原子炉２を中心に原子炉給水配管３、主蒸
気配管４が配置されており、原子炉水は、原子炉
再循環配管５に設けた原子炉循環ポンプ６により
循環撹拌される。原子炉制御駆動機構７には原子
炉制御棒の駆動水配管８を通して駆動水が供給さ
れる。格納容器１内の雰囲気は格納容器雰囲気サ
ンプルポンプ９によつて格納容器サンプリング配
管１０内に吸引され、露店湿度計１１、水素濃度
計１２、放射能モニタ１３によつて露点湿度、水
素濃度、および放射能が計測される。 Figure 2 schematically shows the system piping of the reactor containment vessel to which the method of the present invention is applied.
Inside, a reactor water supply pipe 3 and a main steam pipe 4 are arranged around the reactor 2, and reactor water is circulated and agitated by a reactor circulation pump 6 provided in a reactor recirculation pipe 5. Driving water is supplied to the reactor control drive mechanism 7 through a driving water pipe 8 of the reactor control rod. The atmosphere inside the containment vessel 1 is sucked into the containment vessel sampling piping 10 by the containment vessel atmosphere sample pump 9, and the dew point humidity, hydrogen concentration, and Radioactivity is measured.
格納容器内の雰囲気はまた、常時除湿器１４に
おいて、冷却水配管１５から導入される冷却水に
よつて冷却、除湿される。除湿された凝縮水ドレ
ンは、除湿器ドレン配管１６を通り、ドレン流量
計１７で流量監視された後、格納容器内サンプ１
８に流入し、更にサンプ吐出ポンプ１９で加圧さ
れ、叶出配管２０を経て、格納容器１外に排出さ
れる。 The atmosphere inside the containment vessel is also cooled and dehumidified by cooling water introduced from a cooling water pipe 15 in a constant dehumidifier 14 . The dehumidified condensed water drain passes through the dehumidifier drain piping 16, and after the flow rate is monitored by the drain flow meter 17, it is transferred to the sump 1 in the containment vessel.
8, is further pressurized by the sump discharge pump 19, and is discharged to the outside of the containment vessel 1 through the discharge pipe 20.
上述のように構成した原子炉格納容器内におい
て、主蒸気、原子炉水の一次系冷却材が格納容器
内に漏洩した場合、漏洩原子炉水の大部分は格納
容器内で蒸発し、露点を高めるとともに、除湿器
１４で冷却凝縮され、除湿器ドレン配管１６を経
て格納容器サンプ１８に流入し、一部は直接格納
容器サンプ１８に流入する。その結果、格納容器
内に漏洩した一次系冷却材中に含まれる放射性核
種は最終的には格納容器サンプ１８に流入する。 In the reactor containment vessel configured as described above, if main steam and primary coolant for reactor water leak into the containment vessel, most of the leaked reactor water will evaporate within the containment vessel, causing the dew point to drop. At the same time, it is cooled and condensed in the dehumidifier 14 and flows into the containment vessel sump 18 via the dehumidifier drain pipe 16, and a portion directly flows into the containment vessel sump 18. As a result, radionuclides contained in the primary coolant leaking into the containment vessel eventually flow into the containment vessel sump 18.
そこで格納容器サンプ水中の放射性核種である
Ｉ−131、Na−24等を測定し、その濃度比、Ｒ＝
濃度（Ｉ−131）／濃度（Na−24）を求める。こ
の濃度比Ｒが原子炉水におけるＩ−131、Na−24
の濃度比に等しい時には、格納容器内への一次系
冷却材漏洩は原子炉水そのものということにな
る。 Therefore, the radionuclides I-131, Na-24, etc. in the containment vessel sump water were measured, and the concentration ratio, R=
Calculate concentration (I-131)/concentration (Na-24). This concentration ratio R is I-131 and Na-24 in the reactor water.
When the concentration ratio is equal to , the primary coolant leaking into the containment vessel is the reactor water itself.
また、濃度比Ｒが原子炉水の濃度比より高く、
100倍程度の時には主蒸気等、蒸気系からの漏洩
と判断される。これは、主蒸気等の蒸気相への沃
素の移行率がNa−24等に比べ約200倍も高いこと
による。 In addition, the concentration ratio R is higher than the concentration ratio of reactor water,
When it is about 100 times higher, it is determined that there is a leak from the main steam or other steam system. This is because the transfer rate of iodine to the vapor phase such as main steam is about 200 times higher than that of Na-24 etc.
このように、一次系漏洩により格納容器サンプ
水中に存在することとなるＩ−131とNa−24の濃
度比を求めて評価することにより、格納容器内に
おける一次系漏洩源の判別が可能となる。その結
果、一次系漏洩源の早期確認、プラント停止時の
対応処理等が極めて容易となり、沸騰水形原子力
発電プラントの安全性確保、向上に大きく寄与す
ることができる。 In this way, by determining and evaluating the concentration ratio of I-131 and Na-24, which are present in the containment vessel sump water due to a primary system leak, it is possible to determine the source of the primary system leak within the containment vessel. . As a result, it becomes extremely easy to quickly identify the source of a primary system leak, and to perform countermeasures when the plant is shut down, making it possible to greatly contribute to ensuring and improving the safety of boiling water nuclear power plants.
なお、上記実施例ではＩ−131とNa−24の濃度
比を求めたが、本発明はこれに限定されることな
く、原子炉冷却水中に存在しかつ原子炉冷却水か
ら主蒸気への移行率が顕著に異なる少なくとも２
種類の放射核種のサンプ水中の濃度比を求めるこ
とにより、格納容器内における一次系漏洩源を判
別することができる。 Although the concentration ratio of I-131 and Na-24 was determined in the above example, the present invention is not limited to this. at least two with significantly different rates
By determining the concentration ratio of different types of radionuclides in the sump water, it is possible to determine the primary leak source within the containment vessel.
また、格納容器内への漏洩は単に主蒸気、原子
炉水のみに限らず、除湿器冷却水、原子炉給水、
制御棒駆動水等の放射能をほとんど含まない水の
漏洩が考えられるが、本発明に述べた方法による
と、放射能の有無、水素濃度上昇の有無により漏
洩源の大まかな分類も可能となる。 In addition, leakage into the containment vessel is not limited to main steam and reactor water, but also dehumidifier cooling water, reactor supply water,
Although it is possible that water that contains almost no radioactivity, such as control rod drive water, leaks, the method described in the present invention makes it possible to roughly classify the leak source based on the presence or absence of radioactivity and the presence or absence of an increase in hydrogen concentration. .
さらにまた、主蒸気中、原子炉水中に存在する
多種の核種濃度や酸素（O2）濃度等に着目して、
漏洩源と、漏洩量を評価することも可能である。 Furthermore, focusing on the concentrations of various nuclides and oxygen (O 2 ) present in main steam and reactor water,
It is also possible to evaluate the source of leakage and the amount of leakage.
［発明の効果］
上述の如く、本発明によれば、一次系漏洩によ
り格納容器のサンプ水中に存在することとなる２
種類以上の放射性核種の濃度比を求めて評価する
ことにより、格納容器内における一次系漏洩源の
判別が可能となる。その結果、一次系漏洩源の早
期確認、プラント停止時の対応処置等が極めて容
易となり、沸騰水形原子力発電プラントの安全性
確保、向上に大きく寄与することができる。[Effects of the Invention] As described above, according to the present invention, the primary system leakage causes 2.
By determining and evaluating the concentration ratio of more than one type of radionuclide, it becomes possible to identify the primary leak source within the containment vessel. As a result, early confirmation of the primary system leak source, countermeasures when the plant is shut down, etc. become extremely easy, and this can greatly contribute to ensuring and improving the safety of boiling water nuclear power plants.
第１図は、格納容器内に一次系からの漏洩が発
生した場合の格納容器内雰囲気露点、水素濃度、
放射線モニタ指示及び漏洩量変化の様子を例示す
るグラフ、第２図は沸騰水形原子力発電プラント
の原子炉格納容器内の概要を示す説明図である。
１……原子炉格納容器、２……原子炉、３……
原子炉給水配管、４……主蒸気配管、５……原子
炉再循環配管、６……原子炉再循環ポンプ、７…
…原子炉制御棒駆動機構、８……駆動水配管、９
……格納容器雰囲気サンプルポンプ、１０……格
納容器サンプリング配管、１１……露点湿度計、
１２……水素濃度計、１３……放射能モニタ、１
４……除湿器、１５……冷却水配管、１６……除
湿器ドレン配管、１７……ドレン流量計、１８…
…格納容器内サンプ、１９……サンプ吐出ポン
プ、２０……吐出配管。
Figure 1 shows the atmospheric dew point, hydrogen concentration, and
A graph illustrating radiation monitoring instructions and changes in leakage amount, and FIG. 2 is an explanatory diagram showing an overview of the inside of a reactor containment vessel of a boiling water nuclear power plant. 1... Reactor containment vessel, 2... Nuclear reactor, 3...
Reactor water supply piping, 4...Main steam piping, 5...Reactor recirculation piping, 6...Reactor recirculation pump, 7...
... Reactor control rod drive mechanism, 8 ... Drive water piping, 9
...Containment vessel atmosphere sample pump, 10...Containment vessel sampling piping, 11...Dew point hygrometer,
12...Hydrogen concentration meter, 13...Radioactivity monitor, 1
4... Dehumidifier, 15... Cooling water piping, 16... Dehumidifier drain piping, 17... Drain flow meter, 18...
...Sump in the containment vessel, 19...Sump discharge pump, 20...Discharge piping.
Claims (1)
蒸気中に移行する比率が異なる少なくとも２種類
の放射性核種について、原子炉格納容器内のサン
プ水中の放射能濃度を測定し、該放射能濃度の比
を原子炉水中の同濃度比と比較して漏洩源が蒸気
系であるか原子炉水系であるかを判別することを
特徴とする原子炉格納容器における漏洩源の判別
方法。 ２ 少なくとも２種類の放射性核種は、Ｉ−131
およびＩ−135の中の１種と、Na−24およびMn
−56の中の１種である特許請求の範囲第１項記載
の原子炉格納容器における漏洩源の判別方法。[Scope of Claims] 1. Radioactivity concentration in sump water in the reactor containment vessel is measured for at least two types of radionuclides that migrate into main steam at different rates among the radionuclides present in the reactor water. , determining whether the leak source is a steam system or a reactor water system by comparing the radioactivity concentration ratio with the same concentration ratio in reactor water. Method. 2 At least two radionuclides are I-131
and one of I-135, Na-24 and Mn
A method for determining a leak source in a nuclear reactor containment vessel according to claim 1, which is one type of reactor containment vessel.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58022443A JPS59150388A (en) | 1983-02-14 | 1983-02-14 | Method of judging leakage source in reactor container |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58022443A JPS59150388A (en) | 1983-02-14 | 1983-02-14 | Method of judging leakage source in reactor container |
Related Child Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP3280148A Division JPH0769456B2 (en) | 1991-10-28 | 1991-10-28 | Method of identifying leakage source in containment vessel |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS59150388A JPS59150388A (en) | 1984-08-28 |
| JPH0423235B2 true JPH0423235B2 (en) | 1992-04-21 |
Family
ID=12082846
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP58022443A Granted JPS59150388A (en) | 1983-02-14 | 1983-02-14 | Method of judging leakage source in reactor container |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS59150388A (en) |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP4755061B2 (en) * | 2006-10-13 | 2011-08-24 | 株式会社日立製作所 | Nuclear facility leakage monitoring system and leakage monitoring method thereof |
| JP5752566B2 (en) * | 2011-06-15 | 2015-07-22 | 株式会社東芝 | Reactor containment atmosphere monitoring device |
-
1983
- 1983-02-14 JP JP58022443A patent/JPS59150388A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS59150388A (en) | 1984-08-28 |
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