JPS6243154B2 - - Google Patents
Info
- Publication number
- JPS6243154B2 JPS6243154B2 JP54168350A JP16835079A JPS6243154B2 JP S6243154 B2 JPS6243154 B2 JP S6243154B2 JP 54168350 A JP54168350 A JP 54168350A JP 16835079 A JP16835079 A JP 16835079A JP S6243154 B2 JPS6243154 B2 JP S6243154B2
- Authority
- JP
- Japan
- Prior art keywords
- gas
- fuel
- krypton
- damage
- reactor
- 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
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
- Monitoring And Testing Of Nuclear Reactors (AREA)
Description
【発明の詳細な説明】
本発明は原子炉の燃料破損検出方法及びその装
置に係り、特にオフガス中の核分裂生成ガスであ
るクリプトン−85の検出によつて燃料破損の発生
時刻および原子炉運転パラメータとの関係を知る
ようにした燃料破損検出方法とその装置に関す
る。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a method and apparatus for detecting fuel damage in a nuclear reactor, and in particular, detects krypton-85, which is a fission gas in off-gas, to detect the time of occurrence of fuel damage and reactor operating parameters. The present invention relates to a method and device for detecting fuel damage that allows the user to know the relationship between
従来、原子炉の燃料破損を検出する方法として
は、ウランの核分裂により生成する水溶性核種
(例えばヨウ素−131、ヨウ素−132、セシウム−
134、セシウム−137)の炉水中の濃度を測定する
方法、及び、ウランの核分裂の結果発生するガス
成分核種(例えばキセノン−133、キセノン−
135、キセノン−135m、キセノン−138、クリプ
トン−85、クリプトン−87、クリプトン−88)の
原子炉オフガス中の濃度を測定する方法がある。 Conventionally, methods for detecting fuel damage in nuclear reactors have been based on water-soluble nuclides (e.g. iodine-131, iodine-132, cesium-
134, cesium-137) in reactor water, and gas component nuclides generated as a result of uranium fission (e.g. xenon-133, xenon-137).
There is a method to measure the concentration of 135, xenon-135m, xenon-138, krypton-85, krypton-87, krypton-88) in the reactor off-gas.
しかしながら、前者の方法によると、燃料破損
により炉水の放射能濃度が急上昇するため、最初
の1回は燃料破損の検出が容易であるものの、破
損した燃料を原子炉から取出した後も炉水の放射
能濃度が下がらず、このため新たに燃料破損が発
生しても、これを検出することは困難である。さ
らに、燃料破損が生じた時期を知ることは不可能
な状態にある。 However, according to the former method, the radioactivity concentration in the reactor water increases rapidly due to fuel damage, so although it is easy to detect fuel damage the first time, even after the damaged fuel is removed from the reactor, the radioactivity concentration in the reactor water increases rapidly. The radioactivity concentration in the fuel does not decrease, so even if a new fuel failure occurs, it is difficult to detect it. Furthermore, it is impossible to know when a fuel failure has occurred.
他方、後者の方法は第1図に示す装置によつて
なされるのが一般的である。図において、原子炉
1で発生した主蒸気により蒸気タービン2が回さ
れ、タービン2は発電機を駆動する。蒸気は主復
水器3で凝縮され破線で示す原子炉給水系へと送
られる。この間、原子炉1内で発生した核分裂生
成ガスは主蒸気と一緒にタービン2を径て復水器
3へと移動する。そして、復水器3より主蒸気を
作動媒体とする空気抽出器4によつて引抜かれ、
酸水素再結合器5によつてガス中の水素と酸素が
結合される。その後排ガス復水器6によりガス中
の水蒸気が凝縮されガスと分離される。こうした
処理の後、ガスは希ガスホールドアツプ装置等の
減衰装置により減衰後大気に放出する。この間、
ガスは採取装置9によつて1部がサンプリングさ
れ、モニタリング装置へ送られ、成分分析によつ
て燃料破損が検出される。 On the other hand, the latter method is generally carried out using the apparatus shown in FIG. In the figure, main steam generated in a nuclear reactor 1 rotates a steam turbine 2, and the turbine 2 drives a generator. The steam is condensed in the main condenser 3 and sent to the reactor water supply system shown by the broken line. During this time, the fission product gas generated within the nuclear reactor 1 moves through the turbine 2 to the condenser 3 together with the main steam. Then, it is extracted from the condenser 3 by an air extractor 4 using main steam as a working medium.
The oxyhydrogen recombiner 5 combines hydrogen and oxygen in the gas. Thereafter, water vapor in the gas is condensed by the exhaust gas condenser 6 and separated from the gas. After such treatment, the gas is attenuated by an attenuator, such as a rare gas hold-up device, and then released to the atmosphere. During this time,
A portion of the gas is sampled by a sampling device 9 and sent to a monitoring device, where fuel damage is detected by component analysis.
しかしながら、この第2の方法でも、1度燃料
破損が発生すると核分裂生成ガスは破損した燃料
から原子炉系へ放出され続けるので、新たに燃料
破損が発生したかどうかを検出するのは困難であ
つた。 However, even with this second method, once a fuel failure occurs, fission product gases continue to be released from the damaged fuel into the reactor system, making it difficult to detect whether a new fuel failure has occurred. Ta.
本発明は、上記する従来技術の欠点に鑑みてな
されたもので、燃料破損の発生とその発生時刻を
検知し、燃料破損の原因をも追跡できる燃料破損
検出方法及びその装置を提供することを目的とす
る。 The present invention has been made in view of the above-mentioned shortcomings of the prior art, and it is an object of the present invention to provide a method and device for detecting fuel damage that can detect the occurrence and time of occurrence of fuel damage, and also trace the cause of fuel damage. purpose.
本発明は、核分裂生成ガスの1つであるクリプ
トン−85を連続測定し、燃料破損が発生した時に
生ずるピークから、燃料破損の発生とその時刻を
検知し、更に原子炉運転状態との相関から燃料破
損の原因を確認できるようにしたものである。 The present invention continuously measures krypton-85, which is one of the gases produced by nuclear fission, and detects the occurrence and time of fuel failure based on the peak that occurs when fuel failure occurs, and furthermore detects the occurrence and time of fuel failure based on the correlation with the operating status of the nuclear reactor. This allows the cause of fuel damage to be confirmed.
以下、本発明を実施例によつて詳細に説明す
る。 Hereinafter, the present invention will be explained in detail with reference to Examples.
本発明の実施例を第2図に示す。図において、
第1図と同様に原子炉系から排出されるオフガス
は、第1図の場合と同様にして処理される。燃料
破損の検出は、採取装置によつてガスの1部を採
取するこことによつて行われる。採取したガスを
乾燥器11に導いて乾燥後、ブロア18によつて
昇圧し活性炭カラム12に送り、所定の時間ホー
ルドアツプを行つた後、β線検出器13に導き、
β線線量を測定する。 An embodiment of the invention is shown in FIG. In the figure,
As in FIG. 1, off-gas discharged from the reactor system is treated in the same manner as in FIG. Detection of fuel failure is carried out by sampling a portion of the gas by means of a sampling device. The collected gas is led to a dryer 11 and dried, then the pressure is increased by a blower 18, and sent to an activated carbon column 12, held up for a predetermined time, and then led to a β-ray detector 13.
Measure the beta-ray dose.
ここで、ウランの核分裂の結果発生するガス成
分核種とその半減期は次の通りである。 Here, the gas component nuclides generated as a result of uranium fission and their half-lives are as follows.
核種
キセノン−133 5.27日
キセノン−135 9.14時間
キセノン−135m 15.6分
キセノン−138 17.5分
クリプトン−85 10.76年
クリプトン−87 76分
クリプトン−88 2.80時間
この内、クリプトン−85は、半減期が10.76年
と他のものに比して著しく長く、従つて、燃焼が
進むにしたがつて燃料プレナムに蓄積される量
は、燃料の燃焼度に大略比例する。一方、他の核
種は半減期が短かいので、プレナム中の蓄積量は
ある出力で運転している期間と、運転状態が変化
してからの時間に依存する。 Nuclides Xenon-133 5.27 days Xenon-135 9.14 hours Xenon-135m 15.6 minutes It is significantly longer than the others, so the amount that accumulates in the fuel plenum as combustion progresses is roughly proportional to the burn-up of the fuel. On the other hand, other nuclides have short half-lives, so the amount accumulated in the plenum depends on the period of operation at a certain output and the time since the operating condition changed.
燃料破損が発生すると、プレナム中に蓄積され
ていた核分裂生成ガスは、燃料から原子炉系に漏
洩する。そして、空気抽出器4により抽出されて
前述したオフガス検出系を通りβ線検出器に導か
れる。活性炭カラム12は約10℃で運転する。こ
の時、ホールドアツプ時間はクリプトンが約50時
間、キセノンが約60日である。したがつて、活性
炭カラムを出た後は、クリプトン−85以外の核種
は殆んど減衰しており、検出器13ではクリプト
ン−85のβ線線量が有効に計測できる。このクリ
プトン−85のβ線線量を連続的に計測すれば燃料
破損の検出が可能である。すなわち、燃料破損発
生に伴ない蓄積されていたクリプトン−85が一度
に放出されることにより、クリプトン−85のβ線
線量のピークが観測されるからである。ピークの
高さ、面積から破損した燃料の大略の燃焼度を推
定することが可能である。 When a fuel failure occurs, the fission product gases accumulated in the plenum leak from the fuel into the reactor system. Then, it is extracted by the air extractor 4 and guided to the β-ray detector through the above-mentioned off-gas detection system. Activated carbon column 12 is operated at approximately 10°C. At this time, the hold-up time is approximately 50 hours for krypton and approximately 60 days for xenon. Therefore, after leaving the activated carbon column, most of the nuclides other than krypton-85 are attenuated, and the detector 13 can effectively measure the β-ray dose of krypton-85. Fuel damage can be detected by continuously measuring the beta-ray dose of krypton-85. In other words, the krypton-85 that had been accumulated due to fuel failure is released all at once, and the peak of the krypton-85 beta ray dose is observed. It is possible to estimate the approximate burnup of the damaged fuel from the height and area of the peak.
またβ線線量を記録装置によつて記録し、この
記録と制御棒操作、出力変更、流量変更などの原
子炉運転パラメータと記録との比較を行えば、燃
料破損原因を分析することができる。記録装置8
は上述する運転データを記録する装置であり、通
常設けられているものである。この記録装置8か
ら運転データを取出し、時間遅れ要素15を介し
て解折装置16へ導入すると、解析装置では相関
を取り、破損原因を究明する。 Furthermore, by recording the β-ray dose using a recording device and comparing this record with reactor operating parameters such as control rod operations, output changes, flow rate changes, etc., the cause of fuel damage can be analyzed. Recording device 8
is a device for recording the above-mentioned driving data, and is normally provided. When the operating data is taken out from the recording device 8 and introduced into the cracking device 16 via the time delay element 15, the analysis device takes a correlation and investigates the cause of the damage.
なお、上記の装置には装置の作動をチエツクす
るために規定量のクリプトン−85を注入できる基
準クリプトン抽入装置10を備えている。この装
置から定期的にクリプトン−85を放出することに
より、検出器13の作動を確認することが出来
る。 The above apparatus is equipped with a reference krypton extraction device 10 capable of injecting a prescribed amount of krypton-85 in order to check the operation of the apparatus. By periodically emitting krypton-85 from this device, the operation of the detector 13 can be confirmed.
第1図は従来のオフガスを利用した燃料破損検
出方法、第2図は本発明になる燃料破損検出方法
を具体化した装置を示す図である。
1……原子炉、2……蒸気タービン、4……空
気抽出器、9……採取装置、12……活性炭カラ
ム、13……β線検出器、14……記録装置、1
6……解析装置。
FIG. 1 shows a conventional method for detecting fuel damage using off-gas, and FIG. 2 shows an apparatus embodying the method for detecting fuel damage according to the present invention. 1... Nuclear reactor, 2... Steam turbine, 4... Air extractor, 9... Sampling device, 12... Activated carbon column, 13... Beta ray detector, 14... Recording device, 1
6...Analysis device.
Claims (1)
量を計測することによつて燃料破損を検出する方
法において、前記オフガスの一部を採取し、前記
採取したオフガス中の核分裂生成物の放射能を減
衰させ、その後、前記採取したオフガス中のクリ
プトン−85の増加量を計測することを特徴とする
燃料破損検出方法。 2 原子炉からオフガスを採取する手段と、採取
した前記オフガスをホールドアツプする手段と、
前記ホールドアツプ手段にて所定時間ホールドア
ツプされた前記オフガスのβ線量を計測する手段
と、前記β線量の増加量に基づいて燃料破損を判
定する手段とからなることを特徴とする燃料破損
検出装置。[Claims] 1. A method for detecting fuel failure by measuring the radiation dose of fissile gas in off-gas of a nuclear reactor, in which a part of the off-gas is sampled, and nuclear fission in the sampled off-gas is detected. A method for detecting fuel damage, comprising attenuating the radioactivity of the product and then measuring an increase in the amount of krypton-85 in the collected off-gas. 2. A means for collecting off-gas from a nuclear reactor, and a means for holding up the collected off-gas,
A fuel damage detection device comprising means for measuring the β-ray dose of the off-gas held up for a predetermined period of time by the hold-up means, and means for determining fuel damage based on the amount of increase in the β-ray dose. .
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP16835079A JPS5692498A (en) | 1979-12-26 | 1979-12-26 | Method and device for detecting fuel failure |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP16835079A JPS5692498A (en) | 1979-12-26 | 1979-12-26 | Method and device for detecting fuel failure |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS5692498A JPS5692498A (en) | 1981-07-27 |
| JPS6243154B2 true JPS6243154B2 (en) | 1987-09-11 |
Family
ID=15866428
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP16835079A Granted JPS5692498A (en) | 1979-12-26 | 1979-12-26 | Method and device for detecting fuel failure |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS5692498A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| KR102608925B1 (en) * | 2023-10-06 | 2023-12-01 | 박문수 | Filter of airconditioner |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS6147590A (en) * | 1984-08-14 | 1986-03-08 | 株式会社東芝 | Detector for damaged fuel |
Family Cites Families (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS542181A (en) * | 1977-06-08 | 1979-01-09 | Toshiba Corp | Krypton monitoring apparatus of improved s/n ratio |
| JPS55107998A (en) * | 1979-02-15 | 1980-08-19 | Tokyo Shibaura Electric Co | Nuclear reactor fuel failure diagnosis device |
-
1979
- 1979-12-26 JP JP16835079A patent/JPS5692498A/en active Granted
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| KR102608925B1 (en) * | 2023-10-06 | 2023-12-01 | 박문수 | Filter of airconditioner |
Also Published As
| Publication number | Publication date |
|---|---|
| JPS5692498A (en) | 1981-07-27 |
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