JPS6025756B2 - Damaged fuel detection method - Google Patents
Damaged fuel detection methodInfo
- Publication number
- JPS6025756B2 JPS6025756B2 JP54134394A JP13439479A JPS6025756B2 JP S6025756 B2 JPS6025756 B2 JP S6025756B2 JP 54134394 A JP54134394 A JP 54134394A JP 13439479 A JP13439479 A JP 13439479A JP S6025756 B2 JPS6025756 B2 JP S6025756B2
- Authority
- JP
- Japan
- Prior art keywords
- gas
- channel
- tank
- fuel
- 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】
この発明は、原子炉において破損燃料を検出する方法に
関する。DETAILED DESCRIPTION OF THE INVENTION This invention relates to a method for detecting damaged fuel in a nuclear reactor.
従来、沸騰水形原子炉における破損燃料の検出は、原子
炉圧力容器の蓋を開けたのち、炉内シッピング装置によ
り燃料チャネル内の炉水を吸い上げ、この試料水の核種
分析を行なうことにより、燃料破損の有無を判定してい
る。Conventionally, damaged fuel in a boiling water reactor is detected by opening the lid of the reactor pressure vessel, sucking up the reactor water in the fuel channel using an in-reactor shipping device, and performing nuclide analysis on this sample water. The presence or absence of fuel damage is being determined.
しかしながらこの方法によると、破損した被覆管から核
分裂生成物(FPガス)が炉水中に拡散するのを待たな
ければならないために時間がかかり、また炉水自体の放
射能レベルの影響を受けるため検出精度に問題があった
。この発明は上記事情にもとづきなされたものでその目
的とするところは、検出精度が高く、また検出時間を短
縮できる破損燃料検出方法を提供することにある。However, with this method, it takes time to wait for fission products (FP gas) to diffuse into the reactor water from the damaged cladding, and detection is affected by the radioactivity level of the reactor water itself. There was a problem with accuracy. The present invention has been made based on the above circumstances, and an object thereof is to provide a method for detecting damaged fuel that has high detection accuracy and can shorten detection time.
以下この発明を図示する一実施例にもとづき説明する。The present invention will be described below based on an illustrated embodiment.
図中1は沸騰水形原子炉内に設けられる燃料集合体を示
す。2はこの燃料集合体1の燃料チャネルであり、この
チャネル2は上下端が閉口している。In the figure, numeral 1 indicates a fuel assembly installed in a boiling water reactor. 2 is a fuel channel of this fuel assembly 1, and this channel 2 is closed at its upper and lower ends.
3は燃料棒を束ねた燃料東、Aは炉水を示す。3 indicates the fuel east, which is a bundle of fuel rods, and A indicates the reactor water.
また、4は本発明に係る破損燃料検出装置であり、以下
この検出装置4について説明する。Further, 4 is a damaged fuel detection device according to the present invention, and this detection device 4 will be explained below.
すなわち、5は上記燃料チャネル2の上部開□を気密に
閉塞するチャンバであって、このチャンバ5は図示しな
い駆動機構によってチャネル2に脱着されるようになっ
ている。そして上記チャンバ5には、後述する送排気機
構10を介してガス収容タンク6が接続されている。こ
のタンク6には、開閉弁14を有するガス供孫合管7を
介して、ガス供給源8が接続されている。このガス供給
源8には、不活性度の高いガス例えばヘリウムガスが高
圧で充填されている。そして上記タンク6とチャンバ5
との間にガスの送排気機構10が設けられている。この
送排気機構1川ま、タンク6に接続された送気管1 1
および排気管12と、これらの管11,12をチャンバ
5に接続する送排気管13とを備えて構成され、上記各
管11,12,13にはそれぞれ開閉弁15,16,1
7,18が設けられている。また上記排気管12の途中
には、圧縮機20が設けられている。さらに、上記タン
ク6には排気管12より分岐させたガス取出管21が接
続されている。That is, 5 is a chamber that airtightly closes the upper opening □ of the fuel channel 2, and this chamber 5 is attached to and detached from the channel 2 by a drive mechanism (not shown). A gas storage tank 6 is connected to the chamber 5 via a pumping/exhausting mechanism 10, which will be described later. A gas supply source 8 is connected to this tank 6 via a gas supply pipe 7 having an on-off valve 14 . This gas supply source 8 is filled with a highly inert gas such as helium gas at high pressure. And the tank 6 and chamber 5
A gas supply/exhaust mechanism 10 is provided between the two. This air supply/exhaust mechanism 1 has an air supply pipe 1 connected to a tank 6.
and an exhaust pipe 12, and a supply/exhaust pipe 13 connecting these pipes 11, 12 to the chamber 5, and each pipe 11, 12, 13 is provided with an on-off valve 15, 16, 1, respectively.
7 and 18 are provided. Further, a compressor 20 is provided in the middle of the exhaust pipe 12. Furthermore, a gas extraction pipe 21 branched from the exhaust pipe 12 is connected to the tank 6 .
そしてこのガス取出管21の排出側に放射能検出器22
が設けられている。19は開閉弁である。A radioactivity detector 22 is installed on the discharge side of this gas extraction pipe 21.
is provided. 19 is an on-off valve.
次に上記実施例装置を使用して破損燃料を検出する方法
について説明する。Next, a method for detecting damaged fuel using the above embodiment device will be explained.
原子炉運転停止後、各開閉弁14〜19を全て閉じた状
態で、燃料チャネル2の上部閉口にチャンバ5を被せる
。一方、ガス供給管7の開閉弁14を開けて、ガス供給
源8よりヘリウムガスを所定の圧力でタンク6内に充填
する。なお、この充填圧力Pは、タンク6の容量をV,
,チャネル2内の容量をV2,チャネル下部の水圧をP
cとした場合、P=pcN,十V2)十ば
とする。After the reactor operation is shut down, the chamber 5 is placed over the upper end of the fuel channel 2 with all of the on-off valves 14 to 19 closed. On the other hand, the on-off valve 14 of the gas supply pipe 7 is opened, and the tank 6 is filled with helium gas from the gas supply source 8 at a predetermined pressure. Note that this filling pressure P is the capacity of the tank 6 as V,
, the capacity in channel 2 is V2, and the water pressure at the bottom of the channel is P
If c, P=pcN, 10V2) 10ba
shall be.
V,そして、ガス送気工程に入る。この工程では、上記
開閉弁14を閉じるとともに、送気管11および送排気
管13の開閉弁15,16を開けることによって、上記
タンク6内のヘリウムガスをチャネル2内に送給する。
すると、そのガス圧によってチャネル2内の炉水Aは押
し下げられて水位が低下してゆき、送り込まれたガスは
チャネル2内の炉水と置換する。そして、第2図に示さ
れるようにチャネル2の最下部付近まで水位が低下した
ところで開閉弁15,16を閉じ、ガスの送給を停止さ
せる。そして一定時間放置する。このとき、チャネル2
内に破損燃料があると、その破損箇所から漏れるFPガ
スがチャネル2内のガス空間に放出される。しかるのち
、ガス排気工程に移り、この工程では開閉弁16,17
,18を開弁させるとともに、圧縮機20を作動させ、
チャネル2内のガスを再びタンク6内に圧縮して回収す
る。これにより、チャネル2内の炉水の液面が再び上昇
し、その液面上昇に伴なつて破損燃料からのFPガスの
放出が促進される。そして第3図に示されるごとく、チ
ャネル2内に再び炉水を充満させたところで上記開閉弁
16,17,18を閉じる。そして、以上の操作、すな
わちガス送気工程と排気工程とを複数回繰り返す。V, and enters the gas supply process. In this step, the helium gas in the tank 6 is fed into the channel 2 by closing the on-off valve 14 and opening the on-off valves 15 and 16 of the air supply pipe 11 and the air supply/exhaust pipe 13.
Then, the reactor water A in the channel 2 is pushed down by the gas pressure, and the water level decreases, and the fed gas replaces the reactor water in the channel 2. Then, as shown in FIG. 2, when the water level drops to near the bottom of the channel 2, the on-off valves 15 and 16 are closed to stop the gas supply. Then leave it for a certain period of time. At this time, channel 2
If there is any damaged fuel inside, the FP gas leaking from the break will be released into the gas space within the channel 2. After that, the process moves to the gas exhaust process, and in this process, the on-off valves 16 and 17 are
, 18 and operate the compressor 20,
The gas in channel 2 is again compressed and recovered in tank 6. As a result, the liquid level of the reactor water in the channel 2 rises again, and as the liquid level rises, the release of FP gas from the damaged fuel is promoted. Then, as shown in FIG. 3, once the channel 2 is filled with reactor water again, the on-off valves 16, 17, and 18 are closed. Then, the above operations, that is, the gas supply process and the exhaust process are repeated multiple times.
これによりタンク6内のガス中のFPガス濃度が次第に
高まり、測定誤差を生じにくい濃度となる。そこで上記
工程を繰り返したのち、開閉弁18,19を開けて、タ
ンク6内のガスを放射能検出器22に送り、測定を行な
うことにより、燃料破損の有無が検出される。しかして
上記実施例方法によれば、タンク6とチャネル2との間
で同一のガスを繰り返し往復させることにより、タンク
6内のFPガス濃度を次第に高めることができ、FPガ
スを高濃度にして放射能検出器22による測定を行なう
ことができるから、測定精度が向上する。As a result, the FP gas concentration in the gas in the tank 6 gradually increases, and becomes a concentration that is less likely to cause measurement errors. Therefore, after repeating the above steps, the on-off valves 18 and 19 are opened, and the gas in the tank 6 is sent to the radioactivity detector 22 for measurement, thereby detecting the presence or absence of fuel damage. However, according to the method of the above embodiment, by repeatedly transporting the same gas between the tank 6 and the channel 2, the FP gas concentration in the tank 6 can be gradually increased. Since measurement can be performed using the radioactivity detector 22, measurement accuracy is improved.
しかもFPガスはチャネル2内のガス空間中に放出され
るため、破損燃料からのFPガス放出が迅やかに行なわ
れることに加えて、チャネル2内を炉水液面が上下する
際の圧力変動によってFPガスの放出が更に促進される
ため、ガス放出を待つ時間が短かくて済み、定検期間が
短縮される。また本実施例装置によれば、タンク6内へ
のガスの回収は、圧縮機20によってタンク6内に圧縮
して行なうため、この圧縮機201こ高能力のものを用
いることによってタンク6内に高圧縮でガスを充填させ
ることが可能である。Moreover, since the FP gas is released into the gas space in channel 2, in addition to the rapid release of FP gas from the damaged fuel, the pressure when the reactor water level rises and falls in channel 2 increases. Since the release of FP gas is further promoted by the fluctuation, the time to wait for gas release is shortened, and the regular inspection period is shortened. Furthermore, according to the device of this embodiment, the gas is recovered into the tank 6 by being compressed into the tank 6 by the compressor 20. It is possible to fill the gas with high compression.
したがって、タンク6の容量を小さくすることができる
。この場合、チャネル2にガスを送給したときのタンク
6内のガス残留分が少なくなるため、FPガス濃度をよ
り高めることができる利点がある。なお本実施例は以上
のごとく構成したが、この発明の実施に当ってはこの発
明の要旨に反しない限り、チャンバ、タンク、あるいは
これらを結ぶ配管構造、放射能検知器等の具体的態様を
種々に構成して実施できることは勿論である。Therefore, the capacity of the tank 6 can be reduced. In this case, there is an advantage that the FP gas concentration can be further increased because the amount of gas remaining in the tank 6 is reduced when the gas is supplied to the channel 2. Although this embodiment has been constructed as described above, in carrying out the present invention, specific aspects of the chamber, the tank, the piping structure connecting these, the radioactivity detector, etc. may be changed unless it goes against the gist of the invention. Of course, various configurations and implementations are possible.
また、使用するガスはヘリウムガスに限らず、種々のガ
スを適用できる。以上説明したように本発明方法によれ
ば、ガスを収容したタンクから燃料チャネル内にガスを
送給して水と置換させる工程とチャネル内のガスを再び
タンクに回収する工程とを繰り返すことにより、破損燃
料より放出されるFPガスを高濃度にしてタンクに集め
ることができる。Further, the gas used is not limited to helium gas, but various gases can be used. As explained above, according to the method of the present invention, by repeating the steps of supplying gas from a tank containing gas into a fuel channel to replace water and collecting the gas in the channel again into the tank, , the FP gas released from the damaged fuel can be concentrated and collected in the tank.
したがって、このように濃縮されたガスの放射能測定を
行なうことにより、たとえば炉水自体の持つ放射能レベ
ルなどに影響されることなく燃料の検出が行なえ、検出
精度を高めることができる。しかもFPガスはチャネル
内のガス空間に放出されることに加えて、炉水液面の上
下動により、FPガス放出が促進されるため、FPガス
放出に要する時間が短か〈、したがって定検時間の短縮
が可能となる。したがって、原子炉の信頼性が向上し、
また定検期間短縮により原子炉稼動率を向上させること
ができる。Therefore, by measuring the radioactivity of the gas concentrated in this way, fuel can be detected without being affected by, for example, the radioactivity level of the reactor water itself, and detection accuracy can be improved. Moreover, in addition to being released into the gas space in the channel, FP gas release is promoted by the vertical movement of the reactor water level, so the time required for FP gas release is short. It becomes possible to shorten the time. Therefore, the reliability of the reactor is improved,
In addition, by shortening the regular inspection period, the reactor operating rate can be improved.
図面はこの発明の一実施例を示し、第1図は燃料集合体
と破損燃料検出装置を糠図的に表わした構成説明図、第
2図はガス送給状態における燃料集合体の概略的縦断面
図、第3図はガス排出状態における同燃料集合体の概略
的縦断面図である。
2・・・・・・燃料チャネル、5・・・・・・チヤンバ
、6・・・・・・タンク、20……圧縮機、22…・・
・放射能検出器、A・・・・・・炉水。
第1図
第2図
第3図The drawings show an embodiment of the present invention, and FIG. 1 is a structural explanatory diagram diagrammatically showing a fuel assembly and a damaged fuel detection device, and FIG. 2 is a schematic vertical cross-section of the fuel assembly in a gas supply state. The top view and FIG. 3 are schematic longitudinal cross-sectional views of the same fuel assembly in a gas exhaust state. 2... Fuel channel, 5... Chamber, 6... Tank, 20... Compressor, 22...
・Radioactivity detector, A... Reactor water. Figure 1 Figure 2 Figure 3
Claims (1)
たのち、ガスを収容したタンクよりガスを上記チヤネル
内に送給してチヤネル内の水と置換させる工程と所定時
間経過後にチヤネル内のガスを再び上記タンクに回収す
る工程とを繰り返し、そののち上記タンクよりガスを取
出して放射能測定を行なうことを特徴とする破損燃料検
出方法。1. After the upper opening of the fuel channel in the reactor is airtightly closed, gas is fed into the channel from a tank containing gas to replace the water in the channel, and after a predetermined period of time, the gas in the channel is removed. A method for detecting damaged fuel, comprising repeating the step of recovering the gas into the tank, and then extracting gas from the tank and measuring radioactivity.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP54134394A JPS6025756B2 (en) | 1979-10-18 | 1979-10-18 | Damaged fuel detection method |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP54134394A JPS6025756B2 (en) | 1979-10-18 | 1979-10-18 | Damaged fuel detection method |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS5658697A JPS5658697A (en) | 1981-05-21 |
| JPS6025756B2 true JPS6025756B2 (en) | 1985-06-20 |
Family
ID=15127367
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP54134394A Expired JPS6025756B2 (en) | 1979-10-18 | 1979-10-18 | Damaged fuel detection method |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS6025756B2 (en) |
Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2019065126A1 (en) | 2017-09-28 | 2019-04-04 | ウシオ電機株式会社 | Sterilization method and sterilization apparatus |
| WO2021070780A1 (en) | 2019-10-07 | 2021-04-15 | ウシオ電機株式会社 | Ultraviolet ray radiation device |
| EP3950012A1 (en) | 2020-08-05 | 2022-02-09 | Ushio Denki Kabushiki Kaisha | Method for inactivating bacteria or viruses and inactivating apparatus for bacteria or viruses |
| WO2022113442A1 (en) | 2020-11-25 | 2022-06-02 | ウシオ電機株式会社 | Microbe and virus inactivation device |
| KR20220119307A (en) | 2021-02-19 | 2022-08-29 | 나노씨엠에스(주) | Sterilization device harmless to human body |
| KR102472256B1 (en) | 2021-08-10 | 2022-12-01 | 나노씨엠에스(주) | Sterilization device harmless to human body |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS6243597A (en) * | 1985-08-20 | 1987-02-25 | 株式会社東芝 | Shipping device |
-
1979
- 1979-10-18 JP JP54134394A patent/JPS6025756B2/en not_active Expired
Cited By (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2019065126A1 (en) | 2017-09-28 | 2019-04-04 | ウシオ電機株式会社 | Sterilization method and sterilization apparatus |
| KR20200024951A (en) | 2017-09-28 | 2020-03-09 | 우시오덴키 가부시키가이샤 | Sterilization Method, Sterilization Device |
| WO2021070780A1 (en) | 2019-10-07 | 2021-04-15 | ウシオ電機株式会社 | Ultraviolet ray radiation device |
| EP3950012A1 (en) | 2020-08-05 | 2022-02-09 | Ushio Denki Kabushiki Kaisha | Method for inactivating bacteria or viruses and inactivating apparatus for bacteria or viruses |
| WO2022113442A1 (en) | 2020-11-25 | 2022-06-02 | ウシオ電機株式会社 | Microbe and virus inactivation device |
| KR20220119307A (en) | 2021-02-19 | 2022-08-29 | 나노씨엠에스(주) | Sterilization device harmless to human body |
| KR102472256B1 (en) | 2021-08-10 | 2022-12-01 | 나노씨엠에스(주) | Sterilization device harmless to human body |
Also Published As
| Publication number | Publication date |
|---|---|
| JPS5658697A (en) | 1981-05-21 |
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