JPH0236337A - Analytic test piece sampling device for nuclear plant - Google Patents
Analytic test piece sampling device for nuclear plantInfo
- Publication number
- JPH0236337A JPH0236337A JP63185363A JP18536388A JPH0236337A JP H0236337 A JPH0236337 A JP H0236337A JP 63185363 A JP63185363 A JP 63185363A JP 18536388 A JP18536388 A JP 18536388A JP H0236337 A JPH0236337 A JP H0236337A
- Authority
- JP
- Japan
- Prior art keywords
- waste liquid
- sample collection
- containment vessel
- sample
- reactor containment
- 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.)
- Granted
Links
- 238000005070 sampling Methods 0.000 title abstract description 6
- 239000007788 liquid Substances 0.000 claims abstract description 65
- 239000002699 waste material Substances 0.000 claims abstract description 64
- 238000001816 cooling Methods 0.000 abstract description 6
- 238000000034 method Methods 0.000 abstract description 2
- 239000000463 material Substances 0.000 abstract 1
- 239000000523 sample Substances 0.000 description 68
- 239000010808 liquid waste Substances 0.000 description 11
- 239000002826 coolant Substances 0.000 description 10
- 239000000538 analytical sample Substances 0.000 description 6
- 238000004140 cleaning Methods 0.000 description 4
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 4
- 238000011109 contamination Methods 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 239000012857 radioactive material Substances 0.000 description 2
- 238000012790 confirmation Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000001704 evaporation Methods 0.000 description 1
- 230000008020 evaporation Effects 0.000 description 1
- 230000002285 radioactive effect Effects 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
- Sampling And Sample Adjustment (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
Description
【発明の詳細な説明】
（産業上の利用分野）
本発明は原子力プラントの分析用試料採取装置に関する
ものである。DETAILED DESCRIPTION OF THE INVENTION (Field of Industrial Application) The present invention relates to a sample collection device for analysis in a nuclear power plant.
（従来の技術） 原子力発電所では、万一事故が発生した場合。(Conventional technology) In the unlikely event that an accident occurs at a nuclear power plant.
直ちに事故の終息及び復旧を図るように配慮されている
。事故の発生した原子力発電所の状況は。Efforts are being made to immediately end the accident and restore the situation. What is the status of the nuclear power plant where the accident occurred?
種々の計測機器により監視、 ６！認される。またこの
とき、計測機器による確認を捕捉するために。Monitored by various measuring instruments, 6! recognized. Also at this time, to capture confirmation by measuring instruments.
原子炉の冷却材及び原子炉格納容器内の雰囲気ガスから
試料が直接採取されて１分析される。この事故発生時の
試料採取には７通常運転時に原子炉の冷却材及び原子炉
格納容器内の雰囲気ガスから試料を採取して分析する分
析用試料採取装置が使用されている。Samples are directly taken from the reactor coolant and the atmospheric gas in the reactor containment vessel and analyzed. To collect samples in the event of an accident, an analytical sample collection device is used that collects and analyzes samples from the reactor coolant and atmospheric gas in the reactor containment vessel during normal operation.
一般に試料を採取する場合には１分析績度を向上するた
めに、試料自身を使用してサンプル採取管を予め洗浄し
ているが、原子力発電所では、サンプル採取管を洗浄す
る場合、サンプル採取管を洗浄した冷却材の全てが廃液
になる。また原子炉格納容器内の雰囲気ガスを試料とし
て採取する場合、雰囲気ガス中に含まれている水蒸気の
凝縮水が廃液になり、この廃液と上記サンプル採取管洗
浄後の廃液とを処理する必要がある
この廃液処理設備及び分析用試料採取装置の従来例を第
２図により説明すると、 （２０）が原子炉格納容器壁
、（２１）が原子炉格納容器の内部、 （２２）が原子
炉格納容器の外部、（１）が弁、 （２ａ）が原子炉格
納容器内から原子炉格納容器外へ延びたサンプル採取管
、（３）がトラップ、（４）が試料採取容器、（５）が
コンプレッサ、 （６ａ）が原子炉格納容器外から原子
炉格納容器内へ延びたサンプル返送管、（７）が液体廃
棄物処理設備の受タンク、 （２ｂ）が上記サンプル採
取管（２ａ）のトラップ（３）から同受タンク（７）へ
延びた配管、 （６ｂ）が上記サンプル返送管（６ａ）
のトラップ（３）から上記受タンク（７）へ延びた配管
。Generally, when collecting a sample, the sample collection tube is cleaned in advance using the sample itself in order to improve the analysis performance.However, at nuclear power plants, when cleaning the sample collection tube, the sample collection tube is All of the coolant that cleaned the pipes becomes waste liquid. In addition, when collecting the atmospheric gas inside the reactor containment vessel as a sample, the condensed water of the water vapor contained in the atmospheric gas becomes waste liquid, and it is necessary to treat this waste liquid and the waste liquid after cleaning the sample collection tube. A conventional example of this waste liquid treatment equipment and analytical sample collection device is explained with reference to Fig. 2. (20) is the reactor containment vessel wall, (21) is the inside of the reactor containment vessel, and (22) is the reactor containment vessel wall. Outside the vessel, (1) is the valve, (2a) is the sample collection tube extending from inside the reactor containment vessel to outside the reactor containment vessel, (3) is the trap, (4) is the sample collection vessel, and (5) is the A compressor, (6a) a sample return pipe extending from outside the reactor containment vessel into the reactor containment vessel, (7) a receiving tank of the liquid waste treatment equipment, and (2b) a trap of the sample collection pipe (2a). The pipe extending from (3) to the receiving tank (7), (6b) is the sample return pipe (6a)
Piping extends from the trap (3) to the receiving tank (7).
（８ａ）が原子炉冷却材系から延びたサンプル、採取管
。(8a) is a sample collection tube extending from the reactor coolant system.
（９）が冷却器、 （１０）がサンプル採取容器、 （
１１）が液体廃棄物処理設備の受タンク、 （８ｃ）が
同受タンク（１１）から上記受タンク（７）（または原
子炉冷却系）へ延びた配管、 （６ｅ）が他のトラップ
（３゛）から上記受タンク（７）へ延びた配管、 （６
ｆ）が上記受タンク（７）から液体廃棄物処理設備の蒸
発装置（１９）（または原子炉冷却系）へ延びた配管で
１通常運転時には、原子炉冷却材の試料（２４）がサン
プル採取管（８ａ）を通って冷却器（９）へ導かれ、こ
こで冷却された後１通常運転時も事故発生時も作業環境
上間邪のない場所に設置された試料採取容器（１０）へ
導かれて、採取される。またこの試料採取前に洗浄が行
われるが、このとき１発生する廃液が受タンク（１１）
に集められた後、受タンク（７）を経て液体廃棄物処理
設備の蒸発装置（１９）等へ導かれて処理されるか、原
子炉冷却系へ導かれて、再利用される。またこのとき、
原子炉格納容器（２１）内の雰囲気ガスの試料（２３）
がコンプレッサ（５）からサンプル採取管（２ａ）−試
料採取容器（４）−サンプル返送管（６ａ）一原子炉格
納容器内を循環して、試料が試料採取容器（４）により
採取される。またこのとき、トラップ（３）により集取
された凝縮水が液体廃棄物処理設備の受タンク（７）へ
導かれた後。(9) is the cooler, (10) is the sample collection container, (
11) is the receiving tank of the liquid waste treatment equipment, (8c) is the pipe extending from the receiving tank (11) to the receiving tank (7) (or reactor cooling system), and (6e) is the other trap (3). Piping extending from ゛) to the receiving tank (7), (6
f) is the pipe extending from the receiving tank (7) to the evaporator (19) (or reactor cooling system) of the liquid waste treatment facility.1 During normal operation, a sample of the reactor coolant (24) is sampled. The sample is guided through the pipe (8a) to the cooler (9), where it is cooled and then transferred to the sample collection container (10), which is placed in a place that is safe from the working environment during normal operation and in the event of an accident. Guided and collected. In addition, cleaning is performed before this sample collection, and the waste liquid generated at this time is transferred to the receiving tank (11).
After being collected, the waste is either guided through the receiving tank (7) to the evaporator (19) of the liquid waste treatment facility for treatment, or guided to the reactor cooling system for reuse. Also at this time,
Atmospheric gas sample (23) inside the reactor containment vessel (21)
The sample is circulated from the compressor (5) through the sample collection tube (2a), sample collection container (4), and sample return pipe (6a) within the reactor containment vessel, and a sample is collected by the sample collection container (4). Also at this time, after the condensed water collected by the trap (3) is led to the receiving tank (7) of the liquid waste treatment facility.
蒸発装置（１９）等により処理される。It is processed by an evaporator (19) or the like.
一方、事故発生時には、上記通常運転時と同様に試料が
採取されるが、事故発生時の原子炉冷却材及び格納容器
内の雰囲気ガスは１高温度の放射性物質により汚染され
ている可能性があり、放射能汚染が高い場合には、試料
の採取に伴って発生する廃液を通常運転時と同様に処理
するのは、放出、放射能の観点から好ましくなく、この
場合には受タンク（７）或いは受タンク（１１）に集液
した状態で貯蔵管理される
（発明が解決しようとする課題）
前記のように第２図に示す従来の原子力プラントの分析
用試料採取装置では、事故発生時の試料採取に伴って発
生する廃液を受タンク（７）或いは受タンク（１１）に
集液した状態で貯蔵管理しており。On the other hand, when an accident occurs, samples are collected in the same way as during normal operation, but the reactor coolant and atmospheric gas inside the containment vessel at the time of the accident may be contaminated with high-temperature radioactive materials. If radioactive contamination is high, it is undesirable to treat the waste liquid generated during sample collection in the same way as during normal operation from the standpoint of release and radioactivity. ), or the liquid is stored and managed in a collected state in the receiving tank (11) (problem to be solved by the invention). The waste liquid generated during sample collection is collected and stored in a receiving tank (7) or a receiving tank (11).
受タンク（７） （１１）の貯蔵容量によっては試料採
取の回数が制約されるという問題があった本発明は前記
の問題点に鑑み提案するものであり、その目的とする処
は、事故発生時の試料採取に伴って発生した廃液を原子
炉格納容器へ返送。The present invention has been proposed in view of the above-mentioned problem in that the number of sample collections is limited depending on the storage capacity of the receiving tank (7) (11). Waste liquid generated during sample collection was returned to the reactor containment vessel.
処理できて、試料採取の回数に制約を受けない原子力プ
ラントの分析用試料採取装置を提供しようとする点にあ
る。The object of the present invention is to provide a sample collection device for analysis in a nuclear power plant that is capable of processing and is not subject to restrictions on the number of sample collections.
（課題を解決するための手段）
上記目的を達成するために１本発明の原子力プラントの
分析用試料採取装置は、原子炉格納容器内から同格納容
器外へ延びたサンプル採取管と。(Means for Solving the Problems) In order to achieve the above object, a sample collection device for analysis of a nuclear power plant according to the present invention includes a sample collection pipe extending from inside the reactor containment vessel to outside the containment vessel.
同サンプル採取管の系統に試料採取に伴って発生する廃
液を上記原子炉格納容器内へ戻す廃液返送管とを弁を介
して連絡している。The sample collection pipe system is connected via a valve to a waste liquid return pipe that returns waste liquid generated during sample collection to the reactor containment vessel.
（作用）
本発明の原子力プラントの分析用試料採取装置は前記の
ように原子炉格納容器内から同格納容器外へ延びたサン
プル採取管と、同サンプル採取管の系統に試料採取に伴
って発生する廃液を上記原子炉格納容器内へ戻す廃液返
送管とを弁を介して連絡しており、事故発生時に試料採
取に伴って発生する廃液を弁を開いて原子炉格納容器へ
返送。(Function) As described above, the analytical sample collection device for a nuclear power plant of the present invention has a sample collection pipe extending from inside the reactor containment vessel to the outside of the containment vessel, and a system of the sample collection pipe that generates a sample during sample collection. It is connected via a valve to the waste liquid return pipe that returns the waste liquid to the reactor containment vessel, and in the event of an accident, the waste liquid generated during sample collection is returned to the reactor containment vessel by opening the valve.
処理することが可能で、試料採取の回数に制約を受けな
い。There are no restrictions on the number of times samples can be taken.
（実施例）
次に本発明の原子力プラントの分析用試料採取装置を第
１図に示す一実施例により説明すると。(Example) Next, the analytical sample collection device for a nuclear power plant of the present invention will be explained using an example shown in FIG.
（２０）が原子炉格納容器壁、 （２１）が原子炉格納
容器の内部、 （２２）が原子炉格納容器の外部、（１
）が弁。(20) is the reactor containment vessel wall, (21) is the inside of the reactor containment vessel, (22) is the outside of the reactor containment vessel, (1
) is the valve.
（２ａ）が原子炉格納容器内から原子炉格納容器外へ延
びたサンプル採取管、（３）がトラップ、（４）が試料
採取容器、（５）がコンプレッサ、 （６ａ）が原子炉
格納容器外から原子炉格納容器内へ延びたサンプル返通
管、（７）が液体廃棄物処理設備の受タンク、 （２ｂ
）が上記サンプル採取管（２ａ）のトラップ（３）から
同受タンク（７）へ延びた配管、 （１７）が廃液集収
タンク、 （２ｃ）が上記配管（２ｂ）から分岐した廃
液返送管。(2a) is the sample collection tube extending from inside the reactor containment vessel to the outside of the reactor containment vessel, (3) is the trap, (4) is the sample collection vessel, (5) is the compressor, and (6a) is the reactor containment vessel. Sample return pipe extending from the outside into the reactor containment vessel, (7) is the receiving tank of the liquid waste treatment equipment, (2b
) is a pipe extending from the trap (3) of the sample collection pipe (2a) to the receiving tank (7), (17) is a waste liquid collection tank, and (2c) is a waste liquid return pipe branched from the pipe (2b).
（２ｄ）が同廃液返送管（２Ｃ）から上記廃液集収タン
ク（１７）へ延びた廃液返送管、 （６ｂ）が上記サン
プル返送管（６ａ）のトラップ（３）から同受タンク（
７）へ延びた配管、 （６ｃ）が同配管（６ｂ）から分
岐した廃液返送管、 （６ｄ）が同廃液返送管（６ｃ）
から上記廃液集収タンク（１７）へ延びた廃液返送管、
（６ｅ）が他のトラップ（３″）から同廃液集収タン
ク（１７）へ延びた廃液返送管、 （６ｆ）が上記受タ
ンク（７）から液体廃棄物処理設備の蒸発装置（１９）
（または原子炉冷却系）へ延びた配管、 （８ａ）
（８ｂ）が原子炉冷却材系から延びたサンプル採取管、
（９）が冷却器、 （１０）がサンプル採取容器、 （
１６ａ）が上記サンプル採取管（８ａ）（８ｂ）間から
分岐した廃液返送管で１同廃液返送管（１６ａ）が原子
炉格納容器内へ延びている。また（１１）が液体廃棄物
処理設備の受タンク、 （８ｃ）が同受タンク（１１）
から上記受タンク（７）（または原子炉冷却系）へ延び
た配管、 （１６ｂ）が上記廃液集収タンク（１７）か
ら上記廃液返送管（１６ａ）へ延びた廃液返送管、 （
１８）が同廃液返送管（１６ｂ）に設けたポンプ（１２
）〜（１５）が弁である。(2d) is a waste liquid return pipe extending from the waste liquid return pipe (2C) to the waste liquid collection tank (17), and (6b) is a waste liquid return pipe extending from the sample return pipe (6a) from the trap (3) to the waste liquid receiving tank (
7), (6c) is the waste liquid return pipe branched from the same pipe (6b), (6d) is the same waste liquid return pipe (6c)
a waste liquid return pipe extending from the waste liquid collection tank (17);
(6e) is the waste liquid return pipe extending from the other trap (3'') to the waste liquid collection tank (17), and (6f) is the evaporator (19) of the liquid waste treatment equipment from the receiving tank (7).
(or reactor cooling system), (8a)
(8b) a sample collection tube extending from the reactor coolant system;
(9) is the cooler, (10) is the sample collection container, (
16a) is a waste liquid return pipe branched from between the sample collection pipes (8a) and (8b), and one waste liquid return pipe (16a) extends into the reactor containment vessel. Also, (11) is the receiving tank of the liquid waste treatment equipment, and (8c) is the same receiving tank (11).
(16b) is a waste liquid return pipe extending from the waste liquid collection tank (17) to the waste liquid return pipe (16a);
18) is the pump (12) installed in the waste liquid return pipe (16b).
) to (15) are valves.
次に前記第１図に示す原子力プラントの分析用試料採取
装置の作用を説明する。Next, the operation of the analytical sample collection device for a nuclear power plant shown in FIG. 1 will be explained.
通常運転時には、原子炉冷却材の試料（２４）がサンプ
ル採取管（８ａ）を通って冷却器（９）へ導かれここで
冷却された後、試料採取容器（１０）へ導かれて３採取
される。またこの試料採取前に洗浄が行われるが、この
とき９発生する廃液が受タンク（１１）に集められた後
、受タンク（７）を経て液体廃棄物処理設備の蒸発装置
（１９）等へ導かれて１処理されるか、原子炉冷却系へ
導かれて、再利用される。During normal operation, a reactor coolant sample (24) is guided through the sample collection tube (8a) to the cooler (9) where it is cooled, and then led to the sample collection container (10) for three collections. be done. In addition, cleaning is performed before this sample collection, and the waste liquid generated at this time is collected in the receiving tank (11), and then sent to the evaporator (19) of the liquid waste treatment equipment via the receiving tank (7). Either it is guided to the reactor cooling system and recycled.
またこのとき、原子炉格納容器（２１）内の雰囲気ガス
の試料（２３）がコンプレッサ（５）からサンプル採取
管（２ａ）−試料採取容器（４）−サンプル返送管（６
ａ）−原子炉格納容器内を循環して１試料が試料採取容
器（４）により採取される。またこのとき、トラップ（
３）により集収された凝縮水が液体廃棄物処理設備の受
タンク（７）へ導かれた後、蒸発装置（１９）等により
処理される。At this time, the sample (23) of the atmospheric gas in the reactor containment vessel (21) is transferred from the compressor (5) to the sample collection tube (2a) - sample collection container (4) - sample return pipe (6).
a) - One sample is collected by the sampling container (4) while circulating inside the reactor containment vessel. Also at this time, the trap (
After the condensed water collected by step 3) is led to the receiving tank (7) of the liquid waste treatment facility, it is treated by an evaporator (19) or the like.
一方、事故発生時、原子炉冷却材を試料として採取する
場合には、弁（１４）を閉じ、弁（１５）を開いて、サ
ンプル採取容器（１０）からの廃液を廃液返送管（１６
ａ）を経て原子炉格納容器内へ直接返送する。On the other hand, when collecting reactor coolant as a sample in the event of an accident, the valve (14) is closed, the valve (15) is opened, and the waste liquid from the sample collection container (10) is transferred to the waste liquid return pipe (16).
Directly return to the reactor containment vessel via a).
またこのとき、原子炉格納容器（２１）内の雰囲気ガス
を試料（２３）として採取する場合には、弁（１２）を
閉じ、弁（１３）を開いて、トラップ（３）からの廃液
を廃液返送管（２ｃ） （２ｄ）及び（６ｃ） （６ｄ
）を経て廃液集収タンク（１７）へ集収する。また同廃
液集収タンク（１７）が満杯近くになると、ポンプ（１
８）を起動して。At this time, if the atmospheric gas inside the reactor containment vessel (21) is to be collected as a sample (23), the valve (12) is closed, the valve (13) is opened, and the waste liquid from the trap (3) is collected. Waste liquid return pipe (2c) (2d) and (6c) (6d
) to the waste liquid collection tank (17). Also, when the waste liquid collection tank (17) is almost full, the pump (1
8) Start it.
同廃液集収タンク（１７）内の廃液を廃液返送管（１６
ｂ）−廃液返送管（１６ａ）を経て原子炉格納容器内へ
返送する。この場合、ポンプ（１８）の代わりに廃液集
収タンク（１７）の気相部をＮ２ガス等により加圧して
、圧送するようにしてもよい。なお前記通常運転時には
、原子炉格納容器内が事故発生時のように高濃度の放射
性物質で汚染されていないので１通常運転時に試料採取
に伴って発生する廃液を原子炉格納容器内へ返送すると
、原子炉容器格納容器内が汚染の原因になる。このため
２通常運転時には、試料採取に伴って発生する廃液は従
来と同じように原子炉冷却材として再利用するか液体廃
棄物処理設備へ送って、°蒸発処理等を行う。The waste liquid in the waste liquid collection tank (17) is transferred to the waste liquid return pipe (16).
b) - Return to the reactor containment vessel via the waste liquid return pipe (16a). In this case, instead of the pump (18), the gas phase portion of the waste liquid collection tank (17) may be pressurized with N2 gas or the like and the liquid may be fed under pressure. Furthermore, during normal operation, the inside of the reactor containment vessel is not contaminated with highly concentrated radioactive materials as it was during the accident. , causing contamination inside the reactor vessel containment vessel. Therefore, during normal operation, the waste liquid generated during sample collection is either reused as a reactor coolant or sent to a liquid waste treatment facility for evaporation treatment, etc., as in the past.
（発明の効果）
本発明の原子力プラントの分析用試料採取装置は前記の
ように原子炉格納容器内から同格納容器外へ延びたサン
プル採取管と、同サンプル採取管の系統に試料採取に伴
って発生する廃液を上記原子炉格納容器内へ戻す廃液返
送管とを弁を介して連絡しており、事故発生時に試料採
取に伴って発生する廃液を弁を開いて原子炉格納容器へ
返送。(Effects of the Invention) As described above, the analytical sample collection device for a nuclear power plant of the present invention has a sample collection pipe extending from inside the reactor containment vessel to the outside of the containment vessel, and a system of the sample collection pipe. It is connected via a valve to the waste liquid return pipe that returns the waste liquid generated during the process to the reactor containment vessel, and in the event of an accident, the waste liquid generated during sample collection is returned to the reactor containment vessel by opening the valve.
処理するので、試料採取の回数に制約を受けない効果が
ある。Because it is processed, there is no restriction on the number of times samples can be taken.
第１図は本発明に係わる原子力プラントの分析用試料採
取装置の一実施例を示す系統図、第２図は従来の原子力
プラントの分析用試料採取装置を示す系統図である。
（２ａ）及び（８ａ）・・・サンプル保取管、 （２ｃ
） （２ｄ） 。
（６ｃ） （６ｄ） 、 （１６ａ） （１６ｂ）
・・・廃液返送管、 （２０）・・原子炉格納容器壁、
（２１） ・・・原子炉格納容器内、 （２２）
・・・原子炉格納容器外。FIG. 1 is a system diagram showing an embodiment of a sample collection device for analysis in a nuclear power plant according to the present invention, and FIG. 2 is a system diagram showing a conventional sample collection device for analysis in a nuclear power plant. (2a) and (8a)...sample storage, (2c
) (2d). (6c) (6d) , (16a) (16b)
... Waste liquid return pipe, (20) ... Reactor containment vessel wall,
(21) ...Inside the reactor containment vessel, (22)
...Outside the reactor containment vessel.
Claims (1)
採取管と、同サンプル採取管の系統に試料採取に伴って
発生する廃液を上記原子炉格納容器内へ戻す廃液返送管
とを弁を介して連絡したことを特徴とする原子力プラン
トの分析用試料採取装置。A sample collection pipe extending from inside the reactor containment vessel to outside the containment vessel, and a waste liquid return pipe that returns waste liquid generated due to sample collection to the reactor containment vessel are connected to the system of the sample collection pipe via a valve. A sample collection device for analysis of a nuclear power plant, characterized in that
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63185363A JP2625161B2 (en) | 1988-07-27 | 1988-07-27 | Analytical sampling equipment for nuclear power plants |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63185363A JP2625161B2 (en) | 1988-07-27 | 1988-07-27 | Analytical sampling equipment for nuclear power plants |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH0236337A true JPH0236337A (en) | 1990-02-06 |
| JP2625161B2 JP2625161B2 (en) | 1997-07-02 |
Family
ID=16169490
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP63185363A Expired - Lifetime JP2625161B2 (en) | 1988-07-27 | 1988-07-27 | Analytical sampling equipment for nuclear power plants |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JP2625161B2 (en) |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US9260577B2 (en) | 2009-07-14 | 2016-02-16 | Toray Plastics (America), Inc. | Crosslinked polyolefin foam sheet with exceptional softness, haptics, moldability, thermal stability and shear strength |
| CN110223791A (en) * | 2019-04-12 | 2019-09-10 | 中国核动力研究设计院 | A kind of core sampling system that can be used for after pressurized-water reactor nuclear power plant accident |
| CN117213927A (en) * | 2023-09-15 | 2023-12-12 | 中核环保产业有限公司 | Nuclear power station wastewater sampling device capable of being remotely operated and application method thereof |
Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS6212831A (en) * | 1985-07-10 | 1987-01-21 | Hitachi Ltd | Sample collecting system |
-
1988
- 1988-07-27 JP JP63185363A patent/JP2625161B2/en not_active Expired - Lifetime
Patent Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS6212831A (en) * | 1985-07-10 | 1987-01-21 | Hitachi Ltd | Sample collecting system |
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US9260577B2 (en) | 2009-07-14 | 2016-02-16 | Toray Plastics (America), Inc. | Crosslinked polyolefin foam sheet with exceptional softness, haptics, moldability, thermal stability and shear strength |
| US10301447B2 (en) | 2009-07-14 | 2019-05-28 | Toray Plastics (America), Inc. | Crosslinked polyolefin foam sheet with exceptional softness, haptics, moldability, thermal stability and shear strength |
| CN110223791A (en) * | 2019-04-12 | 2019-09-10 | 中国核动力研究设计院 | A kind of core sampling system that can be used for after pressurized-water reactor nuclear power plant accident |
| CN117213927A (en) * | 2023-09-15 | 2023-12-12 | 中核环保产业有限公司 | Nuclear power station wastewater sampling device capable of being remotely operated and application method thereof |
| CN117213927B (en) * | 2023-09-15 | 2024-04-23 | 中核环保产业有限公司 | Nuclear power station wastewater sampling device capable of being remotely operated and application method thereof |
Also Published As
| Publication number | Publication date |
|---|---|
| JP2625161B2 (en) | 1997-07-02 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| JPH0236337A (en) | Analytic test piece sampling device for nuclear plant | |
| US4828760A (en) | Method of cleaning a spent fuel assembly | |
| KR101061466B1 (en) | Automatic tritium sampler and control method therefore | |
| JPH0151937B2 (en) | ||
| EP0281680B1 (en) | Method of cleaning a spent fuel assembly | |
| JP3668656B2 (en) | Fuel inspection device | |
| JPH10332889A (en) | Leak detector in storage tank in cell | |
| EP1290699B1 (en) | Method of applying foam reagents for radioactive decontamination | |
| JP2005098741A (en) | Leak detection method | |
| JPS6212831A (en) | Sample collecting system | |
| Naruse et al. | Operation of the Tritium Process Laboratory (TPL) in the Japan Atomic Energy Research Institute | |
| Corcoran et al. | Decontamination and decommissioning of UK tritium facilities | |
| RU2123210C1 (en) | Method for cleaning reactor equipment from sodium | |
| Symonds | Absorption System for Radioactive Iodine | |
| Maienschein et al. | Experiences with decontaminating tritium-handling apparatus | |
| JP2653445B2 (en) | Radioactive waste decontamination system | |
| Witbeck | Argonne, Illinois 60439 | |
| JPS6188189A (en) | In-pile shipping device | |
| JPH0220670Y2 (en) | ||
| JPS6139999Y2 (en) | ||
| Reilly et al. | Processing and removal of the Three Mile Island makeup and purification system resins | |
| Vater et al. | Rapid determination of transuranium nuclides in the primary coolant of a nuclear power plant by using nuclear track micro filters and investigation of α-emitting particles on the loaded filters by α-autoradiography | |
| Row | Radioactive waste systems and radioactive effluents | |
| Harllee et al. | Dry active waste sorting at a nuclear power plant | |
| JPH0456960B2 (en) |