JPS61172100A - Method of removing deposit of spent nuclear fuel aggregate - Google Patents

Method of removing deposit of spent nuclear fuel aggregate

Info

Publication number
JPS61172100A
JPS61172100A JP1241185A JP1241185A JPS61172100A JP S61172100 A JPS61172100 A JP S61172100A JP 1241185 A JP1241185 A JP 1241185A JP 1241185 A JP1241185 A JP 1241185A JP S61172100 A JPS61172100 A JP S61172100A
Authority
JP
Japan
Prior art keywords
container
limescale
nuclear fuel
water
air
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
Application number
JP1241185A
Other languages
Japanese (ja)
Inventor
瀬谷 通
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Hitachi Ltd
Original Assignee
Hitachi Ltd
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Hitachi Ltd filed Critical Hitachi Ltd
Priority to JP1241185A priority Critical patent/JPS61172100A/en
Publication of JPS61172100A publication Critical patent/JPS61172100A/en
Pending legal-status Critical Current

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  • Solid Fuels And Fuel-Associated Substances (AREA)

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】 〔発明の利用分野〕 本発明は、主に軽水冷却型原子炉に装荷された使用済核
燃料集合体表面に付着した水垢除去に最適な方法に関す
る。
DETAILED DESCRIPTION OF THE INVENTION [Field of Application of the Invention] The present invention mainly relates to an optimal method for removing limescale adhering to the surface of a spent nuclear fuel assembly loaded in a light water-cooled nuclear reactor.

〔発明の背景〕[Background of the invention]

従来の装置は、特開昭59−90200号公報に記載の
ように核燃料集合体を乾燥室に密閉後、炉水を排除し高
温高圧ガスで急速度に乾燥して剥離すると共に炉水を強
制的に供給して燃料棒を洗浄するとなっていた。しかし
、核燃料集合体は核分裂生成物の崩壊により、原子炉を
停止し例えば1週間後の発熱量は約10 kca Q 
/ seeに達し、燃料棒表面が高温になってしまうこ
とが考慮されていなかった。
Conventional equipment, as described in Japanese Unexamined Patent Publication No. 59-90200, seals the nuclear fuel assembly in a drying chamber, removes reactor water, rapidly dries it with high-temperature, high-pressure gas, and peels it off, while forcing the reactor water. It was supposed to clean the fuel rods by supplying them with water. However, the calorific value of a nuclear fuel assembly, for example, one week after the reactor is shut down due to the decay of fission products, is approximately 10 kca Q.
/see and the surface of the fuel rods would become hot.

〔発明の目的〕[Purpose of the invention]

本発明の目的は、使用済核燃料集合体に付着した水垢を
、燃料貯蔵プール内に設置した容器に密閉し、容器の水
を排除し冷却しながら水垢を乾燥させ、高圧空気を注入
し、乾燥の迅速化を計ると共に、燃料棒に高圧空気との
接触衝撃を与えさらに空気を混入した洗浄水を注入する
ことにより気泡の消滅力で水垢を燃料棒から剥離し、剥
離した水垢を受槽に搬出させる方法を提供することにあ
る。
The purpose of the present invention is to seal water scales attached to spent nuclear fuel assemblies in a container installed in a fuel storage pool, remove water from the container, dry the scales while cooling, and inject high-pressure air to dry the water scales. In addition to speeding up the process, the fuel rods are subjected to contact impact with high-pressure air, and cleaning water mixed with air is injected to remove limescale from the fuel rods with the force of extinguishing air bubbles, and the peeled scale is transported to a receiving tank. The goal is to provide a method to do so.

〔発明の概要〕[Summary of the invention]

核燃料集合体に付着した水垢除去方法として従来から、
化学薬品の使用と水中での高圧水噴射法または超音波法
および乾燥除去法等が考えられていたが、化学薬品を使
用すると核燃料集合体自体への影響が懸念されるだけで
なく、使用した薬品の処理が困菫である。また水中での
高圧水噴射法は、高圧水が水中で減衰するため核燃料集
合体の内側に配列された燃料棒は外側燃料棒の陰になっ
ているので水垢は除去されず、水垢が除去されるのは主
に外周燃料棒の1部のみである。一方超音波を用いた場
合も超音波が接触する外周燃料棒の外面しか水垢は除去
できず非常に効率が悪いなお、燃料棒に付着している水
垢は、燃料棒表面に近い部分がスピネル構造をもつ強固
に付着した水垢層で二重構造になっているため、前記し
た高圧水注入のみでは強固な水垢層の除去は困難である
。以上のことから最もよい水垢除去法として、水垢が付
着した核燃料集合体を大気中の状態にし水垢を乾燥する
ことにより、膨潤状態の水垢と乾燥状態の水垢の体積差
を引用して除去する乾燥法があるが、核燃料集合体は、
核分裂生成物の崩壊による崩壊熱の影響があり例えば原
子炉停止1週間後の崩壊熱は約10 kca Q / 
seeに達する。この状態で燃料棒に付着した水垢を乾
燥させるには棒燃棒表面が高温になるため冷却が必要と
なり、冷却ガスの使用等、冷却装置の規模を大きくしな
ければならない。しかしながら、使用済核燃料集合体は
再処理に搬出される前に半年〜1年間使用済燃料貯蔵プ
ール内で保管されこの間に燃料棒の表面温度が150〜
200℃まで低下する1本発明はこの温度低下に着眼し
、冷却された使用済核燃料集合体に付着している水垢を
効果的に除去する装置を提供することを目的とし、水中
に設置した容器内に使用済核燃料集合体を密閉し、容器
内を簡単な冷却設備で冷却しながら容器内の水を排除し
て空冷で使用済核燃料集合体に付着した水垢を乾燥させ
るのと共に温度上昇を防止する。次に高圧空気を噴射し
乾燥を迅速化すると共に高圧空気による燃料棒への接触
衝撃により水垢を燃料棒から剥離させる。さらに空気を
混入した洗浄水を燃料棒に注入し、気泡の消滅力を利用
して再度燃料棒から水垢を剥離することを特徴とするも
のである。すなわち本発明は、使用済燃料貯蔵プール内
で冷却された使用済核燃料集合体の水垢を空冷を行ない
ながら乾燥し接触衝撃および気泡の消滅力を利用した水
垢除去方法である。
Traditionally, as a method for removing limescale adhering to nuclear fuel assemblies,
The use of chemicals, underwater high-pressure water injection method, ultrasonic method, and dry removal method were considered, but there were concerns that using chemicals would not only affect the nuclear fuel assembly itself, but also that Processing of chemicals is difficult. In addition, in the underwater high-pressure water injection method, water scale is not removed because the fuel rods arranged inside the nuclear fuel assembly are in the shadow of the outer fuel rods because the high-pressure water is attenuated in the water. Mainly, only a portion of the outer fuel rods are affected. On the other hand, even when ultrasonic waves are used, water scale can only be removed from the outer surface of the outer peripheral fuel rod, which is in contact with the ultrasonic waves, which is very inefficient.In addition, the water scale attached to the fuel rods has a spinel structure in the part near the surface of the fuel rod. Since it has a double structure with a strongly adhered limescale layer, it is difficult to remove the strong limescale layer only by injecting high-pressure water as described above. Based on the above, the best way to remove limescale is to expose the nuclear fuel assembly with limescale to the atmosphere and dry the scale, which removes the scale based on the difference in volume between the swollen scale and the dry scale. There is a law, but nuclear fuel assemblies are
There is an effect of decay heat due to the decay of nuclear fission products, and for example, the decay heat after one week of reactor shutdown is approximately 10 kca Q /
reach see. In order to dry the limescale adhering to the fuel rods in this state, the surface of the fuel rods becomes hot and requires cooling, which requires the use of cooling gas or a larger scale cooling system. However, spent nuclear fuel assemblies are stored in spent fuel storage pools for six months to one year before being transported for reprocessing, and during this time the surface temperature of the fuel rods is 150 to 150°C.
Focusing on this temperature drop, the present invention aims to provide a device for effectively removing limescale adhering to a cooled spent nuclear fuel assembly. The spent nuclear fuel assembly is sealed inside the container, and while the inside of the container is cooled with simple cooling equipment, the water inside the container is removed, air cooling is used to dry the limescale attached to the spent nuclear fuel assembly, and prevent temperature rise. do. Next, high-pressure air is injected to speed up drying, and the contact impact of the high-pressure air on the fuel rods causes limescale to be peeled off from the fuel rods. Furthermore, cleaning water mixed with air is injected into the fuel rods, and scale is again removed from the fuel rods by utilizing the extinguishing power of air bubbles. That is, the present invention is a method for removing scale by drying scale from a spent nuclear fuel assembly cooled in a spent fuel storage pool while cooling the pool in air, and utilizing contact impact and the vanishing power of bubbles.

〔発明の実施例〕[Embodiments of the invention]

第2図に核燃料集合体1の基本構造を示す。この核燃料
集合体1は、正方格子状に並べた複数本の燃料棒2と7
個のスペーサ3と燃料棒2を保持する上部下部タイプレ
ート4,5燃料捧2の周囲を取囲むチャンネルボックス
6さらにチャンネルボックス7を上部タイプレート4に
固定するチャンネルファスナー7から構成されている。
FIG. 2 shows the basic structure of the nuclear fuel assembly 1. This nuclear fuel assembly 1 consists of a plurality of fuel rods 2 and 7 arranged in a square grid.
The fuel rod 2 is comprised of spacers 3, upper and lower tie plates 4, 5 for holding the fuel rods 2, a channel box 6 surrounding the fuel rod 2, and channel fasteners 7 for fixing the channel box 7 to the upper tie plate 4.

冷却水は下部タイプレート5のノーズピースからチャン
ネルボックス6内を流れ燃料棒2を冷却し上部タイプレ
ート4に向っていく。そして長期間使用している・と燃
料棒2の表面に水垢8が付着する。
Cooling water flows through the channel box 6 from the nose piece of the lower tie plate 5, cools the fuel rods 2, and then flows toward the upper tie plate 4. If the fuel rod 2 is used for a long period of time, water scale 8 will adhere to the surface of the fuel rod 2.

第1図は本発明の一実施例を示す、10は水中に設置さ
れたクランプ式開閉蓋を備えた四角の細長い容器でこの
中に水垢が付着している使用済核燃料集合体9を収納密
閉する。なお使用済核燃料集合体9は、第2図に示した
核燃料集合体1よりチャンネルボックス6を取外したも
のであり、第1図はこれを模式的に示している。容器1
0の内部には使用済核燃料集合体9を保持するためのア
ダプター11と中間サポート12およびエアースパージ
ャ管13、洗浄水注入ヘッダー管14、冷却コイル15
が設けられている。また容器10には洗浄水供給系21
.(22,23,24)と空気供給系18 (19,2
0)および水の排出処理系25(26〜3o)、熱伝対
17が設けられている。冷却コイル15は使用済核燃料
集合体の全スパンを網羅しており冷却コイル15内には
例えば、アルゴンガスのような冷却ガスが密閉されモー
タ16により冷却ガスを圧縮し容器全体を冷却する。一
方エアースパーシャ管からエアーコンプレッサ19を介
して注入し、洗浄水6弁22を介して注入する。また洗
浄水は高圧ポンプ24を有し弁23を介して洗浄水注入
ヘッダー14から注入する。容器10内の水の排出処理
系25は容器10の排出口26から弁27を介して水を
排出する排水ポンプ28と排出された水のろ過器29と
処理水タンク30を有している。次にこの装置を用いて
水垢を除去する方法について説明する。
FIG. 1 shows an embodiment of the present invention. Reference numeral 10 is a rectangular and elongated container equipped with a clamp-type opening/closing lid that is installed underwater, and a spent nuclear fuel assembly 9 with limescale attached therein is stored and sealed. do. The spent nuclear fuel assembly 9 is obtained by removing the channel box 6 from the nuclear fuel assembly 1 shown in FIG. 2, and FIG. 1 schematically shows this. container 1
Inside the 0, there are an adapter 11 for holding the spent nuclear fuel assembly 9, an intermediate support 12, an air sparger pipe 13, a cleaning water injection header pipe 14, and a cooling coil 15.
is provided. The container 10 also has a cleaning water supply system 21.
.. (22, 23, 24) and air supply system 18 (19, 2
0), a water discharge treatment system 25 (26 to 3o), and a thermocouple 17. The cooling coil 15 covers the entire span of the spent nuclear fuel assembly, and a cooling gas such as argon gas is sealed inside the cooling coil 15, and a motor 16 compresses the cooling gas to cool the entire container. On the other hand, the air is injected from the air sparge pipe through the air compressor 19, and the cleaning water is injected through the 6-valve 22. Further, the washing water is injected from the washing water injection header 14 via a valve 23 having a high pressure pump 24. A discharge treatment system 25 for water in the container 10 includes a drainage pump 28 for discharging water from an outlet 26 of the container 10 via a valve 27, a filter 29 for discharged water, and a treated water tank 30. Next, a method for removing limescale using this device will be explained.

(1)半年〜1年間使用済燃料貯蔵プール内で冷却され
た使用済核燃料集合体9からチャンネルボックスを取外
し、水中に設置した容器10内に収納密閉する。
(1) The channel box is removed from the spent nuclear fuel assembly 9 that has been cooled in the spent fuel storage pool for six months to one year, and the channel box is sealed and stored in the container 10 installed underwater.

(2)モータ16を作動し容器1oの内部を冷却する。(2) Operate the motor 16 to cool the inside of the container 1o.

(3)容器10内の温度を熱伝対17によって計り、弁
27を開いて容器10内の水を排水ポンプ28を用いて
排水口26から排出する。排出された水はろ過器29を
経て処理水タンク30に入る。
(3) The temperature inside the container 10 is measured by the thermocouple 17, the valve 27 is opened, and the water inside the container 10 is discharged from the drain port 26 using the drain pump 28. The discharged water passes through a filter 29 and enters a treated water tank 30.

(4)エアー弁20を開はコンプレッサ19を介し圧力
調整後、エアースパージャ管13より高圧空気を使用済
核燃料集合体9に注入し水垢の乾燥を迅速化すると共に
高圧空気による燃料棒への接触衝撃で水垢を燃料棒から
剥離する。
(4) Open the air valve 20 to adjust the pressure via the compressor 19, and then inject high-pressure air into the spent nuclear fuel assembly 9 from the air sparger pipe 13 to speed up the drying of scale and to bring the high-pressure air into contact with the fuel rods. The impact separates scale from the fuel rods.

(5)高圧空気注入を止め、注入圧力設定値を多少下げ
ておく、次に弁22に開は空気が混入している純水をエ
アースパージャ管13に送り、再びエアー弁20を開け
、空気が混入している純水を使用済核燃料集合体に注入
する。これにより燃料棒が圧力のかかった純水との衝撃
と気泡の消滅力で水垢が燃料棒表面から剥離する。
(5) Stop the high-pressure air injection and lower the injection pressure set value to some extent. Next, open the valve 22 to send the pure water mixed with air to the air sparger pipe 13, and open the air valve 20 again to inject the air. Inject the pure water mixed with the spent nuclear fuel into the spent nuclear fuel assembly. As a result, water scale is peeled off from the surface of the fuel rod due to the impact of the pressurized pure water and the extinguishing force of the bubbles.

この場合空中で純水に圧力をかけて注入するため圧力の
減衰はなく燃料棒の配列間隔を通し、核燃料集合体の内
部まで届き、衝撃力と気泡の  □消滅力で効率よく水
垢を除去できる。
In this case, since the pure water is injected under pressure in the air, there is no pressure attenuation, and the water reaches the inside of the nuclear fuel assembly through the spacing between the fuel rods, and water scale can be efficiently removed by the impact force and the extinguishing force of air bubbles. .

(6)排水ポンプ28を作動し容器10内の底に留った
水垢を排水口26から弁27を介してろ過器に収納しな
がらエアー弁20と純水弁22に止める。
(6) The drain pump 28 is operated to collect limescale remaining at the bottom of the container 10 from the drain port 26 through the valve 27 and into the filter while stopping it at the air valve 20 and the pure water valve 22.

(7)高圧ポンプ24を作動し弁23を介し洗浄水を洗
浄水注入ヘッダー14から使用済核燃料集合体に注入す
る。この場合、運転時の冷却水が核燃料集合体下部側か
ら流れている力を逆に上部側から洗浄水を流すことによ
り水垢をさらに除去するのを、使用済核燃料集合体の洗
浄を行なう目的をかねている。
(7) The high-pressure pump 24 is operated to inject wash water from the wash water injection header 14 into the spent nuclear fuel assembly via the valve 23. In this case, the purpose of cleaning spent nuclear fuel assemblies is to reverse the flow of cooling water from the lower side of the nuclear fuel assembly during operation and to flow cleaning water from the upper side to further remove limescale. It's been a long time.

〔発明の効果〕〔Effect of the invention〕

本発明によれば、非常に簡単な冷却設備で使用済核燃料
集合体を冷却でき効果的に水垢を除去することが可能で
あり、化学薬品を用いないので。
According to the present invention, spent nuclear fuel assemblies can be cooled with very simple cooling equipment, scale can be effectively removed, and no chemicals are used.

里子炉建屋内の使用済燃料貯蔵プール内で施行できる。It can be carried out inside the spent fuel storage pool in the Satoshi reactor building.

また、密閉容器内で水垢を除去するので作業員の被曝低
減が計れる。
Additionally, since limescale is removed in a sealed container, worker exposure to radiation can be reduced.

【図面の簡単な説明】[Brief explanation of drawings]

第1図は1本発明の使用済核燃料集合体の水垢除去装置
の一実施例を示す構成図、第2図は核燃料集合体の部分
断面図と燃料棒表面に付着した水垢の形態図である。 1・・・核燃料集合体、2・・・燃料棒、3・・・スペ
ーサ、4・・・上部タイプレート、5・・・下部タイプ
レート、9・・・使用済核燃料集合体、10・・・密閉
容器、11・・・下部アダプター、12・・・中間サポ
ート、14・・・洗浄水注入ヘッダー、15・・・冷却
コイル、16・・・冷却作動モータ、27・・・弁、2
8・・・排水ポンプ、29・・・ろ過器、30・・・処
理水タンク。
Fig. 1 is a configuration diagram showing an embodiment of the apparatus for removing limescale from a spent nuclear fuel assembly according to the present invention, and Fig. 2 is a partial sectional view of the nuclear fuel assembly and a diagram showing the form of limescale adhering to the surface of the fuel rods. . DESCRIPTION OF SYMBOLS 1...Nuclear fuel assembly, 2...Fuel rod, 3...Spacer, 4...Upper tie plate, 5...Lower tie plate, 9...Spent nuclear fuel assembly, 10... - Sealed container, 11... Lower adapter, 12... Intermediate support, 14... Cleaning water injection header, 15... Cooling coil, 16... Cooling operation motor, 27... Valve, 2
8... Drain pump, 29... Filter, 30... Treated water tank.

Claims (1)

【特許請求の範囲】[Claims] 1、水垢が付着した使用済核燃料集合体を使用済燃料貯
蔵プール内にクランプ式開閉蓋を備えた収納容器に密閉
することにより容器に接続されている排水管から容器内
のプール水を除去し、熱伝対により容器内の温度を監視
すると共に、容器に内蔵してある冷却コイルで容器内を
冷却し空冷を行ないながら水垢を乾燥し、次に容器に設
置したスパージヤー管から高圧空気を注入し水垢の乾燥
を迅速化させる共に、高圧空気と燃料棒の接触衝撃によ
り水垢を燃料棒から剥離させ、さらに空気を混入させた
洗浄水を燃料棒に注入し、気泡の消滅力を利用して再度
水垢を燃料棒から剥離させることを特徴として使用済核
燃料集合体の水垢除去方法。
1. Spent nuclear fuel assemblies with limescale attached are sealed in a storage container with a clamp-type opening/closing lid inside a spent fuel storage pool, and the pool water inside the container is removed from the drain pipe connected to the container. The temperature inside the container is monitored by a thermocouple, and the inside of the container is cooled by a cooling coil built into the container, and water scale is dried while cooling the container.Then, high-pressure air is injected from a spargeer pipe installed in the container. In addition to speeding up the drying of limescale, the contact impact between high-pressure air and fuel rods causes limescale to be peeled off from the fuel rods, and cleaning water mixed with air is injected into the fuel rods, making use of the vanishing power of air bubbles. A method for removing limescale from spent nuclear fuel assemblies, characterized by peeling the limescale from the fuel rods again.
JP1241185A 1985-01-28 1985-01-28 Method of removing deposit of spent nuclear fuel aggregate Pending JPS61172100A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP1241185A JPS61172100A (en) 1985-01-28 1985-01-28 Method of removing deposit of spent nuclear fuel aggregate

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP1241185A JPS61172100A (en) 1985-01-28 1985-01-28 Method of removing deposit of spent nuclear fuel aggregate

Publications (1)

Publication Number Publication Date
JPS61172100A true JPS61172100A (en) 1986-08-02

Family

ID=11804517

Family Applications (1)

Application Number Title Priority Date Filing Date
JP1241185A Pending JPS61172100A (en) 1985-01-28 1985-01-28 Method of removing deposit of spent nuclear fuel aggregate

Country Status (1)

Country Link
JP (1) JPS61172100A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2009075007A (en) * 2007-09-21 2009-04-09 Tokyo Electric Power Co Inc:The Foreign material recovery device

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2009075007A (en) * 2007-09-21 2009-04-09 Tokyo Electric Power Co Inc:The Foreign material recovery device
JP4758404B2 (en) * 2007-09-21 2011-08-31 東京電力株式会社 Foreign material recovery device

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