JPH01189600A - High temperature gas blow washing of spent fuel - Google Patents

High temperature gas blow washing of spent fuel

Info

Publication number
JPH01189600A
JPH01189600A JP63013317A JP1331788A JPH01189600A JP H01189600 A JPH01189600 A JP H01189600A JP 63013317 A JP63013317 A JP 63013317A JP 1331788 A JP1331788 A JP 1331788A JP H01189600 A JPH01189600 A JP H01189600A
Authority
JP
Japan
Prior art keywords
sodium
spent fuel
argon gas
gas
fuel
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
JP63013317A
Other languages
Japanese (ja)
Inventor
Yasuaki Gunji
泰明 郡司
Katsuhiko Shimizu
克彦 清水
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.)
Power Reactor and Nuclear Fuel Development Corp
Original Assignee
Power Reactor and Nuclear Fuel Development Corp
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 Power Reactor and Nuclear Fuel Development Corp filed Critical Power Reactor and Nuclear Fuel Development Corp
Priority to JP63013317A priority Critical patent/JPH01189600A/en
Publication of JPH01189600A publication Critical patent/JPH01189600A/en
Pending legal-status Critical Current

Links

Classifications

    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Cleaning By Liquid Or Steam (AREA)

Abstract

PURPOSE:To intend a cost reduction of a facility operation, by blowing a heated and pressurized inert gas to a spent fuel, to blow out and to remove a stuck sodium from the fuel. CONSTITUTION:After feeding an argon gas into a system from an argon gas feeding system 30, a spent fuel 10 is placed in a washing basin 12 and a system is isolated to form a closed loop. Thereafter, the argon gas in the system is pressurized by a blower 26 and is heated to 200 deg.C by an economizer 20 and a heater 28 and then the gas is fed to the washing basin 12. The gas is blown to the spent fuel 10 to blow out a sodium stuck on a surface or other places of the fuel. Most of the blown-out sodium drips down and some part of the sodium vaporizes. The effluent argon gas containing sodium vapor, from the washing basin 12 is cooled down by the economizer 20 and the sodium vapor is removed by a vapor trap 22 and then the argon gas is repressurized by the blower 26 after going through a cooler 24. While on the other hand, the sodium 38 dripped and deposited at a lower part of the basin 12 is taken out to a primary sodium drain tank 34 and also the sodium trapped with the trap 22 is taken out to the tank 34.

Description

【発明の詳細な説明】 [産業上の利用分野] 本発明は、高速増殖炉のようにナトリウムを冷却材とす
る原子炉で使用した燃料を洗浄する方法に関し、更に詳
しくは、昇圧した高温の不活性ガスを使用済燃料にブロ
ーし、付着ナトリウムを吹き飛ばして除去する使用済燃
料の高温ガスブロー洗浄方法に関するものである。
[Detailed Description of the Invention] [Industrial Application Field] The present invention relates to a method for cleaning fuel used in a nuclear reactor that uses sodium as a coolant, such as a fast breeder reactor. The present invention relates to a high-temperature gas blow cleaning method for spent fuel, in which inert gas is blown onto the spent fuel to blow off and remove adhering sodium.

[従来の技術] 高速増殖炉のようにナトリウムを冷却材とする原子炉に
おいて、使用済燃料を再処理するまでの間、水プール等
で保管する場合には、先ず使用済燃料に付着している冷
却材ナトリウムを洗浄除去する必要がある。従来このよ
うな使用済燃料の洗浄は、脱塩水を使用し、それを循環
させて洗浄する所謂「脱塩水循環方式」が主流である。
[Prior art] In a nuclear reactor that uses sodium as a coolant, such as a fast breeder reactor, when stored spent fuel in a water pool or the like until it is reprocessed, first the spent fuel is It is necessary to wash away the coolant sodium present. Conventionally, the mainstream method for cleaning such spent fuel has been the so-called "desalinated water circulation method," which uses demineralized water and circulates it for cleaning.

また一部海外では真空蒸発洗浄方式を採用しているとこ
ろもある。
In some countries overseas, a vacuum evaporation cleaning method is also used.

[発明が解決しようとする課H] 従来の脱塩水循環方式では、燃料の構造上の特性(例え
ば燃料要素の間隔を均一に保持するランピング・ワイヤ
等による圧損)が洗浄性に大きな影響を及ぼし、所定の
レベルまで洗浄するにはそれ相当(約1〜2rJ)の脱
塩水が必要となる。ところがこれらは全て放射性廃棄物
(廃液)となるため、それらを処理する設備が必要とな
る。また放射性腐蝕生成物により系統の線量が増大し廃
液処理作業やメンテナンス時の被曝源となる問題があっ
た。またナトリウムは水と激しく反応するため、設備上
取合という観点からナトリウム系と水系の隔離及び取合
を考慮する必要がある。このため回転・上下動機構等、
システムが複雑化しメンテナンス頻度も増大する。
[Problem H to be solved by the invention] In the conventional demineralized water circulation system, the structural characteristics of the fuel (for example, pressure loss due to ramping wires that maintain uniform spacing between fuel elements) have a large effect on cleaning performance. , a corresponding amount (approximately 1 to 2 rJ) of demineralized water is required to clean to a predetermined level. However, all of this becomes radioactive waste (waste liquid), so equipment to process it is required. There was also the problem that radioactive corrosion products increased the radiation dose in the system and became a source of radiation exposure during wastewater treatment and maintenance. In addition, since sodium reacts violently with water, it is necessary to consider the separation and combination of sodium and water systems from the perspective of equipment integration. For this reason, rotation/vertical movement mechanisms, etc.
The system becomes more complex and the frequency of maintenance increases.

更に真空蒸発洗浄方式では、高温かつ高真空が必要不可
欠であるから必然的に設備が大型化する問題があるほか
、使用済燃料の残留熱の冷却に限界がある。
Furthermore, the vacuum evaporation cleaning method requires high temperature and high vacuum, which inevitably increases the size of the equipment, and there is a limit to the ability to cool the residual heat of the spent fuel.

本発明の目的は、上記のような従来技術が有する課題を
解決し、放射性廃棄物が発生せず設備の簡素化を図るこ
とができ、メンテナンス頻度の合理化による建設・運転
コストの低減化、及び被曝の低減化を図ることができる
ような高温ガスブローによる使用済燃料の洗浄方法を提
供することにある。
The purpose of the present invention is to solve the problems of the conventional technology as described above, to simplify equipment without generating radioactive waste, to reduce construction and operating costs by rationalizing maintenance frequency, and to It is an object of the present invention to provide a method for cleaning spent fuel using high-temperature gas blowing, which can reduce exposure to radiation.

[課題を解決するための手段] 上記目的を達成することができる本発明は、ナトリウム
を冷却材とする原子炉の使用済燃料に加熱廊圧した不活
性ガスをプローし、付着しているナトリウムを吹き飛ば
し除去するように構成した使用済燃料の高温ガスブロー
洗浄方法である。
[Means for Solving the Problems] The present invention, which can achieve the above object, sprays heated inert gas into the spent fuel of a nuclear reactor using sodium as a coolant, and removes the adhering sodium. This is a high-temperature gas blow cleaning method for spent fuel configured to blow away and remove.

ここで高温の不活性ガスとしては、例えば200℃程度
に加熱されたアルゴンガス等を使用する。
Here, as the high temperature inert gas, for example, argon gas or the like heated to about 200° C. is used.

またガスブローによって吹き飛ばされ滴下したナトリウ
ムを集めて原子炉の1次系に戻すような構成が望ましい
Further, it is desirable to have a configuration in which sodium dropped and blown off by gas blow is collected and returned to the primary system of the reactor.

[作用] 高温の不活性ガスを使用済燃料にプローすることによっ
て該使用済燃料に付着しているナトリウムは吹き飛ばさ
れ、また一部は蒸発する。
[Operation] By blowing high-temperature inert gas onto the spent fuel, the sodium adhering to the spent fuel is blown off and some of it evaporates.

このようにして付着ナトリウムが除去され使用済燃料の
洗浄が行われる。
In this way, the attached sodium is removed and the spent fuel is cleaned.

この洗浄は不活性雰囲気中での不活性ガスプローによる
ものであるから、滴下したナトリウムをそのまま1次系
に戻すことができる。これによって放射性廃棄物の発生
がなくなり、当然のことながら処理する必要もな(なる
Since this cleaning is performed using an inert gas blower in an inert atmosphere, the dropped sodium can be directly returned to the primary system. This eliminates the generation of radioactive waste, and naturally there is no need to dispose of it.

[実施例1 第1図は本発明に係る使用済燃料の高温ガスプロー洗浄
方法を実施するのに好適な設備構成の一例を示している
。この洗浄設備は、使用済燃料10を収納する洗浄槽1
2と、高温ガスを循環するためのガス系設備、及び各種
電気計装品等から構成される。
[Example 1] FIG. 1 shows an example of an equipment configuration suitable for carrying out the method for cleaning spent fuel with a high-temperature gas blower according to the present invention. This cleaning equipment includes a cleaning tank 1 that stores spent fuel 10.
2, gas system equipment for circulating high-temperature gas, and various electrical instruments.

洗浄槽12は使用済燃料10を縦方向に挿入可能な竪型
構造になっており、内部に設けた保持部材14等によっ
て使用済燃料10を保持でき、上端開口はドアパルプ1
6等で密封可能な構造である。
The cleaning tank 12 has a vertical structure into which the spent fuel 10 can be inserted vertically, and the spent fuel 10 can be held by a holding member 14 provided inside, and the upper end opening is a door pulp 1.
It has a structure that can be sealed at 6th grade.

高温ガスを循環するためのガス系設備は、エコノマイザ
20、ベーパトラップ22、冷却器24、プロワ26、
加熱器28、その他配管や弁等から構成され、洗浄槽1
2を通る閉ループを構成できる。また、このガス系設備
にはアルゴンガス供給系30が接続され、そこからアル
ゴンガスを導入できるようになっている。各種電気計装
品としては、閉ループの各所に設けられた圧力計や温度
計、流量計等である。
Gas system equipment for circulating high-temperature gas includes an economizer 20, a vapor trap 22, a cooler 24, a blower 26,
Consists of a heater 28, other piping, valves, etc., and a cleaning tank 1
A closed loop passing through 2 can be constructed. Further, an argon gas supply system 30 is connected to this gas system equipment, from which argon gas can be introduced. Various electrical instruments include pressure gauges, thermometers, flow meters, etc. installed at various locations in the closed loop.

この実施例ではベーパトラップ22、冷却器24、ブロ
ア26がそれぞれ2台ずつ並設されている。更に洗浄槽
12の上部および前記ガス系設備の一部からは弁を介し
て気体廃棄物処理系32へ配管で結ばれており、また洗
浄槽12の底部と両ベーパトラップ22からはそれぞれ
弁を備えた配管により1次ナトリウムドレーンタンク3
4へ接続されている。そして冷却器24には冷却水系3
6の配管が接続されている。
In this embodiment, two vapor traps 22, two coolers 24, and two blowers 26 are arranged in parallel. Further, the upper part of the cleaning tank 12 and a part of the gas system equipment are connected to the gaseous waste treatment system 32 via valves, and the bottom of the cleaning tank 12 and both vapor traps 22 are connected with valves, respectively. The primary sodium drain tank 3 is equipped with piping.
Connected to 4. The cooler 24 has a cooling water system 3.
6 pipes are connected.

このような設備による高温ガスプロー洗浄は次のように
行う、先ずアルゴンガス供給系30から系統内へアルゴ
ンガスを供給した後、洗浄槽12内に使用済燃料10を
収納し、系統を隔離して閉ループを構成する。系統内の
アルゴンガスをプロワ26で昇圧し、エコノマイザ20
及び加熱器28で約200″C程度まで加熱した後、洗
浄槽12へ供給する。そして使用済燃料1oにブローし
、その表面や内部、間隙部等に付着したナトリウムを吹
き飛ばす、吹き飛ばされたナトリウムの大部分は滴下し
、また一部分は蒸発する。洗浄槽12から流出したナト
リウムベーパを含んだアルゴンガスはエコノマイザ20
で冷却され、ベーパトラップ22においてナトリウムベ
ーパが除去される。そして冷却器24で更に降温された
後に、ブロワ26に至り再び昇圧される。
High-temperature gas blow cleaning using such equipment is carried out as follows. First, argon gas is supplied into the system from the argon gas supply system 30, and then the spent fuel 10 is stored in the cleaning tank 12, and the system is isolated. Configure a closed loop. The pressure of argon gas in the system is increased by the blower 26, and the economizer 20
The blown sodium is then heated to about 200"C in the heater 28 and then supplied to the cleaning tank 12.Then, the blown sodium is blown onto the spent fuel 1o to blow off the sodium attached to its surface, inside, gaps, etc. Most of the sodium vapor drips, and a portion evaporates.The argon gas containing sodium vapor that flows out from the cleaning tank 12 is
Sodium vapor is removed in a vapor trap 22. After the temperature is further lowered by the cooler 24, the temperature reaches the blower 26 and the pressure is increased again.

このような高温の不活性ガスの循環を数分もしくは数十
分行い、使用済燃料10に付着しているナトリウムを除
去する。ガスブローによって使用済燃料10から吹き飛
ばされたナトリウムは洗浄槽12の下部に滴下堆積する
。この滴下ナトリウム3日は洗浄終了後に1次ナトリウ
ムドレーンタンク34へ排出される。またベーパトラッ
プ22にトラップされたナトリウムも同様に1次ナトリ
ウムドレーンタンク34へと排出される。洗浄終了後、
系統内のアルゴンガスは気体廃棄物処理系34へ送られ
、そこで処理されることになる。
The circulation of such high-temperature inert gas is performed for several minutes or tens of minutes to remove the sodium adhering to the spent fuel 10. Sodium blown off from the spent fuel 10 by the gas blow drips and accumulates in the lower part of the cleaning tank 12. This dripping sodium for three days is discharged to the primary sodium drain tank 34 after washing is completed. Further, the sodium trapped in the vapor trap 22 is similarly discharged to the primary sodium drain tank 34. After cleaning,
The argon gas in the system will be sent to the gaseous waste treatment system 34 where it will be treated.

上記の実施例では装置の信鯨性並びにメンテナンス等の
観点からベーパトラップや冷却器、ブロワ等を2台並列
に接続しているが、原理的にはそれらは各1台であワて
もよい。
In the above embodiment, two vapor traps, coolers, blowers, etc. are connected in parallel from the viewpoint of reliability and maintenance of the device, but in principle, each of them may be used alone. .

[発明の効果] 本発明は上記のように不活性雰囲気中で高温の不活性ガ
スを使用済燃料にブローし、付着しているナトリウムを
吹き飛ばし除去するように構成した使用済燃料の高温ガ
スブロー洗浄方法であるから、吹き飛ばされたナトリウ
ムをそのまま1次系に戻すことができ、そのため放射性
廃棄物が発生せず、勿論それを処理する必要もなくなる
。その結果、設備の単純化を図ることができるため設備
の建設コストを大幅に低減できると共に、メンテナンス
頻度等を削減でき、設備の運転コスト並びに被曝を大幅
に低減化できる効果がある。
[Effects of the Invention] As described above, the present invention provides high-temperature gas blow cleaning for spent fuel, which is configured to blow away adhering sodium by blowing a high-temperature inert gas onto the spent fuel in an inert atmosphere. Because this method allows the blown sodium to be returned to the primary system as it is, no radioactive waste is generated and of course there is no need to dispose of it. As a result, since the equipment can be simplified, the construction cost of the equipment can be significantly reduced, and the frequency of maintenance can be reduced, which has the effect of significantly reducing the operating cost and radiation exposure of the equipment.

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

第1図は本発明方法を実施するのに好適な高温ガスブロ
ー洗浄設備の一例を示す説明図である。 10・・・使用済燃料、12・・・洗浄槽、22・・・
ベーパトラップ、24・・・冷却器、26・・・ブロワ
、28・・・加熱器、30・・・アルゴンガス供給系、
34・・・1次ナトリウムドレーンタンク。
FIG. 1 is an explanatory diagram showing an example of high temperature gas blow cleaning equipment suitable for carrying out the method of the present invention. 10...Spent fuel, 12...Cleaning tank, 22...
Vapor trap, 24... Cooler, 26... Blower, 28... Heater, 30... Argon gas supply system,
34...Primary sodium drain tank.

Claims (1)

【特許請求の範囲】 1、ナトリウムを冷却材とする原子炉の使用済燃料を洗
浄する方法において、加熱昇圧した不活性ガスを使用済
燃料にブローし、付着しているナトリウムを吹き飛ばし
除去することを特徴とする使用済燃料の高温ガスブロー
洗浄方法。 2、吹き飛ばされ滴下したナトリウムを原子炉の1次系
に戻す請求項1記載の使用済燃料の高温ガスブロー洗浄
方法。
[Claims] 1. A method for cleaning spent fuel in a nuclear reactor using sodium as a coolant, in which heated and pressurized inert gas is blown into the spent fuel to blow off and remove adhering sodium. A high-temperature gas blow cleaning method for spent fuel, characterized by: 2. The method for high-temperature gas blow cleaning of spent fuel according to claim 1, wherein the blown and dripped sodium is returned to the primary system of the nuclear reactor.
JP63013317A 1988-01-23 1988-01-23 High temperature gas blow washing of spent fuel Pending JPH01189600A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP63013317A JPH01189600A (en) 1988-01-23 1988-01-23 High temperature gas blow washing of spent fuel

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP63013317A JPH01189600A (en) 1988-01-23 1988-01-23 High temperature gas blow washing of spent fuel

Publications (1)

Publication Number Publication Date
JPH01189600A true JPH01189600A (en) 1989-07-28

Family

ID=11829795

Family Applications (1)

Application Number Title Priority Date Filing Date
JP63013317A Pending JPH01189600A (en) 1988-01-23 1988-01-23 High temperature gas blow washing of spent fuel

Country Status (1)

Country Link
JP (1) JPH01189600A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US6718002B2 (en) * 1997-05-21 2004-04-06 Westinghouse Atom Ab Method and device for removing radioactive deposits
CN102671878A (en) * 2011-03-10 2012-09-19 中国原子能科学研究院 Fast reactor spent component cleaning device

Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5546122A (en) * 1978-09-29 1980-03-31 Tokyo Shibaura Electric Co Cleaning device for sodium equipment
JPS5786800A (en) * 1980-11-20 1982-05-29 Tokyo Shibaura Electric Co Cleaning device for decontaminated sodium instruments
JPS6367597A (en) * 1986-09-10 1988-03-26 財団法人 電力中央研究所 Method of washing spent fuel aggregate
JPS63250598A (en) * 1987-04-07 1988-10-18 川崎重工業株式会社 Method of removing sodium of fast-reactor core component

Patent Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5546122A (en) * 1978-09-29 1980-03-31 Tokyo Shibaura Electric Co Cleaning device for sodium equipment
JPS5786800A (en) * 1980-11-20 1982-05-29 Tokyo Shibaura Electric Co Cleaning device for decontaminated sodium instruments
JPS6367597A (en) * 1986-09-10 1988-03-26 財団法人 電力中央研究所 Method of washing spent fuel aggregate
JPS63250598A (en) * 1987-04-07 1988-10-18 川崎重工業株式会社 Method of removing sodium of fast-reactor core component

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US6718002B2 (en) * 1997-05-21 2004-04-06 Westinghouse Atom Ab Method and device for removing radioactive deposits
CN102671878A (en) * 2011-03-10 2012-09-19 中国原子能科学研究院 Fast reactor spent component cleaning device

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