JPS62129795A - Method of washing spent fuel in fast breeder reactor - Google Patents
Method of washing spent fuel in fast breeder reactorInfo
- Publication number
- JPS62129795A JPS62129795A JP60269336A JP26933685A JPS62129795A JP S62129795 A JPS62129795 A JP S62129795A JP 60269336 A JP60269336 A JP 60269336A JP 26933685 A JP26933685 A JP 26933685A JP S62129795 A JPS62129795 A JP S62129795A
- Authority
- JP
- Japan
- Prior art keywords
- spent fuel
- cleaning
- sodium
- fuel
- gas
- 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
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)
- Cleaning By Liquid Or Steam (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】
〔産業上の利用分野〕
本発明は、高速増殖炉において使用済燃料に付着してい
るナトリウムを、腐食性の低い化合物に反応させて洗浄
する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 spent fuel in a fast breeder reactor by reacting the sodium adhering to the spent fuel with a less corrosive compound.
ナトリウムを冷却材として使用する高速増殖炉の焼判交
換に際しては、炉内から取り出した#用′fJ燃料はま
だ高い崩PJ熱レベルを有するために、一旦炉外の水中
貯蔵槽内に貯蔵し、放射能を充分減涙させたのちに再処
理などの工程に送られる。その際燃料被覆材などにはナ
トリウムが付着しているために、水中貯蔵槽に収納する
前処理としてナトリウムの洗浄除去がおこなわれている
。When replacing a fast breeder reactor that uses sodium as a coolant, #'fJ fuel taken out of the reactor still has a high PJ heat level, so it is temporarily stored in an underwater storage tank outside the reactor. After the radioactivity is sufficiently reduced, it is sent to processes such as reprocessing. At this time, since sodium adheres to fuel cladding materials, etc., sodium is washed and removed as a pretreatment before storing them in an underwater storage tank.
従来、使用済燃料の洗浄方法としては、まず使用済燃料
を洗浄槽に受は入れ、乾燥した不活性ガス例えばアルゴ
ンまたは窒素ガスを強制循環させて、400℃程度の高
温状態にある燃料を120°C位まで冷却する。ついで
不活性ガスと水蒸気とを混合した湿潤ガスを洗浄槽に供
給すると、燃料被覆材に付着しているす) リウムと水
蒸気とが反応して水酸化す) l)ラムを生成する。こ
の場合の反応式は
2 Na+2820=2 NaOH十Hzとなる。なお
この反応において、不測の過大な反応を防止するために
、供給初期では水蒸気濃度を低く保ち、反応状態を確認
しながら徐々に水蒸気濃度を高めるようにして運転がお
こなわれる。ついで純水により燃料被覆材に付着状態と
なっている高濃度の水酸化ナトリウムを洗い落とし、し
かるのち燃料を水中貯蔵槽に貯蔵し、再処理などの工程
に送られるようになっている。Conventionally, the spent fuel cleaning method involves first receiving the spent fuel in a cleaning tank, then forcedly circulating a dry inert gas such as argon or nitrogen gas to clean the fuel at a high temperature of about 400°C. Cool to around °C. Then, when a wet gas, which is a mixture of inert gas and water vapor, is supplied to the cleaning tank, the laminate adhering to the fuel cladding material reacts with the water vapor to oxidize it. The reaction formula in this case is 2 Na+2820=2 NaOH10Hz. In this reaction, in order to prevent an unexpectedly excessive reaction, operation is carried out by keeping the water vapor concentration low at the initial stage of supply, and gradually increasing the water vapor concentration while checking the reaction state. The highly concentrated sodium hydroxide adhering to the fuel cladding material is then washed away with pure water, and the fuel is then stored in an underwater storage tank and sent to processes such as reprocessing.
ところで、この湿潤ガスによる洗浄方法においては、燃
料被覆材の表面にはナトリウムと水蒸気の反応によって
高濃度の水酸化す) リッムが生成するが、この化合物
は腐食性が激しく燃料被覆材の構成材料であるステンレ
ス材に対しても一般に120°C以上の高温度条件下で
は応力腐食割れを招来する原因になるといわれている。By the way, in this cleaning method using wet gas, a high concentration of hydroxide (hydroxide) rim is generated on the surface of the fuel cladding material due to the reaction between sodium and water vapor, but this compound is highly corrosive and can be used as a component of the fuel cladding material. It is generally said that stress corrosion cracking may occur in stainless steel materials under high temperature conditions of 120°C or higher.
この被覆材の腐食は、放射性腐食生成物の発生量を増加
させ、また応力腐食割れは、燃料破損の誘因ともなり、
いずれも好ましくない。Corrosion of this coating material increases the amount of radioactive corrosion products generated, and stress corrosion cracking can also cause fuel failure.
Neither is preferable.
そのため、前従来使用済燃料を洗浄する場合には、萌述
のごとく湿潤ガス洗浄工程に入る前に被覆材温度を充分
下げる運伝を行なっていたが、使用済燃料の崩壊熱レベ
ルが高い場合にはこの冷却のために大量の冷却ガスを必
要とし、がつ冷却に要する時間も多くを必要とすること
になる。Therefore, when cleaning spent fuel in the past, the temperature of the cladding material was sufficiently lowered before entering the wet gas cleaning process as described above, but when the decay heat level of the spent fuel was high, A large amount of cooling gas is required for this cooling, and a large amount of time is required for cooling.
本発明は、上記の問題点に鑑みなされたもので、被覆材
に付着したナトリフムを、腐食性の低い化合物に反応生
成させる洗浄方法を提供する。The present invention was devised in view of the above-mentioned problems, and provides a cleaning method in which natrihum adhering to a coating material is reacted and generated into a less corrosive compound.
本発明による洗浄方法は、高速増殖炉において使用済燃
料を洗浄槽に収納し、該洗浄槽内において水蒸気および
炭酸ガスを混合した湿潤ガスにて使用済燃料を洗浄し、
該燃料に付着しているナトリウムと湿潤ガスどを反応さ
せてナトリウムの炭酸塩を生成させることを特徴とする
ものである。The cleaning method according to the present invention includes storing spent fuel in a cleaning tank in a fast breeder reactor, cleaning the spent fuel in the cleaning tank with a wet gas mixed with water vapor and carbon dioxide,
It is characterized in that the sodium adhering to the fuel is reacted with a wet gas to generate sodium carbonate.
この洗浄方法において、ナトリウム(N n)は湿潤ガ
ス中の水蒸気(H2O)と反応し、2 Na十HzO=
Na20+H2
となり、酸化ナトリウム (N a20 )を生成する
。In this cleaning method, sodium (N n) reacts with water vapor (H2O) in the humid gas, forming 2Na+HzO=
It becomes Na20+H2 and produces sodium oxide (Na20).
ついで、このNn20はただちに炭酸ガス(CO2)お
よびH2Oと反応して
N a 20 + CO2= N n 2 CO3N
a20 + H20= 2 N ao Hとなり、さら
にここで生成された水酸化ナトリウム (N (108
)の一部は引き続きCo2と反応して
N n OH+ CO2= N a HCOsとなり、
また上記の炭酸ナトリウム(N n 2 COコ)の一
部は加水分解して
N a 2 CO* + H20= N a HCO3
+N a OHとなる。このようにして炭酸ナトリウム
(Na2CO0)および炭酸水素ナトリウム(N a
HCO3)等のナトリウムの炭酸塩を生成する。Next, this Nn20 immediately reacts with carbon dioxide gas (CO2) and H2O to form Na 20 + CO2= N n 2 CO3N
a20 + H20 = 2 N ao H, and the sodium hydroxide (N (108
) continues to react with Co2 to form N n OH+ CO2= Na HCOs,
In addition, a part of the above sodium carbonate (N n 2 CO) is hydrolyzed to form Na 2 CO* + H20= Na HCO3
+N a OH. In this way, sodium carbonate (Na2CO0) and sodium bicarbonate (Na
Generates sodium carbonate such as HCO3).
本発明の洗浄方法の実施例を、第1図に示す洗浄装置の
ブロック接続図により説明する。An embodiment of the cleaning method of the present invention will be described with reference to a block connection diagram of a cleaning device shown in FIG.
図において1は洗浄槽であり、使用済燃料2は上部弁1
4を通して収納、取り出しされるようになっている。こ
の洗浄槽1の上部近くには不活性ガスの供給’!?3、
洗浄用の脱塩水供給管4および湿潤ガス供給管5が接続
され、また洗浄槽1内で発生した廃ガスを抽出するため
の廃ガス管6が接続されている。洗浄Jfe1には、冷
却器7、気水分離器8、不活性ガス用の循環ブロック、
および加熱器10が直列に接続されjこ冷却回路11が
設けられ、その入口側は洗浄槽1のド部付近に、また出
口側は前記湿潤ガス供給管5にそれぞれ接続されている
。12は洗浄水の循環ポンプであり、洗浄水を洗浄槽1
の下部から抜き出し上部に再循環させるように接続され
、またその途中には廃液タンク13に至る分岐管が接続
されている。In the figure, 1 is the cleaning tank, and the spent fuel 2 is the upper valve 1.
It is designed to be stored and taken out through 4. Inert gas is supplied near the top of this cleaning tank 1! ? 3,
A desalinated water supply pipe 4 and a wet gas supply pipe 5 for cleaning are connected, and a waste gas pipe 6 for extracting waste gas generated in the cleaning tank 1 is also connected. The cleaning Jfe1 includes a cooler 7, a steam/water separator 8, a circulation block for inert gas,
and a heater 10 are connected in series, and a cooling circuit 11 is provided, the inlet side of which is connected to the vicinity of the corner of the cleaning tank 1, and the outlet side connected to the humid gas supply pipe 5, respectively. 12 is a washing water circulation pump, which transports washing water to washing tank 1.
A branch pipe is connected to the waste liquid tank 13 in such a way that the liquid is extracted from the lower part and recirculated to the upper part.
以上のごとく構成されており、使用済燃料2を洗浄槽1
内に収納し、洗浄槽の上部弁14を閉じたのちまず循環
ブロワ9を起動し、冷却回路11および洗浄槽1などに
内包されている不活性ガスを循環させて使用済燃料の冷
却をおこなう。The structure is as described above, and the spent fuel 2 is transferred to the cleaning tank 1.
After closing the upper valve 14 of the cleaning tank, the circulation blower 9 is started to circulate the inert gas contained in the cooling circuit 11, the cleaning tank 1, etc. to cool the spent fuel. .
次いでこの不活性ガス中に湿潤ガス供給管5から供給さ
れた湿潤ガスを混合して洗浄槽1に供給する。湿潤ガス
は水蒸気と炭酸ガスとが混合されており、この湿潤ガス
が使用済燃料2に付着しているナトリウムと反応して炭
酸ナトリウムおよび炭酸水素ナトリウム等のナトリウム
の炭酸塩が生成する。なおここで不活性ガスおよび余剰
水蒸気、炭酸ガスは冷却回路11にもどり、冷却器7に
て冷却され、気水分離器8にて水分が除去されたのち、
循環ブロワ9を経て加熱器10にて供給温度調整がおこ
なわれ、再び湿潤ガスと混合して洗浄槽1に供給される
。Next, the wet gas supplied from the wet gas supply pipe 5 is mixed with this inert gas and the mixture is supplied to the cleaning tank 1. The wet gas is a mixture of water vapor and carbon dioxide gas, and this wet gas reacts with sodium adhering to the spent fuel 2 to generate sodium carbonates such as sodium carbonate and sodium hydrogen carbonate. Here, the inert gas, excess water vapor, and carbon dioxide gas return to the cooling circuit 11, are cooled in the cooler 7, and after moisture is removed in the steam separator 8,
The supply temperature is adjusted by the heater 10 through the circulation blower 9, and the gas is mixed with the wet gas again and supplied to the cleaning tank 1.
この反応中に洗浄槽1内に発生する水素ガスなどは供給
W3から供給される不活性ガスによって希釈され、適時
廃ガス管6がら抽出される。Hydrogen gas and the like generated in the cleaning tank 1 during this reaction are diluted by the inert gas supplied from the supply W3 and extracted from the waste gas pipe 6 at an appropriate time.
この反応が進行中は、たえず不活性ガス中の水素濃度を
監視し、この反応生成物である水素の発生が少なくなっ
た時点で反応が完了したとみなし、ついで脱塩水供給W
4から脱塩水を洗浄槽1に供給し、循環ポンプ12を運
転して洗浄槽1内に洗浄水を循環する。このようにして
生成した炭酸ナトリウム、炭酸水素ナトリウムおよび若
干量の水酸化ナトリウムを溶解し、これらの溶液は廃液
タンク13に貯留されて使用済燃料2の洗浄は完了する
。While this reaction is in progress, the hydrogen concentration in the inert gas is constantly monitored, and when the amount of hydrogen produced as a reaction product decreases, the reaction is considered to be complete, and then desalinated water is supplied to W.
4 supplies desalinated water to the cleaning tank 1, and the circulation pump 12 is operated to circulate the cleaning water into the cleaning tank 1. Sodium carbonate, sodium hydrogen carbonate, and a small amount of sodium hydroxide thus produced are dissolved, and these solutions are stored in the waste liquid tank 13, completing the cleaning of the spent fuel 2.
以上説明したごとく本発明は、使用済燃料に付着したナ
トリウムを水蒸気および炭酸ガスを混合した湿潤ガスに
て洗浄し、洗浄後には炭酸ナトリウムと炭酸水素ナトリ
ウムなどのナトリウムの炭酸塩が生成する。この生成物
は従来の水酸化ナトリウムと比較して腐食性は者しく低
いために、燃料被覆材の構成材料の腐食や応力腐食割れ
を防止することができ、また120“C以上の高温条件
においても洗浄処理が可能となるので、燃料洗浄装置に
おける燃料冷却のための設備を小さくすることが可能と
なり、設備費用が廉価となる。さらに被覆管材の冷却の
ために要する時間も短縮できるとともに、使用済燃料の
洗浄が迅速にでき、運転費の軽減に寄与する。従って本
発明による洗浄方法は崩壊熱レベルの高い使用済燃料を
洗浄する場合に特に効果が大きい。As explained above, the present invention cleans sodium adhering to spent fuel with a wet gas mixed with water vapor and carbon dioxide, and after cleaning, sodium carbonates such as sodium carbonate and sodium hydrogen carbonate are produced. This product is significantly less corrosive than conventional sodium hydroxide, so it can prevent corrosion and stress corrosion cracking of fuel cladding materials, and it can also be used in high-temperature conditions of 120"C or higher. Since cleaning treatment is also possible, it is possible to downsize the equipment for cooling the fuel in the fuel cleaning equipment, reducing equipment costs.Furthermore, the time required to cool the cladding material can be shortened, and the use The spent fuel can be washed quickly, contributing to a reduction in operating costs.Therefore, the cleaning method according to the present invention is particularly effective when cleaning spent fuel with a high level of decay heat.
f51図は本発明の洗浄方法を説明する洗浄装置のブロ
ック接続図である。
1 ・・・・・・洗浄槽、 2 ・・・・・・使用済燃
料、 3・・・・・・不活性ガスの供給管、 4 ・・
・・・・脱塩水供給管、 5・・・・・・湿潤ガス供給
管、 11 ・・・・・・冷却回路、 12 ・・・
・・・循環ポンプ、 13 ・・・・・・廃液タンクFigure f51 is a block connection diagram of a cleaning device for explaining the cleaning method of the present invention. 1...Cleaning tank, 2...Spent fuel, 3...Inert gas supply pipe, 4...
... Desalinated water supply pipe, 5 ... Moist gas supply pipe, 11 ... Cooling circuit, 12 ...
... Circulation pump, 13 ... Waste liquid tank
Claims (1)
気および炭酸ガスを混合した湿潤ガスにて使用済燃料を
洗浄し、該燃料に付着しているナトリウムと湿潤ガスと
を反応させてナトリウムの炭酸塩を生成させることを特
徴とする高速増殖炉における使用済燃料の洗浄方法。The spent fuel is stored in a cleaning tank, and in the cleaning tank, the spent fuel is cleaned with a wet gas that is a mixture of water vapor and carbon dioxide, and the sodium adhering to the fuel is reacted with the wet gas to remove sodium. A method for cleaning spent fuel in a fast breeder reactor, characterized by generating carbonate.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP60269336A JPH06100675B2 (en) | 1985-12-02 | 1985-12-02 | Cleaning method of spent fuel in fast breeder reactor |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP60269336A JPH06100675B2 (en) | 1985-12-02 | 1985-12-02 | Cleaning method of spent fuel in fast breeder reactor |
Publications (2)
Publication Number | Publication Date |
---|---|
JPS62129795A true JPS62129795A (en) | 1987-06-12 |
JPH06100675B2 JPH06100675B2 (en) | 1994-12-12 |
Family
ID=17470945
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP60269336A Expired - Fee Related JPH06100675B2 (en) | 1985-12-02 | 1985-12-02 | Cleaning method of spent fuel in fast breeder reactor |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPH06100675B2 (en) |
Cited By (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPH01232299A (en) * | 1988-03-11 | 1989-09-18 | Kawasaki Heavy Ind Ltd | Method and device for treating sticking sodium of fast bleeder reactor constituent element |
JP2008218267A (en) * | 2007-03-06 | 2008-09-18 | Matsushita Electric Ind Co Ltd | Heating element unit and heating device |
US20110098521A1 (en) * | 2008-06-25 | 2011-04-28 | Serge Sellier | Method of treating a structure containing sodium and a radioactive substance |
JP2017512976A (en) * | 2014-01-22 | 2017-05-25 | コミサリヤ・ア・レネルジ・アトミク・エ・オ・エネルジ・アルテルナテイブ | Method for treating sodium with saline solution and method for cleaning a nuclear reactor fuel assembly using said treatment method |
CN112687419A (en) * | 2020-12-18 | 2021-04-20 | 岭东核电有限公司 | Metal removing well for spent fuel and method for removing liquid metal on spent fuel |
Citations (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPS50148798A (en) * | 1974-05-23 | 1975-11-28 |
-
1985
- 1985-12-02 JP JP60269336A patent/JPH06100675B2/en not_active Expired - Fee Related
Patent Citations (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPS50148798A (en) * | 1974-05-23 | 1975-11-28 |
Cited By (7)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPH01232299A (en) * | 1988-03-11 | 1989-09-18 | Kawasaki Heavy Ind Ltd | Method and device for treating sticking sodium of fast bleeder reactor constituent element |
JP2008218267A (en) * | 2007-03-06 | 2008-09-18 | Matsushita Electric Ind Co Ltd | Heating element unit and heating device |
US20110098521A1 (en) * | 2008-06-25 | 2011-04-28 | Serge Sellier | Method of treating a structure containing sodium and a radioactive substance |
US8206677B2 (en) * | 2008-06-25 | 2012-06-26 | Commissariat A L'energie Atomique Et Aux Energies Alternatives | Method of treating a structure containing sodium and a radioactive substance |
JP2017512976A (en) * | 2014-01-22 | 2017-05-25 | コミサリヤ・ア・レネルジ・アトミク・エ・オ・エネルジ・アルテルナテイブ | Method for treating sodium with saline solution and method for cleaning a nuclear reactor fuel assembly using said treatment method |
CN112687419A (en) * | 2020-12-18 | 2021-04-20 | 岭东核电有限公司 | Metal removing well for spent fuel and method for removing liquid metal on spent fuel |
CN112687419B (en) * | 2020-12-18 | 2022-04-12 | 岭东核电有限公司 | Metal removing well for spent fuel and method for removing liquid metal on spent fuel |
Also Published As
Publication number | Publication date |
---|---|
JPH06100675B2 (en) | 1994-12-12 |
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Legal Events
Date | Code | Title | Description |
---|---|---|---|
LAPS | Cancellation because of no payment of annual fees |