JP3477357B2 - How to treat spent fuel - Google Patents
How to treat spent fuelInfo
- Publication number
- JP3477357B2 JP3477357B2 JP05550798A JP5550798A JP3477357B2 JP 3477357 B2 JP3477357 B2 JP 3477357B2 JP 05550798 A JP05550798 A JP 05550798A JP 5550798 A JP5550798 A JP 5550798A JP 3477357 B2 JP3477357 B2 JP 3477357B2
- Authority
- JP
- Japan
- Prior art keywords
- spent fuel
- nitrogen
- fuel
- minutes
- atmosphere
- 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 - Fee Related
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
-
- 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
- Y02W—CLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
- Y02W30/00—Technologies for solid waste management
- Y02W30/50—Reuse, recycling or recovery technologies
Landscapes
- Inorganic Compounds Of Heavy Metals (AREA)
Description
【発明の詳細な説明】Detailed Description of the Invention
【０００１】[0001]
【発明の属する技術分野】本発明は、原子炉で使用され
た燃料の処理方法に関する。FIELD OF THE INVENTION The present invention relates to a method for treating fuel used in a nuclear reactor.
【０００２】[0002]
【従来の技術】原子炉で使用された燃料（以下「使用済
燃料」という）にはウラン、プルトニウム等の有用な燃
料成分が含まれており、これらの燃料成分を原子炉燃料
として再利用するためには、使用済燃料の中から燃料成
分のみを回収する必要がある。2. Description of the Related Art Fuel used in a nuclear reactor (hereinafter referred to as "spent fuel") contains useful fuel components such as uranium and plutonium, and these fuel components are reused as nuclear reactor fuel. In order to do so, it is necessary to recover only the fuel component from the spent fuel.
【０００３】従来、使用済燃料の中から燃料成分を回収
する方法としては種々の方法が提案されており、使用済
燃料に含まれるウランをドライ雰囲気で回収する方法と
しては、使用済燃料を高温に加熱し、その状態で使用済
燃料中のウランに酸素を含む気体と水素を含む気体を交
互に接触させてウランを酸化物の形態で回収する方法が
知られている（Ｎｕｃｌｅａｒ Ｔｅｃｈｎｏｌｏｇｙ
誌 第４１巻 １３７〜１３８頁参照）。Conventionally, various methods have been proposed as a method for recovering a fuel component from spent fuel, and as a method for recovering uranium contained in the spent fuel in a dry atmosphere, the spent fuel has a high temperature. A method of recovering uranium in the form of an oxide by heating the uranium in the spent fuel in such a state that the gas containing oxygen and the gas containing hydrogen are alternately contacted with the uranium in the spent fuel in that state is known (Nuclear Technology).
See Vol. 41, pp. 137-138).
【０００４】[0004]
【発明が解決しようとする課題】ところで、原子炉で使
用される燃料はＵＯ2等のウラン酸化物を主成分とする
酸化物燃料が一般的であるが、これに代わる新燃料とし
てＵＮ等のウラン窒化物を主成分とする窒化物燃料の研
究開発が進められている。このような窒化物燃料は熱伝
導度、内部転換比、融点等に優れていることから、安全
性及び経済性の向上が期待されている。By the way, a fuel used in a nuclear reactor is generally an oxide fuel containing uranium oxide such as UO 2 as a main component. Research and development of nitride fuels containing uranium nitride as a main component are underway. Since such a nitride fuel is excellent in thermal conductivity, internal conversion ratio, melting point, etc., it is expected to improve safety and economy.
【０００５】しかしながら、上述した窒化物燃料の再処
理については現在まで確立されていないのが現状であ
り、酸化物燃料を対象とした従来方法をそのまま適用し
た場合には、使用済燃料中のウラン窒化物が空気による
加熱処理によってウラン酸化物となってしまい、ウラン
窒化物を主成分とする使用済燃料の中からウランを窒化
物の形態で回収できないという問題があった。また、ウ
ラン窒化物を主成分とする使用済燃料を窒素雰囲気の中
で高温に加熱すると、ウラン窒化物がＵＮからＵ2Ｎ3に
変化し、窒素分圧を下げればＵ2Ｎ3がＵＮに戻ることは
化学平衡論的に知られているが、使用済の窒化物燃料を
窒素と反応させたＵ2Ｎ3の粉体とするとともに脱被覆
し、ＵＮとして回収できる最適な処理方法（ＵＮとＵ2
Ｎ3との反応速度、粉体化等の条件を考慮した最適な加
熱温度と加熱時間の関係）が明らかになっていないとい
う課題があった。However, the above-mentioned reprocessing of the nitride fuel is not established until now, and when the conventional method for oxide fuel is applied as it is, uranium in the spent fuel is not used. There is a problem that the nitride becomes uranium oxide by the heat treatment with air, and uranium cannot be recovered in the form of nitride from the spent fuel containing uranium nitride as a main component. When the spent fuel containing uranium nitride as a main component is heated to a high temperature in a nitrogen atmosphere, the uranium nitride changes from UN to U 2 N 3 , and if the nitrogen partial pressure is lowered, U 2 N 3 becomes UN. Although it is known from chemical equilibrium theory that it returns to the above, the optimum treatment method that can recover spent nitride fuel as powder of U 2 N 3 reacted with nitrogen and decover it as UN ( UN and U 2
There is a problem in that the relationship between the optimum heating temperature and the heating time in consideration of the reaction rate with N 3 and the conditions such as pulverization) has not been clarified.
【０００６】本発明は上記の事情に鑑みてなされたもの
で、ウラン窒化物を主成分とする使用済燃料の中からウ
ランを窒化物の形態で回収することのできる使用済燃料
の処理方法を提供することを目的とするものである。The present invention has been made in view of the above circumstances, and provides a method for treating spent fuel capable of recovering uranium in the form of nitride from spent fuel containing uranium nitride as a main component. It is intended to be provided.
【０００７】[0007]
【課題を解決するための手段】かかる目的を達成するた
めに、請求項１の発明は、ウラン窒化物を主成分とする
使用済燃料を窒素分圧０．０１気圧以上の１５Ｎを含む
窒素雰囲気の中で６００℃〜８００℃の範囲で１０分〜
３０分加熱し、前記ウラン窒化物を雰囲気中の窒素と反
応させてウラン窒化物を脱被覆及び粉体化するととも
に、前記使用済燃料中の揮発性核反応生成物を分離除去
することを特徴とする。請求項２の発明は、ウラン窒化
物を主成分とする使用済燃料を窒素分圧０．０１気圧以
上の１５Ｎを含む窒素雰囲気の中で６００℃〜８００℃
の範囲で１０分〜３０分加熱した後、窒素を１気圧以下
の分圧にした雰囲気若しくは真空又は不活性ガス雰囲気
の中で前記使用済燃料を８００℃〜１４５０℃の範囲で
３０分以上加熱することを特徴とする。請求項３の発明
は、ウラン窒化物を主成分とする使用済燃料を窒素分圧
０．０１気圧以上の１５Ｎを含む窒素雰囲気の中で６０
０℃〜８００℃の範囲で１０分〜３０分加熱し、次いで
窒素を１気圧以下の分圧にした雰囲気若しくは真空又は
不活性ガス雰囲気の中で前記使用済燃料を８００℃〜１
４５０℃の範囲で３０分以上加熱した後、前記使用済燃
料に振動を付与して前記使用済燃料を粉体燃料と被覆材
とに分離することを特徴とする。請求項４の発明は、請
求項１又は請求項２記載の使用済燃料の処理方法におい
て、前記使用済燃料の加熱処理によって前記使用済燃料
中から揮発した核反応生成物を核反応生成物除去装置に
より除去することを特徴とする。In order to achieve the above object, the invention of claim 1 uses a spent fuel containing uranium nitride as a main component in a nitrogen atmosphere containing 15N with a nitrogen partial pressure of 0.01 atm or more. In the temperature range of 600 ° C to 800 ° C for 10 minutes
Heating for 30 minutes to react the uranium nitride with nitrogen in the atmosphere to decoat and powder the uranium nitride, and to separate and remove volatile nuclear reaction products in the spent fuel. And According to the invention of claim 2, the spent fuel whose main component is uranium nitride is 600 ° C. to 800 ° C. in a nitrogen atmosphere containing 15 N having a nitrogen partial pressure of 0.01 atm or more.
After heating in the range of 10 minutes to 30 minutes, the spent fuel is heated in the range of 800 ° C to 1450 ° C for 30 minutes or more in an atmosphere of nitrogen at a partial pressure of 1 atm or less or in a vacuum or an inert gas atmosphere. It is characterized by doing. According to the invention of claim 3, the spent fuel containing uranium nitride as a main component is used in a nitrogen atmosphere containing 15N with a nitrogen partial pressure of 0.01 atm or more.
The spent fuel is heated in the range of 0 ° C. to 800 ° C. for 10 minutes to 30 minutes , and then the spent fuel is heated to 800 ° C. to 1 degree in an atmosphere of nitrogen at a partial pressure of 1 atm or less, or in a vacuum or an inert gas atmosphere.
After heating in the range of 450 ° C. for 30 minutes or more, the spent fuel is vibrated to separate the spent fuel into a powder fuel and a coating material. According to the invention of claim 4, in the method for treating spent fuel according to claim 1 or 2, the nuclear reaction products which are volatilized from the spent fuel by the heat treatment of the spent fuel are removed. It is characterized by being removed by a device.
【０００８】[0008]
【発明の実施の形態】以下、本発明の実施形態を図面に
基づいて説明する。本発明に係る使用済燃料の処理方法
を説明する前に、ウラン窒化物（ＵＮ）を窒素雰囲気の
中で加熱処理した場合の実験結果を図３を参照して説明
する。図３はペレット状のウラン窒化物を窒素分圧１気
圧の窒素ガス雰囲気の中で約１５℃／ｍｉｎの速度で加
熱した場合におけるウラン窒化物の重量変化を示す線図
である。BEST MODE FOR CARRYING OUT THE INVENTION Embodiments of the present invention will be described below with reference to the drawings. Before explaining the method for treating spent fuel according to the present invention, the experimental results when uranium nitride (UN) is heat-treated in a nitrogen atmosphere will be described with reference to FIG. FIG. 3 is a diagram showing a change in weight of uranium nitride when pelletized uranium nitride is heated at a rate of about 15 ° C./min in a nitrogen gas atmosphere with a nitrogen partial pressure of 1 atm.
【０００９】図３に示す実験結果から明らかなように、
ウラン窒化物を窒素分圧１気圧の窒素ガス雰囲気の中で
加熱し、このときの加熱温度を６００〜８００℃、加熱
時間を１０〜３０分に設定すると、ウラン窒化物が雰囲
気中のＮ2と反応してＵＮからＵ2Ｎ3に変化し、さらに
ウラン窒化物が体積膨張すると共に粉体化することが確
認された。As is clear from the experimental results shown in FIG.
When the uranium nitride is heated in a nitrogen gas atmosphere with a nitrogen partial pressure of 1 atm, and the heating temperature at this time is set to 600 to 800 ° C. and the heating time is set to 10 to 30 minutes, the uranium nitride is converted into N 2 in the atmosphere. It was confirmed that the reaction changed from UN to U 2 N 3 and the uranium nitride expanded in volume and powdered.
【００１０】また、同図に示す実験結果から明らかなよ
うに、ＵＮからＵ2Ｎ3に変化したウラン窒化物を窒素分
圧１気圧の窒素ガス雰囲気の中で加熱し、このときの加
熱温度を８００〜１４５０℃、加熱時間を３０分以上に
設定すると、Ｕ2Ｎ3が粉体の状態でＵＮになることが確
認された。As is clear from the experimental results shown in the figure, the uranium nitride changed from UN to U 2 N 3 was heated in a nitrogen gas atmosphere with a nitrogen partial pressure of 1 atm, and the heating temperature at this time was changed. Was set to 800 to 1450 ° C. and the heating time was set to 30 minutes or longer, it was confirmed that U 2 N 3 became UN in a powder state.
【００１１】したがって、ウラン窒化物を主成分とする
使用済燃料からウランを回収する場合には、先ず、使用
済燃料を窒素分圧０．０１気圧以上の15Ｎを含む窒素ガ
ス雰囲気の中で加熱する。このとき、加熱温度を６００
〜８００℃、加熱時間を１０〜３０分に設定すると、図
１に示すように、使用済燃料に含まれるウラン窒化物が
窒素ガス雰囲気中のＮ2と反応してＵＮからＵ2Ｎ3に変
化する。また、これと同時に使用済燃料中のウラン窒化
物が体積膨張し、これにより被覆材からのウラン窒化物
の脱被覆と粉体化が促進され、ウラン窒化物の脱被覆と
粉体化が促進されることによりヘリウム、クリプトン、
キセノン、ヨウ素、カーボン等の揮発性核反応生成物が
使用済燃料中から揮発する。Therefore, when recovering uranium from a spent fuel containing uranium nitride as a main component, the spent fuel is first removed in a nitrogen gas atmosphere containing 15 N with a nitrogen partial pressure of 0.01 atm or more. To heat. At this time, the heating temperature is 600
When the heating time is set to ˜800 ° C. and the heating time is set to 10 to 30 minutes, as shown in FIG. 1, the uranium nitride contained in the spent fuel reacts with N 2 in the nitrogen gas atmosphere to change from UN to U 2 N 3 . Change. At the same time, the uranium nitride in the spent fuel expands in volume, which promotes the decoating and pulverization of the uranium nitride from the coating material, and promotes the decoating and pulverization of the uranium nitride. Helium, krypton,
Volatile nuclear reaction products such as xenon, iodine and carbon volatilize from the spent fuel.
【００１２】次に、使用済燃料を窒素分圧１気圧以下の
雰囲気若しくは真空又は不活性ガス雰囲気の中で３０分
以上加熱する。このとき、加熱温度を８００〜１４５０
℃とすると、図１に示すように、粉体化したウラン窒化
物がＵ2Ｎ3からＵＮに変化するとともに、セシウム、ル
テニウムなどのセミ揮発性核反応生成物が使用済燃料中
から揮発する。Next, the spent fuel is heated for 30 minutes or more in an atmosphere having a nitrogen partial pressure of 1 atm or less, a vacuum, or an inert gas atmosphere. At this time, the heating temperature is set to 800 to 1450.
At ℃, as shown in Fig. 1, powdered uranium nitride changes from U 2 N 3 to UN, and semi-volatile nuclear reaction products such as cesium and ruthenium volatilize from the spent fuel. .
【００１３】上述したように、本発明ではウラン窒化物
を主成分とする使用済燃料を窒素分圧０．０１気圧以上
の15Ｎを含む窒素ガス雰囲気の中で６００〜８００℃の
範囲で１０〜３０分程度加熱した後、窒素を１気圧以下
の分圧にした雰囲気若しくは真空又は不活性ガス雰囲気
の中で使用済燃料を８００℃〜１４５０℃の範囲で３０
分間以上加熱することにより、使用済燃料に含まれるウ
ランを窒化物の形態で回収することができる。As described above, according to the present invention, spent fuel containing uranium nitride as a main component is used at a temperature of 600 to 800 ° C. in a nitrogen gas atmosphere containing 15 N with a nitrogen partial pressure of 0.01 atm or more. After heating for about 30 minutes, spent fuel is heated at a temperature of 800 ° C to 1450 ° C for 30 minutes in an atmosphere of nitrogen at a partial pressure of 1 atm or less, a vacuum, or an inert gas atmosphere.
By heating for more than one minute, uranium contained in the spent fuel can be recovered in the form of nitride.
【００１４】なお、使用済燃料を窒素雰囲気で加熱処理
する場合に窒素分圧を０．０１気圧以上とした理由は、
ＵＮをＮ2と８００℃以下の温度で反応させるためには
窒素分圧が０．０００１気圧以上であれば理論上可能で
あるが、圧力維持制御や処理速度（反応速度）を考慮す
ると、窒素分圧を０．０１気圧以上としたほうが使用済
燃料に含まれるウランを回収し易いためである。また、
図３に示した実験結果によれば、使用済燃料を高温条件
下１気圧の窒素雰囲気でＵ2Ｎ3からＵＮに反応変化して
いる。The reason why the nitrogen partial pressure is 0.01 atm or more when the spent fuel is heat-treated in a nitrogen atmosphere is as follows.
In order to react UN with N 2 at a temperature of 800 ° C. or lower, it is theoretically possible if the nitrogen partial pressure is 0.0001 atm or more, but in consideration of pressure maintenance control and processing speed (reaction speed), nitrogen This is because it is easier to collect uranium contained in the spent fuel when the partial pressure is 0.01 atm or more. Also,
According to the experimental results shown in FIG. 3, the spent fuel undergoes a reaction change from U 2 N 3 to UN in a nitrogen atmosphere at 1 atm under high temperature conditions.
【化１】
の反応式でわかるように、Ｎ2すなわち窒素ガスの分圧
をより低くすることにより、反応式の左側から右側へ反
応が進む。従って、窒素を１気圧以下の分圧にした雰囲
気でもＵ2Ｎ3をＵＮに戻すことができ、同様の理由で真
空又は不活性ガス雰囲気でもＵ2Ｎ3をＵＮに戻すことが
できる。[Chemical 1] As can be seen from the reaction formula, the reaction proceeds from the left side to the right side of the reaction formula by lowering the partial pressure of N 2, that is, nitrogen gas. Therefore, nitrogen can also be returned to U 2 N 3 to UN in an atmosphere and the partial pressure of 1 atm or less, it can be returned to U 2 N 3 to UN in a vacuum or inert gas atmosphere for the same reason.
【００１５】次に、上述した本発明に係る使用済燃料の
処理方法を実施するための処理設備の一例を図２に示
す。同図において、１はウラン窒化物を主成分とする使
用済燃料、２は使用済燃料１を窒素ガス雰囲気の中で加
熱するための反応容器、３は反応容器２を加熱するため
のヒータ、４は反応容器２に15Ｎを含む窒素ガスを供給
するための窒素ガス供給ライン、５は反応容器２に不活
性ガスを供給するための不活性ガス供給ラインであり、
これらの窒素ガス供給ライン４及び不活性ガス供給ライ
ン５から反応容器２に供給されたガスは、使用済燃料１
を窒素ガス雰囲気または不活性ガス雰囲気の中で加熱処
理しているときには反応容器２に接続されたガス排出ラ
イン６から核反応生成物除去装置７に送られ、この核反
応生成物除去装置７でガス中の核反応生成物が除去され
る。そして、核反応生成物除去装置７で核反応生成物が
除去されたガスは浄化ガス回収ライン８、開閉弁９、窒
素ガス回収タンク１０および窒素ガス供給ライン４を経
て反応容器２に再供給され、上述した経路を循環するよ
うになっている。Next, FIG. 2 shows an example of processing equipment for carrying out the method for processing spent fuel according to the present invention described above. In the figure, 1 is a spent fuel containing uranium nitride as a main component, 2 is a reaction vessel for heating the spent fuel 1 in a nitrogen gas atmosphere, 3 is a heater for heating the reaction vessel 2, Reference numeral 4 is a nitrogen gas supply line for supplying a nitrogen gas containing 15 N to the reaction vessel 2, and 5 is an inert gas supply line for supplying an inert gas to the reaction vessel 2,
The gas supplied from the nitrogen gas supply line 4 and the inert gas supply line 5 to the reaction vessel 2 is the spent fuel 1
Is being heat-treated in a nitrogen gas atmosphere or an inert gas atmosphere, it is sent to a nuclear reaction product removing device 7 from a gas discharge line 6 connected to the reaction vessel 2, and this nuclear reaction product removing device 7 Nuclear reaction products in the gas are removed. Then, the gas from which the nuclear reaction products have been removed by the nuclear reaction product removing device 7 is re-supplied to the reaction vessel 2 through the purified gas recovery line 8, the on-off valve 9, the nitrogen gas recovery tank 10 and the nitrogen gas supply line 4. The above-mentioned route is circulated.
【００１６】また、１１は反応容器２内で加熱処理され
た使用済燃料１に振動を加えて同燃料１を粉体燃料１ａ
と被覆材１ｂとに分離する分離装置であり、この分離装
置１１のメッシュスクリーン１１ａで被覆材１ｂから分
離された粉体燃料１ａは分級装置１２で分級された後、
充填装置１３により被覆管内に充填され、原子炉１５の
燃料１４として用いられる。なお、浄化ガス回収ライン
８には核反応生成物除去装置７から排出される浄化ガス
をオフガスとして排出するためのガス排出ライン１７が
開閉弁１６を介して接続されている。Further, 11 is applied to the spent fuel 1 which has been heat-treated in the reaction vessel 2 by vibrating the spent fuel 1 to powder fuel 1a.
And the coating material 1b, the powder fuel 1a separated from the coating material 1b by the mesh screen 11a of the separating device 11 is classified by the classifying device 12,
The cladding is filled by the filling device 13 and used as the fuel 14 of the nuclear reactor 15. A gas discharge line 17 for discharging the purified gas discharged from the nuclear reaction product removing device 7 as an off gas is connected to the purified gas recovery line 8 via an opening / closing valve 16.
【００１７】上記のような構成の処理設備を用いれば、
ウラン窒化物を燃料成分とする使用済燃料１からウラン
を窒化物の形態で回収できるとともに、使用済燃料１に
含まれるヘリウム、クリプトン、キセノン、ヨウ素、カ
ーボン、セシウム、ルテニウムなどの核反応生成物をウ
ラン窒化物１から分離除去することができる。また、加
熱処理された使用済燃料１をメッシュスクリーン１１ａ
付きの分離装置１１に投入することにより、使用済燃料
１を粉体燃料１ａと被覆材１ｂとに分離することができ
る。If the processing equipment having the above-mentioned structure is used,
Uranium can be recovered in the form of nitride from spent fuel 1 containing uranium nitride as a fuel component, and nuclear reaction products such as helium, krypton, xenon, iodine, carbon, cesium and ruthenium contained in spent fuel 1 can be recovered. Can be separated and removed from the uranium nitride 1. In addition, the spent fuel 1 that has been heat-treated is treated with a mesh screen 11a.
The spent fuel 1 can be separated into the powdered fuel 1a and the coating material 1b by charging the spent fuel 1 into the attached separator 11.
【００１８】[0018]
【発明の効果】以上説明したように、本発明によれば、
ウラン窒化物を主成分とする使用済燃料からウランを窒
化物の形態で回収することができる。また、使用済燃料
に含まれるネプツニウム、プルトニウム及びアメリシウ
ムをウランと分離することなく、原子炉燃料としてその
まま再加工し、原子炉で再利用することができる。As described above, according to the present invention,
Uranium can be recovered in the form of nitrides from spent fuel containing uranium nitride as a main component. Further, neptunium, plutonium and americium contained in spent fuel can be directly reprocessed as a reactor fuel without being separated from uranium, and can be reused in a reactor.
【図１】本発明に係る使用済燃料の処理方法を説明する
ための図である。FIG. 1 is a diagram for explaining a method for treating spent fuel according to the present invention.
【図２】本発明に係る使用済燃料の処理方法を実施する
ための処理設備の一例を示す図である。FIG. 2 is a diagram showing an example of processing equipment for carrying out the method for processing spent fuel according to the present invention.
【図３】ペレット状のウラン窒化物を窒素分圧１気圧の
窒素ガス雰囲気の中で約１５℃／ｍｉｎの速度で加熱し
た場合におけるウラン窒化物の重量変化を示す線図であ
る。FIG. 3 is a diagram showing a weight change of uranium nitride in the case where pelletized uranium nitride is heated at a rate of about 15 ° C./min in a nitrogen gas atmosphere having a nitrogen partial pressure of 1 atm.
１ 使用済燃料 ２ 反応容器 ４ 窒素ガス供給ライン ５ 不活性ガス供給ライン ７ 核反応生成物除去装置 １１ 分離装置 １２ 分級装置 1 Spent fuel 2 reaction vessels 4 Nitrogen gas supply line 5 Inert gas supply line 7 Nuclear reaction product removal device 11 Separation device 12 classifier
フロントページの続き (72)発明者 飯塚 達哉 茨城県那珂郡東海村舟石川622番地12 ニュークリア・デベロップメント株式会 社内 (72)発明者 高阪 裕二 茨城県那珂郡東海村舟石川622番地12 ニュークリア・デベロップメント株式会 社内 (56)参考文献 特開 平９−43390（ＪＰ，Ａ) 特開 平６−94888（ＪＰ，Ａ) 波多野守、榎田洋一、黒田貞臣、中島 勲、河北孝司、伊藤邦博、田下昌紀，Ｇ 36 ＦＢＲ燃料リサイクルシステム概念 の検討（その１）−システム概念−，日 本原子力学会「1995秋の大会」予稿集, 日本，日本原子力学会，1995年 ９月20 日，Ｐ524 河北孝司、伊藤邦博，Ｇ37 ＦＢＲ核 燃料リサイクルシステム概念の検討（そ の２）−炉心・燃料−，日本原子力学会 「1995秋の大会」予稿集，日本，日本原 子力学会，1995年 ９月20日，Ｐ525 (58)調査した分野(Int.Cl.7，ＤＢ名) G21C 19/44 G21C 3/62 Front page continued (72) Inventor Tatsuya Iizuka 622-12, Funaishikawa, Tokai-mura, Naka-gun, Ibaraki Prefecture 12 Nuclear Development Stock Company In-house (72) Yuji Takasaka, 622, 12-kawa, Ishikawa, Tokai-mura, Ibaraki Prefecture・ Development Stock Association In-house (56) Reference JP-A-9-43390 (JP, A) JP-A-6-94888 (JP, A) Mamoru Hatano, Yoichi Enokida, Sadaomi Kuroda, Isao Nakajima, Koji Kawakita, Kunihiro Ito, Masanori Tashita, Examination of G 36 FBR Fuel Recycling System Concept (Part 1) -System Concept-, Proceedings of the Japan Atomic Energy Society "Autumn Meeting 1995", Japan, Atomic Energy Society of Japan, September 20, 1995, P524 Kawakita Koji, Ito Kunihiro, G37 FBR Nuclear Fuel Recycling System Concept (No. 2) -Core / Fuel-, Atomic Energy Society of Japan Proceedings of the 1995 Autumn Meeting, Japan, The Japan Society of Nuclear Power, September 20, 1995 Research on P525 (58) on the day Field (Int.Cl. 7, DB name) G21C 19/44 G21C 3/62
Claims (4)
を窒素分圧０．０１気圧以上の１５Ｎを含む窒素雰囲気
の中で６００℃〜８００℃の範囲で１０分〜３０分加熱
し、前記ウラン窒化物を雰囲気中の窒素と反応させてウ
ラン窒化物を脱被覆及び粉体化するとともに、前記使用
済燃料中の揮発性核反応生成物を分離除去することを特
徴とする使用済燃料の処理方法。1. A spent fuel containing uranium nitride as a main component is heated at 600 ° C. to 800 ° C. for 10 to 30 minutes in a nitrogen atmosphere containing 15 N having a nitrogen partial pressure of 0.01 atm or more, A spent fuel characterized by reacting the uranium nitride with nitrogen in an atmosphere to decoat and powder the uranium nitride, and to separate and remove volatile nuclear reaction products in the spent fuel. Processing method.
を窒素分圧０．０１気圧以上の１５Ｎを含む窒素雰囲気
の中で６００℃〜８００℃の範囲で１０分〜３０分加熱
した後、窒素を１気圧以下の分圧にした雰囲気若しくは
真空又は不活性ガス雰囲気の中で前記使用済燃料を８０
０℃〜１４５０℃の範囲で３０分以上加熱することを特
徴とする使用済燃料の処理方法。2. After heating a spent fuel containing uranium nitride as a main component in a nitrogen atmosphere containing 15N having a nitrogen partial pressure of 0.01 atm or more at 600 ° C. to 800 ° C. for 10 minutes to 30 minutes. 80% of the spent fuel in an atmosphere of nitrogen at a partial pressure of 1 atm or less, a vacuum, or an inert gas atmosphere.
A method for treating spent fuel, which comprises heating in the range of 0 ° C to 1450 ° C for 30 minutes or more.
を窒素分圧０．０１気圧以上の１５Ｎを含む窒素雰囲気
の中で６００℃〜８００℃の範囲で１０分〜３０分加熱
し、次いで窒素を１気圧以下の分圧にした雰囲気若しく
は真空又は不活性ガス雰囲気の中で前記使用済燃料を８
００℃〜１４５０℃の範囲で３０分以上加熱した後、前
記使用済燃料に振動を付与して前記使用済燃料を粉体燃
料と被覆材とに分離することを特徴とする使用済燃料の
処理方法。3. A spent fuel containing uranium nitride as a main component is heated at 600 ° C. to 800 ° C. for 10 minutes to 30 minutes in a nitrogen atmosphere containing 15 N having a nitrogen partial pressure of 0.01 atm or more, Then, the spent fuel is placed in an atmosphere of nitrogen at a partial pressure of 1 atm or less, a vacuum, or an inert gas atmosphere.
Treatment of spent fuel, which comprises heating the spent fuel in the range of 00 ° C to 1450 ° C for 30 minutes or more and then applying vibration to the spent fuel to separate the spent fuel into a powder fuel and a coating material. Method.
の処理方法において、前記使用済燃料の加熱処理によっ
て前記使用済燃料中から揮発した核反応生成物を核反応
生成物除去装置により除去することを特徴とする使用済
燃料の処理方法。4. The method for treating spent fuel according to claim 1 or 2, wherein a nuclear reaction product removing device volatilizes nuclear reaction products from the spent fuel by heat treatment of the spent fuel. A method for treating spent fuel, characterized by removing the spent fuel.
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|---|---|---|---|
| JP05550798A JP3477357B2 (en) | 1998-03-06 | 1998-03-06 | How to treat spent fuel |
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| JP3477357B2 true JP3477357B2 (en) | 2003-12-10 |
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| US20050286676A1 (en) * | 2004-06-29 | 2005-12-29 | Lahoda Edward J | Use of isotopically enriched nitride in actinide fuel in nuclear reactors |
| KR100759941B1 (en) | 2006-06-28 | 2007-09-18 | 한국원자력연구원 | Separation method and its apparatus of inner particle from coating layer particle of breached triso fuel |
| KR100969644B1 (en) * | 2008-04-15 | 2010-07-14 | 한국원자력연구원 | A fabrication method of nuclear fuel pellet by using high burnup spent nuclear fuel |
| KR100969640B1 (en) * | 2008-04-15 | 2010-07-14 | 한국원자력연구원 | A fabrication method of nuclear fuel pellet by using high burnup spent nuclear fuel containing metal impurities |
| US10378084B2 (en) | 2012-08-31 | 2019-08-13 | Hosei University | Method for concentrating metal compound by reduction and oxidation |
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1998
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Non-Patent Citations (2)
| Title |
|---|
| 河北孝司、伊藤邦博，Ｇ３７ ＦＢＲ核燃料リサイクルシステム概念の検討（その２）−炉心・燃料−，日本原子力学会「１９９５秋の大会」予稿集，日本，日本原子力学会，１９９５年 ９月２０日，Ｐ５２５ |
| 波多野守、榎田洋一、黒田貞臣、中島勲、河北孝司、伊藤邦博、田下昌紀，Ｇ３６ ＦＢＲ燃料リサイクルシステム概念の検討（その１）−システム概念−，日本原子力学会「１９９５秋の大会」予稿集，日本，日本原子力学会，１９９５年 ９月２０日，Ｐ５２４ |
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