JPH0375595A - Stripping method of spent metallic fuel - Google Patents
Stripping method of spent metallic fuelInfo
- Publication number
- JPH0375595A JPH0375595A JP1210766A JP21076689A JPH0375595A JP H0375595 A JPH0375595 A JP H0375595A JP 1210766 A JP1210766 A JP 1210766A JP 21076689 A JP21076689 A JP 21076689A JP H0375595 A JPH0375595 A JP H0375595A
- Authority
- JP
- Japan
- Prior art keywords
- fuel
- hydrogen
- tank
- spent
- dehydrogenation
- 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
Links
- 239000000446 fuel Substances 0.000 title claims abstract description 35
- 238000000034 method Methods 0.000 title claims abstract description 14
- 229910052751 metal Inorganic materials 0.000 claims abstract description 32
- 239000002184 metal Substances 0.000 claims abstract description 32
- 238000006356 dehydrogenation reaction Methods 0.000 claims abstract description 13
- 238000005984 hydrogenation reaction Methods 0.000 claims abstract description 13
- 238000012958 reprocessing Methods 0.000 claims description 5
- 238000010309 melting process Methods 0.000 claims description 4
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 abstract description 27
- 239000001257 hydrogen Substances 0.000 abstract description 27
- 229910052739 hydrogen Inorganic materials 0.000 abstract description 27
- 239000002915 spent fuel radioactive waste Substances 0.000 abstract description 11
- 238000004090 dissolution Methods 0.000 abstract description 6
- RTAQQCXQSZGOHL-UHFFFAOYSA-N Titanium Chemical compound [Ti] RTAQQCXQSZGOHL-UHFFFAOYSA-N 0.000 abstract description 2
- 229910052719 titanium Inorganic materials 0.000 abstract description 2
- 239000010936 titanium Substances 0.000 abstract description 2
- 239000000843 powder Substances 0.000 abstract 1
- 238000001179 sorption measurement Methods 0.000 abstract 1
- 238000005253 cladding Methods 0.000 description 6
- 239000000463 material Substances 0.000 description 6
- 238000002844 melting Methods 0.000 description 5
- 230000008018 melting Effects 0.000 description 5
- 229910045601 alloy Inorganic materials 0.000 description 4
- 239000000956 alloy Substances 0.000 description 4
- 229910052770 Uranium Inorganic materials 0.000 description 3
- 239000011248 coating agent Substances 0.000 description 3
- 238000000576 coating method Methods 0.000 description 3
- 230000008961 swelling Effects 0.000 description 3
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 3
- 229910001093 Zr alloy Inorganic materials 0.000 description 2
- 150000002431 hydrogen Chemical class 0.000 description 2
- NBWXXYPQEPQUSB-UHFFFAOYSA-N uranium zirconium Chemical compound [Zr].[Zr].[U] NBWXXYPQEPQUSB-UHFFFAOYSA-N 0.000 description 2
- 229910000711 U alloy Inorganic materials 0.000 description 1
- 229910052793 cadmium Inorganic materials 0.000 description 1
- BDOSMKKIYDKNTQ-UHFFFAOYSA-N cadmium atom Chemical compound [Cd] BDOSMKKIYDKNTQ-UHFFFAOYSA-N 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000004880 explosion Methods 0.000 description 1
- 239000011261 inert gas Substances 0.000 description 1
- 239000011810 insulating material Substances 0.000 description 1
- 238000005259 measurement Methods 0.000 description 1
- 238000010422 painting Methods 0.000 description 1
- 238000012545 processing Methods 0.000 description 1
- 238000007670 refining Methods 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
- Manufacture Of Metal Powder And Suspensions Thereof (AREA)
Abstract
Description
【発明の詳細な説明】
（産業上の利用分野）
本発明は、高速増殖炉などから発生する使用済金属燃料
の再処理において使用済金属燃料の溶解処理の前処理と
して実施される脱被覆法に関する。Detailed Description of the Invention (Field of Industrial Application) The present invention relates to a decoating method that is carried out as a pretreatment for melting spent metal fuel in the reprocessing of spent metal fuel generated from fast breeder reactors, etc. Regarding.
（従来の技術）
従来、使用済金属燃料の再処理においては、金属燃料の
溶解に先立って被覆材を取り去る脱被覆が行なわれてい
る。この脱被覆は、燃焼度が低くスエリングが小さな使
用済金属燃料例えば低燃焼度のＥＢＲ−Ｉｔブランケッ
ト燃料（ウラン−ジルコニウム合金）については回転刃
を使って皮を剥くように被覆材を機械的に剥ぎとる方法
が行なわれているが、燃焼度の高い使用済金属燃料では
スエリングにより燃料が被覆管に固着しており上述の剥
ぎとり方法の適用は困難である。そこで、このように燃
焼度が高くスエリングにより被覆管と燃料が固着してい
るような使用済燃料に対しては適当な大きさに切断ある
いは機械的に剪断するのみであった。(Prior Art) Conventionally, in the reprocessing of spent metal fuel, decoating is performed to remove the coating material prior to melting the metal fuel. This decoating is done mechanically by peeling off the coating material using a rotating blade for spent metal fuels with low burnup and small swelling, such as low burnup EBR-It blanket fuel (uranium-zirconium alloy). A stripping method has been used, but with spent metal fuel having a high burnup, the fuel adheres to the cladding due to swelling, making it difficult to apply the stripping method described above. Therefore, spent fuel with a high burnup and in which the cladding tube and fuel are stuck together due to swelling is simply cut into an appropriate size or mechanically sheared.
（発明が解決しようとする課題）
このため、使用済金属燃料の画材断面を除く大部分が被
覆材に囲繞されたままであることから、溶解工程の溶解
処理液例えば電解精練の陽極溶融金属・カドミウムに接
する表面積があまりとれずに溶解速度が小さくなるとい
う問題がある。(Problem to be Solved by the Invention) For this reason, most of the spent metal fuel except for the cross section of the painting material remains surrounded by the coating material, so that the melting solution in the melting process, such as the anode molten metal and cadmium in electrolytic refining, There is a problem that the dissolution rate is low because there is not enough surface area in contact with.
本発明は、使用済金属燃料の再処理において溶解工程で
の燃料溶解を促進するため、この溶解工程に先立って、
使用済金属燃料を被覆材から取り出しかつ比表面積を大
きくする使用済金属燃料の脱被覆方法を提供することを
目的とする。In order to promote fuel dissolution in the melting step in the reprocessing of spent metal fuel, the present invention includes the following steps prior to the melting step:
It is an object of the present invention to provide a method for decoating spent metal fuel, which removes the spent metal fuel from the cladding material and increases the specific surface area.
（課題を解決するための手段）
かかる目的を達成するため、本発明の使用済金属燃料の
脱被覆法は、使用済金属燃料の再処理において、溶解処
理工程の前処理として、使用済金属燃料の水素化・脱水
素化を繰返すようにしている。(Means for Solving the Problems) In order to achieve the above object, the spent metal fuel decoating method of the present invention provides a method for decoating the spent metal fuel as a pretreatment of the melting process in the reprocessing of the spent metal fuel. The process of hydrogenation and dehydrogenation is repeated.
（作用）
したがって、使用済金属燃料は水素化と脱水素化とを繰
返す間に膨張し、かつ粉末あるいはポーラス状となる。(Function) Therefore, the spent metal fuel expands during repeated hydrogenation and dehydrogenation and becomes powdery or porous.
（実施例）
以下、本発明の構成を図面に示す実施例に基づいて詳細
に説明する。(Example) Hereinafter, the configuration of the present invention will be described in detail based on an example shown in the drawings.
まず、使用済燃料■を適当な長さに剪断した後、あるい
は剪断せずに脱被覆槽２に装入する［第１図（Ａ）］、
ここで使用済み燃料１の脱被覆槽２への搬入は例えば肌
付台車３等に載置して行なわれる。尚、脱被覆槽２には
水素供給槽４が接続されている。この水素供給槽４は、
例えばチタン・Ｔ１等の水素貯蔵用金属５と、ヒータ６
による温度調整により、脱被覆槽２にパルプ７を通して
供給する水素の圧力を自在に変化できるようになってい
る。尚、図中符号６はヒータであり、断熱材で覆われた
脱被覆槽２及び水素供給槽４内を加熱し得るように設け
られている。First, the spent fuel (2) is sheared into an appropriate length or charged into the decoating tank 2 without being sheared [Fig. 1 (A)].
Here, the spent fuel 1 is carried into the decoating tank 2 by being placed on, for example, a skinned truck 3 or the like. Note that a hydrogen supply tank 4 is connected to the decoating tank 2. This hydrogen supply tank 4 is
For example, a hydrogen storage metal 5 such as titanium/T1, and a heater 6
The pressure of hydrogen supplied to the decoating tank 2 through the pulp 7 can be freely changed by controlling the temperature. In addition, the reference numeral 6 in the figure is a heater, which is provided to heat the inside of the decoating tank 2 and the hydrogen supply tank 4, which are covered with a heat insulating material.
次いで、ゲート８を閉じて密閉状態として真空に排気し
、バルブ７を開放して水素供給槽４から水素を脱被覆槽
２に供給し、使用済燃料１の水素化と脱水素化を繰返す
［第１図（Ｂ）］、水素ガスとしては爆発を防ぐために
Ａｒ等の不活性ガスと混合したものの使用が望ましい、
そして、脱被覆槽２と水素供給槽４の温度をそれぞれ調
節することにより、使用済燃料の水素分圧を水素貯蔵合
金の水素分圧より小さくして使用済ｍ料を水素化し、ま
た逆にして脱水素化する。このとき、水素化させる温度
は１００〜３００℃で、脱水素化させる温度は４００〜
６００℃とすればよく、脆化現象がおきるまで繰り返す
、この水素化と脱水素化によって使用済金属１が膨張し
、脆化現象によって粉末状あるいはポーラス状になる６
例えば、金属ウランでは約７５％の体積変化がある。こ
のとき、使用済金属燃料１の膨張によりその周囲の被覆
管９が破砕する。Next, the gate 8 is closed to evacuate the tank in a sealed state, and the valve 7 is opened to supply hydrogen from the hydrogen supply tank 4 to the decoating tank 2, and the hydrogenation and dehydrogenation of the spent fuel 1 are repeated. Figure 1 (B)], it is preferable to use hydrogen gas mixed with an inert gas such as Ar to prevent explosion.
By adjusting the temperatures of the decladding tank 2 and the hydrogen supply tank 4, the spent fuel is hydrogenated by making the hydrogen partial pressure of the spent fuel smaller than the hydrogen partial pressure of the hydrogen storage alloy, and vice versa. and dehydrogenate. At this time, the hydrogenation temperature is 100-300℃, and the dehydrogenation temperature is 400-300℃.
The temperature may be 600°C, and the hydrogenation and dehydrogenation are repeated until the embrittlement phenomenon occurs.The spent metal 1 expands and becomes powdery or porous due to the embrittlement phenomenon6.
For example, uranium metal has a volume change of about 75%. At this time, the expansion of the spent metal fuel 1 causes the surrounding cladding tube 9 to fracture.
ウラン合金の水素化・脱水素化による脆化現象は例えば
ウラン−ジルコニウム合金では第２図に示すように２５
０℃で水素化、６７３℃で脱水素化が可能で、これを数
回例えば４回繰返すことにより、膨張してポーラスな金
属となる１例えば、第２図に示されるように、５２３ｋ
（約２５０℃）でＵ Ｈ２，ａにまで水素化したウラ
ンを１０’Ｐａの一定水素圧の下で温度を５０に以上あ
げると矢印Ａで示されるように水素はほとんど除去され
る。The embrittlement phenomenon caused by hydrogenation and dehydrogenation of uranium alloys is, for example, 25% in uranium-zirconium alloys as shown in Figure 2.
Hydrogenation at 0°C and dehydrogenation at 673°C are possible, and by repeating this several times, for example 4 times, it expands and becomes a porous metal.
When uranium is hydrogenated to U H2,a at about 250°C and the temperature is raised to 50°C or more under a constant hydrogen pressure of 10'Pa, most of the hydrogen is removed as shown by arrow A.
そこで、この脆化して粉砕あるいはポーラスになった使
用済金属燃料ｌＯと破砕した被覆管９とを肌付台車３に
載せてたまま脱被覆槽２から取り出し、次の溶解工程に
搬出する［第１図（Ｃ）］。Therefore, the spent metal fuel lO, which has become brittle and pulverized or has become porous, and the crushed cladding tube 9 are taken out from the decoating tank 2 while being placed on the skinned truck 3, and transported to the next melting process. Figure 1 (C)].
第３図は本発明の脱被覆装置の一例であり、水素貯蔵合
金５を設置した水素供給槽４と使用済燃料が設置される
脱被覆槽２とが遠隔操作によって開閉できる二ニーマチ
ックバルブ１１により結合されており、また温度計測器
１６並びに圧力計測器１５が設置され、各測定が使用中
に行えるようになっている。尚、図中符号１２は耐熱・
密封容器、１３は搬入搬出用の台、１４は真空排気系の
パイプ、１７は温度制ｍ機、１８は水素貯蔵合金の受皿
である。FIG. 3 shows an example of the decoating device of the present invention, in which the hydrogen supply tank 4 in which the hydrogen storage alloy 5 is installed and the decoating tank 2 in which the spent fuel is installed can be opened and closed by a two-mnematic valve 11 by remote control. A temperature measuring device 16 and a pressure measuring device 15 are installed so that each measurement can be performed during use. In addition, the code 12 in the figure is a heat-resistant
A sealed container, 13 a table for loading and unloading, 14 a pipe for a vacuum exhaust system, 17 a temperature controller, and 18 a hydrogen storage alloy receiving tray.
（発明の効果）
以上の説明より明らかなように、本発明は、使用済金属
燃料の再処理において、溶解処理工程の前処理として、
使用済金属燃料の水素化・脱水素を繰返すようにしたの
で、その間に使用済燃料がｍ張して被覆管を破砕する。(Effects of the Invention) As is clear from the above explanation, the present invention provides the following advantages:
Since hydrogenation and dehydrogenation of the spent metal fuel are repeated, the spent fuel is stretched during this time and the cladding tube is crushed.
しかも、使用済金属燃料は、水素化と脱水素化とを繰返
す間に水素脆化を起して粉末状あるいはポーラスになる
ので、溶解工程において溶解処理液例えば電解精練の溶
融金属と接する表面積が大きくなり、溶解処理速度が向
上する。Moreover, during repeated hydrogenation and dehydrogenation, spent metal fuel undergoes hydrogen embrittlement and becomes powdery or porous. This increases the dissolution processing speed.
第１図（Ａ）〜（Ｃ）は本発明の脱被覆法の原理を示す
図であり、（Ａ）は使用済燃料の装荷、（Ｂ）は水素導
入と排出の繰返し、（Ｃ）は脆化後使用済燃料の取出し
状態を示している。第２図はウラン中に吸収される水素
量と水素分圧及び温度との関係を示すグラフである。第
３図は本発明方法に使用される脱被覆装置の一実施例を
示す中央縦断面図である。
１・・・使用済金属燃料、
２・・・脱被覆槽、
３・・・器付台車、
４・・・水素供給槽、
５・・・水素貯蔵合金、
６・・・水素、
７・・・被覆材。Figures 1 (A) to (C) are diagrams showing the principle of the decoating method of the present invention, in which (A) is loading of spent fuel, (B) is repeated hydrogen introduction and discharge, and (C) is This shows the state of spent fuel being taken out after embrittlement. FIG. 2 is a graph showing the relationship between the amount of hydrogen absorbed in uranium, hydrogen partial pressure, and temperature. FIG. 3 is a central vertical cross-sectional view showing an embodiment of the decoating apparatus used in the method of the present invention. DESCRIPTION OF SYMBOLS 1... Spent metal fuel, 2... Decoating tank, 3... Trolley with equipment, 4... Hydrogen supply tank, 5... Hydrogen storage alloy, 6... Hydrogen, 7...・Covering material.
Claims (1)
理として、使用済金属燃料の水素化・脱水素化を繰返す
ことを特徴とする使用済金属燃料の脱被覆法。A method for decoating spent metal fuel, which comprises repeating hydrogenation and dehydrogenation of spent metal fuel as a pretreatment for a melting process in reprocessing spent metal fuel.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1210766A JPH0375595A (en) | 1989-08-17 | 1989-08-17 | Stripping method of spent metallic fuel |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1210766A JPH0375595A (en) | 1989-08-17 | 1989-08-17 | Stripping method of spent metallic fuel |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH0375595A true JPH0375595A (en) | 1991-03-29 |
Family
ID=16594779
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP1210766A Pending JPH0375595A (en) | 1989-08-17 | 1989-08-17 | Stripping method of spent metallic fuel |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0375595A (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS63289094A (en) * | 1987-05-20 | 1988-11-25 | Nippon Oil Co Ltd | Lead-free, high-octane gasoline |
| WO2000025321A1 (en) * | 1998-10-22 | 2000-05-04 | British Nuclear Fuels Plc | Electrochemical dissolution |
-
1989
- 1989-08-17 JP JP1210766A patent/JPH0375595A/en active Pending
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS63289094A (en) * | 1987-05-20 | 1988-11-25 | Nippon Oil Co Ltd | Lead-free, high-octane gasoline |
| WO2000025321A1 (en) * | 1998-10-22 | 2000-05-04 | British Nuclear Fuels Plc | Electrochemical dissolution |
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