JPH01316695A - Reprocessing of nuclear fuel by using vacuum freeze drying method - Google Patents
Reprocessing of nuclear fuel by using vacuum freeze drying methodInfo
- Publication number
- JPH01316695A JPH01316695A JP63149653A JP14965388A JPH01316695A JP H01316695 A JPH01316695 A JP H01316695A JP 63149653 A JP63149653 A JP 63149653A JP 14965388 A JP14965388 A JP 14965388A JP H01316695 A JPH01316695 A JP H01316695A
- Authority
- JP
- Japan
- Prior art keywords
- nitrate
- drying method
- waste liquid
- freeze
- separated
- 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
- 238000000034 method Methods 0.000 title claims abstract description 59
- 238000012958 reprocessing Methods 0.000 title claims abstract description 17
- 239000003758 nuclear fuel Substances 0.000 title claims description 11
- 238000009777 vacuum freeze-drying Methods 0.000 title abstract 3
- 239000007788 liquid Substances 0.000 claims abstract description 25
- 239000002904 solvent Substances 0.000 claims abstract description 18
- 239000002699 waste material Substances 0.000 claims abstract description 18
- ZQPKENGPMDNVKK-UHFFFAOYSA-N nitric acid;plutonium Chemical compound [Pu].O[N+]([O-])=O ZQPKENGPMDNVKK-UHFFFAOYSA-N 0.000 claims abstract description 11
- 229910002007 uranyl nitrate Inorganic materials 0.000 claims abstract description 10
- SNRUBQQJIBEYMU-UHFFFAOYSA-N dodecane Chemical compound CCCCCCCCCCCC SNRUBQQJIBEYMU-UHFFFAOYSA-N 0.000 claims abstract description 9
- 238000004108 freeze drying Methods 0.000 claims abstract description 8
- 239000000446 fuel Substances 0.000 claims abstract description 7
- 229940094933 n-dodecane Drugs 0.000 claims abstract description 7
- 229910002651 NO3 Inorganic materials 0.000 claims abstract description 5
- NHNBFGGVMKEFGY-UHFFFAOYSA-N Nitrate Chemical compound [O-][N+]([O-])=O NHNBFGGVMKEFGY-UHFFFAOYSA-N 0.000 claims abstract description 5
- 238000004140 cleaning Methods 0.000 claims abstract description 4
- 238000001291 vacuum drying Methods 0.000 claims description 19
- 238000004519 manufacturing process Methods 0.000 claims description 6
- STCOOQWBFONSKY-UHFFFAOYSA-N tributyl phosphate Chemical compound CCCCOP(=O)(OCCCC)OCCCC STCOOQWBFONSKY-UHFFFAOYSA-N 0.000 abstract description 10
- 238000000638 solvent extraction Methods 0.000 abstract description 7
- CDBYLPFSWZWCQE-UHFFFAOYSA-L Sodium Carbonate Chemical compound [Na+].[Na+].[O-]C([O-])=O CDBYLPFSWZWCQE-UHFFFAOYSA-L 0.000 abstract description 6
- 239000010426 asphalt Substances 0.000 abstract description 5
- 239000002901 radioactive waste Substances 0.000 abstract description 4
- 238000012545 processing Methods 0.000 abstract description 3
- 229910000029 sodium carbonate Inorganic materials 0.000 abstract description 3
- 150000005690 diesters Chemical class 0.000 abstract description 2
- 230000003247 decreasing effect Effects 0.000 abstract 1
- 239000011521 glass Substances 0.000 abstract 1
- 238000010348 incorporation Methods 0.000 abstract 1
- -1 monoester Chemical compound 0.000 abstract 1
- GRYLNZFGIOXLOG-UHFFFAOYSA-N Nitric acid Chemical compound O[N+]([O-])=O GRYLNZFGIOXLOG-UHFFFAOYSA-N 0.000 description 10
- 229910017604 nitric acid Inorganic materials 0.000 description 10
- VWDWKYIASSYTQR-UHFFFAOYSA-N sodium nitrate Chemical compound [Na+].[O-][N+]([O-])=O VWDWKYIASSYTQR-UHFFFAOYSA-N 0.000 description 10
- HEMHJVSKTPXQMS-UHFFFAOYSA-M Sodium hydroxide Chemical compound [OH-].[Na+] HEMHJVSKTPXQMS-UHFFFAOYSA-M 0.000 description 6
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 description 5
- 229910052708 sodium Inorganic materials 0.000 description 5
- 239000011734 sodium Substances 0.000 description 5
- 235000010344 sodium nitrate Nutrition 0.000 description 5
- 239000004317 sodium nitrate Substances 0.000 description 5
- 239000012535 impurity Substances 0.000 description 4
- 238000007711 solidification Methods 0.000 description 4
- 230000008023 solidification Effects 0.000 description 4
- 238000004017 vitrification Methods 0.000 description 4
- 229910052778 Plutonium Inorganic materials 0.000 description 3
- 239000000470 constituent Substances 0.000 description 3
- 238000005260 corrosion Methods 0.000 description 3
- 230000007797 corrosion Effects 0.000 description 3
- 238000004090 dissolution Methods 0.000 description 3
- 239000000463 material Substances 0.000 description 3
- 150000002823 nitrates Chemical class 0.000 description 3
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 description 3
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 3
- 229910001868 water Inorganic materials 0.000 description 3
- FAPWRFPIFSIZLT-UHFFFAOYSA-M Sodium chloride Chemical compound [Na+].[Cl-] FAPWRFPIFSIZLT-UHFFFAOYSA-M 0.000 description 2
- 229910052770 Uranium Inorganic materials 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 238000006386 neutralization reaction Methods 0.000 description 2
- 239000012857 radioactive material Substances 0.000 description 2
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 2
- 238000005406 washing Methods 0.000 description 2
- 229910052695 Americium Inorganic materials 0.000 description 1
- 235000014653 Carica parviflora Nutrition 0.000 description 1
- 241000243321 Cnidaria Species 0.000 description 1
- 239000002253 acid Substances 0.000 description 1
- LXQXZNRPTYVCNG-UHFFFAOYSA-N americium atom Chemical compound [Am] LXQXZNRPTYVCNG-UHFFFAOYSA-N 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 238000004880 explosion Methods 0.000 description 1
- 238000001914 filtration Methods 0.000 description 1
- 239000012530 fluid Substances 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 239000000843 powder Substances 0.000 description 1
- 238000011084 recovery Methods 0.000 description 1
- 238000011946 reduction process Methods 0.000 description 1
- 239000010802 sludge Substances 0.000 description 1
- 239000011780 sodium chloride Substances 0.000 description 1
- 159000000000 sodium salts Chemical class 0.000 description 1
- 238000009270 solid waste treatment Methods 0.000 description 1
- 238000003860 storage Methods 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
- 229910000439 uranium oxide Inorganic materials 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
-
- 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
- Extraction Or Liquid Replacement (AREA)
Abstract
Description
【発明の詳細な説明】
〔産業上の利用分野〕
本発明は再処理工場や燃料製造工場のスクラップ処理工
程に利用できる凍結真空乾燥法を用いた核燃料再処理方
法に関するものである。DETAILED DESCRIPTION OF THE INVENTION [Field of Industrial Application] The present invention relates to a nuclear fuel reprocessing method using a freeze-vacuum drying method that can be used in a scrap processing process in a reprocessing plant or a fuel manufacturing plant.
一般に、再処理工場や燃料製造工場の溶媒抽出工程に用
いて劣化した溶媒は、炭酸ナトリウム、水酸化ナトリウ
ム溶液で洗浄し、不純物を除去してから再利用している
。Generally, degraded solvents used in solvent extraction processes at reprocessing plants and fuel manufacturing plants are washed with sodium carbonate and sodium hydroxide solutions to remove impurities before being reused.
しかしながら、上記の方法はナトリウムを含む洗浄廃液
が発生すること、劣化が進んだ溶媒は洗浄しても不純物
は除去できない欠点がある。さらに、これらナトリウム
を含む廃液は、硝酸と結合して硝酸ナトリウムとなり、
硝酸ナトリウムを含む廃液は蒸発缶で′ａ縮しても、硝
酸ナトリウム含有珊により成る以上は減容できない。However, the above method has disadvantages in that a washing waste liquid containing sodium is generated, and impurities cannot be removed even if a deteriorated solvent is washed. Furthermore, these sodium-containing waste liquids combine with nitric acid to become sodium nitrate.
Even if waste liquid containing sodium nitrate is condensed in an evaporator, the volume cannot be reduced as long as it is made of coral containing sodium nitrate.
硝酸ナトリウムの同化は、通常低放射性の場合はアスフ
ァルト固化を行い、高放射性の場合はガラス固化を行っ
ている。しかし、現実には放射性物質を固化するのでは
なく、あたかも放射性物質に同伴する大量の硝酸ナトリ
ウムを固化するのが目的であるかのようになっている。Assimilation of sodium nitrate is usually performed by asphalt solidification if the radioactivity is low, and by vitrification if the radioactivity is high. However, in reality, the purpose is not to solidify the radioactive material, but rather to solidify the large amount of sodium nitrate that accompanies the radioactive material.
そのため、可能な躍りナトリウムを利用しないプロセス
の開発が望まれている。また、放射性廃液の濃縮は、蒸
発缶が考えられるが、高温下での処理を行うため硝酸に
よる構成材料の腐食が問題となっている。Therefore, it is desired to develop a possible process that does not use sodium chloride. In addition, an evaporator can be used to condense radioactive waste liquid, but since the treatment is carried out at high temperatures, corrosion of the constituent materials by nitric acid poses a problem.
本発明は上記問題点を解決するためのもので、凍結真空
乾燥法を用い、構成材料の腐食防止、火災、爆発の恐れ
がなく、安全性が高く、可能な限りナトリウム含有物質
を利用せず、アスファルト固化設備、ガラス固化設備の
省略化や筒素化が図れ、ソルトフリーの工程を目指すも
ので、さらに凍結真空乾燥法を廃液処理に用い、回収酸
は利用し、閉サイクルを構成し、残渣は可能な限り減容
した形状で回収することができる凍結真空乾燥法を用い
た核燃料再処理方法を捷供することを目的とする。The present invention is intended to solve the above problems, and uses a freeze-vacuum drying method to prevent corrosion of the constituent materials, eliminate the risk of fire or explosion, and is highly safe, and does not use sodium-containing substances as much as possible. , the asphalt solidification equipment and vitrification equipment can be omitted and made into cylinders, aiming for a salt-free process.Furthermore, the freeze-vacuum drying method is used for waste liquid treatment, the recovered acid is used, and a closed cycle is constructed. The purpose is to provide a nuclear fuel reprocessing method using a freeze-vacuum drying method that allows residues to be recovered in a form with the volume reduced as much as possible.
そのために本発明の凍結真空乾燥法を用いた核燃料再処
理方法は、再処理工場や燃料製造工場の湿式工程におい
て、溶媒抽出工程での処理で分離された硝酸プルトニウ
ム、硝酸ウラニルの溶液、使用済溶媒、及び廃液を凍結
真空乾燥法により処理し、硝酸プルトニウム、硝酸ウラ
ニルの溶液を凍結乾燥法により、硝酸塩と凝縮液とに分
離し、使用済溶媒を凍結乾燥処理することにより、ＴＢ
Ｐ、ＤＢＰ、ＭＢＰとｎ・ドデカンに分離し、廃液を凍
結乾燥法により処理し、液体と残渣とに分離したことを
特徴とする。For this purpose, the nuclear fuel reprocessing method using the freeze-vacuum drying method of the present invention is used to collect solutions of plutonium nitrate and uranyl nitrate separated in the solvent extraction process in the wet process of reprocessing plants and fuel manufacturing plants. By treating the solvent and waste liquid by freeze-vacuum drying, separating the solution of plutonium nitrate and uranyl nitrate into nitrate and condensate by freeze-drying, and freeze-drying the used solvent, TB
It is characterized in that P, DBP, MBP and n-dodecane are separated, and the waste liquid is treated by a freeze-drying method to separate it into a liquid and a residue.
本発明の凍結真空乾燥法を用いた核燃料再処理方法は、
再処理工場や燃料製造工場の溶媒洗浄工程に凍結真空乾
燥法を用いることにより、炭酸ナトリウム、水酸化ナト
リウム等を使用せず、廃液発生量を凍らすと共に、アス
ファルト固化工程、ガラス固化工程へ送られる廃液中に
ナトリウム分を含まないようにする。これにより、アス
ファルト固化用溶液、ガラス固化溶液にナトリウム分を
含まないため、処理工程が単純化され、いっそう合理的
なプロセスが選択できる。The nuclear fuel reprocessing method using the freeze-vacuum drying method of the present invention includes:
By using the freeze-vacuum drying method in the solvent cleaning process at reprocessing plants and fuel manufacturing plants, waste liquid is frozen and sent to the asphalt solidification process and vitrification process without using sodium carbonate, sodium hydroxide, etc. Ensure that sodium content is not included in the waste liquid. As a result, the asphalt solidification solution and the vitrification solution do not contain sodium, which simplifies the treatment process and allows a more rational process to be selected.
（実施例） 以下、実施例を図面を参照して説明する。(Example) Examples will be described below with reference to the drawings.
第１図は本発明の凍結真空乾燥法を用いた核燃Ｖ’ｌ再
処理方法の一実施例におけるプロセスフローを示す図で
ある。FIG. 1 is a diagram showing a process flow in one embodiment of the nuclear fuel V'l reprocessing method using the freeze-vacuum drying method of the present invention.
燃料製造工場で発生した不純物を含むプルトニウム・ウ
ラン酸化物スクラップは、工程■において硝酸溶液と共
に溶解槽に供給される。プルトニウム・ウラン溶液は調
整されてから溶媒抽出工程■へ送られ、ＴＢＰ（リン酸
トリーｎブチル）。Plutonium/uranium oxide scrap containing impurities generated at a fuel manufacturing plant is supplied to a dissolution tank together with a nitric acid solution in step (2). After the plutonium/uranium solution is adjusted, it is sent to the solvent extraction step (2), where it is extracted with TBP (tri-n-butyl phosphate).
ｎ・ドデカン等よりなる溶媒硝酸溶液を用い、硝酸プル
トニウム溶液・硝酸ウラニル溶液■と、使用済溶媒■と
、廃液■とに分離される。Using a solvent nitric acid solution made of n.dodecane or the like, the solution is separated into a plutonium nitrate solution/uranyl nitrate solution (2), a used solvent (2), and a waste liquid (2).
硝酸プルトニウム溶液・硝酸ウラニル溶液■は凍結真空
乾燥装置■で濃縮されて硝酸塩■と凝縮液■になる。凝
縮液■は、凍結真空乾燥装置＠へ送られる。硝酸塩■は
脱硝工程■へ送られ、例えばマイクロ波加熱して酸化物
にしてから、焙焼還元工程［相］で必要に応じて粉末調
整して製品０にする。Plutonium nitrate solution/uranyl nitrate solution (■) is concentrated in a freeze-vacuum dryer (■) to become nitrate (■) and condensate (■). The condensate ■ is sent to the freeze-vacuum dryer @. The nitrates (1) are sent to the denitrification process (2), where they are converted into oxides by heating with microwaves, for example, and then adjusted to powder as necessary in the roasting and reduction process (phase) to form a product (0).
使用済溶媒■は凍結真空乾燥装置＠でＴｌ３Ｐ。The used solvent ■ is converted to Tl3P using a freeze-vacuum dryer @.
ＤＢＰ（ジエステル）、ＭＢＰ （モノエステル）等［
相］とｎ・ドデカン等［相］に分けられる。ＴＢＰ。DBP (diester), MBP (monoester), etc. [
phase] and n-dodecane etc. [phase]. TBP.
ＤＩ３Ｐ、ＭＢＰ等０は中和洗浄工程［相］において約
２０％濃Ｎ ａ Ｏ）Ｔ溶液で洗浄され、ＴＢＰ■と硝
酸溶液等［相］になる。ＴＢＰ■は調整工程［相］で必
要に応してＴＢＰ、ｎ・ドデカンを加え、調整後溶媒工
程■へ送られる。硝酸溶液等［株］は凍結真空乾燥装置
■へ送られる。また、ｎ・ドデカン■はこのプロセスで
は焼却炉＠へ送られ、処理される。DI3P, MBP, etc. 0 are washed with an approximately 20% concentrated NaO)T solution in the neutralization washing process [phase], and become TBP■ and a nitric acid solution [phase]. TBP (2) is added with TBP and n-dodecane as necessary in the adjustment step (phase), and after adjustment is sent to the solvent step (2). The nitric acid solution etc. is sent to the freeze-vacuum dryer ■. Also, in this process, n-dodecane ■ is sent to an incinerator @ and treated.
廃液■は凍結真空乾燥装置０へ送られ、プルトニウム、
ウラン、アメリシウム等の不純物よりなる残渣０と、水
及び硝酸［相］に分けられる。残渣０（硝酸塩）は回収
のため、工程［相］で保管または固体廃棄物処理系へ送
られる。水及び硝酸０は工程［相］で必要に応じて水、
硝酸を加え、もしくは濃縮したり、希釈したりして、調
整し、利用され（工程ｏ）、例えば溶解槽■、溶媒抽出
工程■、その他このフローには記入していないオフガス
洗浄工程等へ送られる。もし、余裕が生じた場合には放
出される（工程＠）。The waste liquid ■ is sent to freeze-vacuum drying equipment 0, and plutonium,
It is divided into 0 residues consisting of impurities such as uranium and americium, and water and nitric acid [phase]. Residue 0 (nitrates) is stored in the process [phase] or sent to a solid waste treatment system for recovery. Water and nitric acid 0 are added as needed in the process [phase].
It is adjusted by adding nitric acid, concentrated, or diluted, and then used (process o), and then sent to, for example, a dissolution tank ■, a solvent extraction process ■, or other off-gas cleaning processes not included in this flow. It will be done. If there is a surplus, it will be released (process @).
なお、この工程のフローでは凍結真空乾燥装置を■、■
、＠の３台用いているが、もちろん貯槽を設けて運転す
れば１台でもよい。In addition, in this process flow, the freeze vacuum drying equipment is
, @ are used, but of course one can be used if a storage tank is installed and operated.
以上のように本発明によれば、溶媒抽出工程に凍結真空
乾燥法を用い、硝酸プルトニウム溶液、硝酸ウラニル溶
液、ＴＢＰ、ＤＢＰ、ＭＢＰとｎ・ドデカン、の分離が
でき、ナトリウム塩の使用量を大幅に減らすことができ
、放射性廃液発生量が減少し、処理が節単になる。また
、放射性廃液の中和・濾過が不要となり、スラッジ発生
が少なくなる。また凍結真空乾燥法は低温のため、構成
材料の腐食の恐れがない。As described above, according to the present invention, plutonium nitrate solution, uranyl nitrate solution, TBP, DBP, MBP and n-dodecane can be separated by using the freeze-vacuum drying method in the solvent extraction step, and the amount of sodium salt used can be reduced. This can significantly reduce the amount of radioactive waste fluid generated, making processing simpler. In addition, neutralization and filtration of radioactive waste liquid are no longer necessary, and sludge generation is reduced. Furthermore, since the freeze-vacuum drying method uses low temperatures, there is no risk of corrosion of the constituent materials.
第１図は本発明の凍結真空乾燥法を用いた核燃料再処理
方法の一実施例におけるプロセスフローを示す図である
。
■・・・溶解槽、■・・・溶媒抽出工程、■・・・硝酸
プルトニウム溶液・硝酸ウラニル溶液、■・・・使用済
溶媒■、■・・・廃液、■、■、０・・・凍結真空乾燥
装置、■・・・硝酸塩、■凝縮液、■・・・ＴＢＰ、Ｄ
ＢＰ、ＭＢＰ等、■・・・凝縮液、０・・・残渣、［相
］・・・水、硝酸。FIG. 1 is a diagram showing a process flow in one embodiment of the nuclear fuel reprocessing method using the freeze-vacuum drying method of the present invention. ■...Dissolution tank, ■...Solvent extraction process, ■...Plutonium nitrate solution/uranyl nitrate solution, ■...Spent solvent ■, ■...Waste liquid, ■, ■, 0... Freeze vacuum dryer, ■...Nitrate, ■Condensate, ■...TBP, D
BP, MBP, etc. ■...Condensate, 0...Residue, [Phase]...Water, nitric acid.
Claims (4)
溶媒洗浄工程での処理で分離された硝酸プルトニウム、
硝酸ウラニルの溶液、使用済溶媒、及び廃液を凍結真空
乾燥法により処理したことを特徴とする凍結真空乾燥法
を用いた核燃料再処理方法。(1) In the wet process of reprocessing plants and fuel manufacturing plants,
Plutonium nitrate separated during the solvent cleaning process,
A nuclear fuel reprocessing method using a freeze-vacuum drying method, characterized in that a solution of uranyl nitrate, a spent solvent, and a waste liquid are treated by a freeze-vacuum drying method.
燥法により、硝酸塩と凝縮液とに分離した請求項１記載
の凍結真空乾燥法を用いた核燃料再処理方法。(2) A nuclear fuel reprocessing method using a freeze-vacuum drying method according to claim 1, wherein a solution of plutonium nitrate and uranyl nitrate is separated into a nitrate and a condensate by a freeze-drying method.
Ｐ、ＤＢＰ、ＭＢＰとｎ・ドデカンに分離した請求項１
記載の凍結真空乾燥法を用いた核燃料再処理方法。(3) By freeze-drying the used solvent, TB
Claim 1 separated into P, DBP, MBP and n-dodecane
A nuclear fuel reprocessing method using the freeze-vacuum drying method described.
分離した請求項１記載の凍結真空乾燥法を用いた核燃料
再処理方法。(4) A nuclear fuel reprocessing method using a freeze-vacuum drying method according to claim 1, wherein the waste liquid is treated by a freeze-drying method and separated into a liquid and a residue.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63149653A JPH01316695A (en) | 1988-06-17 | 1988-06-17 | Reprocessing of nuclear fuel by using vacuum freeze drying method |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63149653A JPH01316695A (en) | 1988-06-17 | 1988-06-17 | Reprocessing of nuclear fuel by using vacuum freeze drying method |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH01316695A true JPH01316695A (en) | 1989-12-21 |
Family
ID=15479926
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP63149653A Pending JPH01316695A (en) | 1988-06-17 | 1988-06-17 | Reprocessing of nuclear fuel by using vacuum freeze drying method |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH01316695A (en) |
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH0495899A (en) * | 1990-08-14 | 1992-03-27 | Power Reactor & Nuclear Fuel Dev Corp | Extraction and separation of spent solution generated from nuclear fuel cycle |
| FR2667434A1 (en) * | 1990-10-01 | 1992-04-03 | Doryokuro Kakunenryo | LOW TEMPERATURE PLUTONIUM NITRATE SOLUTION CONCENTRATION PROCESS. |
| US5112581A (en) * | 1990-10-01 | 1992-05-12 | Doryokuro Kakunenryo Kaihatsu Jigyodan | Method of separating uranium and plutonium from mixed solution containing uranium and plutonium |
| WO2007083588A1 (en) * | 2006-01-19 | 2007-07-26 | Japan Nuclear Fuel Limited | Sodium salt recycling system for use in wet reprocessing of used nuclear fuel |
| CN112939084A (en) * | 2019-12-10 | 2021-06-11 | 中核北方核燃料元件有限公司 | Preparation method of fine powder of uranyl nitrate of nuclear purity grade |
Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5423900A (en) * | 1977-07-25 | 1979-02-22 | Mitsubishi Metal Corp | Recovering regeneration method of radioactive retreating waste organic solvent |
| JPS56115991A (en) * | 1980-02-19 | 1981-09-11 | Tokyo Shibaura Electric Co | Microwave heating deniration device |
| JPS6227697A (en) * | 1985-07-29 | 1987-02-05 | 動力炉・核燃料開発事業団 | Method and device for processing waste liquor containing radioactive substance |
| JPS6249296A (en) * | 1985-08-28 | 1987-03-03 | 株式会社東芝 | Evaporating concentrator |
-
1988
- 1988-06-17 JP JP63149653A patent/JPH01316695A/en active Pending
Patent Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5423900A (en) * | 1977-07-25 | 1979-02-22 | Mitsubishi Metal Corp | Recovering regeneration method of radioactive retreating waste organic solvent |
| JPS56115991A (en) * | 1980-02-19 | 1981-09-11 | Tokyo Shibaura Electric Co | Microwave heating deniration device |
| JPS6227697A (en) * | 1985-07-29 | 1987-02-05 | 動力炉・核燃料開発事業団 | Method and device for processing waste liquor containing radioactive substance |
| JPS6249296A (en) * | 1985-08-28 | 1987-03-03 | 株式会社東芝 | Evaporating concentrator |
Cited By (11)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH0495899A (en) * | 1990-08-14 | 1992-03-27 | Power Reactor & Nuclear Fuel Dev Corp | Extraction and separation of spent solution generated from nuclear fuel cycle |
| FR2667434A1 (en) * | 1990-10-01 | 1992-04-03 | Doryokuro Kakunenryo | LOW TEMPERATURE PLUTONIUM NITRATE SOLUTION CONCENTRATION PROCESS. |
| US5112581A (en) * | 1990-10-01 | 1992-05-12 | Doryokuro Kakunenryo Kaihatsu Jigyodan | Method of separating uranium and plutonium from mixed solution containing uranium and plutonium |
| JPH04140697A (en) * | 1990-10-01 | 1992-05-14 | Power Reactor & Nuclear Fuel Dev Corp | Cold condensation of plutonium nitrate solution |
| WO2007083588A1 (en) * | 2006-01-19 | 2007-07-26 | Japan Nuclear Fuel Limited | Sodium salt recycling system for use in wet reprocessing of used nuclear fuel |
| EP1975945A1 (en) * | 2006-01-19 | 2008-10-01 | Japan nuclear fuel limite | Sodium salt recycling system for use in wet reprocessing of used nuclear fuel |
| JPWO2007083588A1 (en) * | 2006-01-19 | 2009-06-11 | 日本原燃株式会社 | Sodium salt recycling system in wet reprocessing of spent nuclear fuel |
| US7666370B2 (en) | 2006-01-19 | 2010-02-23 | Japan Nuclear Fuel Limited | Sodium salt recycling process for use in wet reprocessing process of spent nuclear fuel |
| JP5038160B2 (en) * | 2006-01-19 | 2012-10-03 | 日本原燃株式会社 | Sodium salt recycling system in wet reprocessing of spent nuclear fuel |
| EP1975945A4 (en) * | 2006-01-19 | 2014-09-17 | Japan Nuclear Fuel Limite | Sodium salt recycling system for use in wet reprocessing of used nuclear fuel |
| CN112939084A (en) * | 2019-12-10 | 2021-06-11 | 中核北方核燃料元件有限公司 | Preparation method of fine powder of uranyl nitrate of nuclear purity grade |
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