JPH04110795A - Reduction method for generation of non-radioactive waste from nuclear fuel reprocessing process - Google Patents
Reduction method for generation of non-radioactive waste from nuclear fuel reprocessing processInfo
- Publication number
- JPH04110795A JPH04110795A JP2231847A JP23184790A JPH04110795A JP H04110795 A JPH04110795 A JP H04110795A JP 2231847 A JP2231847 A JP 2231847A JP 23184790 A JP23184790 A JP 23184790A JP H04110795 A JPH04110795 A JP H04110795A
- Authority
- JP
- Japan
- Prior art keywords
- nitric acid
- nuclear fuel
- electrolytic cell
- fuel reprocessing
- reprocessing process
- 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
- 238000000034 method Methods 0.000 title claims abstract description 20
- 238000012958 reprocessing Methods 0.000 title claims abstract description 16
- 239000003758 nuclear fuel Substances 0.000 title claims abstract description 14
- 239000002901 radioactive waste Substances 0.000 title claims description 6
- GRYLNZFGIOXLOG-UHFFFAOYSA-N Nitric acid Chemical compound O[N+]([O-])=O GRYLNZFGIOXLOG-UHFFFAOYSA-N 0.000 claims abstract description 32
- 229910017604 nitric acid Inorganic materials 0.000 claims abstract description 32
- 238000004821 distillation Methods 0.000 claims abstract description 7
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 7
- 238000005868 electrolysis reaction Methods 0.000 claims abstract description 6
- 239000012159 carrier gas Substances 0.000 claims abstract description 4
- 239000012153 distilled water Substances 0.000 claims description 2
- VWDWKYIASSYTQR-UHFFFAOYSA-N sodium nitrate Chemical compound [Na+].[O-][N+]([O-])=O VWDWKYIASSYTQR-UHFFFAOYSA-N 0.000 abstract description 12
- 235000010344 sodium nitrate Nutrition 0.000 abstract description 6
- 239000002699 waste material Substances 0.000 abstract description 5
- 238000000354 decomposition reaction Methods 0.000 abstract description 3
- 239000007789 gas Substances 0.000 abstract description 3
- LPXPTNMVRIOKMN-UHFFFAOYSA-M sodium nitrite Chemical compound [Na+].[O-]N=O LPXPTNMVRIOKMN-UHFFFAOYSA-M 0.000 description 2
- 239000007864 aqueous solution Substances 0.000 description 1
- 239000003795 chemical substances by application Substances 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 230000003472 neutralizing effect Effects 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 235000010288 sodium nitrite Nutrition 0.000 description 1
- 239000002910 solid waste Substances 0.000 description 1
- 239000002915 spent fuel radioactive waste Substances 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
- Water Treatment By Electricity Or Magnetism (AREA)
Abstract
Description
【発明の詳細な説明】
［産業上の利用分野］
本発明は、核燃料の再処理工程において発生する非放射
性廃棄物の量を低減し、固体の廃棄物が実質上発生しな
いようにした方法に関する。Detailed Description of the Invention [Field of Industrial Application] The present invention relates to a method for reducing the amount of non-radioactive waste generated in a nuclear fuel reprocessing process and substantially eliminating the generation of solid waste. .
［従来の技術］
使用ずみ核燃料を再処理する代表的なプロセスでは、前
処理工程におけるヨウ素の追い出しと、プルトニウム精
製工程にあけるＰｕ酸化のために、ＮＯｘ （ＮＯ＋Ｎ
Ｏ２）を必要とする。 このＮｏ は、従来はＮａＮ
Ｏ２にＨＮＯ３を作用させることにより供給していた。[Prior art] In a typical process for reprocessing spent nuclear fuel, NOx (NO+N
O2) is required. Conventionally, this number is NaN
It was supplied by making HNO3 act on O2.
その結果発生するＮａＮＯ３は、非放射性であるため
取扱いにとりたてて困難はないものの、利用価値が乏し
く廃棄するほかない。 再処理の規模が大きくなれば、
それにつれてＮａＮＯ３の発生も大量にのぼるので、そ
の量を低減することが要望されていた。The NaNO3 generated as a result is non-radioactive, so it is not difficult to handle, but it has little utility value and has no choice but to be discarded. As the scale of reprocessing increases,
As a result, a large amount of NaNO3 is generated, and it has been desired to reduce the amount of NaNO3.
出願人は、核燃料再処理工程から回収される余剰硝酸を
分解してＮＯｘを発生させることにより、Ｎｏ 供給
のためのＮａＮＯ２が不要になり、かつ、その結果とし
て廃棄物ＮａＮＯ３の発生を回避することを着想し、改
良された核燃料再処理方法を発明して、すでに提案した
く特願平２−５４５５０）。The applicant decomposes excess nitric acid recovered from the nuclear fuel reprocessing process to generate NOx, thereby eliminating the need for NaNO2 for supplying NO and, as a result, avoiding the generation of waste NaNO3. I came up with the idea, invented an improved nuclear fuel reprocessing method, and have already proposed it (Japanese Patent Application No. 2-54550).
しかし、常に回収余剰硝酸が使用できるとは限らないた
め、出願人は、新鮮な硝酸からＮＯｘを製造し、これを
核燃料再処理工程に供給するシステムを考案した。However, since recovered surplus nitric acid cannot always be used, the applicant has devised a system for producing NOx from fresh nitric acid and supplying it to the nuclear fuel reprocessing process.
［発明が解決しようとする課題］
本発明の目的は、上記のシステムに従って核燃料再処理
工程に硝酸の電気分解を組み合わせることにより、非放
射性廃棄物の発生量を低減する方法を提供することにあ
る。[Problems to be Solved by the Invention] An object of the present invention is to provide a method for reducing the amount of non-radioactive waste generated by combining nitric acid electrolysis with the nuclear fuel reprocessing process according to the above system. .
［課題を解決するための手段］
本発明の核燃料再処理工程からの非放射性廃棄物の発生
量を低減する方法は、図にフローを示すように、電解槽
において硝酸を電解し、電解により発生したＮＯｘをキ
ャリアガスにのせて電解槽からとり出して核燃料再処理
工程へ供給し、槽に残った希薄硝酸を蒸留により濃縮し
、得られた濃縮硝酸を電解槽へ循環させて前記の廃棄物
とともに電解し、留出した水だけを廃棄することからな
る。[Means for solving the problem] The method of reducing the amount of non-radioactive waste generated from the nuclear fuel reprocessing process of the present invention is as shown in the flowchart in the figure. The generated NOx is taken out from the electrolytic cell on a carrier gas and supplied to the nuclear fuel reprocessing process, the dilute nitric acid remaining in the tank is concentrated by distillation, and the resulting concentrated nitric acid is circulated to the electrolytic cell to remove the above-mentioned waste. This consists of electrolyzing the water and disposing of only the distilled water.
［作 用］
硝酸の水溶液を電解すると、陽極において０２ガスが発
生するとともに、陰極においてＮｏおよびＮｏ２が発生
する。 従って、この現象を利用して、硝酸を直接電解
し、電解の結果希釈された形となる硝酸を蒸留により濃
縮して、図のフロに示すように循環させる。[Function] When an aqueous solution of nitric acid is electrolyzed, 02 gas is generated at the anode, and No and No2 are generated at the cathode. Therefore, by utilizing this phenomenon, nitric acid is directly electrolyzed, and the diluted nitric acid resulting from the electrolysis is concentrated by distillation and circulated as shown in the flowchart of the figure.
蒸留により、塔頂から微量の硝酸を含んだ水が留出し、
塔底から濃縮された硝酸が得られる。Through distillation, water containing a trace amount of nitric acid is distilled out from the top of the column.
Concentrated nitric acid is obtained from the bottom of the column.
水は、必要な中和剤を加えて廃棄することができる。The water can be discarded with the addition of necessary neutralizing agents.
［発明の効果］
本発明を実施すれば、核燃料再処理工程に使用するＮＯ
ｘガスが硝酸の分解によって供給できるから、従来技術
とちがってＮａＮＯ３の発生がなく、廃棄物の量を著し
く低減できる。[Effect of the invention] If the present invention is implemented, NO used in the nuclear fuel reprocessing process can be reduced.
Since the x gas can be supplied by decomposing nitric acid, unlike the prior art, there is no generation of NaNO3, and the amount of waste can be significantly reduced.
本発明に従い、電解による硝酸の分解と、電解槽からの
希薄硝酸の蒸留濃縮とを組み合わせることにより、供給
する硝酸の量は少なくて済む。According to the invention, by combining the decomposition of nitric acid by electrolysis and the distillative concentration of dilute nitric acid from the electrolytic cell, only a small amount of nitric acid is required to be supplied.
このようにして、処理すべき非放射性廃棄物の発生量を
、画期的に低減できる。In this way, the amount of non-radioactive waste to be disposed of can be dramatically reduced.
図面は、本発明の方法の工程を示すフローチャートであ
る。The drawing is a flowchart illustrating the steps of the method of the invention.
Claims (1)
＿ｘをキャリアガスにのせて電解槽からとり出して核燃
料再処理工程へ供給し、槽に残った希薄硝酸を蒸留によ
り濃縮し、得られた濃縮硝酸を電解槽へ循環させて前記
の硝酸とともに電解し、留出した水だけを廃棄すること
からなる、核燃料再処理工程からの非放射性廃棄物の発
生量を低減する方法。Nitric acid is electrolyzed in an electrolytic tank, and the NO generated by electrolysis is
__x is taken out from the electrolytic cell on a carrier gas and supplied to the nuclear fuel reprocessing process, the dilute nitric acid remaining in the tank is concentrated by distillation, and the obtained concentrated nitric acid is circulated to the electrolytic cell and electrolyzed together with the nitric acid mentioned above. A method of reducing the amount of non-radioactive waste generated from the nuclear fuel reprocessing process, which consists of disposing of only the distilled water.
Priority Applications (3)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP23184790A JPH0760194B2 (en) | 1990-08-31 | 1990-08-31 | Methods to reduce the amount of non-radioactive waste generated from nuclear fuel reprocessing processes |
| GB9118496A GB2250853B (en) | 1990-08-31 | 1991-08-29 | Method of treating nitric acid recovered from spent nuclear fuel reprocessing process |
| FR9110723A FR2666441B1 (en) | 1990-08-31 | 1991-08-29 | PROCESS FOR TREATING RECOVERED NITRIC ACID FROM NUCLEAR FUEL PROCESSING STEPS. |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP23184790A JPH0760194B2 (en) | 1990-08-31 | 1990-08-31 | Methods to reduce the amount of non-radioactive waste generated from nuclear fuel reprocessing processes |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH04110795A true JPH04110795A (en) | 1992-04-13 |
| JPH0760194B2 JPH0760194B2 (en) | 1995-06-28 |
Family
ID=16929946
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP23184790A Expired - Lifetime JPH0760194B2 (en) | 1990-08-31 | 1990-08-31 | Methods to reduce the amount of non-radioactive waste generated from nuclear fuel reprocessing processes |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0760194B2 (en) |
-
1990
- 1990-08-31 JP JP23184790A patent/JPH0760194B2/en not_active Expired - Lifetime
Also Published As
| Publication number | Publication date |
|---|---|
| JPH0760194B2 (en) | 1995-06-28 |
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