US3914388A - Volatilization of iodine from nitric acid using peroxide - Google Patents
Volatilization of iodine from nitric acid using peroxide Download PDFInfo
- Publication number
- US3914388A US3914388A US396336A US39633673A US3914388A US 3914388 A US3914388 A US 3914388A US 396336 A US396336 A US 396336A US 39633673 A US39633673 A US 39633673A US 3914388 A US3914388 A US 3914388A
- Authority
- US
- United States
- Prior art keywords
- solution
- iodine
- nitric acid
- hydrogen peroxide
- boiling
- 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 - Lifetime
Links
- 229910052740 iodine Inorganic materials 0.000 title claims abstract description 56
- 239000011630 iodine Substances 0.000 title claims abstract description 56
- ZCYVEMRRCGMTRW-UHFFFAOYSA-N 7553-56-2 Chemical compound [I] ZCYVEMRRCGMTRW-UHFFFAOYSA-N 0.000 title claims abstract description 51
- GRYLNZFGIOXLOG-UHFFFAOYSA-N Nitric acid Chemical compound O[N+]([O-])=O GRYLNZFGIOXLOG-UHFFFAOYSA-N 0.000 title claims abstract description 21
- 229910017604 nitric acid Inorganic materials 0.000 title claims abstract description 21
- 150000002978 peroxides Chemical class 0.000 title description 6
- MHAJPDPJQMAIIY-UHFFFAOYSA-N Hydrogen peroxide Chemical compound OO MHAJPDPJQMAIIY-UHFFFAOYSA-N 0.000 claims abstract description 39
- 238000000034 method Methods 0.000 claims abstract description 30
- 230000002285 radioactive effect Effects 0.000 claims abstract description 23
- XMBWDFGMSWQBCA-UHFFFAOYSA-N hydrogen iodide Chemical compound I XMBWDFGMSWQBCA-UHFFFAOYSA-N 0.000 claims abstract description 19
- 229910000043 hydrogen iodide Inorganic materials 0.000 claims abstract description 18
- 238000009835 boiling Methods 0.000 claims abstract description 16
- 239000000243 solution Substances 0.000 claims description 49
- PNDPGZBMCMUPRI-UHFFFAOYSA-N iodine Chemical compound II PNDPGZBMCMUPRI-UHFFFAOYSA-N 0.000 claims description 5
- 230000015572 biosynthetic process Effects 0.000 claims description 4
- 239000007864 aqueous solution Substances 0.000 claims description 2
- 238000007865 diluting Methods 0.000 claims description 2
- 239000000126 substance Substances 0.000 claims description 2
- 238000009834 vaporization Methods 0.000 claims description 2
- 230000008016 vaporization Effects 0.000 claims description 2
- 238000004821 distillation Methods 0.000 description 10
- 238000006243 chemical reaction Methods 0.000 description 9
- 230000000694 effects Effects 0.000 description 3
- 241000894007 species Species 0.000 description 3
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 3
- CBENFWSGALASAD-UHFFFAOYSA-N Ozone Chemical compound [O-][O+]=O CBENFWSGALASAD-UHFFFAOYSA-N 0.000 description 2
- 239000003795 chemical substances by application Substances 0.000 description 2
- 239000003758 nuclear fuel Substances 0.000 description 2
- 238000012958 reprocessing Methods 0.000 description 2
- 241000196324 Embryophyta Species 0.000 description 1
- 208000035342 Isolated congenital onychodysplasia Diseases 0.000 description 1
- 244000261422 Lysimachia clethroides Species 0.000 description 1
- 101100400378 Mus musculus Marveld2 gene Proteins 0.000 description 1
- 229910052778 Plutonium Inorganic materials 0.000 description 1
- 229910052770 Uranium Inorganic materials 0.000 description 1
- 239000002253 acid Substances 0.000 description 1
- 230000005587 bubbling Effects 0.000 description 1
- 239000006227 byproduct Substances 0.000 description 1
- 239000003638 chemical reducing agent Substances 0.000 description 1
- 239000012141 concentrate Substances 0.000 description 1
- 238000000354 decomposition reaction Methods 0.000 description 1
- 239000003085 diluting agent Substances 0.000 description 1
- 238000010790 dilution Methods 0.000 description 1
- 239000012895 dilution Substances 0.000 description 1
- 239000012527 feed solution Substances 0.000 description 1
- 239000012535 impurity Substances 0.000 description 1
- 230000000155 isotopic effect Effects 0.000 description 1
- 238000011005 laboratory method Methods 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 230000003340 mental effect Effects 0.000 description 1
- 201000010158 nonsyndromic congenital nail disorder 7 Diseases 0.000 description 1
- 230000003647 oxidation Effects 0.000 description 1
- 238000007254 oxidation reaction Methods 0.000 description 1
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 description 1
- 238000012545 processing Methods 0.000 description 1
- 238000012827 research and development Methods 0.000 description 1
- 238000000638 solvent extraction Methods 0.000 description 1
- 239000002915 spent fuel radioactive waste Substances 0.000 description 1
- 239000012085 test solution Substances 0.000 description 1
- 210000001685 thyroid gland Anatomy 0.000 description 1
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 1
Classifications
-
- C—CHEMISTRY; METALLURGY
- C01—INORGANIC CHEMISTRY
- C01B—NON-METALLIC ELEMENTS; COMPOUNDS THEREOF; METALLOIDS OR COMPOUNDS THEREOF NOT COVERED BY SUBCLASS C01C
- C01B7/00—Halogens; Halogen acids
- C01B7/13—Iodine; Hydrogen iodide
- C01B7/14—Iodine
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/04—Treating liquids
- G21F9/06—Processing
- G21F9/08—Processing by evaporation; by distillation
Definitions
- ABSTRACT A method for removing radioactive iodine from nitric acid solution by adding hydrogen peroxide to the solution while concurrently holding the solution at the boiling point and distilling hydrogen iodide from the solution.
- Radioactive iodine i.e., I and 1"
- I and 1 Radioactive iodine
- iodine is one of the more dangerous radioactive elements. Iodine is volatile and if ingested tends to concentrate in the thyroid. It is thus desirable to separate and isolate the radioactive iodine from the nitric acid solution prior to further processing in order to protect plant personnel and the environment from possible exposure.
- iodine may be removed from nitric acid solution by conventional distillation.
- the iodine level is reduced to a residual level of about 10 to M or less, the remaining iodine cannot be removed by such conventional distillation techniques. It is at this point where the process of this invention as well as the processes of our copending applications begins. Experimental evidence has indicated that the small amount of iodine which remains in the nitric acid solution is in an oxidized state.
- elemental iodine is visually apparent in the process of this invention.
- Hydrogen iodide is given off as a colorless vapor. As the vapor nears the collection point, it contacts air and immediately oxidizes to release elemental iodine vapor which is distinctively reddish-violet in color.
- distillation arrangements may be used in carrying out the process of this invention.
- the batch laboratory method used in the examples comprised a 500 ml distillation flask, containing 250 ml solution, fitted with a goose-neck vapor take-off line and means for adding either H 0 or K1 to the Oh is, of course, understood that this would be considerably increased in scale on a production basis.
- the process of this invention is generally carried out with a four to six molar nitric acid solution having an iodine molarity of less than 5 X 10 M.
- Hydrogen peroxide is generally added to the solution as a 6 wt. water solution (about 2 M). However, any concentration of hydrogen peroxide may be used so as to maintain superficially an H 0 concentration after dilution and before reaction or decomposition of at least 4 X 10 M (0.012 wt. percent).
- the hydrogen peroxide is added continuously during the process to replace that which is lost due to reaction.
- the solution is maintained at boiling during the entire process. Boiling generally occurs in the system at a temperature between about to C.
- reaction which occurs to create the hydrogen iodide is thought to be 1 H 0 2H1 T +O
- a similar reaction is thought to occur with iodine in the higher oxidation states.
- this reaction is thermodynamically unfavorable (i.e., AG 0), and the solution must be kept at boiling in order for it to proceed.
- the process of this invention is preferably carried out in a stepwise fashion of successive distillations followed by replenishing the solution to its initial volume and initial iodine concentration.
- Non-radioactive iodine is added to replace the lost radioactive iodine and to act as a carrier for the remaining radioactive iodine.
- the solution Prior to distillation and hydrogen peroxide addition the solution may be pretreated by bubbling with ozone to minimize the effect of organic impurities which have the effect of tying up the radioactive iodine as organic iodide species.
- the hydrogen peroxide solution may also be treated with ozone.
- the hydrogen peroxide also appears to promote isotopic exchange between the nonradioactive iodine diluent and the radioactive iodine which is tied up by the organic species. By this exchange the radioactive iodine may be distilled leaving the non-radioactive iodine with the organic specie. 10-13 Having generally described the invention the following specific examples are given as a further illustration thereof.
- EXAMPLE 1 Test solutions of 250 ml of4 M HNO were prepared by adding '1 to provide a radioactive iodine molarity of about 10 M. This solution was boiled at 108C. at a distillation rate of about 0.5 ml/min. Five distillate cuts, each of about 10, were taken and the starting solution was evaluated for iodine content after each such cut. Hydrogen peroxide (30% solution) was added at a rate of 0.25 ml every 15 minutes during the distillation. Makeup water was added to the feed solution after 4 What is claimed is: 1. In a process wherein neutron irradiated substances are dissolved in nitric acid to form a solution and said solution includes radioactive iodine as a solute therein,
Landscapes
- Chemical & Material Sciences (AREA)
- Organic Chemistry (AREA)
- Inorganic Chemistry (AREA)
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Organic Low-Molecular-Weight Compounds And Preparation Thereof (AREA)
- Treatment Of Water By Oxidation Or Reduction (AREA)
Abstract
A method for removing radioactive iodine from nitric acid solution by adding hydrogen peroxide to the solution while concurrently holding the solution at the boiling point and distilling hydrogen iodide from the solution.
Description
United States Patent 1191 Cathers et al.
[4 1 Oct. 21, 1975 VOLATILIZATION OF IODINE FROM NITRIC ACID USING PEROXIDE [75] Inventors: George I. Cathers; Calvin J.
Shipman, both of Knoxville, Tenn.
[73] Assignee: The United States of America as represented by the United States Energy Research and Development Administration, Washington, DC.
[22] Filed: Sept. 11, 1973 [21] Appl. No.: 396,336
[52] U.S. Cl 423/249; 423/500; 252/301.1 R [51] Int. Cl. COIF 13/00 [58] Field of Search 423/249, 500; 252/30l.1 R
Primary Examiner- Stephen J. Lechert, Jr. Attorney, Agent, or FirmJohn A. I-loran; David S. Zachry; John B. Hardaway [57] ABSTRACT A method for removing radioactive iodine from nitric acid solution by adding hydrogen peroxide to the solution while concurrently holding the solution at the boiling point and distilling hydrogen iodide from the solution.
7 Claims, No Drawings VOLATILIZATION OF IODINE FROM NITRIC ACID USING PEROXIDE BACKGROUND OF THE INVENTION This invention was made in the course of, or under, a contract with the United States Atomic Energy Commission. It relates generally to the art of nuclear reactor fuel reprocessing.
As is disclosed in commonly assigned copending applications Ser. Nos. 231,820 and 317,455, a problem encountered in the field of nuclear fuel reprocessing is the removal of radioactive iodine from nitric acid solution. The problem arises from a process wherein spent fuel is dissolved in nitric acid and the desired elements, uranium and plutonium, are separated by solvent extraction from the nitric acid. Radioactive iodine (i.e., I and 1"") is a by-product of the fissioning process and is thus one of the elements present in the nitric acid solution.
From the standpoint of human safety iodine is one of the more dangerous radioactive elements. Iodine is volatile and if ingested tends to concentrate in the thyroid. It is thus desirable to separate and isolate the radioactive iodine from the nitric acid solution prior to further processing in order to protect plant personnel and the environment from possible exposure.
SUMMARY OF THE INVENTION It is thus an object of this invention to provide a process for removing radioactive iodine from nitric acid solution.
It is a further object of this invention to provide a process in which essentially all of the radioactive iodine is removed from the nitric acid solution.
These as well as other objects are accomplished by a process wherein hydrogen peroxide is added to a nitric acid solution containing radioactive iodine. The solution is boiled concurrently with peroxide addition to distill off the iodine as hydrogen iodide.
DETAILED DESCRIPTION According to this invention it has been found that residual traces of radioactive iodine may be removed from nitric acid solution by adding hydrogen peroxide to the solution while concurrently holding the solution at the boiling point to give off hydrogen iodide vapors and collecting the iodine thus given off.
In general, iodine may be removed from nitric acid solution by conventional distillation. However, when the iodine level is reduced to a residual level of about 10 to M or less, the remaining iodine cannot be removed by such conventional distillation techniques. It is at this point where the process of this invention as well as the processes of our copending applications begins. Experimental evidence has indicated that the small amount of iodine which remains in the nitric acid solution is in an oxidized state.
It has been unexpectedly found that hydrogen peroxide appears to act as a reducing agent when added to a nitric acid solution containing iodine. This enables the formation of hydrogen iodide which can be distilled from the solution by boiling. The particular reactions which produce hydrogen iodide are thermodynamically unfavorable; however, it has been found that by keeping the solution at boiling and allowing hydrogen iodide vapors to escape, the reaction will proceed. it is critical to the process of this invention that the solution be kept 2 at boiling or otherwise the reaction which produces hydrogen iodide will not proceed. It is further critical that the hydrogen peroxide be added only at boiling or otherwise the hydrogen peroxide will be lost before the reaction can begin.
The formation of elemental iodine is visually apparent in the process of this invention. Hydrogen iodide is given off as a colorless vapor. As the vapor nears the collection point, it contacts air and immediately oxidizes to release elemental iodine vapor which is distinctively reddish-violet in color.
Many types of distillation arrangements may be used in carrying out the process of this invention. The batch laboratory method used in the examples comprised a 500 ml distillation flask, containing 250 ml solution, fitted with a goose-neck vapor take-off line and means for adding either H 0 or K1 to the Oh is, of course, understood that this would be considerably increased in scale on a production basis.
The process of this invention is generally carried out with a four to six molar nitric acid solution having an iodine molarity of less than 5 X 10 M. Hydrogen peroxide is generally added to the solution as a 6 wt. water solution (about 2 M). However, any concentration of hydrogen peroxide may be used so as to maintain superficially an H 0 concentration after dilution and before reaction or decomposition of at least 4 X 10 M (0.012 wt. percent). Preferably the hydrogen peroxide is added continuously during the process to replace that which is lost due to reaction. The solution is maintained at boiling during the entire process. Boiling generally occurs in the system at a temperature between about to C.
The reaction which occurs to create the hydrogen iodide is thought to be 1 H 0 2H1 T +O A similar reaction is thought to occur with iodine in the higher oxidation states. As pointed out before, this reaction is thermodynamically unfavorable (i.e., AG 0), and the solution must be kept at boiling in order for it to proceed.
The process of this invention is preferably carried out in a stepwise fashion of successive distillations followed by replenishing the solution to its initial volume and initial iodine concentration. Non-radioactive iodine is added to replace the lost radioactive iodine and to act as a carrier for the remaining radioactive iodine. Prior to distillation and hydrogen peroxide addition the solution may be pretreated by bubbling with ozone to minimize the effect of organic impurities which have the effect of tying up the radioactive iodine as organic iodide species. The hydrogen peroxide solution may also be treated with ozone. The hydrogen peroxide also appears to promote isotopic exchange between the nonradioactive iodine diluent and the radioactive iodine which is tied up by the organic species. By this exchange the radioactive iodine may be distilled leaving the non-radioactive iodine with the organic specie. 10-13 Having generally described the invention the following specific examples are given as a further illustration thereof.
EXAMPLE 1 Test solutions of 250 ml of4 M HNO were prepared by adding '1 to provide a radioactive iodine molarity of about 10 M. This solution was boiled at 108C. at a distillation rate of about 0.5 ml/min. Five distillate cuts, each of about 10, were taken and the starting solution was evaluated for iodine content after each such cut. Hydrogen peroxide (30% solution) was added at a rate of 0.25 ml every 15 minutes during the distillation. Makeup water was added to the feed solution after 4 What is claimed is: 1. In a process wherein neutron irradiated substances are dissolved in nitric acid to form a solution and said solution includes radioactive iodine as a solute therein,
each distillate cut was taken. In the case of Run 2, 020- and wherein said iodine is removed from said solution, nated water was utilized for makeup. The results of the improvement comprising removing residual iodine these runs are shown in Table l. The final iodine confrom said solution by: centration was less than 5 X M. boiling said solution;
adding hydrogen peroxide to said boiling solution to TABLE I 10 cause the formation of volat|le hydrogen iodide Resldua' 9 9 and the vaporization of said hydrogen iodide; and
Successive 10% Distillation Cuts Run collecting iodine from said hydrogen iodide. 2nd 3rd 4th 5th 2. The method according to claim 1 wherein said ni- 47 23 [2 tric acid is a four to six molar aqueous solution.
5 3- -3 l5 3. The method according to claim 1 wherein said iodine is present in said solution at a concentration of 5 Normal H,0 makeup X 1() M or [egg hemmed make? 4. The method according to claim 1 wherein said hydrogen iodide is oxidized to form elemental iodine and said l mental iodine is collected. EXAMPLE n e e 5. The method according to claim 1 wherein said step The effect of hydrogen peroxide on the volatilization of boiling is carried out at a temperature within the of iodine from 4 M HMO was studied using solutions r ng of 105C, to 115C. having -5 X 10 M iOdifle Concentration 8 W85 6. The method according to claim 1 wherein said hy- 2.5 X 10" M). In each run the initial solution was 250 drogen peroxide is added to maintain an instantaneous ml and diStillat On Was performed at about hydrogen peroxide concentration of at least 0.012 wt. and the H 0 addition (at the specified concentration) t, was added continuously at about 0.5 ml/min. After 7, Th ethod according to claim 1 comprising the ea h 5 percent d ill i n h ni i l i n nfurther step of isotopically diluting said radioactive iocentration was re-established by adding Kl. The results dine with non-radioactive iodine. are shown in Table II.
TABLE II Residual Iodine (7: Original) After Successive 5% Distillation Cuts H 0 Run Conc. No. (71) Comments 1 st 2nd 3rd 4th 5th 6th 4 3 1.1 0.25 0.14 0.10 0.076 0.066 5 0 control 46 42 37 35 28 6 6 0.31 0.27 0.15 0.l5 0.076 0.060
7 6 b 0.8l 0.l 1 0.059 8 6 a.b 1.3 0.l4 0.037
"Solution 2.5 X 10 M Iodine "Held solution with H1O, being added at 90 for 2 hr. after carrier rcaddition
Claims (7)
1. IN A PROCESS WHEREIN NEUTRON IRRADICTED SUBSTANCES ARE DISSOLVED IN NITRIC ACID TO FORM A SOLUTION AND SAID SOLUTION INCLUDES RADIOACTIVE IODINE AS A SOLUTE THEREIN, AND WHEREIN SAID IODIN IS REMOVED FROM SAID SOLUTION, THE IMPROVEMENT COMPRISING REMOVING RESIDUAL IODINE FROM SAID SOLUTION BY: BOILING SAID SOLUTION, ADDING HYDROGEN PEROXIDE TO SAID BOILING SOLUTION TO CAUSE THE FORMATION OF VOLATILE HYDROGEN IODIDE AND THE VAPORIZATION OF SAID HYDROGEN IODIDE, AND COLLECTING IODINE FROM SAID HYDROGEN IODIDE.
2. The method according to claim 1 wherein said nitric acid is a four to six molar aqueous solution.
3. The method according to claim 1 wherein said iodine is present in said solution at a concentration of 5 X 10 4 M or less.
4. The method according to claim 1 wherein said hydrogen iodide is oxidized to form elemental iodine and said elemental iodine is collected.
5. The method according to claim 1 wherein said step of boiling is carried out at a temperature within the range of 105*C. to 115*C.
6. The method according to claim 1 wherein said hydrogen peroxide is added to maintain an instantaneous hydrogen peroxide concentration of at least 0.012 wt. percent.
7. The method according to claim 1 comprising the further step of isotopically diluting said radioactive iodine with non-radioactive iodine.
Priority Applications (4)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| US396336A US3914388A (en) | 1973-09-11 | 1973-09-11 | Volatilization of iodine from nitric acid using peroxide |
| JP49103395A JPS5055597A (en) | 1973-09-11 | 1974-09-06 | |
| DE2443520A DE2443520A1 (en) | 1973-09-11 | 1974-09-11 | EVOLUTION OF IODINE FROM NITRIC ACID WITH THE USE OF PEROXIDE |
| FR7430803A FR2243148B3 (en) | 1973-09-11 | 1974-09-11 |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| US396336A US3914388A (en) | 1973-09-11 | 1973-09-11 | Volatilization of iodine from nitric acid using peroxide |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| US3914388A true US3914388A (en) | 1975-10-21 |
Family
ID=23566808
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| US396336A Expired - Lifetime US3914388A (en) | 1973-09-11 | 1973-09-11 | Volatilization of iodine from nitric acid using peroxide |
Country Status (4)
| Country | Link |
|---|---|
| US (1) | US3914388A (en) |
| JP (1) | JPS5055597A (en) |
| DE (1) | DE2443520A1 (en) |
| FR (1) | FR2243148B3 (en) |
Cited By (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4275045A (en) * | 1974-07-03 | 1981-06-23 | Commissariat A L'energie Atomique | Method of extraction, trapping and storage of radioactive iodine contained in irradiated nuclear fuels |
| US4432955A (en) * | 1979-12-20 | 1984-02-21 | Kernforschungszentrum Karlsruhe Gmbh | Process for desorbing fission iodine from nitric acid fuel solution |
| US4737315A (en) * | 1983-06-08 | 1988-04-12 | Jgc Corporation | Method of treating radioactive organic wastes |
| US4834936A (en) * | 1986-09-01 | 1989-05-30 | Hitachi, Ltd. | Continuous dissolution apparatus for spent nuclear fuel |
| US4877558A (en) * | 1986-08-20 | 1989-10-31 | Fuji Electric Co., Ltd. | Method of treating radioactive ion-exchange resins by oxidative decomposition |
| US5352367A (en) * | 1991-11-05 | 1994-10-04 | Doryokuro Kakunenryo Kaihatsu Jigyodan | Process for the separation of radioactive iodine compounds by precipitation |
| US5464603A (en) * | 1994-01-25 | 1995-11-07 | Kansas State University Research Foundation | Method of treating aqueous iodide solutions |
| CN115565705A (en) * | 2022-11-03 | 2023-01-03 | 山东核电有限公司 | A method for purifying iodine in primary loop during maintenance of nuclear power plant |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2641119A1 (en) * | 1988-12-28 | 1990-06-29 | Commissariat Energie Atomique | Process for complementary desorption of the radioactive iodine present in the nitric solution for dissolving irradiated fuel elements |
| CN109336053B (en) * | 2018-11-29 | 2020-06-02 | 河北博泰环保科技有限公司 | Method for extracting iodine from saline water after secondary zinc oxide rinsing |
Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US2942943A (en) * | 1958-04-30 | 1960-06-28 | Margaret W Greene | Process for separating iodine-132 from fission products |
| US3282655A (en) * | 1966-11-01 | Production of |
-
1973
- 1973-09-11 US US396336A patent/US3914388A/en not_active Expired - Lifetime
-
1974
- 1974-09-06 JP JP49103395A patent/JPS5055597A/ja active Pending
- 1974-09-11 DE DE2443520A patent/DE2443520A1/en active Pending
- 1974-09-11 FR FR7430803A patent/FR2243148B3/fr not_active Expired
Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3282655A (en) * | 1966-11-01 | Production of | ||
| US2942943A (en) * | 1958-04-30 | 1960-06-28 | Margaret W Greene | Process for separating iodine-132 from fission products |
Cited By (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4275045A (en) * | 1974-07-03 | 1981-06-23 | Commissariat A L'energie Atomique | Method of extraction, trapping and storage of radioactive iodine contained in irradiated nuclear fuels |
| US4432955A (en) * | 1979-12-20 | 1984-02-21 | Kernforschungszentrum Karlsruhe Gmbh | Process for desorbing fission iodine from nitric acid fuel solution |
| US4737315A (en) * | 1983-06-08 | 1988-04-12 | Jgc Corporation | Method of treating radioactive organic wastes |
| US4877558A (en) * | 1986-08-20 | 1989-10-31 | Fuji Electric Co., Ltd. | Method of treating radioactive ion-exchange resins by oxidative decomposition |
| US4834936A (en) * | 1986-09-01 | 1989-05-30 | Hitachi, Ltd. | Continuous dissolution apparatus for spent nuclear fuel |
| US5352367A (en) * | 1991-11-05 | 1994-10-04 | Doryokuro Kakunenryo Kaihatsu Jigyodan | Process for the separation of radioactive iodine compounds by precipitation |
| US5464603A (en) * | 1994-01-25 | 1995-11-07 | Kansas State University Research Foundation | Method of treating aqueous iodide solutions |
| CN115565705A (en) * | 2022-11-03 | 2023-01-03 | 山东核电有限公司 | A method for purifying iodine in primary loop during maintenance of nuclear power plant |
Also Published As
| Publication number | Publication date |
|---|---|
| FR2243148B3 (en) | 1977-06-17 |
| DE2443520A1 (en) | 1975-03-13 |
| JPS5055597A (en) | 1975-05-15 |
| FR2243148A1 (en) | 1975-04-04 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| US4162231A (en) | Method for recovering palladium and technetium values from nuclear fuel reprocessing waste solutions | |
| US3993728A (en) | Bidentate organophosphorus solvent extraction process for actinide recovery and partition | |
| US3393981A (en) | Method of decomposing a nuclear fuel in a fused salt system by using nitric oxide | |
| US3914388A (en) | Volatilization of iodine from nitric acid using peroxide | |
| IL28878A (en) | Neptunium recovery process | |
| Persson et al. | Hot test of a TALSPEAK procedure for separation of actinides and lanthanides using recirculating DTPA-lactic acid solution | |
| US4528165A (en) | Separation of uranium from technetium in recovery of spent nuclear fuel | |
| US4059671A (en) | Method for increasing the lifetime of an extraction medium used for reprocessing spent nuclear fuel and/or breeder materials | |
| US3803295A (en) | Method for removing iodine from nitric acid | |
| US4131527A (en) | Method for selectively reducing plutonium values by a photochemical process | |
| US5085834A (en) | Method for separating by using crown compounds plutonium from uranium and from fission products in the initial stages for the reprocessing of irradiated nuclear fuels | |
| CA1239799A (en) | Process for the separation of large amounts of uranium from small amounts of radioactive fission products, which are present in basic, aqueous carbonate containing solutions | |
| US3119658A (en) | Aluminum cladding dissolution | |
| US2882124A (en) | Solvent extraction process for plutonium | |
| US5028402A (en) | Process for separating by means of crown ethers the uranium and plutonium present in an aqueous medium resulting from the reprocessing of irradiated nuclear fuels | |
| US5112581A (en) | Method of separating uranium and plutonium from mixed solution containing uranium and plutonium | |
| GB1465241A (en) | Method for the extraction properties of a tributyl phosphate solution | |
| US3979498A (en) | Recovery of cesium and palladium from nuclear reactor fuel processing waste | |
| US3580705A (en) | Selective stripping of plutonium from organic extracts | |
| US3792154A (en) | Removal of iodine from nitric acid solutions | |
| US3743696A (en) | Separation of americium and curium | |
| US2885260A (en) | Method for decontamination of reactor solutions | |
| US3853979A (en) | Method for removing rare earths from spent molten metallic fluoride salt mixtures | |
| DE3642841C2 (en) | ||
| US2823978A (en) | Precipitation method of separating plutonium from contaminating elements |