US2882129A - Nitric acid recovery from waste solutions - Google Patents

Nitric acid recovery from waste solutions Download PDF

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US2882129A
US2882129A US692010A US69201057A US2882129A US 2882129 A US2882129 A US 2882129A US 692010 A US692010 A US 692010A US 69201057 A US69201057 A US 69201057A US 2882129 A US2882129 A US 2882129A
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nitric acid
ruthenium
solution
distillation
distillate
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Archie S Wilson
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    • CCHEMISTRY; METALLURGY
    • C01INORGANIC CHEMISTRY
    • C01BNON-METALLIC ELEMENTS; COMPOUNDS THEREOF; METALLOIDS OR COMPOUNDS THEREOF NOT COVERED BY SUBCLASS C01C
    • C01B21/00Nitrogen; Compounds thereof
    • C01B21/20Nitrogen oxides; Oxyacids of nitrogen; Salts thereof
    • C01B21/38Nitric acid
    • C01B21/46Purification; Separation ; Stabilisation
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/04Treating liquids
    • G21F9/06Processing
    • G21F9/08Processing by evaporation; by distillation

Definitions

  • the process of the invention thus comprises incorporating nitrous acid to a nitric acid solution containing radioactive ruthenium values, heating the solution to above its boiling point whereby a nitric acid-containing distillate and a ruthenium-containing distillation residue are obtained, and heating said distillate for the concentration of the nitric acid.
  • ruthenium vaporization suppressors In addition to nitrous acid, sodium nitrite and nitrogen dioxide were found suitable ruthenium vaporization suppressors. These substances are referred to hereinafter as nitrite-type ruthenium volatilization suppressors.
  • the quantities of these suppressors may vary widely, relatively small amounts being suitable. For instance, in the case of sodium nitrite a quantity of effective sodium nitrite, which is the excess quantity over that necessary to react with the oxygen in the air space of the still, of about 5 grams per liter of solution containing the ruthenium in concentrations usual for waste solutions was found suflicient; however, about grams per liter was preferred.
  • the process can be carried out as a batch or as a continuous procedure. If a continuous process is used, the nitric acid solution and ruthenium volatilization suppressor are continuously fed into the evaporator vessel, and the heating rate is then adjusted so that the rate of distillation is about the same as that of feed introduction.
  • EXAMPLE I An evaporator was charged with 500 ml. of a solution 7.36 M in nitric acid, 0.09 M in sodium nitrate, containing 1 percent of a dissolver solution (neutron-irradiated uranium dissolved in nitric acid) and also containing 0.25 g. of tetrapotassium ruthenium nitrite, K Ru(NO .H O.
  • a dissolver solution neutral-irradiated uranium dissolved in nitric acid
  • K Ru(NO .H O tetrapotassium ruthenium nitrite
  • the -distillation factors ranged between 3X10 and 20X 10
  • the distillation factor for either, the ruthenium and cerium, for the fraction of from 651 to 695 ml. was 1.5 X 10
  • EXAMPLE II A boiler vessel was charged with 200 ml. of an 8-M nitric acid containing 1 g./1. of tetrapotassium ruthenium nitrite, one percent of the same dissolver solution used in Example I and sodium nitrite in the quantities shown below in Table I. The solution was brought to boiling, and samples of the distillate were taken periodically and analyzed for nitric acid and ruthenium contents. The boiler solution was also analyzed. Furthermore, the cesium content (derived from the added dissolver solution) was determined in order to calculate the entrainment distillation factor. From the analytical results the ruthenium and cesium distillation factors were calculated. They are shown in Table I.
  • This table shows the favorable effect of the addition of sodium nitrite, namely, the. radical increase of the distillation factors.
  • the next example will illustrate the sudden increase of the ruthenium distillation factor when nitrogen die: as was. ntrq ce into. he, b ile oluti n- EXAMPLE III
  • the boiler vessel was charged with 250 ml. of an 8-M nitric acid containing sodium nitrate in a concentration of 1.5 M, '1 g./ l. of tetrapotassium ruthenium nitrite, and one percent of the same dissolver solution used in the previous examples.
  • the distillation was carried out Without the addition of nitrogen dioxidefor the first 8 hours, and then distillation was continued while nitrogen dioxide was introduced and maintained in the vessel at a nsta t P 73 3 4? he ths uin an cesiumr i ti lafla fa or r marized in Table H.
  • a process of recovering nitric acid from a solution containing said nitric acid together with ruthenium values comprising incorporating nitrous acid in said solution, heating the solution to above its boiling point so that nitric acid distills away from a ruthenium-containing distillation residue, condensing the nitric acid vapors to form a distillate, and heating said distillate for concentration of the nitric acid.

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  • 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)
  • Inorganic Compounds Of Heavy Metals (AREA)

Description

United States Patent NITRIC ACID RECOVERY FROM WASTE SOLUTIONS Archie S. Wilson, Richland, Wash., assignor to the United States of America as represented by the United States Atomic Energy Commission Application October 23, 1957 Serial No. 692,010
4 Claims. (Cl. 23-161) No Drawing.
because by this the volume is reduced so that less space I is required for the disposal and storage of the radioactive waste material and also because the nitric acid is regenerated thereby for reuse. However, there is a problem connected with the concentration of such nitric acid solutions, namely, the radioactive fission product ruthenium also volatilizes during evaporation; this volatilization of ruthenium takes place especially at nitric acid concentrations of between 5 and 13 M. The distillation of radioactive ruthenium involves a hazard and requires complex shielding equipment, and it also causes contamination of the distillate which makes reuse of the nitric acid dangerous or impossible.
It is an object of this invention to provide a process of evaporating nitric acid containing radioactive fission products in which the distillation of radioactive material is reduced to a minimum and a distillate containing a negligible amount of radioactivity is obtained.
It was found that ruthenium normally, in the presence of air, distills not in the form of ruthenium tetroxide, as one would expect, but that ruthenium distills as another unidentified compound. It was also found that by adding nitrous acid, or a substance that forms nitrous acid with nitric acid, the ruthenium volatilization is reduced to a negligible degree, so that the distillate obtained then is practically free from radioactive contaminants.
The process of the invention thus comprises incorporating nitrous acid to a nitric acid solution containing radioactive ruthenium values, heating the solution to above its boiling point whereby a nitric acid-containing distillate and a ruthenium-containing distillation residue are obtained, and heating said distillate for the concentration of the nitric acid.
In addition to nitrous acid, sodium nitrite and nitrogen dioxide were found suitable ruthenium vaporization suppressors. These substances are referred to hereinafter as nitrite-type ruthenium volatilization suppressors. The quantities of these suppressors may vary widely, relatively small amounts being suitable. For instance, in the case of sodium nitrite a quantity of effective sodium nitrite, which is the excess quantity over that necessary to react with the oxygen in the air space of the still, of about 5 grams per liter of solution containing the ruthenium in concentrations usual for waste solutions was found suflicient; however, about grams per liter was preferred.
The process can be carried out as a batch or as a continuous procedure. If a continuous process is used, the nitric acid solution and ruthenium volatilization suppressor are continuously fed into the evaporator vessel, and the heating rate is then adjusted so that the rate of distillation is about the same as that of feed introduction.
In the experiments that led to this invention samples of the distillate were analyzed at various intervals for macroconstituents by conventional chemical analyses and for radioactive constituents by counting techniques. Entrainment limited the attainable decontamination to a factor of about 10 as was shown by determination of the decontamination factor for the nonvolatile fission product cerium. (The decontamination factor is the ratio of activity in the total charge of the evaporator to the activity in the total distillate obtained.)
The examples given below are illustrative of the improvement accomplished by the process of this invention, but they are not supposed to limit the invention to the details given therein.
EXAMPLE I An evaporator was charged with 500 ml. of a solution 7.36 M in nitric acid, 0.09 M in sodium nitrate, containing 1 percent of a dissolver solution (neutron-irradiated uranium dissolved in nitric acid) and also containing 0.25 g. of tetrapotassium ruthenium nitrite, K Ru(NO .H O. During distillation a 1.15 M nitric acid was continually fed into the evaporator at an average rate of ml. per hour. The distillation run lasted seven hours, and the distillate was collected in seven fractions of one hour each; no nitrous acid was present in these runs. The ydistillation factors (=ratio of activity per ml. of boiler solution to that per ml. of distillate) ranged between 5.7x l0 and 33 l0 The distillation factors for ruthenium and cerium, for the fraction of from 434 to 518 ml.,
were found to be 120 and 3.5 l0 respectively.
Thereafter another set of runs was carried out in which the evaporator was charged with 500 ml. of a 9 M nitric acid, 1.5 M in sodium nitrate, containing 1 percent of the same dissolver solution used in the above-described runs and also containing 0.25 g. of the same tetrapotassium ruthenium nitrite. The nitric acid removed from the evaporator was continually replaced by feeding a mixture of nitric and nitrous acids at a speed of 43 ml. per hour to the evaporator. The acid mixture had a total acidity of 3.74 M and a nitrous acid concentration of 0.51 M. The -distillation factors ranged between 3X10 and 20X 10 The distillation factor for either, the ruthenium and cerium, for the fraction of from 651 to 695 ml. was 1.5 X 10 EXAMPLE II A boiler vessel was charged with 200 ml. of an 8-M nitric acid containing 1 g./1. of tetrapotassium ruthenium nitrite, one percent of the same dissolver solution used in Example I and sodium nitrite in the quantities shown below in Table I. The solution was brought to boiling, and samples of the distillate were taken periodically and analyzed for nitric acid and ruthenium contents. The boiler solution was also analyzed. Furthermore, the cesium content (derived from the added dissolver solution) was determined in order to calculate the entrainment distillation factor. From the analytical results the ruthenium and cesium distillation factors were calculated. They are shown in Table I.
Table 1 B .1 ees N NO Tlmein ate 0 er a gm/l hours MHNO; MHNO; tlon 18121011 Factor Factor 18 3. 06 10. 46 120 20x10 16 1. 49 s. 16 3, 100 11x10 23 1.99 9.1 760 1 x10 6.90 23 1. 49 7. so, 000 1.2x1m
This table shows the favorable effect of the addition of sodium nitrite, namely, the. radical increase of the distillation factors.
The next example will illustrate the sudden increase of the ruthenium distillation factor when nitrogen die: as was. ntrq ce into. he, b ile oluti n- EXAMPLE III The boiler vessel was charged with 250 ml. of an 8-M nitric acid containing sodium nitrate in a concentration of 1.5 M, '1 g./ l. of tetrapotassium ruthenium nitrite, and one percent of the same dissolver solution used in the previous examples. The distillation was carried out Without the addition of nitrogen dioxidefor the first 8 hours, and then distillation was continued while nitrogen dioxide was introduced and maintained in the vessel at a nsta t P 73 3 4? he ths uin an cesiumr i ti lafla fa or r marized in Table H. I
Table.
. .Dlstfl- Ruthenium Cesium Time in Hours, late, Distillation Distillation- M H N Factor" Factor 2. 2 6.5 10 1.3 10 2. 4 1.5X 2. 4 1.1)(10 v 2. 4 1-.2X10 5.7X10 2. 4, 1.2X10 2. 4 1.1X10 5.9X10 2: 4 2.0'X10" 4.9X10 2-.1 1.0X103; 5.5X1O
N0; gas introduced after 8 hours 2. 7 1.2X10 3.1X10' 2. 6 12x10 2. 4 1.2)(10 1.4X10 2. 4 4.1X10 2. 4 4.7)(10 1.4)(10 2.2 3 X10 4.3)(10 It is obvious that the nitrogen dioxide had a radical fisc the e entiqno hem he inm n. h o e lution.
It will be understood that this invention is not to be limited to the details given herein, but that it may be modified within the scope of. the appended claims.
What is claimed is:
l. A process of recovering nitric acid from a solution containing said nitric acid together with ruthenium values comprising incorporating nitrous acid in said solution, heating the solution to above its boiling point so that nitric acid distills away from a ruthenium-containing distillation residue, condensing the nitric acid vapors to form a distillate, and heating said distillate for concentration of the nitric acid.
2. The process of claim 1 wherein nitrous acid is incorporated by the addition of nitrous acid.
3; The process of claim 1 wherein the nitrous acid is incorporated by'theadd-ition of sodium nitrite to the nitric acid solution.
.4. The process of claim 1 wherein the; nitrous acid is incorporated by the addition of nitrogen dioxide to the nitric acid solution.
No references cited.

Claims (1)

1. A PROCESS OF RECOVERING NITRIC ACID FROM A SOLUTION CONTAINING SAID NITRIC ACID TOGETHER WITH RUTHENIUM VALUES COMPRISING INCORPORATING NITROUS ACID IN SAID SOLUTION, HEATING THE SOLUTION TO ABOVE ITS BOILING POINT SO THAT NITRIC ACID DISTILLS AWAY FROM A RUTHENIUM-CONTAINING DISTILLATION RESIDUE, CONDENSING THE NITRIC ACID VAPORS TO FORM A DISTILLATE, AND HEATING SAID DISTILATE FOR CONCENTRATION OF THE NITRIC ACID.
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Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2535103A1 (en) * 1982-10-21 1984-04-27 Nukem Gmbh METHOD FOR VOLUME REDUCTION OF AQUEOUS RADIOACTIVE WASTE
FR2536061A1 (en) * 1982-11-15 1984-05-18 Doryokuro Kakunenryo PROCESS FOR IMPROVING THE EFFICACY OF RUTHENIUM DECONTAMINATION IN THE TREATMENT OF NITRIC ACID BY EVAPORATION

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
None *

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2535103A1 (en) * 1982-10-21 1984-04-27 Nukem Gmbh METHOD FOR VOLUME REDUCTION OF AQUEOUS RADIOACTIVE WASTE
FR2536061A1 (en) * 1982-11-15 1984-05-18 Doryokuro Kakunenryo PROCESS FOR IMPROVING THE EFFICACY OF RUTHENIUM DECONTAMINATION IN THE TREATMENT OF NITRIC ACID BY EVAPORATION

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