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Removal of Radioactivity by Ion-Exchange H. GLADYS SWOPE Chemical Engineering Division Argonne National Laboratory, Lemont, Illinois The use of ion-exchange resins may be of considerable value to industries and hospitals for the removal of radioactivity. The general handling of radioactive wastes at this Laboratory was described in a paper presented at the Eighth Purdue Industrial Waste Conference (1). The wastes from laboratory drains in buildings in which there is radioactivity discharge to retention tanks. These wastes are monitored and those over-tolerance are sent to the Waste Processing Group, the others discharge directly to the Laboratory Waste Treatment Plant. The experiments reported here have shown that of the cation resins which are available today only those of the polystyrene divinyl benzene sulfonic acid type are satisfactory for good removal of radioactivity. These have a high capacity over a wide pH range, and are stable towards acids, bases and organic solvents. After normal exhaustion of the resin, i.e., breakthrough of calcium and magnesium, the resin is effective in removing 65 to 75 percent of the total beta activity in the feed from mixed fission product activity. Fission product analysis of the effluents after passage through cation columns have shown that strontium and rare earths were removed even after breakthrough of calcium and magnesium. Ruthenium and cesium leaked before resin exhaustion. To verify and to try to find an explanation for the removal of radioactivity after hardness breakthrough, an experiment was run in which mixed fission products were passed in parallel through columns containing sodium, calcium, magnesium and iron forms of the resin. These results indicated that when tap water was at pH 2.5 the sodium form of the resin removed more activity prior to hardness breakthrough than any of the other three forms of the resin. After hardness breakthrough the decontamination with the sodium form dropped below that for the other forms. An important point to note is that the iron form of the resin did not remove strontium90. When the tap water was at pH 7.0, best results for total beta decontamination were obtained with 118
Object Description
Purdue Identification Number | ETRIWC195412 |
Title | Removal of radioactivity by ion-exchange |
Author | Swope, H. Gladys |
Date of Original | 1954 |
Conference Title | Proceedings of the ninth Industrial Waste Conference |
Conference Front Matter (copy and paste) | http://earchives.lib.purdue.edu/cdm4/document.php?CISOROOT=/engext&CISOPTR=3516&REC=13 |
Extent of Original | p. 118-131 |
Collection Title | Engineering Technical Reports Collection, Purdue University |
Repository | Purdue University Libraries |
Rights Statement | Digital object copyright Purdue University. All rights reserved. |
Language | eng |
Type (DCMI) | text |
Format | JP2 |
Date Digitized | 2008-09-22 |
Capture Device | Fujitsu fi-5650C |
Capture Details | ScandAll 21 |
Resolution | 300 ppi |
Color Depth | 8 bit |
Description
Title | page 118 |
Collection Title | Engineering Technical Reports Collection, Purdue University |
Repository | Purdue University Libraries |
Rights Statement | Digital object copyright Purdue University. All rights reserved. |
Language | eng |
Type (DCMI) | text |
Format | JP2 |
Capture Device | Fujitsu fi-5650C |
Capture Details | ScandAll 21 |
Transcript | Removal of Radioactivity by Ion-Exchange H. GLADYS SWOPE Chemical Engineering Division Argonne National Laboratory, Lemont, Illinois The use of ion-exchange resins may be of considerable value to industries and hospitals for the removal of radioactivity. The general handling of radioactive wastes at this Laboratory was described in a paper presented at the Eighth Purdue Industrial Waste Conference (1). The wastes from laboratory drains in buildings in which there is radioactivity discharge to retention tanks. These wastes are monitored and those over-tolerance are sent to the Waste Processing Group, the others discharge directly to the Laboratory Waste Treatment Plant. The experiments reported here have shown that of the cation resins which are available today only those of the polystyrene divinyl benzene sulfonic acid type are satisfactory for good removal of radioactivity. These have a high capacity over a wide pH range, and are stable towards acids, bases and organic solvents. After normal exhaustion of the resin, i.e., breakthrough of calcium and magnesium, the resin is effective in removing 65 to 75 percent of the total beta activity in the feed from mixed fission product activity. Fission product analysis of the effluents after passage through cation columns have shown that strontium and rare earths were removed even after breakthrough of calcium and magnesium. Ruthenium and cesium leaked before resin exhaustion. To verify and to try to find an explanation for the removal of radioactivity after hardness breakthrough, an experiment was run in which mixed fission products were passed in parallel through columns containing sodium, calcium, magnesium and iron forms of the resin. These results indicated that when tap water was at pH 2.5 the sodium form of the resin removed more activity prior to hardness breakthrough than any of the other three forms of the resin. After hardness breakthrough the decontamination with the sodium form dropped below that for the other forms. An important point to note is that the iron form of the resin did not remove strontium90. When the tap water was at pH 7.0, best results for total beta decontamination were obtained with 118 |
Resolution | 300 ppi |
Color Depth | 8 bit |
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