skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Development of ultrafiltration and inorganic adsorbents for reducing volumes of low-level and intermediate-level liquid waste: October--December 1977

Abstract

The exposures of noncellulosic ultrafiltration membranes to a radioactive environment simulating up to 24 months of exposure to a ..beta.. dose of 10 ..mu..Ci/cm/sup 3/, a ..gamma.. dose of 10/sup -5/ ..mu..Ci/cm/sup 3/, and an ..cap alpha.. dose of 4.9 x 10/sup -3/ ..mu..Ci/cm/sup 3/ were completed. Exposure to ..beta.. and ..gamma.. radiation did not affect membrane performance. After a simulated six months of exposure to ..cap alpha.. radiation some degradation of membrane performance occurred. Several experiments were made on a laboratory-scale reverse-osmosis unit using the product from ultrafiltration as feed. Rejection of activity ranged from 88 to 99 percent. The ''continuous'' ultrafiltration pilot run was completed. Approximately 40,000 gal were processed in over 70 hr of operating time without shutdown for cleaning. Flux and rejection were maintained relatively steady over this period. Rejection of gross alpha ranged from 80 to 99.5 percent depending on the ionic content of the waste stream. Flux rates ranged from 5 to 8 liters/min over this period. The engineering column tests were continued using uranium-233 with product from the ultrafiltration pilot plant. Flow rates and pH were varied in order to determine optimum operating conditions.

Authors:
; ;
Publication Date:
Research Org.:
Mound Lab., Miamisburg, Ohio (USA)
OSTI Identifier:
5150672
Report Number(s):
MLM-2503
TRN: 78-007304
DOE Contract Number:
EY-76-C-04-0063
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; RADIOACTIVE WASTE PROCESSING; ADSORPTION; LIQUID WASTES; ULTRAFILTRATION; INTERMEDIATE-LEVEL RADIOACTIVE WASTES; LOW-LEVEL RADIOACTIVE WASTES; MEMBRANES; OSMOSIS; PILOT PLANTS; RESEARCH PROGRAMS; FUNCTIONAL MODELS; MANAGEMENT; PROCESSING; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; SEPARATION PROCESSES; SORPTION; WASTE MANAGEMENT; WASTE PROCESSING; WASTES; 052001* - Nuclear Fuels- Waste Processing

Citation Formats

Koenst, J.W., Herald, W.R., and Roberts, R.C.. Development of ultrafiltration and inorganic adsorbents for reducing volumes of low-level and intermediate-level liquid waste: October--December 1977. United States: N. p., 1978. Web. doi:10.2172/5150672.
Copy to clipboard
Koenst, J.W., Herald, W.R., & Roberts, R.C.. Development of ultrafiltration and inorganic adsorbents for reducing volumes of low-level and intermediate-level liquid waste: October--December 1977. United States. doi:10.2172/5150672.
Copy to clipboard
Koenst, J.W., Herald, W.R., and Roberts, R.C.. Fri . "Development of ultrafiltration and inorganic adsorbents for reducing volumes of low-level and intermediate-level liquid waste: October--December 1977". United States. doi:10.2172/5150672. https://www.osti.gov/servlets/purl/5150672.
Copy to clipboard
@article{osti_5150672,
title = {Development of ultrafiltration and inorganic adsorbents for reducing volumes of low-level and intermediate-level liquid waste: October--December 1977},
author = {Koenst, J.W. and Herald, W.R. and Roberts, R.C.},
abstractNote = {The exposures of noncellulosic ultrafiltration membranes to a radioactive environment simulating up to 24 months of exposure to a ..beta.. dose of 10 ..mu..Ci/cm/sup 3/, a ..gamma.. dose of 10/sup -5/ ..mu..Ci/cm/sup 3/, and an ..cap alpha.. dose of 4.9 x 10/sup -3/ ..mu..Ci/cm/sup 3/ were completed. Exposure to ..beta.. and ..gamma.. radiation did not affect membrane performance. After a simulated six months of exposure to ..cap alpha.. radiation some degradation of membrane performance occurred. Several experiments were made on a laboratory-scale reverse-osmosis unit using the product from ultrafiltration as feed. Rejection of activity ranged from 88 to 99 percent. The ''continuous'' ultrafiltration pilot run was completed. Approximately 40,000 gal were processed in over 70 hr of operating time without shutdown for cleaning. Flux and rejection were maintained relatively steady over this period. Rejection of gross alpha ranged from 80 to 99.5 percent depending on the ionic content of the waste stream. Flux rates ranged from 5 to 8 liters/min over this period. The engineering column tests were continued using uranium-233 with product from the ultrafiltration pilot plant. Flow rates and pH were varied in order to determine optimum operating conditions.},
doi = {10.2172/5150672},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Feb 24 00:00:00 EST 1978},
month = {Fri Feb 24 00:00:00 EST 1978}
}
Copy to clipboard
Technical Report:
View Technical Report (0.93 MB)
DOI:  10.2172/5150672
Save / Share:
Export Metadata
Save to My Library
You must Sign In or Create an Account in order to save documents to your library.

  • The objective of this program is to develop and demonstrate separation methods for removing radionuclides from liquid process waste streams. As part of this program, Mound Laboratory will develop lower cost alternatives for use i n1980 fuel reprocessing and waste solidification plants, evaluate the processes within the nuclear fuel cycle which contribute to low-level and intermediate-level waste, and determine the feasibility of ultrafiltration, reverse osmosis, inorganic adsorbents and other separation concepts as additions to process design to reduce the generation of this type of waste. In the initial phase of this program, membrane equipment will be obtained from a commercialmore » membrane manufacturer. After the pilot plant is installed, it will be checked out on cold feed in order to obtain initial flux and rejection data for comparison to data obtained later in the program. After completion of the cold tests, the membrane pilot plant will be run on a combined contaminated feed emanating from showers, laboratory drains, janitorial sinks and decontamination in processing areas, as well as a laundry waste stream containing alpha-contaminated wastes. This combined waste stream contains only alpha contamination (uranium and plutonium). However, as part of this program, gamma activity will be added to the waste stream. These wastes will be representative of those streams found at fuel reprocessing plants, as well as various ERDA processing facilities such as Mound, LASL, Hanford, and Rocky Flats. For the second part of the program, laboratory tests will be run on various adsorbents to evaluate their capacities for removing radionuclides. As part of this program, a technique for screening adsorbents developed at Mound Laboratory will be utilized.« less

  • ; ;
    The ultrafiltration (UF) pilot system is being evaluated at Mound Facility. The effect of pressure drop, temperature, and pH of the feed on system performance has been studied. The system has been run through a number of cleaning cycles including tap water flush, enzyme soak, detergent wash, and citric acid/oxalic acid wash. A continuous run was started on waste from the Waste Processing Facility; about 11,500 gal has been processed. Studies to determine the effect of (..cap alpha.., ..beta.., and ..gamma..) radiation on membrane characteristics were initiated. The small laboratory column tests were completed. Isotherms were run on several inorganicmore » adsorbents, including titanium phosphate and sodium titanate. Tests were continued on the Engineering Test Ion Exchange System. Waste solution from the Waste Processing Facility spiked with plutonium-238 and ultrafiltration product spiked with uranium-233 were used as feeds. 6 tables, 1 figure.« less

  • ; ;
    Ultrafication (UF) membranes have demonstrated 90 to 98% rejection of gross alpha in laboratory tests. In the treatment of laundry wastes, rejection of activity ranged from 98 to 99.9% gross alpha. The pilot UF system was installed and started up. Flux decline curves and volume reduction performance were determined. Volume reductions of 210 : 1 were achieved at flux rates of 1.1 gal/min (system is rated at 2 to 3 gal/min, 90% recovery) at activity rejection of 99.94% gross alpha. Adsorbent studies demonstrated capacities in excess of 10/sup 9/ dis/min/g for uranium-233 and in excess of 10/sup 8/ dis/min/g formore » plutonium-238. Construction and start-up of the Engineering Test Facility has been completed.« less

  • ;
    A series of runs was performed in which waste processing facility influent was spiked with americium-241, neptunium-237, and uranium-233 and run through the ultrafiltration and reverse osmosis (RO) units. The results of these experiments show that the ultrafiltration membranes are ionic dependent, whereas the RO unit is not. Membrane irradiation studies have been started. Continuous run parameters are being verified through a series of experiments. The small laboratory column tests were continued this quarter on several adsorbents. Decontamination factors were calculated for these adsorbents in removing neptunium-237 and americium-241 from waste solutions. Tests were continued with the 2-in. Engineering Columnsmore » using ultrafiltration product spiked with uranium-233. A 6-in. diameter column was installed in the combined raffinate line from the three Engineering Columns. This ''mixed bed'' column will polish the waste solution that is returned to the waste processing facility tanks. A quality control program was started this quarter.« less

  • ; ;
    Solution processed through the ultrafiltration system was spiked with either uranium-233, neptunium-237, or plutonium 238. This solution was then pumped through the 2-in. diameter columns contained in the engineering pilot plant. Bone char was the best adsorber tested with both uranium (DF 145.6 at pH 6.5) and neptunium (DF 952.9 at pH 10). The adsorber IRA-938 had a DF of 220.9 at pH 7.4 in removing plutonium from solution. Closed system concentration runs were performed on the UF system. The results of these runs show that rejection of activity remains very good even though suspended solids and radiation levels ofmore » the feed increase dramatically during the course of the run. Also, sponge-ball cleaning techniques were demonstrated. The results of these experiments show that sponge-ball cleaning may be a workable alternative to detergent cleaning. Viscosity studies were begun this quarter. All 84 membranes have been subjected to the experimental radiation exposures, about half have been dissolved in solvent, and viscosity data are now being obtained.« less