Tests of Cs-137 removal from DWPF samples prior to analysis
The Defense Waste Processing Facility (DWPF) will be used to encapsulate high-level radioactive waste into borosilicate glass at the Savannah River Site. To ensure that the process streams will be blended in the right proportions to produce durable glass, process control analyses will be performed in a laboratory in the DWPF. The high radioactivity of DWPF samples will require that sample preparation, including dissolution and dilution of samples, be performed in shielded cells. However the final analyses will be made with instruments and spectrometers contained in unshielded fume hoods. The primary radiation concern is the exposure to y-rays from the decay of Cs-137 after samples are removed from the shielded cells. Since there are several methods available for removing Cs-137 from samples, investigations were made into removing Cs-137 from DWPF samples prior to analysis in order to reduce worker exposure. Results are presented of the efficiency of various Cs-137 removal techniques and the effects of these techniques on analytical precision and accuracy.
- Research Organization:
- Westinghouse Savannah River Co., Aiken, SC (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC09-89SR18035
- OSTI ID:
- 10110497
- Report Number(s):
- WSRC-MS-94-0590; CONF-940813-34; ON: DE95005006
- Resource Relation:
- Conference: 208. American Chemical Society (ACS) national meeting,Washington, DC (United States),21-26 Aug 1994; Other Information: PBD: 10 Nov 1994
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
37 INORGANIC
ORGANIC
PHYSICAL AND ANALYTICAL CHEMISTRY
CESIUM 137
REMOVAL
HIGH-LEVEL RADIOACTIVE WASTES
VITRIFICATION
SAVANNAH RIVER PLANT
RADIOACTIVE WASTE PROCESSING
BOROSILICATE GLASS
RADIOCHEMICAL ANALYSIS
BENCH-SCALE EXPERIMENTS
052001
400105
WASTE PROCESSING
SEPARATION PROCEDURES