Properties of radioactive wastes and waste containers. Quarterly progress report, October-December 1979. [Solidification of boric acid waste; impact of urea-formaldehyde waste forms]
Experiments were conducted to establish appropriate waste/binder ratios within which boric acid (simulated reactor waste) may be incorporated into portland type III cement to produce acceptable waste form. Both pH-adjusted and pH-unadjusted boric acid solutions were used. NaOH was used to adjust the boric acid pH. Data are reported for 3, 6, and 12 wt % boric acid wastes, with pH-adjusted values of 7, 10, and 12. Range of waste/binder ratios investigated are from 0.3 to 1.5. Results show: (a) pH-unadjusted 12 wt % boric acid waste (typical reactor waste concentration) does not solidify without neutralization with NaOH at waste/binder ratios investigated, (b) boric acid waste neutralized with NaOH, before solidification, requires shorter cure time compared with pH-unadjusted waste, and (c) the amount of pH adjustment, of boric acid with NaOH, needed to assure satisfactory solidification is a variable related to boric acid concentration in the waste. Impact tests were performed on urea-formaldehyde waste forms containing simulated BWR precoat filter cake in diatomaceous earth. Impact energies of 7.85, 15.7, and 31.4 joules were used. Data are provided, in graphical form, for formulations with waste/binder ratios of 1.6, 2.0, and 2.4. Results show: (a) higher impact loadings generate greater number of particulates in all size ranges, and (b) waste forms with higher waste/binder ratio produce greater number of particulate for a given impact loading. 8 figures, 7 tables.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- EY-76-C-02-0016
- OSTI ID:
- 5602282
- Report Number(s):
- NUREG/CR-1326; BNL-NUREG-51148
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
BINDERS
BORIC ACID
FORMALDEHYDE
ORGANIC POLYMERS
PORTLAND CEMENT
RADIOACTIVE WASTE PROCESSING
SOLIDIFICATION
RADIOACTIVE WASTES
IMPACT TESTS
RESEARCH PROGRAMS
SODIUM HYDROXIDES
SOLID WASTES
SOLUTIONS
UREA
ALDEHYDES
ALKALI METAL COMPOUNDS
AMIDES
BUILDING MATERIALS
CARBONIC ACID DERIVATIVES
CEMENTS
DISPERSIONS
HYDROGEN COMPOUNDS
HYDROXIDES
INORGANIC ACIDS
MANAGEMENT
MATERIALS
MATERIALS TESTING
MECHANICAL TESTS
MIXTURES
ORGANIC COMPOUNDS
ORGANIC NITROGEN COMPOUNDS
OXYGEN COMPOUNDS
PHASE TRANSFORMATIONS
POLYMERS
PROCESSING
RADIOACTIVE MATERIALS
SODIUM COMPOUNDS
TESTING
WASTE MANAGEMENT
WASTE PROCESSING
WASTES
052000* - Nuclear Fuels- Waste Management