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Title: Development of cement solidification process for sodium borate waste generated from PWR plants

Conference ·
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  1. Power and Industrial Systems Research and Development Center, Nuclear Chemical System and Process, R and D Dept., Toshiba Corporation, Kawasaki-ku, Kawasaki-shi, Kanagawa-ken, 210-0862 (Japan)

A cement solidification process for treating sodium borate waste produced in pressurized water reactor (PWR) plants was studied. To obtain high volume reduction and high mechanical strength of the waste, simulated concentrated borate liquid waste with a sodium / boron (Na/B) mole ratio of 0.27 was dehydrated and powdered by using a wiped film evaporator. To investigate the effect of the Na/B mole ratio on the solidification process, a sodium tetraborate decahydrate reagent with a Na/B mole ratio of 0.5 was also used. Ordinary portland cement (OPC) and some additives were used for the solidification. Solidified cement prepared from powdered waste with a Na/B mole ratio 0.24 and having a high silica sand content (silica sand/cement>2) showed to improved uniaxial compressive strength. (authors)

Research Organization:
American Society of Mechanical Engineers - ASME, Nuclear Engineering Division, Environmental Engineering Division, Two Park Avenue, New York, NY 10016-5990 (United States)
OSTI ID:
22535182
Resource Relation:
Conference: ICEM2013 - ASME 2013: 15. International Conference on Environmental Remediation and Radioactive Waste Management, Brussels (Belgium), 8-12 Sep 2013; Other Information: Country of input: France; 8 refs
Country of Publication:
United States
Language:
English