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

Conference · Mon Jul 01 04:00:00 EDT 2013

DOI:https://doi.org/10.1115/ICEM2013-96324· OSTI ID:22535182

Okabe, Hirofumi; Sato, Tatsuaki; Shoji, Yuichi; Haruguchi, Yoshiko; Kaneko, Masaaki; Saso, Michitaka; Toyohara, Masumitsu ^[1]

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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
• Country of Publication: United States
• Language: English

Related Subjects

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
36 MATERIALS SCIENCE
BORATES
BORON
COMPRESSION STRENGTH
LIQUID WASTES
PORTLAND CEMENT
POWDERS
PWR TYPE REACTORS
SILICA
SODIUM COMPOUNDS
SOLIDIFICATION