A high performance cement for solidification of spent ion-exchange resin

Book · Fri Dec 31 00:00:00 EST 1993

OSTI ID:113069

Kikuchi, M; Matsuda, M; Nishi, T ^[1]; Tamata, S; Izumida, T ^[2]

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1. Energy Research Lab., Hitachi, Ibaraki (Japan)
2. Hitachi Works, Ibaraki (Japan)

A high performance cement has been developed to improve ion-exchange resin embedding in cement-based materials. The cement mainly consists of slag cement, reinforcing carbon fiber and natural zeolite. The fiber allowed waste loading to be increased from 25 to 60kg-dry resin/200 liters. The zeolite, whose main constituent was clinoptilolite, reduced cesium leachability from the waste form to about 1/10. Laboratory- and full-scale experiments were performed to estimate properties of the waste form, using simulated spent ion-exchange resin. Emphasis was laid on such long-term properties as radiation stability and water resistance.

• OSTI ID: 113069
• Report Number(s): CONF-930906-; ISBN 0-7918-0691-X; TRN: 95:022370
• Resource Relation: Conference: `93 international conference on nuclear waste management and environmental remediation, Prague (Czech Republic), 5-11 Sep 1993; Other Information: PBD: 1993; Related Information: Is Part Of Proceedings of the 1993 international conference on nuclear waste management and environmental remediation. Volume 3: Environmental remediation and environmental management issues; Baschwitz, R.; Kohout, R.; Marek, J.; Richter, P.I.; Slate, S.C. [eds.]; PB: 919 p.
• Country of Publication: United States
• Language: English

Related Subjects

05 NUCLEAR FUELS
ION EXCHANGE MATERIALS
SOLIDIFICATION
CEMENTS
PERFORMANCE
WASTE FORMS
LEACHING
CORROSION RESISTANCE
RADIOACTIVE WASTE PROCESSING
TECHNOLOGY ASSESSMENT
LOADING RATE
COMPRESSION STRENGTH
RADIATION EFFECTS
CARBON 14
COBALT 60
STRONTIUM 90
TECHNETIUM 99
IODINE 129
CESIUM 137
EXPERIMENTAL DATA