Advanced cement solidification system

Book · Fri Dec 31 04:00:00 EST 1993

OSTI ID:113070

Nakashima, T ^[1]; Kuribayashi, H ^[2]; Todo, F ^[3]

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1. JGC Corp., Yokohama (Japan)
2. JGC Corp., Tokyo (Japan)
3. JGC Corp., Oharai (Japan)

In order to easily and economically store and transport radioactive waste generated at nuclear power stations, it is essential to reduce the waste volume to the maximum extent. It is also necessary to transform the waste into a stable form for final disposal which will maintain its chemical and physical stability over a long period of time. For this purpose, the Advanced Cement Solidification Process (AC-process) was developed. The AC-process, which utilizes portland cement, can be applied to several kinds of waste such as boric acid waste, laboratory drain waste, incineration ash and spent ion exchange resin. In this paper, the key point of the AC-process, the pretreatment concept for each waste, is described. The AC-process has been adopted for two Japanese PWR stations: the Genkai Nuclear Power Station (Kyushu Electric Power Co.) and the Ikata Nuclear Power Station (Shikoku Electric Power Co.). Construction work has almost finished and commissioning tests are under way at both power stations.

• OSTI ID: 113070
• Report Number(s): CONF-930906--; ISBN 0-7918-0691-X
• Country of Publication: United States
• Language: English

Related Subjects

05 NUCLEAR FUELS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
ALKALINE HYDROLYSIS
ASHES
BORIC ACID
CEMENTS
CHEMICAL PROPERTIES
EXPERIMENTAL DATA
GENKAI-1 REACTOR
IKATA-2 REACTOR
ION EXCHANGE MATERIALS
NUCLEAR POWER PLANTS
PERFORMANCE
PWR TYPE REACTORS
RADIOACTIVE WASTE PROCESSING
RADIOACTIVE WASTES
SOLIDIFICATION
TECHNOLOGY ASSESSMENT
WASTE FORMS