Kanako Toda , Lang Lang , Takumi Saito , Kazuto Endo , Kazuo Yamada , Yasumasa Tojo
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引用次数: 0
Abstract
The melting fly ash (MFA) stored in the Interim Storage Facility in Fukushima, Japan, contains concentrated Cs, requiring stabilization for final disposal. This study investigates the physical properties to evaluate the feasibility of the MFA conditioning with B-type Portland blast furnace slag (BFS) cement and Na/K-activated metakaolin-based geopolymers (NaGP and KGP), with the evaluation of the Cs leaching behavior from solidified forms. Because of the difference in flowability, the volume of the solidified MFA waste can be remarkably reduced by a factor of 2.4 to 2.6 by selecting NaGP or KGP, respectively, compared to BFS cement. MFA incorporation into the cementitious materials reduced the uniaxial compressive strength (UCS), though the UCS values were large enough for the final disposal in Japan.
In ultra-pure water, the Cs cumulative leached fraction (CLF) is significantly lower for geopolymers, followed by BFS cement. Although model MFA contained KCl and NaCl, geopolymers showed better performance at Cs immobilization than BFS cement. In seawater leaching, CLF of Cs exhibits no significant differences among the matrices, likely due to an increase of Cs leaching in GPs by cation exchange. Matrix choice can influence the Cs leaching behavior of solidified MFA, especially in dilute leachate environments. The Cs immobilization ability of MFA solidified with BFS cement, NaGP, and KGP met the requirement set forth by the U.S. Nuclear Regulatory Commission.
期刊介绍:
Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology.
Fundamentals of Reactor Design include:
• Thermal-Hydraulics and Core Physics
• Safety Analysis, Risk Assessment (PSA)
• Structural and Mechanical Engineering
• Materials Science
• Fuel Behavior and Design
• Structural Plant Design
• Engineering of Reactor Components
• Experiments
Aspects beyond fundamentals of Reactor Design covered:
• Accident Mitigation Measures
• Reactor Control Systems
• Licensing Issues
• Safeguard Engineering
• Economy of Plants
• Reprocessing / Waste Disposal
• Applications of Nuclear Energy
• Maintenance
• Decommissioning
Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.