Speaker
Description
In the construction of accelerator facilities in Japan, the concrete to be placed has not been decided at the time of shielding calculations. Therefore, shielding calculations are carried out with concrete compositions selected by the designers, e.g. from ANL-5800 (USA). However, the composition is not data for concrete in Japan, and the basis for the data is also unclear.
We have been developing a standard through a working group of the Atomic Energy Society of Japan (AESJ). The concrete composition data for shielding calculation was made based on the research results of Architectural Institute of Japan.
The concrete composition data defined two types of concrete composition: concrete using Si-based aggregates (andesite and sandstone) often used in Japan, and concrete using Ca-based aggregates (limestone).
The application of the concrete composition data is accelerator facilities below 20MeV (such as PET facilities). Accelerators with 20 MeV or more will be handled separately. This composition is not only applicable in accelerator facilities, but also in nuclear facilities and RI handling facilities.
Because the amount of moisture in concrete changes with wall thickness and age, a compositional correction equation for moisture was also established. Furthermore, in Japan, since the density of concrete is specified by customers in some cases, the correction formula of composition for density was also determined.
When the concrete to be placed is clear, the composition data actually analyzed may be used.
The developed concrete composition data will be published as the Atomic Energy Society of Japan standards.
| Topics | T4. Shielding and dosimetry |
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