American Nuclear Society

Home / Store / Journals / Electronic Articles / Nuclear Technology / Volume 168 / Number 2

Development of Low-Activation Reinforced Concrete Design Methodology - I: Manufacture of Low-Activation Concrete

Masaharu Kinno, Ken-Ichi Kimura, Hirokazu Nishida, Yusuke Fujikura, Norichika Katayose, Takao Tanosaki, Koki Ichitsubo, Masaki Takimoto, Hiroichi Tomotake, Ryoetsu Yoshino, Taiichiro Mori, Katsumi Hayashi, Mikio Uematsu, Tomohiro Ogata, Mikihiro Nakata, Mitsuru Sato, Minoru Saito, Mamabu Sato, Akira Hasegawa

Nuclear Technology

Volume 168 / Number 2 / November 2009 / Pages 564-570


Member Price:$27.00
Member Savings:$3.00

Screening tests using several reactors were performed to select low-activation raw materials. The number of samples was about 1500. Detailed data were obtained on the concentrations of Co and Eu in low-activation aggregates, low-activation cements, low-activation additives, and low-activation B4C sands. After that, we manufactured various types (1/10, 1/20, 1/30, 1/50, 1/100, 1/300) of low-activation concrete. The term "1/10 low-activation" concrete denotes that the activity reduction rate to ordinary concrete is designed to be 1/10. By admixing with a boron content of [approximately]1 × 1021/cm3, the total residual radioactivity reduction rates of low-activation concrete to ordinary concrete, in units of Di/Ci (Di: concentration of radionuclide i, Ci: clearance level of radionuclide i cited from IAEA-RS-G-1.7), are estimated to range from [approximately]1/300 to 1/10 000. It was concluded that most of the shielding concrete around the advanced boiling water reactor (ABWR) or the advanced pressurized water reactor (APWR) are classified below the clearance level of decommissioning by adopting some suitable types of low-activation concrete.

Questions or comments about the site? Contact the ANS Webmaster.