TY - GEN
T1 - Discussion on the standardization of concrete composite for radiation shielding design I - Concept of standard concrete for radiation shielding
AU - Kimura, Ken Ichi
AU - Ogata, Tomohiro
AU - Nakata, Mikihiro
AU - Shigyo, Nobuhiro
AU - Hirao, Yoshihiro
AU - Sakamoto, Yukio
N1 - Copyright:
Copyright 2017 Elsevier B.V., All rights reserved.
PY - 2017
Y1 - 2017
N2 - Concrete is widely used as radiation shield in nuclear reactors and irradiation facilities, because of its flexibility and sufficient supply. However, there are few discussions on the content of the shielding concrete composition, and very old data (which have uncertain information regarding material properties beside of elemental data) are still used in the shielding calculation. So, we organized "Radiation Shielding Material Standardization Working Group under Atomic Energy Society of Japan (AESJ) in order to proceed the standardization of shielding concrete. In this paper, the concept of standard concrete for radiation shield is proposed based on the building material aspects, such as mixture proportion, ratio of water to cement, cement hydration and so on. Furthermore, a few candidates of the standard concrete are listed from various data for raw materials of concrete (aggregate and cement). Based on the above trial introduction of the standard concrete, some sensitivity analyses were conducted for simple cylindrical geometry with proton beam incidence on an iron target. The investigation indicated that the proposed trail standard data located intermediate positions among other concrete data and water contents in the concrete were dominant for the dose attenuation.
AB - Concrete is widely used as radiation shield in nuclear reactors and irradiation facilities, because of its flexibility and sufficient supply. However, there are few discussions on the content of the shielding concrete composition, and very old data (which have uncertain information regarding material properties beside of elemental data) are still used in the shielding calculation. So, we organized "Radiation Shielding Material Standardization Working Group under Atomic Energy Society of Japan (AESJ) in order to proceed the standardization of shielding concrete. In this paper, the concept of standard concrete for radiation shield is proposed based on the building material aspects, such as mixture proportion, ratio of water to cement, cement hydration and so on. Furthermore, a few candidates of the standard concrete are listed from various data for raw materials of concrete (aggregate and cement). Based on the above trial introduction of the standard concrete, some sensitivity analyses were conducted for simple cylindrical geometry with proton beam incidence on an iron target. The investigation indicated that the proposed trail standard data located intermediate positions among other concrete data and water contents in the concrete were dominant for the dose attenuation.
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M3 - Conference contribution
AN - SCOPUS:85036453936
T3 - 2017 International Congress on Advances in Nuclear Power Plants, ICAPP 2017 - A New Paradigm in Nuclear Power Safety, Proceedings
BT - 2017 International Congress on Advances in Nuclear Power Plants, ICAPP 2017 - A New Paradigm in Nuclear Power Safety, Proceedings
PB - International Congress on Advances in Nuclear Power Plants, ICAPP
T2 - 2017 International Congress on Advances in Nuclear Power Plants: A New Paradigm in Nuclear Power Safety, ICAPP 2017
Y2 - 24 April 2017 through 28 April 2017
ER -