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Development of Low-Activation Reinforced Concrete Design Methodology - II: Concrete Activation Analyses of BWR/PWR

Katsumi Hayashi, Shigeki Nemezawa, Motoi Tanaka, Mikio Uematsu, Tomohiro Ogata, Mikihiro Nakata, Katsuyoshi Yamaguchi, Masaharu Kinno, Ken-Ichi Kimura, Takao Tanosaki, Ryoetsu Yoshino, Mitsuru Sato, Minoru Saito, Akira Hasegawa

Nuclear Technology

Volume 168 / Number 2 / November 2009 / Pages 571-575


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A precise method for estimating residual radioactivity and decommissioning cost is indispensable when deciding whether to adopt low-activation material. For this precise estimation, accurate estimation of both the thermal neutron flux and the activation cross section of the structural material is necessary. We developed a new groupwise cross-section library that has ten thermal groups for SN transport calculation and activation calculation. These libraries are tested and used for advanced boiling water reactor (ABWR) and advanced pressurized water reactor (APWR) activation analyses.

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