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

doi:dx.doi.org/10.13182/NT09-A9245

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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

Shielding Materials / Special Issue on the 11th International Conference on Radiation Shielding and the 15th Topical Meeting of the Radiation Protection and Shielding Division (Part 2) / Radiation Measurements and Instrumentation / dx.doi.org/10.13182/NT09-A9245

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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 S_N 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.