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

研究成果: Article査読

抄録

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.

本文言語English
ページ(範囲)571-575
ページ数5
ジャーナルNuclear Technology
168
2
DOI
出版ステータスPublished - 2009 11

ASJC Scopus subject areas

  • 核物理学および高エネルギー物理学
  • 原子力エネルギーおよび原子力工学
  • 凝縮系物理学

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