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

Research output: Contribution to journalArticle

Abstract

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.

Original languageEnglish
Pages (from-to)571-575
Number of pages5
JournalNuclear Technology
Volume168
Issue number2
DOIs
Publication statusPublished - 2009 Nov

Keywords

  • DORT
  • MATXSLIB-J33T10
  • Residual radioactivity

ASJC Scopus subject areas

  • Nuclear and High Energy Physics
  • Nuclear Energy and Engineering
  • Condensed Matter Physics

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    Hayashi, K., Nemezawa, S., Tanaka, M., Uematsu, M., Ogata, T., Nakata, M., Yamaguchi, K., Kinno, M., Kimura, K. I., Tanosaki, T., Yoshino, R., Sato, M., Saito, M., & Hasegawa, A. (2009). Development of low-activation reinforced concrete design methodology-II: Concrete activation analyses of BWR/PWR. Nuclear Technology, 168(2), 571-575. https://doi.org/10.13182/NT09-A9245