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:10.13182/NT09-A9245

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

ENG - Quantum Science and Energy Engineering

Research output: Contribution to journal › Article › peer-review

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 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.

Original language	English
Pages (from-to)	571-575
Number of pages	5
Journal	Nuclear Technology
Volume	168
Issue number	2
DOIs	https://doi.org/10.13182/NT09-A9245
Publication status	Published - 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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10.13182/NT09-A9245

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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

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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.",

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

year = "2009",

month = nov,

doi = "10.13182/NT09-A9245",

language = "English",

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T2 - Concrete activation analyses of BWR/PWR

AU - Hayashi, Katsumi

AU - Nemezawa, Shigeki

AU - Tanaka, Motoi

AU - Uematsu, Mikio

AU - Ogata, Tomohiro

AU - Nakata, Mikihiro

AU - Yamaguchi, Katsuyoshi

AU - Kinno, Masaharu

AU - Kimura, Ken Ichi

AU - Tanosaki, Takao

AU - Yoshino, Ryoetsu

AU - Sato, Mitsuru

AU - Saito, Minoru

AU - Hasegawa, Akira

PY - 2009/11

Y1 - 2009/11

N2 - 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.

AB - 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.

KW - DORT

KW - MATXSLIB-J33T10

KW - Residual radioactivity

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Development of low-activation reinforced concrete design methodology-II: Concrete activation analyses of BWR/PWR

Abstract

Keywords

ASJC Scopus subject areas

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