Design methodology for reinforced concrete of nuclear power plants to reduce radioactive wastes in decommission phase has been developed. To realize this purpose, (1) development of raw materials database of cements, aggregates and steel bars on concentration of radioactive target elements, (2) trial production of low activation cements and steel bars based on the material database developed in (1), and (3) development of tools for estimation and prediction of the amount of radioactive elements in reactor shielding walls have been carried out. Radioactive analysis showed that Co and Eu were the major target elements which decide the radioactivity level of reinforced concrete from wide survey of raw materials for concrete (typically aggregates and cements). Material database for the contents of Co and Eu was developed based on the chemical analysis and radioactivation analysis. Upon the above survey and execution expreiment of concrete, six types of low-activation concrete are proposed for various radioactive portion in the plant. These concrete have a 1/10 – 1/300 rasioactivity compare to the ordinary concrete, which are assumed the concrete with Andesite aggregate and ordinary Portland cement. Baed on the above data base, it was clarified that the low activation cement would be successfully manufactured by adequate selection of raw materials. The prospect to produce the low-heat portland cement which would have a 1/3 radioactivity in comparison with conventioanl cements obtained by means of selection of limestone and natural gypsum. An attempte was carried out to produece low activation heavy-mortar which would have radioactivity below the clearance level when using at the radiation shielding wall of BWR. Characterization and optimization of consturction conditions with new additives have also been carried out. These two new raw materials for low-activation concrete are conducted in pre-manufacture size, and over the laboratry level. Boron added low-activation concrete are also carried out as extreamly high performance low-activation concrete. It was claryfied that the accurcy of calculation results of the radioactivity evaluation was very high compared to available benchmark calculation for the JPDR and commercial light water reactor. The specification of the mapping system for judging the activation classification was also developed by using the general-purpose radio activation calculation tool. This work is supported by a grant-in-aid of Innovative and Viable Nuclear Technology (IVNET) development project of Ministry of Economy, Trade and Industry, Japan.
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16th International Conference on Nuclear Engineering
May 11–15, 2008
Orlando, Florida, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-4814-0
PROCEEDINGS PAPER
Development of Low-Activation Design Method for Reduction of Radioactive Waste Below Clearance Level Available to Purchase
Ken-Ichi Kimura,
Ken-Ichi Kimura
Fujita Corporation, Tomakomai, Hokkaido, Japan
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Akira Hasegawa,
Akira Hasegawa
Tohoku University, Sendai, Miyagi, Japan
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Katsumi Hayashi,
Katsumi Hayashi
Hitachi GE Nuclear Energy, Ltd., Ibaraki, Japan
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Tomohiro Ogata,
Tomohiro Ogata
Mitsubishi Heavy Industries, Japan
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Takao Tanosaki,
Takao Tanosaki
Taiheiyo Cement Corporation, Tokyo, Japan
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Ryoetsu Yoshino,
Ryoetsu Yoshino
Denki Kagaku Kogyo K. K., Tokyo, Japan
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Mituru Sato,
Mituru Sato
Nippon Steel Technoresearch Corp., Higashi, Ibaraki, Japan
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Minoru Saito,
Minoru Saito
Tohoku Electric Power Co., Inc., Sendai, Japan
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Masaharu Kinno
Masaharu Kinno
Fujita Corporation, Tomakomai, Hokkaido, Japan
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Ken-Ichi Kimura
Fujita Corporation, Tomakomai, Hokkaido, Japan
Akira Hasegawa
Tohoku University, Sendai, Miyagi, Japan
Katsumi Hayashi
Hitachi GE Nuclear Energy, Ltd., Ibaraki, Japan
Mikio Uematsu
Toshiba Corporation, Japan
Tomohiro Ogata
Mitsubishi Heavy Industries, Japan
Takao Tanosaki
Taiheiyo Cement Corporation, Tokyo, Japan
Ryoetsu Yoshino
Denki Kagaku Kogyo K. K., Tokyo, Japan
Mituru Sato
Nippon Steel Technoresearch Corp., Higashi, Ibaraki, Japan
Minoru Saito
Tohoku Electric Power Co., Inc., Sendai, Japan
Masaharu Kinno
Fujita Corporation, Tomakomai, Hokkaido, Japan
Paper No:
ICONE16-48484, pp. 617-626; 10 pages
Published Online:
June 24, 2009
Citation
Kimura, K, Hasegawa, A, Hayashi, K, Uematsu, M, Ogata, T, Tanosaki, T, Yoshino, R, Sato, M, Saito, M, & Kinno, M. "Development of Low-Activation Design Method for Reduction of Radioactive Waste Below Clearance Level." Proceedings of the 16th International Conference on Nuclear Engineering. Volume 1: Plant Operations, Maintenance, Installations and Life Cycle; Component Reliability and Materials Issues; Advanced Applications of Nuclear Technology; Codes, Standards, Licensing and Regulatory Issues. Orlando, Florida, USA. May 11–15, 2008. pp. 617-626. ASME. https://doi.org/10.1115/ICONE16-48484
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