Development of low-activation design method for reduction of radioactive waste below clearance level

Ken Ichi Kimura, Katsumi Hayashi, Tomohiro Ogata, Ryoetsu Yoshino, Minoru Saito, Akira Hasegawa, Mikio Uematsu, Takao Tanosaki, Mituru Sato, Masaharu Kinno

Research output: Chapter in Book/Report/Conference proceedingConference contribution

2 Citations (Scopus)


Design methodology for reinforced concrete of nuclear power plants to reduce radioactive wastes in decommission phase has been developed. To realize this purpose, (I) 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 bascd on thc 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 radioaetivation 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 convcntioanl cements obtained by means of selection of limestone and natural gypsum. An attempte was carried out to producce low activation heavy-mortar which would have radioactivity below the clearance level when using at the radiation shiclding wall of BWR. Characterization and optimization of eonsturction 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 perfoniianee 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.

Original languageEnglish
Title of host publication2008 Proceedings of the 16th International Conference on Nuclear Engineering, ICONE16
Number of pages10
Publication statusPublished - 2008
Event16th International Conference on Nuclear Engineering, ICONE16 2008 - Orlando, FL, United States
Duration: 2008 May 112008 May 15

Publication series

NameInternational Conference on Nuclear Engineering, Proceedings, ICONE


Other16th International Conference on Nuclear Engineering, ICONE16 2008
Country/TerritoryUnited States
CityOrlando, FL

ASJC Scopus subject areas

  • Nuclear Energy and Engineering


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