Journal of Nuclear Fuel Cycle and Environment
Online ISSN : 2186-7135
Print ISSN : 1884-7579
ISSN-L : 1343-4446
Volume 29, Issue 1
Displaying 1-2 of 2 articles from this issue
Technical Report
  • Misaki SEKI, Yoshitaka FUJITA, Yasuyuki FUJIHARA, Zhang, J., Hisao YOS ...
    2022 Volume 29 Issue 1 Pages 2-9
    Published: June 15, 2022
    Released on J-STAGE: June 29, 2022
    JOURNAL FREE ACCESS

      The core structural materials of the Japan Materials Testing Reactor (JMTR) are mostly stainless steel, aluminum (Al) and beryllium (Be). In the decommissioning of JMTR, radioactive miscellaneous solid wastes (waste packages) are produced. The burial criteria require that the drums do not contain any materials that would impair the integrity of the drums, and that the radioactivity of the waste packages does not exceed the amount specified in the criteria. In particular, Al generates hydrogen gas when it reacts with alkaline substances. This can cause voids to form inside the waste package, reducing its strength and increasing the internal pressure, causing the solidifier to overflow. Such a waste package will affect the safe management of the facility. The purpose of this paper was to establish a stabilization treatment technology for Al by applying the Beyer process, and the basic treatment process was established through cold tests. The Al samples were irradiated with neutrons at the Kyoto University Research Reactor (KUR) to investigate the removal characteristics of radionuclides produced by additive and impurity elements in Al by this process. As a result, it was found that Al can be converted to alumina (Al2O3) by this process, and there is a prospect that it can be solidified by cement-based filler as in the usual treatment method for radioactive waste.

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Technical Data
  • - A case study of Sweden -
    Ryo NAKABAYASHI, Daisuke SUGIYAMA, Shingo TANAKA, Kazuma KURODA
    2022 Volume 29 Issue 1 Pages 10-21
    Published: June 15, 2022
    Released on J-STAGE: June 29, 2022
    JOURNAL FREE ACCESS

      Regulatory standards for intermediate-depth disposal in Japan will require facility design based on ALARA (As Low As Reasonably Achievable) and BAT (Best Available Technique). However, there are no examples of studies that show specific measures to meet the regulatory requirements for ALARA and BAT. On the other hand, there are some examples of facility design based on ALARA and BAT in radioactive waste disposal projects in other countries. In this paper, the Swedish approach is reviewed, and the methods of presenting ALARA and BAT are discussed to apply them to radioactive waste disposal projects in Japan.

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