Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Munakata, Masahiro; Tezuka, Hiroko*
Proceedings of 16th International Symposium on the Packaging and Transport of Radioactive Materials (PATRAM 2010) (CD-ROM), 8 Pages, 2010/10
We derived the applicable limits for surface contamination by using a model for radiation exposure based on an investigation of actual conditions of the transport in Japan. The dose limits for surface contamination were derived for each 415 nuclides which were included in the IAEA Safety Standard [IAEA, TS-R-1]. In the results, nuclide Ac-227 showed the maximum radiation dose on a package preparation and transport worker (Group A). Based on unit surface contamination (1 Bq/cm
), it was 0.48 mSv/a while that of the model in TECDOC-1449 showed 9.20 mSv/a. If 0.3 mSv/a is used as a reference dose, the applicable surface contamination limit of Ac-227 becomes 0.63 Bq/cm in this model and 0.03 Bq/cm in the TECDOC model. The contamination limit of the TECDOC model is much lower than that of this model. For other radionuclides, the derived limits by this model have a safety margin of about 1 order of magnitude against to the applicable limits derived by the model in TECDOC-1449.
Sasaki, Makoto*; Tezuka, Hiroko*
PNC TJ206 84-02, 168 Pages, 1984/06
no abstracts in English
Munakata, Masahiro; Tezuka, Hiroko*; Yokoyama, Naomi*; Matsuura, Yasutaka*
no journal, ,
In transport of radiological materials, Exposure scenario and assessment model based on a survey of transportation in Japan, was developed. Using the developed model, regulatory limits on non-fixed surface contamination for the transport was discussed.
Hashimoto, Makoto; Tezuka, Hiroko*
no journal, ,
When the nuclide specific surface contamination limit is adopted to the transport of radioactive material, an ideal procedure to control the nuclide specific surface contamination control is the radioactive quantitative analysis of smear sample. It is, however, necessary to make not only 
analysis but alpha and beta analysis of the sample and to spent much time for such analysis. It is not a practical procedure in routine transport. In this presentation, the practical procedure to evaluate the nuclide specific surface contamination with measurement of representative nuclide with consideration of circumstances of the transport package.
Munakata, Masahiro; Tezuka, Hiroko*; Matsuura, Yasutaka*
no journal, ,
no abstracts in English
