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Japan Atomic Energy Agency; National Institute of Radiological Sciences*
JAEA-Review 2015-007, 50 Pages, 2015/10
JAEA-Review-2015-007.pdf:3.2MB
The review of the evacuation area due to the accident of TEPCO Fukushima Daiichi Nuclear Power Station has completed and the deregulation has begun in some regions. The authors started this research in order to contribute to the understanding of individual dose that is assumed after the return of the residents. Measurements and evaluation using personal dosemeters were conducted at the typical living locations in the area where the evacuation orders are ready to be lifted and the residence restriction area. So the relationship between air dose and personal dose equivalent there was demonstrated observationally and experimentally. In addition, the estimation of the residents' individual doses in the pattern of their social lives expected after returning home.
Japan Atomic Energy Agency; Federation of Electric Power Companies of Japan*
JAEA-Review 2007-010, 26 Pages, 2007/03
JAEA-Review-2007-010.pdf:4.0MB
JAEA-Review-2007-010-appendix(CD-ROM).zip:45.44MB
In order to promote the establishment of a regulatory framework and the implementation of TRU waste disposal, the Federation of Electric Power Companies of Japan (FEPC) and the Japan Nuclear Cycle Development Institute (now JAEA) collaborated and published a progress report in Japanese (hereafter TRU-2) in September 2005. The report here is an English version of TRU-2 and has been published to widely inform overseas researchers and engineers of the contents of TRU-2. In this report, the characteristics of TRU waste generated from the nuclear fuel cycle in Japan and its disposal concept are shown. The design of the TRU waste disposal facility was evaluated and safety assessments were carried out to show that safety could be validated by comparing with regulatory guidelines in overseas performance assessment reports. Alternative technologies were developed to deal with various geological environments and to improve safety margins in addition to evaluating other disposal concepts. Furthermore, optimisation through co-location disposal of TRU waste and high level radioactive waste was investigated, and an example layout of a co-location disposal concept was evaluated. Based on these evaluation results, future issues and outstanding items on research and development for TRU waste disposal are summarised.