Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Miwa, Kazuji; Shimada, Taro; Takeda, Seiji
Progress in Nuclear Science and Technology (Internet), 6, p.166 - 170, 2019/01
In this study, in order to validate the restricted use of recycling material at the reference radiocesium concentration (determined in series report (1)), we evaluated worker annual doses, air dose rate at the site boundary and impact of migrated radiocesium into groundwater. Firstly, we evaluated the additional annual dose for workers, on the assumption that typical workers coming in contact with the source after construction (Road: 1.2 mSv/y, Building: 1.3 mSv/y). Secondly, we evaluated the air dose rates by distance from road and building including recycling material, and investigated the distance for not exceeding 1 mSv/y (including additional dose rate by recycling and background dose rate of 0.6 mSv/y) at the site boundary (Road: 25 m, Building: 1 m). Thirdly, we evaluated the Cs migration in groundwater, and investigated the distance required for satisfying the operation target value (
Cs: 1 Bq/L, 
Cs: 1 Bq/L) at the boundary (coastal line) (Road: 10 m, Building: 10 m).
Takeda, Seiji
Str
levern Rappot 2018:4 (Internet), p.62 - 64, 2018/04
The widespread environment was contaminated by radioactive cesium discharged by the severe accident of the Fukushima Daiichi Nuclear Power Station. Decontamination measures have been implemented extensively, resulting in the generation of large volume of decontamination soil that has been placed in temporary storage. To reduce the volume of decontamination soil, it can be effective to recycle the soil as construction material. This report shows the concept of safety assessment method for recycle to public projects in which the management system and allocation of responsibility are clarified, scenario construction and parameter selection, and also the results of safe assessment for the recycle to coastal levees.
Otaki, Kiyoshi*; Tanaka, Yoji*; Katsurai, Kiyomichi*; Aoki, Kazuo*
JAERI-Review 2005-035, 79 Pages, 2005/09
JAERI-Review-2005-035.pdf:4.57MB
In order to collect technical information for the assessment on future nuclear power reactors and fuel cycle systems in Japan, investigation has been made on the characteristics and performance of future reactor options including reduced moderation water reactors (RMWRs) and their fuel cycle systems since the fiscal year 1998. The subjects of investigation are divided into three categories; breeder reactors and their fuel cycle, alternative to sodium-cooled FBR systems,plutonium recycling, spent fuel reprocessing and waste disposal. This report is a summary of the investigation carried out so far.
Sakamoto, Shinichi; Meigo, Shinichiro; Konno, Chikara; Kai, Tetsuya; Kasugai, Yoshimi; Harada, Masahide; Fujimori, Hiroshi*; Kaneko, Naokatsu*; Muto, Suguru*; Ono, Takehiro*; et al.
JAERI-Tech 2004-020, 332 Pages, 2004/03
JAERI-Tech-2004-020.pdf:17.93MB
One of the experimental facilities in Japan Proton Accelerator Research Complex (J-PARC) is the Materials and Life Science Experimental Facility (MLF), where high-intensity neutron beams and muon beams are used as powerful probes for materials science, life science and related engineering. The neutrons and muons are generated with high-intensity proton beam from 3-GeV rapid cycling synchrotron (RCS). The high-intensity proton beam has to be effectively transported, and a neutron production target and a muon production target have to be also properly irradiated. The principal design of the 3-GeV proton beam transport facility (3NBT) is systematized.
Nakamura, Hisashi; Nakashima, Mikio
JAERI-Tech 2002-006, 58 Pages, 2002/03
JAERI-Tech-2002-006.pdf:2.56MB
Radiation exposure was estimated on production and utilization of recycled items using dismantling waste by assuming that their usage are restricted to nuclear facilities. The radiation exposure attributed to production of a steel-plate cast iron waste container, a receptacle for slag, and a drum reinforcement was calculated to be in the range of several 
Sv to several tens of Sv even in recycling contaminated metal waste of which radioactivity concentration of Co-60 is higher than the clearance level by a factor of two figures. It is also elucidated that casting of a multiple casting waste package meets the standards of dose equivalent rate for the transport of a radioactive package and the weight of the package will be able to kept around 20 tons for the convenience of the handling, in case of disposal of metal waste less than 37MBq/g with the steel-plate cast iron waste container. As the results, from the radiological exposure's point of view, it should be possible to use slightly contaminated metal for recycled items in waste management.
Yanagihara, Satoshi
Nihon Kikai Gakkai-Shi, 100(948), p.1174 - 1178, 1997/11
no abstracts in English
; ; E.Kolstad*
Nihon Genshiryoku Gakkai-Shi, 28(7), p.641 - 657, 1986/00
Times Cited Count：4 Percentile：47.77(Nuclear Science & Technology)no abstracts in English
Uezu, Yasuhiro
no journal, ,
This paper will be used for presentation of Fukushima environmental remediation in WM 2017. I will participate this meeting as a panelist. This is contained that strategies of technology development for volume reduction and recycling of soil and wastes.
