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JAEA Reports

Development of elemental components in NDA systems for certifying radioactive wastes with the clearance level

Tsutsumi, Masahiro; Oishi, Tetsuya*; Yamasoto, Kotaro; Yoshida, Makoto

JAERI-Research 2004-021, 43 Pages, 2004/12

JAERI-Research-2004-021.pdf:8.55MB

We have designed and developed a $$gamma$$ measurement system to certify radioactive wastes below the clearance level. By advancing non-destructive $$gamma$$-ray assay technology, it aims at quantitative determination of radionuclides contained in 200 litter drum/container wastes. Unlike the waste from a nuclear power plant, you have to assume that the waste originating from radioisotope usage and nuclear research laboratory have a variety of contents and a complex mixture of radionuclides, and furthermore the uniformity of activity concentration is unknown. To cope with the problems, we have developed the $$gamma$$-ray measuring instruments (units) with effective improvement of capability against each problem. They are (1) germanium $$gamma$$ spectrometry unit for enhanced peak identification, (2) positioning detection unit for positioning of $$gamma$$ interactions and (3)high-efficiency detection unit for separation of low-energy component. This report summarizes the direction of the clearance level measuring system and the three developed measuring units with their performances.

JAEA Reports

Radiation exposure estimates on production and utilization of recycled items using dismantling waste

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 $$mu$$Sv to several tens of $$mu$$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.

JAEA Reports

Safety Evalution of Packages for Ocean Disposal of Low-Level Radioactive Waste

; Wadachi, Yoshiki

JAERI-M 85-195, 19 Pages, 1985/12

JAERI-M-85-195.pdf:0.75MB

no abstracts in English

Journal Articles

Survey on drum container for radioactive wastes

; *;

Nihon Genshiryoku Gakkai-Shi, 23(5), p.338 - 341, 1981/00

 Times Cited Count:0 Percentile:0.02(Nuclear Science & Technology)

no abstracts in English

Oral presentation

Introduction of a laser rust removal device for radioactive waste containers at the NSRI

Suda, Shoya; Kosuge, Atsushi; Kisohara, Naoyuki; Fujii, Mitsuki; Masai, Seita; Iseda, Hirokatsu; Minehara, Eisuke*

no journal, , 

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