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Dose Estimate in Treatment and Disposal of Contaminated Materials due to the Accident at the Fukushima Nuclear Power Plant

Published online by Cambridge University Press:  03 July 2014

Seiji Takeda ,
Takuma Sawaguchi  and
Hideo Kimura
Seiji Takeda
Affiliation:
Japan Atomic Energy Agency, Nuclear Safety Research Center, Environmental Safety Research Group, Tokai-mura, Naka-gun, Ibaraki pref., 319-1195, Japan
Takuma Sawaguchi
Affiliation:
Japan Atomic Energy Agency, Nuclear Safety Research Center, Environmental Safety Research Group, Tokai-mura, Naka-gun, Ibaraki pref., 319-1195, Japan
Hideo Kimura
Affiliation:
Japan Atomic Energy Agency, Nuclear Safety Research Center, Environmental Safety Research Group, Tokai-mura, Naka-gun, Ibaraki pref., 319-1195, Japan
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Abstract

Some kinds of material in the environment due to the accident at the Fukushima Nuclear Power Plant have been contaminated by radioactive cesium (134Cs and 137Cs), which are represented by dehydrated sludge, surface soil and disaster wastes generated by the Great East Japan Earthquake. Treatment (transportation, temporary storage and incineration) and disposal of the contaminated materials should be carried out while ensuring the safety of radiation for the workers and the public. In this study, in order to provide the technical information for making the criteria, the dose estimation for scenarios on the treatment and disposal is conducted, based on the method used for driving the clearance levels in Japan. Minimum radioactive cesium concentration in contaminated material, that is, limiting activity concentration which is practicable for ordinary treatment and/or disposal, is calculated from the dose results, corresponding to the effective dose criteria indicated by the Nuclear Safety Commission of Japan. From the calculation result, it is suggested that it is necessary to forbid reusing the disposal site as construction, resident and agriculture in which the calculated doses for the public are higher than those in the other exposure pathways. Limiting concentration of radioactive cesium (134Cs and 137Cs) is derived to be 8,900Bq/kg for the external exposure pathway in landfill work under the condition of limited reuse of the site. In the case of the concentration below 8,900Bq/kg, the calculated dose of the resident due to direct and sky-shine radiation scattered in the air and ground from the interim storage place is less than 1mSv/y, irrespective of the distance from the storage place.

Keywords

radiation effectsCstransportation
Type
Articles
Information
MRS Online Proceedings Library (OPL) , Volume 1665: Symposium NW – Scientific Basis for Nuclear Waste Management XXXVII , 2014 , pp. 103 - 109
Copyright
Copyright © Materials Research Society 2014 

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References

REFERENCES

Near-term policy to ensure the safety for treating and disposing contaminated waste around the site of Fukushima Dai-ichi Nuclear Power Plants, NSC, June 3, 2011. [in Japanese]Google Scholar
Special Committee on Radioactive Waste and Decommissioning, Radionuclide Concentrations for Materials not Requiring Treatment as Radioactive Wastes Generated from Dismantling etc. of Reactor Facilities and Nuclear Fuel Use Facilities, NSC, 2005. [in Japanese]Google Scholar
International Atomic Energy Agency: Application of the Concepts of Exclusion, Exemption and Clearance, Safety Guide No.RS-G-1.7, IAEA, 2004.Google Scholar
Takeda, S., Kanno, M., Sasaki, T., Minase, N. and Kimura, H.: Development of PASCLR Code System Version 2 to Derive Clearance Levels of Uranium and Trans Uranium Wastes, JAEA-Data/Code 2006–003, JAEA, 2006. [in Japanese]Google Scholar
Briesmeister, J. F. (Ed.), MCNP - A General Monte Carlo N-Particle Transport Code, Version 4C, LA-13709-M, Los Alamos National Laboratory, 2000.Google Scholar
Sakamoto, Y. and Tanaka, S., QAD-CGGP2 and G33-GP2: Revised Versions of QAD-CGGP and G33-GP, JAERI-M 90-110, JAERI, 1990.Google Scholar
Watanabe, M., Takeda, S. and Kimura, H., External Effective Dose Conversion Factors for Deriving Clearance Levels of Uranium and Transuranium Wastes, JAEA-Data/Code 2008–001, JAEA, 2008. [in Japanese]Google Scholar