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Journal Articles

Development of the reasonable confirmation methods concerning radioactive wastes from research facilities

Hayashi, Hirokazu; Okada, Shota; Izumo, Sari; Hoshino, Yuzuru; Tsuji, Tomoyuki; Nakata, Hisakazu; Sakai, Akihiro; Amazawa, Hiroya; Sakamoto, Yoshiaki

Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM), 7 Pages, 2017/04

A near surface disposal for low-level radioactive waste (LLW) generated from commercial nuclear power plants (NPP) is operating in Japan. However, the disposal of LLW from other nuclear facilities and radioisotope utilization facilities has not yet been implemented. Japan Atomic Energy Agency (JAEA) plans to implement the near surface disposal. In order to be disposed of these wastes, it must be confirmed by the regulator that each waste package (radioactive waste solidified with filling materials, such as cement, in a container by a regulated method is termed a waste package) conforms to technical standards that aim for safe disposal. JAEA has studied reasonable confirmation methods to demonstrate the conformity of the waste package to the technical standard as NPP operators have studied it. This report describes the outline of our activities focused on development of the confirmation method applicable to radioactive wastes from research facilities.

JAEA Reports

Study on the evaluation method to determine the radioactivity concentration waste generated from post-irradiation examination facilities

Hoshino, Yuzuru; Sakamoto, Yoshiaki; Muroi, Masayuki*; Mukai, Satoru*

JAEA-Technology 2015-015, 96 Pages, 2015/07

JAEA-Technology-2015-015.pdf:20.34MB

In order to dispose of the radioactive waste which generates from post-irradiation examination (PIE) facilities, the common evaluation method of radioactivity in wastes from PIE should be established by the actual data such as radioactivity values and the theoretical calculation. In this study, the radioactivity concentrations of 17 nuclides (H-3, C-14, Co-60, Ni-63, Sr-90, Tc-99, Cs-137, Eu-154, U-234, U-235, U-238, Pu-238, Pu-239, Pu-240, Pu-241, Am-241, Cm-244) in combustible wastes stored in NUCLEAR DEVEROPMENT CORPORATION were measured from 3 samples and the radioactivity was calculated by ORIGEN-2 based on initial contents and operation record of the spent fuel. From the comparison of the obtained data by the radiological measurement with the calculated values, the subject to be solved for establishment of the radioactivity evaluation method for PIE was extracted.

Oral presentation

Evaluation and issue of radioactive inventory for Fugen's decommissioning

Hayashi, Hirokazu; Mizui, Hiroyuki; Sano, Kazuya; Kitamura, Koichi

no journal, , 

no abstracts in English

Oral presentation

Validation of the Short-Term Emergency Assessment system of Marine Environmental Radioactivity (STEAMER)

Kawamura, Hideyuki; Kobayashi, Takuya; Kamidaira, Yuki

no journal, , 

This study aims to validate accuracies of forecast of the Short-Term Emergency Assessment system of Marine Environmental Radioactivity (STEAMER) developed at JAEA by using forecast and reanalysis ocean current data. Oceanic dispersion simulations were carried out in the northwestern Pacific Ocean for 30 days from first day of every month between 2015 and 2017. It was assumed that $$^{137}$$Cs was continuously released into the ocean from the Fukushima Daiichi Nuclear Power Plant. The released $$^{137}$$Cs was inclined to disperse by mesoscale eddies in the northern part and by the Kuroshio Extension in the southern part. The simulation results with forecast ocean current data were similar to those with reanalysis ocean current data in the early periods and differences between them were remarkable after that. The cause must be accuracies of variable ocean current in the coastal ocean rather than phenomena with long time scale such as the Kuroshio Extension.

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