The calculation and estimation of wastes generated by decommissioning of nuclear facilities

; ; ; Takeda, Seiichiro

JNC TN8420 2001-008, 134 Pages, 2001/07

JNC-TN8420-2001-008.pdf:4.4MB

This investigation was conducted as a part of planning the low-level radioactive waste management program (LLW management program). The aim of this investigation was contributed to compile the radioactive waste database of JNC's LLW management program. All nuclear facilities of the Tokai works and Ningyo-toge Environmental Engineering Center were investigated in this work. The wastes generated by the decomissioning of each nuclear facility were classified into radioactive waste and others (exempt waste and non-radioactive waste), and the amount of the wastes was estimated. The estimated amounts of radioactive wastes generated by decomissioning of the nuclear facilities are as follows. (1)Tokai works. The amount of waste generated by decommissioning of nuclear facilities of the Tokai works is about 1,079,100 ton. The amount of radioactive waste is about 15,400 ton. The amount of exempt waste and non-radioactive waste is about 1,063,700 ton. (2)Ningyo-toge Environmental Engineering Center. The amount of waste generated by decommissioning of nuclear facilities of Ningyo-toge Environmental Engineering Center is about 112,500 ton. The amount of radioactive waste is about 7,800 ton. The amount of exempt waste and non-radioactive waste is about 104,700 ton.

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Tanimoto, Kenichi

PNC TN9450 98-002, 52 Pages, 1998/01

PNC-TN9450-98-002.pdf:11.7MB

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Nakano, Tomoyuki;

PNC TN9420 92-008, 119 Pages, 1992/06

PNC-TN9420-92-008.pdf:3.71MB

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Study on optimization of amount of radioactive waste in radioactive level and worker exposure dose in decommissioning and dismantling work

Sasagawa, Tsuyoshi; Shimada, Taro; Takeda, Seiji

no journal, , 

IAEA standard document (GSR part6) requires appropriate dose control and minimization of radioactive waste for decommissioning of nuclear facilities. It is necessary to develop a method to optimize the amount of radioactive waste and the radiation dose. Therefore, we developed a code to evaluate the optimum conditions of dismantling work by calculating the amount of radioactive waste in radioactive level and the radiation dose according to the conditions of the decommissioning process and analyzing the cost-benefit of both results. Furthermore, based on the information of decommissioning of JPDR, the sensitivity analysis was performed for the case of decontamination and dismantling of three kinds of tanks and associated piping, focusing on the size of cut pieces and the type of container. As a result, different trends were observed for the minimum number of containers of the radioactive waste in radioactive level and the minimum dose to workers. The cost-benefit analysis was performed to derive the optimum conditions of the type of container and the size of cut pieces with cost as an index, and the optimization method by the cost-benefit analysis based on the results of the amount of radioactive waste generated in radioactive level and the radiation dose was shown to be applicable.