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Journal Articles

Impact of MOX fuel use in light-water reactors; Long-term radiological consequences of disposal of high-level waste in a geological repository

Minari, Eriko*; Kabasawa, Satsuki; Mihara, Morihiro; Makino, Hitoshi; Asano, Hidekazu*; Nakase, Masahiko*; Takeshita, Kenji*

Journal of Nuclear Science and Technology, 60(7), p.793 - 803, 2023/07

 Times Cited Count:3 Percentile:38.50(Nuclear Science & Technology)

Oral presentation

Evaluation of long-term safety of geological disposal of high-level waste generated during reprocessing spent MOX-LWR fuels

Minari, Eriko*; Kabasawa, Satsuki; Mihara, Morihiro; Makino, Hitoshi; Nakase, Masahiko*; Asano, Hidekazu*; Takeshita, Kenji*

no journal, , 

As a study on long-term safety of geological disposal of high-level waste (HLW) generated during reprocessing spent mixed oxide fuel in light water reactors (MOX-LWRs), two types of HLW are considered. One is HLW generated from MOX-LWR reprocessing and another is blended MOX-UO$$_{2}$$ HLW generated during reprocessing process whereby MOX fuels are diluted by UO$$_{2}$$ fuels. Radionuclide migration analyses for those two HLWs are conducted, and commonalities and differences between two HLWs in the viewpoint of long-term safety are discussed.

Oral presentation

Study of sensitivity analysis of the effects of longitudinal dispersion in the evaluation of geological disposal nuclide migration

Kabasawa, Satsuki; Yamaguchi, Masaaki; Ebashi, Takeshi; Makino, Hitoshi; Minari, Eriko*

no journal, , 

no abstracts in English

Oral presentation

Development of integrated nuclear fuel cycle simulator; Selection of FP nuclides and development of nuclear data library editing tool for NMB codes

Okamura, Tomohiro*; Oizumi, Akito; Minari, Eriko*; Nakase, Masahiko*; Asano, Hidekazu*; Nishihara, Kenji; Takeshita, Kenji*

no journal, , 

Takeshita Laboratory, Tokyo Institute of Technology, has been improving the Nuclear Material Balance code (NMB code) developed by Japan Atomic Energy Agency based on the knowledge of the nuclear fuel cycle simulation conducted so far. The previous NMB code was specialized in the evaluation of mass balance of actinide and lacked the function of back-end scenario analysis. In this improvement, 3 main points were researched and developed that (1) selection of FP nuclides to be introduced into the NMB code, (2) development of a nuclear data library preparation tool for the NMB code, and (3) burnup calculation and its error evaluation. In this presentation, we reported the results of the studies in (1) to (3).

Oral presentation

Overview of R&D of geological disposal and evaluation of long-term safety of geological disposal of high-level waste generated during reprocessingspent MOX-LWR fuels

Mihara, Morihiro; Minari, Eriko*

no journal, , 

Overview of R&D of geological disposal and evaluation of long-term safety of geological disposal of high-level waste generated during reprocessingspent MOX-LWR fuels are presented.

Oral presentation

Study on nuclear utilization scenario towards the second half of the 21st century, 3; Evaluation of long-term safety of geological disposal of vitrified MOX-LWR high-level waste

Minari, Eriko*; Mihara, Morihiro; Makino, Hitoshi; Okamura, Tomohiro*; Oizumi, Akito; Nishihara, Kenji; Nakase, Masahiko*; Takeshita, Kenji*

no journal, , 

no abstracts in English

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